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Sample records for mcguire nuclear station

  1. 76 FR 24538 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-02

    ..., 50-270, and 50-287] Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Notice of Withdrawal of... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY...

  2. 76 FR 40754 - Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-11

    ..., 50-270, And 50-287] Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Notice of Withdrawal of... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY...

  3. 75 FR 33358 - Duke Energy Carolinas, LLC; McGuire Nuclear Station; Confirmatory Order (Effective Immediately)

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-11

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY... Carolinas, LLC; McGuire Nuclear Station; Confirmatory Order (Effective Immediately) I Duke Energy Carolinas, LLC's (Duke Energy or Licensee) is the holder of License Nos. NPF-9 and NPF-17, issued by the...

  4. 77 FR 47677 - Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2, Notice of Consideration of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-09

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2, Notice of Consideration of... Determination, and Opportunity for a Hearing AGENCY: Nuclear Regulatory Commission. ACTION: License amendment...

  5. Auxiliary feedwater system risk-based inspection guide for the McGuire nuclear power plant

    SciTech Connect

    Bumgardner, J.D.; Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1994-05-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. McGuire was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the McGuire plant.

  6. 76 FR 39913 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-07

    ... Cyber Security Plan and proposed implementation schedule. Before issuance of the proposed license... Inclusion of the Cyber Security Plan in the Facility Operating License itself does not involve any modifications to safety-related structures, systems or components. Rather, the Cyber Security Plan describes how...

  7. Upflow conversion - Eliminating the potential for baffle jetting at McGuire

    SciTech Connect

    Kitlan, M.S. Jr.; McClenny, A.M. Jr. ); Culp, D.C. )

    1991-01-01

    Fuel failures indicative of baffle jetting were observed at Duke Power Company's McGuire units 1 and 2 in 1986 and 1987, respectively. In September 1990 the lower rector internals of unit 2 were modified to permanently eliminate the potential for baffle jetting. The unit 1 internals are to be converted in 1991. McGuire nuclear station is a two-unit, four-loop, Westinghouse pressurized water reactor with 17 by 17 fuel and a gross electrical output of 1,130 MW (electric) per unit. The modification performed on the unit 2 reactor internals resulted in a reversal in the direction of flow through the core barrel and baffle region. This flow reversal reduces the pressure drop across the baffle plates, thus eliminating the driving force for the baffle jets. This modification consists of plugging existing holes in the core barrel and opening new holes in the top former plate to change the flow direction.

  8. 77 FR 76541 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-28

    ... Nuclear Operations, Inc.; Pilgrim Nuclear Power Station AGENCY: Nuclear Regulatory Commission. ACTION... Nuclear Operations, Inc. (the licensee), for operation of the Pilgrim Nuclear Power Station (Pilgrim... Renewal of Nuclear Plants Regarding Pilgrim Nuclear Power Station, Final Report- Appendices,'' published...

  9. 75 FR 43572 - Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-26

    ... conditions. There will be no significant changes in radiation levels during these evolutions. No significant... proposed action will not have a significant effect on the quality of the human environment....

  10. Nuclear applications in manned space station

    NASA Technical Reports Server (NTRS)

    Brooksbank, W. A., Jr.; Sieren, G. J.

    1972-01-01

    The zirconium hydride reactor, coupled to a thermo-electric or Brayton conversion system, and the Pu 238 isotope/Brayton system, are considered to be the viable nuclear candidates for the modular space station electrical power system. The basic integration aspects of these nuclear electrical power systems are reviewed, including unique requirements imposed by the buildup and incremental utilization considerations of the modular station. Also treated are the various programmatic aspects of nuclear power system design and selection.

  11. 77 FR 18271 - Terrestrial Environmental Studies for Nuclear Power Stations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-27

    ... COMMISSION Terrestrial Environmental Studies for Nuclear Power Stations AGENCY: Nuclear Regulatory Commission... revision to Regulatory Guide (RG) 4.11, ``Terrestrial Environmental Studies for Nuclear Power Stations... environmental studies and analyses supporting licensing decisions for nuclear power reactors. ADDRESSES: Please...

  12. 78 FR 61400 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-03

    ... COMMISSION Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision... and ML102210411, respectively), concerns the operation of Pilgrim Nuclear Power Station (Pilgrim... (non- EQ) inaccessible cables at Pilgrim Nuclear Power Station (Pilgrim) are capable of...

  13. 75 FR 2164 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and...), for operation of Pilgrim Nuclear Power Station (Pilgrim), located in Plymouth County, MA. Therefore...

  14. 75 FR 75706 - Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos. 1...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-06

    ... Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos. 1 and 2; Notice of... Nuclear Power Station, Units 2 and 3, respectively, located in Grundy County, Illinois, and to Renewed Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Unit Nos. 1 and 2...

  15. 78 FR 35646 - Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-13

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2 AGENCY: Nuclear... U.S. Nuclear Regulatory Commission (NRC) has received an application, dated May 29, 2013,...

  16. Commentary: childhood cancer near nuclear power stations

    PubMed Central

    2009-01-01

    In 2008, the KiKK study in Germany reported a 1.6-fold increase in solid cancers and a 2.2-fold increase in leukemias among children living within 5 km of all German nuclear power stations. The study has triggered debates as to the cause(s) of these increased cancers. This article reports on the findings of the KiKK study; discusses past and more recent epidemiological studies of leukemias near nuclear installations around the world, and outlines a possible biological mechanism to explain the increased cancers. This suggests that the observed high rates of infant leukemias may be a teratogenic effect from incorporated radionuclides. Doses from environmental emissions from nuclear reactors to embryos and fetuses in pregnant women near nuclear power stations may be larger than suspected. Hematopoietic tissues appear to be considerably more radiosensitive in embryos/fetuses than in newborn babies. Recommendations for advice to local residents and for further research are made. PMID:19775438

  17. 75 FR 12311 - Entergy Nuclear Operations, Inc; Vermont Yankee Nuclear Power Station Environmental Assessment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-15

    ... COMMISSION Entergy Nuclear Operations, Inc; Vermont Yankee Nuclear Power Station Environmental Assessment and... Nuclear Operations, Inc. (Entergy or the licensee), for operation of Vermont Yankee Nuclear Power Station... Statement for Vermont Yankee Nuclear Power Station, Docket No. 50-271, dated July 1972, as supplemented...

  18. 76 FR 50274 - Terrestrial Environmental Studies for Nuclear Power Stations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-12

    ... COMMISSION Terrestrial Environmental Studies for Nuclear Power Stations AGENCY: Nuclear Regulatory Commission... Environmental Studies for Nuclear Power Stations.'' This guide provides technical guidance that the NRC staff... nuclear power reactors. DATES: Submit comments by October 11, 2011. Comments received after this date will...

  19. Tethered nuclear power for the Space Station

    NASA Technical Reports Server (NTRS)

    Bents, D. J.

    1985-01-01

    A nuclear space power system the SP-100 is being developed for future missions where large amounts of electrical power will be required. Although it is primarily intended for unmanned spacecraft, it can be adapted to a manned space platform by tethering it above the station through an electrical transmission line which isolates the reactor far away from the inhabited platform and conveys its power back to where it is needed. The transmission line, used in conjunction with an instrument rate shield, attenuates reactor radiation in the vicinity of the space station to less than one-one hundredth of the natural background which is already there. This combination of shielding and distance attenuation is less than one-tenth the mass of boom-mounted or onboard man-rated shields that are required when the reactor is mounted nearby. This paper describes how connection is made to the platform (configuration, operational requirements) and introduces a new element the coaxial transmission tube which enables efficient transmission of electrical power through long tethers in space. Design methodology for transmission tubes and tube arrays is discussed. An example conceptual design is presented that shows SP-100 at three power levels 100 kWe, 300 kWe, and 1000 kWe connected to space station via a 2 km HVDC transmission line/tether. Power system performance, mass, and radiation hazard are estimated with impacts on space station architecture and operation.

  20. Tethered nuclear power for the space station

    NASA Technical Reports Server (NTRS)

    Bents, D. J.

    1985-01-01

    A nuclear space power system the SP-100 is being developed for future missions where large amounts of electrical power will be required. Although it is primarily intended for unmanned spacecraft, it can be adapted to a manned space platform by tethering it above the station through an electrical transmission line which isolates the reactor far away from the inhabited platform and conveys its power back to where it is needed. The transmission line, used in conjunction with an instrument rate shield, attenuates reactor radiation in the vicinity of the space station to less than one-one hundredth of the natural background which is already there. This combination of shielding and distance attenuation is less than one-tenth the mass of boom-mounted or onboard man-rated shields that are required when the reactor is mounted nearby. This paper describes how connection is made to the platform (configuration, operational requirements) and introduces a new element the coaxial transmission tube which enables efficient transmission of electrical power through long tethers in space. Design methodology for transmission tubes and tube arrays is discussed. An example conceptual design is presented that shows SP-100 at three power levels 100 kWe, 300 kWe, and 1000 kWe connected to space station via a 2 km HVDC transmission line/tether. Power system performance, mass, and radiation hazard are estimated with impacts on space station architecture and operation.

  1. 76 FR 31992 - In the Matter of Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-02

    ... is collocated with a power reactor may choose to comply with the U.S. Nuclear Regulatory Commission... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION In the Matter of Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station...

  2. Final MTI Data Report: Pilgrim Nuclear Station

    SciTech Connect

    Parker, M.J.

    2003-03-17

    During the period from May 2000 to September 2001, ocean surface water temperature data was collected at the Pilgrim Nuclear Power Station near Plymouth, MA. This effort was led by the Savannah River Technology Center (SRTC) with the assistance of a local sub-contractor, Marine BioControl Corporation of Sandwich, MA. Permission for setting up the monitoring system was granted by Energy Corporation, which owns the plant site. This work was done in support of SRTC's ground truth mission for the U.S. Department of Energy's Multispectral Thermal Imager (MTI) satellite.

  3. Nuclear power station main control room habitability

    SciTech Connect

    Paschal, W.B.; Knous, W.S. )

    1989-01-01

    The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews.

  4. Radiological characterization of Yankee Nuclear Power Station

    SciTech Connect

    Bellini, F.X.; Cumming, E.R.; Hollenbeck, P. )

    1993-01-01

    The Yankee nuclear power station located in Rowe, Massachusetts, permanently ceased power operations on February 26, 1992, after 31 yr of operation. Yankee has since initiated decommissioning planning activities. A significant component of these activities is the determination of the extent of radiological contamination of the Yankee site. This paper describes the site radiological characterization program that has been implemented for decommissioning the Yankee plant. Radiological scoping surveys were completed to support submittal of a decommissioning plan to the U.S. Nuclear Regulatory Commission (NRC) by October 1, 1993. These surveys were designed to provide sufficient detail to estimate the extent of contamination, volume of radiological waste, activity of radiological waste, and personnel dose estimates for removal activities. Surveys were conducted both inside and on the grounds outside of the Yankee plant buildings. Survey results were combined with analytical evaluations to characterize the Yankee site.

  5. 78 FR 784 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-04

    ... COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption 1.0 Background Entergy..., which authorizes operation of the Pilgrim Nuclear Power Station (PNPS). The license provides, among... with the Vermont Yankee Nuclear Power Plant and Seabrook Nuclear Power Plant, on February 9, 2011...

  6. Determining Yankee Nuclear Power Station neutron activation

    SciTech Connect

    Heider, K.J.; Morrissey, K.J. )

    1993-01-01

    The Yankee nuclear power station located in Rowe, Massachusetts, permanently ceased power operations on February 26, 1992, after 31 yr of operation. Yankee has since initiated decommissioning planning activities. A significant component of these activities is a determination of the extent of radiological contamination of the Yankee site. Included in this effort was determination of the extent of neutron activation of plant components. This paper describes the determination of the neutron activation of the Yankee reactor vessel, associated internals, and surrounding structures. The Yankee reactor vessel is a 600-MW(thermal) stainless steel-lined, carbon steel vessel with stainless steel internal components designed by Westinghouse. The reactor vessel is surrounded and supported by a carbon steel neutron shield tank that was filled with chromated water during plant operation. A 5-ft-thick concrete biological shield wall surrounds the neutron shield tank. A project is under way to remove the reactor vessel internals from the reactor vessel.

  7. 75 FR 76498 - Firstenergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Environmental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-08

    ... COMMISSION Firstenergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Environmental Assessment... Company (FENOC, the licensee), for operation of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS... nuclear power reactors provide adequate margins of safety during any condition of normal...

  8. 75 FR 14208 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-24

    ... COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption 1.0 Background Entergy..., which authorizes operation of the Pilgrim Nuclear Power Station (Pilgrim). The license provides, among..., ``Requirements for physical protection of licensed activities in nuclear power reactors against radiological...

  9. 77 FR 47680 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station Receipt of Request for Action

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-09

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station Receipt of Request for Action... (NRC or the Commission) take action with regard to the Pilgrim Nuclear Power Station (Pilgrim). The...

  10. 75 FR 14209 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-24

    ... COMMISSION Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption 1.0 Background.... DPR-28, which authorizes operation of the Vermont Yankee Nuclear Power Station (VY). The license....55, ``Requirements for physical protection of licensed activities in nuclear power reactors against...

  11. Decontamination of nuclear systems at the Grand Gulf Nuclear Station

    SciTech Connect

    Weed, R.D.; Baker, K.R.

    1996-12-31

    Early in 1994 Management at the Grand Gulf Nuclear Station realized that a potential decontamination of several reactor systems was needed to maintain the commitments to the {open_quotes}As Low As Reasonably Achievable{close_quotes} (ALARA) program. There was a substantial amount of planned outage work required to repair and replace some internals in loop isolation valves and there were inspections and other outage work that needed to be accomplished as it had been postponed from previous outages because of the radiation exposure levels in and around the system equipment. Management scheduled for the procurement specification to be revised to incorporate additional boundary areas which had not been previously considered. The schedule included the period for gathering bids, awarding a contract, and reviewing the contractor`s procedures and reports and granting approval for the decontamination to proceed during the upcoming outage. In addition to the reviews required by the engineering group for overall control of the process, the plant system engineers had to prepare procedures at the system level to provide for a smooth operation to be made during the decontamination of the systems. The system engineers were required to make certain that the decontamination fluids would be contained within the systems being decontaminated and that they would not cross contaminate any other system not being decontaminated. Since these nuclear stations do not have the provisions for decontaminating these systems with using additional equipment, the equipment required is furnished by the contractor as skid mounted packaged units which can be moved into the area, set up near the system being decontaminated, and after the decontamination is completed, the skid mounted packages are removed as part of the contract. Figure 1 shows a typical setup in block diagram required to perform a reactor system decontamination. 1 fig.

  12. Remediation System Evaluation, Baird and McGuire Superfund Site

    EPA Pesticide Factsheets

    The 32.5-acre Baird and McGuire Superfund Site, located in Holbrook, Massachusetts, addresses VOC,SVOC, and arsenic contamination from a chemical mixing and batching plant that operated between 1912and 1983.

  13. 76 FR 17162 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Notice of Issuance of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-28

    ... COMMISSION Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Notice of Issuance of... Renewed Facility Operating License No. DPR-28 to Entergy Nuclear Vermont Yankee, LLC (Entergy VY), and Entergy Nuclear Operations, Inc. (ENO), (licensee), the operator of the Vermont Yankee Nuclear...

  14. Station blackout at nuclear power plants: Radiological implications for nuclear war

    SciTech Connect

    Shapiro, C.S.

    1986-12-01

    Recent work on station blackout is reviewed its radiological implications for a nuclear war scenario is explored. The major conclusion is that the effects of radiation from many nuclear weapon detonations in a nuclear war would swamp those from possible reactor accidents that result from station blackout.

  15. 77 FR 35080 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Record of Decision and Issuance...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-12

    ... fossil fuel generation, renewable energy sources, demand-side measures such as energy conservation, and... COMMISSION Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Record of Decision and Issuance... Operations Inc. (the licensee), the operator of the Pilgrim Nuclear Power Station (PNPS). Renewed...

  16. 76 FR 39910 - Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station, Unit Nos. 1 and 2; Notice...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-07

    ... Nuclear Station, LLC is owned by Constellation Energy Nuclear Group, LLC (CENG). The indirect transfer of... companies, Constellation Energy Group, Inc (CEG). According to the application dated May 12, 2011, filed by... Throughout the transaction, the direct ownership by CEG of 100 percent of Constellation Nuclear, LLC...

  17. 75 FR 80549 - FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-22

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating...

  18. 75 FR 16523 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-01

    ... COMMISSION FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating License... M.S. Fertel, Nuclear Energy Institute). The licensee's request for an exemption is...

  19. 75 FR 38147 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-01

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating...

  20. Power plant of high safety for underground nuclear power station

    SciTech Connect

    Dolgov, V.N.

    1993-12-31

    An ecologically pure, reliable, and economic nuclear power station is based on the use of nuclear power plants with the liquid-metal coolant. This plant with the inherent safety is protected from external influences due to the underground accommodations in geologically stable formations such as granites, cambrian clays, and salt deposits. The design features of this underground plant are described.

  1. 76 FR 19148 - PSEG Nuclear, LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-06

    ... Station (HCGS) and Salem Nuclear Generating Station, Units 1 and 2 (Salem). Possible alternatives to the proposed action (license renewal) include no action and reasonable alternative energy sources. As discussed... for energy planning decision makers would be unreasonable. This recommendation is based on: (1) The...

  2. Yankee nuclear power station license renewal assessment

    SciTech Connect

    Hinkle, W.D. )

    1992-01-01

    Nuclear power plants are initially licensed to operate for 40 years. Recent changes to US Nuclear Regulatory Commission regulations allow licenses to be renewed for up to 20 additional years. The new regulations require a comprehensive plant assessment to ensure continued effective aging management of equipment important to license renewal (ILR). Under the industry's lead plant program, Yankee Atomic Electric Company (YAEC) has assisted with development and demonstration of a generic license renewal assessment process. The generic assessment process developed under the lead plant program is the Nuclear Management and Resources Council methodology.

  3. A Low-Cost Nuclear Medicine Acquisition Station

    NASA Astrophysics Data System (ADS)

    Goble, John C.

    1986-06-01

    A significant obstacle to the use of local area networks in Nuclear Medicine has been the high cost of computer systems capable of digitizing the analog outputs of conventional gamma cameras. A PC-based Nuclear Image Acquisition Station has been designed using readily available components that permits acquisition, display and transfer of nuclear images. Processing functions, including camera uniformity corrections, image rotation and edge enhancement and other operators Elre available locally. With appropriate file format manipulation, images may alternatively be transferred to a conventional Nuclear Medicine computer for processing and archival storage. Hardware and software costs required to implement these functions on an existing micro are less than $4000.

  4. Engineer and technical training at GPUN's nuclear generating stations

    SciTech Connect

    Coe, R.P. )

    1993-01-01

    GPU Nuclear (GPUN) owns and operates the Oyster Creek and Three Mile Island (TMI) unit I nuclear generating stations. They also continue the recovery efforts of the damaged reactor at TMI-2. Technical training for engineers and support staff is managed by the GPUN Corporate Training Department. The group also manages the Institute of Nuclear Power Operations (INPO)-accredited Engineering Support Personnel (ESP) Training Program and the GPUN New Engineer Training Program. The New Engineer Training Program has been in existence since 1982 and has trained and oriented [approximately]100 new college graduates to the nuclear industry.

  5. Tritium management and removal at Ontario Hydro's nuclear generating stations

    SciTech Connect

    Guglielmi, F.

    1988-09-01

    Tritium of the heavy water systems of Ontario Hydro's Nuclear Generating Stations presents a radiological hazard both to station personnel and to the environment. Careful design of equipment, containment and the use of personal protective equipment reduces but does not remove the hazard. To deal more effectively with the problem, Ontario Hydro plants to remove the tritium in a new facility currently under construction. Accordingly, the management of tritium, by the selective use of the tritium removal facility, will play an important role in reducing the tritium hazards at the stations. This paper describes the models and management techniques used.

  6. Satellite nuclear power station: An engineering analysis

    NASA Technical Reports Server (NTRS)

    Williams, J. R.; Clement, J. D.; Rosa, R. J.; Kirby, K. D.; Yang, Y. Y.

    1973-01-01

    A nuclear-MHD power plant system which uses a compact non-breeder reactor to produce power in the multimegawatt range is analyzed. It is shown that, operated in synchronous orbit, the plant would transmit power safely to the ground by a microwave beam. Fuel reprocessing would take place in space, and no radioactive material would be returned to earth. Even the effect of a disastrous accident would have negligible effect on earth. A hydrogen moderated gas core reactor, or a colloid-core, or NERVA type reactor could also be used. The system is shown to approach closely the ideal of economical power without pollution.

  7. Satellite nuclear power station: An engineering analysis

    NASA Technical Reports Server (NTRS)

    Williams, J. R.; Clement, J. D.; Rosa, R. J.; Kirby, K. D.; Yang, Y. Y.

    1973-01-01

    A nuclear-MHD power plant system which uses a compact non-breeder reactor to produce power in the multimegawatt range is analyzed. It is shown that, operated in synchronous orbit, the plant would transmit power safely to the ground by a microwave beam. Fuel reprocessing would take place in space, and no radioactive material would be returned to earth. Even the effect of a disastrous accident would have negligible effect on earth. A hydrogen moderated gas core reactor, or a colloid-core, or NERVA type reactor could also be used. The system is shown to approach closely the ideal of economical power without pollution.

  8. Yankee Nuclear Power Station - analysis of decommissioning costs

    SciTech Connect

    Lessard, L.P.

    1996-12-31

    The preparation of decommissioning cost estimates for nuclear power generating stations has received a great deal of interest in the last few years. Owners are required by regulation to ensure that adequate funds are collected for the timely decommissioning of their facilities. The unexpected premature shutdown of several facilities and uncertainties associated with radioactive waste disposal and long-term spent-fuel storage, when viewed in the light of a deregulated electric utility industry, has caused many companies to reevaluate their decommissioning cost estimates. The decommissioning of the Yankee Nuclear Power Station represents the first large-scale project involving the complete decontamination and dismantlement of a commercial light water nuclear power generation facility in the United States. Since this pressurized water reactor operated for 32 yr at a respectable 74% lifetime capacity factor, the actual costs and resources required to decommission the plant, when compared with decommissioning estimates, will yield valuable benchmarking data.

  9. 78 FR 22347 - GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-15

    ... COMMISSION GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain Security... Facility Operating License No. DPR-73 issued for Three Mile Island Nuclear Power Station (TMI), Unit 2... protection of licensed activities in nuclear power reactors against radiological sabotage,'' ] states,...

  10. 76 FR 40944 - PSEG Nuclear, LLC, Salem Nuclear Generating Station, Units 1 and 2; Notice of Issuance of Renewed...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-12

    ... COMMISSION PSEG Nuclear, LLC, Salem Nuclear Generating Station, Units 1 and 2; Notice of Issuance of Renewed... License Nos. DPR-70 and DPR-75 to PSEG Nuclear LLC (the licensee), the operator of the Salem Nuclear Generating Station, Units 1 and 2 (Salem). Renewed Facility Operating License Nos. DPR-70 and DPR-75...

  11. 75 FR 10833 - In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-09

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for.... The license authorizes the operation of the Vermont Yankee Nuclear Power Station (Vermont Yankee) in...

  12. 75 FR 8153 - Nebraska Public Power District; Cooper Nuclear Station Environmental Assessment and Finding of No...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-23

    ... COMMISSION Nebraska Public Power District; Cooper Nuclear Station Environmental Assessment and Finding of No... District (NPPD, the licensee), for operation of the Cooper Nuclear Station (CNS), located in Nemaha County... Statement for the Cooper Nuclear Station dated February 1973. Agencies and Persons Consulted In...

  13. 76 FR 82201 - General Site Suitability Criteria for Nuclear Power Stations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-30

    ... Power Stations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for... regulatory guide DG-4021, ``General Site Suitability Criteria for Nuclear Power Stations.'' This guide... for nuclear power stations. DATES: Submit comments by February 25, 2012. Comments received after this...

  14. 75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-24

    ... COMMISSION Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental... Palo Verde Nuclear Generating Station (PVNGS), Unit 3, located in Maricopa County, Arizona. Therefore... Statement for the Palo Verde Nuclear Generating Station, NUREG-0841, dated February 1982. Agencies...

  15. Enhancement of NRC station blackout requirements for nuclear power plants

    SciTech Connect

    McConnell, M. W.

    2012-07-01

    The U.S. Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) in response to Commission direction to conduct a systematic and methodical review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction, in light of the accident at the Fukushima Dai-ichi Nuclear Power Plant. The NTTF's review resulted in a set of recommendations that took a balanced approach to defense-in-depth as applied to low-likelihood, high-consequence events such as prolonged station blackout (SBO) resulting from severe natural phenomena. Part 50, Section 63, of Title 10 of the Code of Federal Regulations (CFR), 'Loss of All Alternating Current Power,' currently requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of an SBO. The SBO duration and mitigation strategy for each nuclear power plant is site specific and is based on the robustness of the local transmission system and the transmission system operator's capability to restore offsite power to the nuclear power plant. With regard to SBO, the NTTF recommended that the NRC strengthen SBO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events. The NTTF also recommended strengthening emergency preparedness for prolonged SBO and multi-unit events. These recommendations, taken together, are intended to clarify and strengthen US nuclear reactor safety regarding protection against and mitigation of the consequences of natural disasters and emergency preparedness during SBO. The focus of this paper is on the existing SBO requirements and NRC initiatives to strengthen SBO capability at all operating and new reactors to address prolonged SBO stemming from design-basis and beyond-design-basis external events. The NRC initiatives are intended to

  16. 75 FR 76055 - Nebraska Public Power District Cooper Nuclear Station; Notice of Issuance of Renewed Facility...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-07

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Docket No. 50-298; NRC-2008-0617] Nebraska Public Power District Cooper Nuclear Station; Notice of... operator of the Cooper Nuclear Station (CNS). Renewed facility operating license No. DPR-46...

  17. 75 FR 5631 - Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station; Environmental Assessment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-03

    ... COMMISSION Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station; Environmental Assessment... Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee), for operation of the Wolf Creek... Statement for License Renewal of Nuclear Plants: Wolf Creek Generating Station--Final Report (NUREG-1437...

  18. 78 FR 45984 - Yankee Atomic Electric Company, Yankee Nuclear Power Station

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-30

    ... COMMISSION Yankee Atomic Electric Company, Yankee Nuclear Power Station AGENCY: Nuclear Regulatory Commission... Atomic Electric Company (YAEC) is the holder of Possession-Only License DPR-3 for the Yankee Nuclear Power Station (YNPS) facility. The license, issued pursuant to the Atomic Energy Act of 1954, as amended...

  19. 76 FR 39134 - ZIONSOLUTIONS, LLC; Zion Nuclear Power Station, Units 1 and 2 Exemption From Recordkeeping...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-05

    ... COMMISSION ZIONSOLUTIONS, LLC; Zion Nuclear Power Station, Units 1 and 2 Exemption From Recordkeeping Requirements 1.0 Background Zion Nuclear Power Station (ZNPS or Zion), Unit 1, is a Westinghouse 3250 MWt... licensing basis requirements previously applicable to the nuclear power units and associated systems...

  20. 76 FR 44376 - Vermont Yankee Nuclear Power Station; Notice of Withdrawal of Application for Amendment to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-25

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Vermont Yankee Nuclear Power Station; Notice of Withdrawal of Application for Amendment to... request of Vermont Yankee Nuclear Power Station (the licensee) to withdraw its August 19, 2010...

  1. [Medical and psychological aspects of safety measures maintenance among nuclear and power station personnel].

    PubMed

    Ipatov, P L; Sorokin, A V; Basov, V I

    2004-01-01

    The article deals with 15-year experience of medical and psychophysiologic service in Medical and Sanitary Establishment No. 156 and Balakovo nuclear power station on providing reliability of occupational activities for the station personnel.

  2. Public response to the Diablo Canyon Nuclear Generating Station

    SciTech Connect

    Pijawka, K.D.

    1982-08-01

    The authors examine the nature of the public response to the Diablo Canyon Nuclear Generating Station located in San Luis Obispo, California, from the early 1960s to the present. Four distinct phases of public intervention were discerned, based on change in both plant-related issues and in the nature of the antinuclear constituencies in the region. The level of public concern varied both geographically and temporally and is related to the area's social structure, environmental predispositions, and distribution of plant-related economic benefits. External events, such as the prolonged debate over the risk assessment of the seismic hazard and the Three Mile Island accident were found to be important factors in explaining variation in public concern and political response.

  3. Installation for a nuclear power station with staggered swimming pools

    SciTech Connect

    Gigou, R.

    1982-12-28

    In an installation for a nuclear power station comprising a ''reactor building'' with a first swimming pool for handling of fuel units and a fuel building with a second swimming pool for the transfer, storage and deactivation of the units, the second swimming pool is located at a lower level than that of the first and is connected to the first by an intermediate auxiliary chamber filled with water and located under the first swimming pool. The auxiliary chamber is connected by a vertical pipeline to the first swimming pool and by a horizontal connecting pipeline to the second swimming pool. Each of the pipelines is provided with a shut-off valve, with interlocking means which prevents the simultaneous opening of the two valves. There is negligible dead space around a conveyor basket for fuel units when it is in the vertical or horizontal pipelines.

  4. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-05

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed... No. DPR-46, issued to Nebraska Public Power District (the licensee), for operation of the...

  5. 78 FR 28005 - System Energy Resources, Inc.; Grand Gulf Nuclear Station; Order Approving Direct and Indirect...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-13

    ... adjacent to Grand Gulf Nuclear Station (GGNS). The GGNS is located in Claiborne County, Mississippi. II By... 2013. For the Nuclear Regulatory Commission. Glenn M. Tracy, Director, Office of New Reactors. BILLING...

  6. Climatographic analysis of the Zion Nuclear Power Station site

    SciTech Connect

    Miller, C.W.; Whitcomb, R.C. ); Lyons, W.A.; Venne, M.G.; Keen, C.S.

    1989-01-01

    The computerized emergency response dose assessment codes (ERDACs) used in the nuclear industry commonly rely on Gaussian plume dispersion techniques. In coastal zones, particularly within 15 km of the shoreline, complex four-dimensional mesoscale meteorological regimes often violate some of the basic assumptions of Gaussian dispersion. For example a land breeze will initially advect materials offshore into unpopulated areas. Such effluents may pool over water only to return to land in the next morning's onshore flow, but in locations and concentrations unknown and undeterminable from on-site data and standard Gaussian modeling techniques. Improving the performance of ERDACs for a given coastal site requires a climatographic inventory of that site and its surroundings. This involves identifying the coastal mesoscale regimes (CMRs) that affect the site, including their annual frequencies of occurrence and the meteorological conditions that characterize them. Such a climatographic analysis has been performed for the Zion nuclear power station (NPS), which is located just north of Chicago, Illinois, on the western shore of southern Lake Michigan. The purpose of this papers is to summarize the results of this study and its implications for radiological emergency response activities. A conceptual framework for allocating resources in developing an adequate emergency response system includes three major factors: (1) frequency of the mesoscale regimes; (2) extent to which the regime can result in high concentrations/doses; (3) ease with which it can be modeled, with due consideration given for input data requirements.

  7. Climatographic analysis of the Zion nuclear power station site

    SciTech Connect

    Lyons, W.A.; Venne, M.G.; Keen, C.S.; Miller, C.W.; Whitcomb, R.C.

    1989-01-01

    The computerized emergency response dose assessment codes (ERDACs) used in the nuclear industry commonly rely on Gaussian plume dispersion techniques. In coastal zones, particularly within 15 km of the shoreline, complex four-dimensional mesoscale meteorological regimes often violate some of the basic assumptions of Gaussian dispersion. For example, a land breeze will initially advect materials offshore into unpopulated areas. Such effluents may pool over water only to return to land in the next morning's onshore flow, but in locations and concentrations unknown and undeterminable from on-site data and standard Gaussian modeling techniques. Improving the performance of ERDACs for a given coastal site requires a climatographic inventory of that site and its surroundings. This involves identifying the coastal mesoscale regimes (CMRs) that affect the site, including their annual frequencies of occurrence and the meteorological conditions that characterize them. Such a climatographic analysis has been performed for the Zion nuclear power station (NPS), which is located just north of Chicago, Illinois, on the western shore of southern Lake Michigan. The purpose of this paper is to summarize the results of this study and its implications for radiological emergency response activities.

  8. 75 FR 15749 - Entergy Operations, Inc., Grand Gulf Nuclear Station, Unit 1; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-30

    ... COMMISSION Entergy Operations, Inc., Grand Gulf Nuclear Station, Unit 1; Exemption 1.0 Background Entergy Operations, Inc. (Entergy or the licensee), is the holder of Facility Operating License No. NPF-29 which authorizes operation of the Grand Gulf Nuclear Station, Unit 1 (GGNS). The license provides, among other...

  9. 75 FR 33366 - Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Notice of Withdrawal of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-11

    ... COMMISSION Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Notice of Withdrawal of..., application for amendment to Facility Operating License No. DPR-16 for the Oyster Creek Nuclear Generating Station (Oyster Creek), located in Ocean County, New Jersey. The proposed amendment would have revised...

  10. 76 FR 79227 - Exemption Request Submitted by Oyster Creek Nuclear Generating Station; Exelon Generation Company...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-21

    ... COMMISSION Exemption Request Submitted by Oyster Creek Nuclear Generating Station; Exelon Generation Company... Generation Company, LLC (the licensee), for operation of the Oyster Creek Nuclear Generating Station (Oyster... for Oyster Creek and NUREG-1437, Vol. 1, Supplement 28, ``Generic Environmental Impact Statement...

  11. 76 FR 41532 - Yankee Atomic Electric Company, Yankee Nuclear Power Station (Yankee-Rowe); Notice of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-14

    ... COMMISSION Yankee Atomic Electric Company, Yankee Nuclear Power Station (Yankee-Rowe); Notice of... indirect transfer of the Facility Operating License No. DPR-3 for the Yankee Nuclear Power Station (Yankee... Officer Powers, and General Hearing Management for NRC Adjudicatory Hearings,'' of 10 CFR part 2....

  12. The Fukushima Nuclear Power Station incident and marine pollution.

    PubMed

    Chang, Yen-Chiang; Zhao, Yue

    2012-05-01

    Based on the facts relating to the radioactive wastewater discharged by the Fukushima Nuclear Power Station in Japan, this paper intends to explore the international legal obligations for Japan from three perspectives, namely, the immediate notification, the prevention of transboundary harm and the prevention of dumping. Furthermore, this article defines and compares two types of international legal liabilities, the traditional state responsibility and the responsibility for transboundary harm. Through comparison, the international legal liability of Japan is discussed. After detailed analysis, the conclusion is that Japan should be responsible for the obligation of immediate notification and since Japan unilaterally discharge the wastes without prior specific permits of other contracting countries, it should also be responsible for the violation of prevention of dumping. Since so far, no material injury has emerged and there would appear to be no culpability as regards the prevention of transboundary harm. Finally, this paper stresses the necessity to develop a worldwide agreement concerning the liability for transboundary harm and to establish an institutional framework for the enforcement of a state's obligations, and also the great significance of international cooperation between nations and organisations in relation to marine environmental protection. Copyright © 2012 Elsevier Ltd. All rights reserved.

  13. 75 FR 10517 - Nebraska Public Power District, Cooper Nuclear Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-08

    ... compliance date for all operating nuclear power plants, but noted that the Commission's regulations provide... COMMISSION Nebraska Public Power District, Cooper Nuclear Station; Exemption 1.0 Background Nebraska Public... licensed activities in nuclear power reactors against radiological sabotage,'' published in the Federal...

  14. Condensers of large steam turbines for thermal and nuclear power stations

    NASA Astrophysics Data System (ADS)

    Nazarov, V. V.; Zaekin, L. P.

    2007-10-01

    Designs and technical characteristics of the condensers of large steam turbines for thermal and nuclear power stations operating in Russia and abroad are described. New technical solutions used in designing them are considered.

  15. Analysis of Digitized Seismograms from Russian Geophysical Survey Stations of Soviet Peaceful Nuclear Explosions

    DTIC Science & Technology

    2008-09-30

    2008 REPRINT 4. TITLE AND SUBTITLE 5a. CONTRACT NUMBER ANALYSIS OF DIGITIZED SEISMOGRAMS FROM RUSSIAN GEOOPHYSICAL FA8718-08-C-0018 SURVEY STATIONS OF...Technologies ANALYSIS OF DIGITIZED SEISMOGRAMS FROM RUSSIAN GEOPHYSICAL SURVEY STATIONS OF SOVIET PEACEFUL NUCLEAR EXPLOSIONS Kevin G. Mackey Michigan State...Soviet Peaceful Nuclear Explosions (PNEs). The analysis seeks to better resolve the crustal and velocity structure of Russia, particularly the Russian

  16. 78 FR 77508 - Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined Licenses Application Review AGENCY: Nuclear Regulatory Commission. ACTION: Final environmental impact...

  17. 75 FR 71467 - Exelon Nuclear Texas Holdings, LLC, Early Site Permit Application for the Victoria County Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Nuclear Texas Holdings, LLC, Early Site Permit Application for the Victoria County Station... Contention Preparation AGENCY: Nuclear Regulatory Commission (NRC or the Commission). ACTION: Notice...

  18. 77 FR 56238 - Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station; Application for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-12

    ... COMMISSION Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station; Application for Amendment... Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems with ADAMS, please... Commission (NRC or the Commission) has granted the request of Wolf Creek Nuclear Operating Corporation (the...

  19. Overview of the regulatory framework applying to nuclear power stations of France

    SciTech Connect

    Astolfi, J.F.

    1993-12-31

    The achievement of French nuclear power plants, because France has not yet issued a specific nuclear law and is tied to a very complex regulatory structure, is submitted to a large number of prior authorizations, which are issued either at a national level or by local authorities according to their goals and importance. This report will outline the regulatory framework applying to nuclear power stations in France.

  20. Natural Disasters and Safety Risks at Nuclear Power Stations

    NASA Astrophysics Data System (ADS)

    Tutnova, T.

    2012-04-01

    In the aftermath of Fukushima natural-technological disaster the global opinion on nuclear energy divided even deeper. While Germany, Italy and the USA are currently reevaluating their previous plans on nuclear growth, many states are committed to expand nuclear energy output. In China and France, where the industry is widely supported by policymakers, there is little talk about abandoning further development of nuclear energy. Moreover, China displays the most remarkable pace of nuclear development in the world: it is responsible for 40% of worldwide reactors under construction, and aims at least to quadruple its nuclear capacity by 2020. In these states the consequences of Fukushima natural-technological accident will probably result in safety checks and advancement of new reactor technologies. Thus, China is buying newer reactor design from the USA which relies on "passive safety systems". It means that emergency power generators, crucial for reactor cooling in case of an accident, won't depend on electricity, so that tsunami won't disable them like it happened in the case of Fukushima. Nuclear energy managed to draw lessons from previous nuclear accidents where technological and human factors played crucial role. But the Fukushima lesson shows that the natural hazards, nevertheless, were undervalued. Though the ongoing technological advancements make it possible to increase the safety of nuclear power plants with consideration of natural risks, it is not just a question of technology improvement. A necessary action that must be taken is the reevaluation of the character and sources of the potential hazards which natural disasters can bring to nuclear industry. One of the examples is a devastating impact of more than one natural disaster happening at the same time. This subject, in fact, was not taken into account before, while it must be a significant point in planning sites for new nuclear power plants. Another important lesson unveiled is that world nuclear

  1. 77 FR 49463 - Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3; Application and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-16

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3; Application and... Edison Company (SCE, the licensee) for operation of the San Onofre Nuclear Generating Station...

  2. 76 FR 72007 - ZionSolutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Security...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-21

    ... COMMISSION ZionSolutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Security Requirements 1.0 Background Zion Nuclear Power Station (ZNPS or Zion), Unit 1, is a Westinghouse 3250 MWt... activities in nuclear power reactors against radiological sabotage,'' paragraph (b)(1) states, ``The licensee...

  3. Radwaste (DAW) volume reduction cost initiative at the Oyster Creek Nuclear Generation Station

    SciTech Connect

    Wacha, A.H.

    1995-05-01

    Oyster Creek Nuclear Generating Station is a General Electric Mark 1, 620 MWe (Net) Boiling Water Reactor operated by GPU Nuclear Corporation and located in Forked River, New Jersey. The plant began commercial operation on December 23, 1969, and achieved its longest continuous run during cycle 14 (413 days) 2-16-93 to 9-11-94. As part of the industry-wide initiative to reduce nuclear plant O&M costs, the Electric Power Research Institute (EPRI) was asked by GPU Nuclear to assist the Oyster Creek Nuclear Generating Station (OCNGS) in identifying opportunities for reducing the costs associated with its Radwaste Minimization Program for Dry Active Waste (DAW). The purpose of the project was to evaluate the existing generation, minimization, processing and disposal programs and to identify a wide variety of potential mechanisms for reducing waste volumes and associated costs.

  4. Space station program phase B definition: Nuclear reactor-powered space station cost and schedules

    NASA Technical Reports Server (NTRS)

    1971-01-01

    Tabulated data are presented on the costs, schedules, and technical characteristics for the space station phases C and D program. The work breakdown structure, schedule data, program ground rules, program costs, cost-estimating rationale, funding schedules, and supporting data are included.

  5. Decontamination of control rod housing from Palisades Nuclear Power Station.

    SciTech Connect

    Kaminski, M.D.; Nunez, L.; Purohit, A.

    1999-05-03

    Argonne National Laboratory has developed a novel decontamination solvent for removing oxide scales formed on ferrous metals typical of nuclear reactor piping. The decontamination process is based on the properties of the diphosphonic acids (specifically 1-hydroxyethane-1,1-diphosphonic acid or HEDPA) coupled with strong reducing-agents (e.g., sodium formaldehyde sulfoxylate, SFS, and hydroxylamine nitrate, HAN). To study this solvent further, ANL has solicited actual stainless steel piping material that has been recently removed from an operating nuclear reactor. On March 3, 1999 ANL received segments of control rod housing from Consumers Energy's Palisades Nuclear Plant (Covert, MI) containing radioactive contamination from both neutron activation and surface scale deposits. Palisades Power plant is a PWR type nuclear generating plant. A total of eight segments were received. These segments were from control rod housing that was in service for about 6.5 years. Of the eight pieces that were received two were chosen for our experimentation--small pieces labeled Piece A and Piece B. The wetted surfaces (with the reactor's pressurized water coolant/moderator) of the pieces were covered with as a scale that is best characterized visually as a smooth, shiny, adherent, and black/brown in color type oxide covering. This tenacious oxide could not be scratched or removed except by aggressive mechanical means (e.g., filing, cutting).

  6. Efficient ways for setting up the operation of nuclear power stations in power systems in the base load mode

    NASA Astrophysics Data System (ADS)

    Aminov, R. Z.; Shkret, A. F.; Burdenkova, E. Yu.; Garievskii, M. V.

    2011-05-01

    The results obtained from studies of efficient ways and methods for organizing the operation of developing nuclear power stations in the base load mode are presented. We also show comparative efficiency of different scenarios for unloading condensing thermal power stations, cogeneration stations, combined-cycle power plants, nuclear power stations, and using off-peak electric energy for electricity-intensive loads: pumped-hydroelectric storage, electric-powered heat supply, and electrolysis of water for producing hydrogen and oxygen.

  7. Christine McGuire: At the Heart of the Maverick Measurement Maven

    ERIC Educational Resources Information Center

    Harris, Ilene B.; Simpson, Deborah

    2005-01-01

    In this article, part of the "Exemplar" series in "Advances in Health Sciences Education," we profile the career of Christine McGuire, and capture her perspectives on the status of medical education practice and research. Her career was prototypical of other exemplars in the series--a pathway characterized by serendipity. As an exemplar, her…

  8. Christine McGuire: At the Heart of the Maverick Measurement Maven

    ERIC Educational Resources Information Center

    Harris, Ilene B.; Simpson, Deborah

    2005-01-01

    In this article, part of the "Exemplar" series in "Advances in Health Sciences Education," we profile the career of Christine McGuire, and capture her perspectives on the status of medical education practice and research. Her career was prototypical of other exemplars in the series--a pathway characterized by serendipity. As an exemplar, her…

  9. Review of the Literature Regarding McGuire's Inoculation Theory: Early Formulations and Recent Applications.

    ERIC Educational Resources Information Center

    Braley, Christopher

    As originally formulated by William J. McGuire, Inoculation Theory provided a means of immunizing cultural truisms against the effects of persuasive attacks. Subsequent studies have demonstrated its efficacy in conferring resistance to issues of considerable complexity and controversy. The efficacy of the Inoculation Theory process has been widely…

  10. NASA Growth Space Station missions and candidate nuclear/solar power systems

    NASA Technical Reports Server (NTRS)

    Heller, Jack A.; Nainiger, Joseph J.

    1987-01-01

    A brief summary is presented of a NASA study contract and in-house investigation on Growth Space Station missions and appropriate nuclear and solar space electric power systems. By the year 2000 some 300 kWe will be needed for missions and housekeeping power for a 12 to 18 person Station crew. Several Space Station configurations employing nuclear reactor power systems are discussed, including shielding requirements and power transmission schemes. Advantages of reactor power include a greatly simplified Station orientation procedure, greatly reduced occultation of views of the earth and deep space, near elimination of energy storage requirements, and significantly reduced station-keeping propellant mass due to very low drag of the reactor power system. The in-house studies of viable alternative Growth Space Station power systems showed that at 300 kWe a rigid silicon solar cell array with NiCd batteries had the highest specific mass at 275 kg/kWe, with solar Stirling the lowest at 40 kg/kWe. However, when 10 year propellant mass requirements are factored in, the 300 kWe nuclear Stirling exhibits the lowest total mass.

  11. NASA Growth Space Station missions and candidate nuclear/solar power systems

    NASA Technical Reports Server (NTRS)

    Heller, Jack A.; Nainiger, Joseph J.

    1987-01-01

    A brief summary is presented of a NASA study contract and in-house investigation on Growth Space Station missions and appropriate nuclear and solar space electric power systems. By the year 2000 some 300 kWe will be needed for missions and housekeeping power for a 12 to 18 person Station crew. Several Space Station configurations employing nuclear reactor power systems are discussed, including shielding requirements and power transmission schemes. Advantages of reactor power include a greatly simplified Station orientation procedure, greatly reduced occultation of views of the earth and deep space, near elimination of energy storage requirements, and significantly reduced station-keeping propellant mass due to very low drag of the reactor power system. The in-house studies of viable alternative Growth Space Station power systems showed that at 300 kWe a rigid silicon solar cell array with NiCd batteries had the highest specific mass at 275 kg/kWe, with solar Stirling the lowest at 40 kg/kWe. However, when 10 year propellant mass requirements are factored in, the 300 kWe nuclear Stirling exhibits the lowest total mass.

  12. Static analysis of rectifier cabinet for nuclear power generating stations based on finite element method

    NASA Astrophysics Data System (ADS)

    Yin, Qiang; Chen, Tian-jin; Li, Wei-yang; Xiong, Ze-cheng; Ma, Rui

    2017-09-01

    In order to obtain the deformation map and equivalent stress distribution of rectifier cabinet for nuclear power generating stations, the quality distribution of structure and electrical are described, the tensile bond strengths of the rings are checked, and the finite element model of cabinet is set up by ANSYS. The transport conditions of the hoisting state and fork loading state are analyzed. The deformation map and equivalent stress distribution are obtained. The attentive problems are put forward. It is a reference for analysis method and the obtained results for the transport of rectifier cabinet for nuclear power generating stations.

  13. Surveys of Food Intake Just after the Nuclear Accident at the Fukushima Daiichi Nuclear Power Station.

    PubMed

    Hirakawa, Sachiko; Yoshizawa, Nobuaki; Murakami, Kana; Takizawa, Mari; Kawai, Masaki; Sato, Osamu; Takagi, Shunji; Suzuki, Gen

    2017-01-01

    As a result of the nuclear accident at the Fukushima Daiichi nuclear power station (FDNPS) after the Great East Japan Earthquake on March 11, 2011, volatile radionuclides including iodine-131 were released into the environment and contaminated open-field vegetables, raw milk, tap water, etc. It is important for the health care of residents to correctly comprehend the level of their exposure to radioactive substances released following the accident. However, an evaluation of the internal exposure doses of residents of Fukushima Prefecture as a result of the ingestion of foods, which is indicated in the report issued by United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR)1 is based on a number of assumptions. For instance, the estimation assumes that foods were ingested as usual, without regard to the places to which residents were evacuated after the accident, the places where food shipment restrictions were imposed, and so forth. The present report aims to improve the accuracy of estimation of the amount of food actually ingested at evacuation areas, in order to reduce as much as possible the level of uncertainty in conventional values estimated directly after the accident, which were in fact values based on conservative assumptions. More concretely, as basic source material to more accurately estimate internal exposure doses from food ingestion, various patterns of evacuation and dietary habits at the time of the accident of the residents of 13 municipalities in Fukushima Prefecture who were evacuated during the period from directly after the accident of March 11, 2011 until the end of March are clarified in this report. From survey results, most of the food that evacuees took immediately after the accident was confirmed to have been sourced from either stockpiles prepared before the accident, or relief supplies from outside of the affected areas. The restriction orders of food supplies such as contaminated vegetables and milk, and tap

  14. 75 FR 13600 - Nine Mile Point Nuclear Station, LLC, Nine Mile Point Nuclear Station, Unit No. 2; Draft...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-22

    ... radioactive gaseous waste management system uses holdup (i.e., time delay to achieve radioactive decay) and... increased power level would not result in increased non-radioactive emissions that would have a significant... Radioactive Gaseous and Liquid Effluents, Direct Radiation Shine, and Solid Waste Nuclear power plants...

  15. 78 FR 27260 - Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3 Request for Action

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-09

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3 Request for... Southern California Edison (SCE) to ] submit a license amendment application for the design...

  16. Ultrafiltration treatment for liquid laundry wastes from nuclear power stations

    SciTech Connect

    Kichik, V.A.; Maslova, M.N.; Svittsov, A.A.; Kuleshov, N.F.

    1988-03-01

    The authors conduct a comprehensive analysis of the waste constituents--radioactive and organic--of the laundry water resulting from the on-site laundering and decontamination of clothing worn in nuclear power plants. The primary isotope contaminants consist of niobium and zirconium 95, manganese 54, cobalt 60, iron 59, and cesium 134 and 137. A variety of filter and adsorbent materials used in an ultrafiltration process are comparatively tested for their effectiveness in removing not only these isotopes but also the organic contaminants in the process of recycling the water. Those materials consist of copper hexacyanoferrate, polyacrylophosphonic acid, and several metal-polymer complexes.

  17. ALARA Overview System at Crystal River Unit 3 Nuclear Station.

    PubMed

    Kline, K B; Cope, W B

    1995-08-01

    During the Spring of 1994 the Health Physics Department at Florida Power Company used video and audio equipment to support remote health physics coverage for their Crystal River Unit 3 refueling outage (Refuel 9). The system consisted of eight cameras with audio interface linked to a control center located in a low-dose area. The system allowed health physics personnel to monitor steam generator and refueling activities with minimum exposure in high-dose areas, cutting by half the dose from the previous outage. B&W Nuclear Technologies provided complete setup, maintenance and tear-down, as well as assuming responsibilities for contaminated video and audio equipment.

  18. In situ monitoring of animal micronuclei before the operation of Daya Bay Nuclear Power Station

    SciTech Connect

    Y.N. Cai; H.Y. He; L.M. Qian; G.C. Sun; J.Y. Zhao

    1994-12-31

    Daya Bay Nuclear Power Station, a newly-built nuclear power station in southern mainland China, started its operation in 1993. We examined micro-nucleated cells of Invertibrate (Bivalves) and Vertibrate (Fish and Amphibia) in different spots within the 50km surroundings of the Power Station during 1986-1993. This paper reports the results of the investigation carried out in Dong Shan, a place 4.7km to the Power Station:Bivalves; Pteria martensil 5.1(1986),4.8(1988),4.8(1991),5,0(1993),Mytilus smardinus 4.7(1987),4.6(1988); Chamys nobilis 4.9(1987);4.9(1991),4.5(1992),4.5(1993). Fish; Therapon jarbua 0.48(1991),0.67(1992),0.47(1993). Amphibia; Bufo melanostictus 0.29 (1987), 0.34(1988),0.39(1992),0.39(1993). These results showed that the environmental situation, estimated by using the frequencies of micronucleated cells, was stable-there was no obvious chromosome damage in the animals studied. It was found that the incidence of micronucleated cells of Bivalves was higher than that of Fish and Amphibia, suggesting the epithelial cells to be more sensitive than peripheral erythrocytes to environmental genotoxic effects. The results of our studies for other spots will be reported afterward. These data can be used as the original background information to monitor the environment when the Nuclear Power Station is in operation.

  19. The TOMAS software system for approximate analysis of emergency situations at nuclear power stations

    NASA Astrophysics Data System (ADS)

    Zhukavin, A. P.

    2009-05-01

    The TOMAS software system for carrying out prompt analysis of different emergency situations in power units of nuclear power stations equipped with VVER-1000 and RBMK-1000 reactors is described. This software system can be used by experts of crisis centers for evaluating various situations, as well as for teaching students in higher schools specializing in the appropriate disciplines.

  20. 76 FR 1197 - Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-07

    ... additional 20 years of operation for the Palo Verde Nuclear Generating Station (PVNGS). Possible alternatives to the proposed action (license renewal) include no action and reasonable alternative energy sources... renewal for energy planning decision makers would be unreasonable. This recommendation is based on: (1...

  1. 75 FR 10328 - Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-05

    ... Operating Corporation, Wolf Creek Generating Station; Exemption 1.0 Background Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) is the holder of Renewed Facility Operating License No. NPF-42, which... those previously imposed by Commission orders issued after the terrorist attacks of September 11, 2001...

  2. Review of Cytogenetic analysis of restoration workers for Fukushima Daiichi nuclear power station accident.

    PubMed

    Suto, Yumiko

    2016-09-01

    Japan faced with the nuclear accident of the Fukushima Daiichi Nuclear Power Station (NPS) caused by the combined disaster of the Great East Japan Earthquake and the subsequent tsunamis on 11 March 2011. National Institute of Radiological Sciences received all nuclear workers who were engaged in emergency response tasks at the NPS and suspected of being overexposed to acute radiation. Biological dosimetry by dicentric chromosome assay was helpful for medical triage and management of the workers. © World Health Organisation 2016. All rights reserved. The World Health Organization has granted Oxford University Press permission for the reproduction of this article.

  3. Personal cooling in nuclear power stations. Final report

    SciTech Connect

    Kamon, E.

    1983-03-01

    Two approaches to personal, non-restrictive cooling of workers exposed to high-temperature work environments in nuclear power plants were evaluated. Both approaches involved a cooling garment designed to be worn under the protective clothing donned in penetration into radiation areas. One garmet was developed to cool by direct body contact with small packets of frozen water enclosed in the pockets of a shirt. The other garmets cooled by circulating a cooled liquid through capillaries in a vest and head cap (System A) or a vest (System B). Testing was conducted in a laboratory simulation of high ambient temperature (55/sup 0/C) and moderate metabolic heat production (200 to 300 kcal/h). Exposure time without cooling (control) was 52 minutes (Group 1) for the workloads demanding 200 kcal/h (48 minutes for Group 2). A long garmet with 7.2 kg of frozen water (LFWG) increased mean exposure time over the control by 242% (163% for the same garmet with 6.2 kg of frozen water). A short-version garmet with 3.8 kg of frozen water (SFWG) increased the stay time by 115%. The circulating-liquid garmets increased mean exposure time 35% (System A) and 27% (System B) over the control. In field observation, the LFWG with 6.2 kg of frozen water improved stay time by 125%.

  4. Childhood cancer mortality in relation to the St Lucie nuclear power station.

    PubMed

    Boice, John D; Mumma, Michael T; Blot, William J; Heath, Clark W

    2005-09-01

    An unusual county-wide excess of childhood cancers of brain and other nervous tissue in the late 1990s in St Lucie County, Florida, prompted the Florida Department of Health to conduct a case-control study within the county assessing residential chemical exposures. No clear associations were found, but claims were then made that the release of radioactive substances such as strontium 90 from the St Lucie nuclear power station, which began operating in 1976, might have played a role. To test the plausibility of this hypothesis, we extended by 17 years a previous study of county mortality conducted by the National Cancer Institute. Rates of total cancer, leukaemia and cancer of brain and other nervous tissue in children and across all ages in St Lucie County were evaluated with respect to the years before and after the nuclear power station began operation and contrasted with rates in two similar counties in Florida (Polk and Volusia). Over the prolonged period 1950-2000, no unusual patterns of childhood cancer mortality were found for St Lucie County as a whole. In particular, no unusual patterns of childhood cancer mortality were seen in relation to the start-up of the St Lucie nuclear power station in 1976. Further, there were no significant differences in mortality between the study and comparison counties for any cancer in the time period after the power station was in operation. Relative rates for all childhood cancers and for childhood leukaemia were higher before the nuclear facility began operating than after, while rates of brain and other nervous tissue cancer were slightly lower in St Lucie County than in the two comparison counties for both time periods. Although definitive conclusions cannot be drawn from descriptive studies, these data provide no support for the hypothesis that the operation of the St Lucie nuclear power station has adversely affected the cancer mortality experience of county residents.

  5. 76 FR 25378 - Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station, Units 2 and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-04

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station, Units 2 and... Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, located in...

  6. 75 FR 6071 - Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station Units 2 and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-05

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station Units 2 and 3... Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3...

  7. 77 FR 21593 - V. C. Summer Nuclear Station, Units 2 and 3 Combined Licenses and Record of Decision

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-10

    ... COMMISSION V. C. Summer Nuclear Station, Units 2 and 3 Combined Licenses and Record of Decision AGENCY... Evaluation Report for Combined Licenses for Virgil C. Summer Nuclear Station, Units 2 and 3'' ML11098A044 NUREG-1939, Vol 1, ``Final Environmental Impact Statement for Combined Licenses for Virgil C....

  8. 76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-29

    ... COMMISSION [Docket Nos. 50-528, 50-529, 50-530; NRC-2009-0012 Arizona Public Service Company, Palo Verde... of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS). Renewed Facility Operating... Palo Verde Nuclear Generating Station,'' issued January 2011, discusses the Commission's...

  9. 75 FR 8149 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-23

    ... COMMISSION Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3... Verde Nuclear Generating Station (PVNGS, the facility), Units 1, 2, and 3, respectively, located in... different resources than those previously considered in the Final Environmental Statement for the Palo...

  10. Accident at the Fukushima Dai-ichi nuclear power stations of TEPCO--outline & lessons learned.

    PubMed

    Tanaka, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others.

  11. Sodium coolant purification systems for a nuclear power station equipped with a BN-1200 reactor

    NASA Astrophysics Data System (ADS)

    Alekseev, V. V.; Kovalev, Yu. P.; Kalyakin, S. G.; Kozlov, F. A.; Kumaev, V. Ya.; Kondrat'ev, A. S.; Matyukhin, V. V.; Pirogov, E. P.; Sergeev, G. P.; Sorokin, A. P.; Torbenkova, I. Yu.

    2013-05-01

    Both traditional coolant purification methods (by means of traps and sorbents for removing cesium), the use of which supported successful operation of nuclear power installations equipped with fast-neutron reactors with a sodium coolant, and the possibility of removing oxygen from sodium through the use of hot traps are analyzed in substantiating the purification system for a nuclear power station equipped with a BN-1200 reactor. It is shown that a cold trap built into the reactor vessel must be a mandatory component of the reactor plant primary coolant circuit's purification system. The use of hot traps allows oxygen to be removed from the sodium coolant down to permissible concentrations when the nuclear power station operates in its rated mode. The main lines of works aimed at improving the performance characteristics of cold traps are suggested based on the results of performed investigations.

  12. Key points of condenser refurbishment illustrated by our experience on Russian technology nuclear power stations

    SciTech Connect

    Somville, C.

    1998-07-01

    In 1990, the refurbishment of the condensers of the VVER 440 MW LOVIISA 2 Finnish power station was the first reference of GEC ALSTHOM Delas on a Russian type nuclear power station, covering the optimization studies, technical and-economical choices, manufacture and site operations. The current contract for the condenser renovation of the 4 units of the VVER 440 MW PAKS Hungarian power station goes even further through an investment of this company in a local manufacturing installation and a significant participation of the local industry. Their expertise has helped reducing site operation times from 28 days for one condenser of one Loviisa unit, to 26 days for two condensers of one Paks unit. This paper describes the various aspects and the improvements brought for both operations and highlights the technical and economical key advantages of a condenser renovation (quick return on investment, better performances, reliability and life extension of the power station).

  13. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    SciTech Connect

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated

  14. Progress on the decommissioning of Zion nuclear generating station

    SciTech Connect

    Moloney, B. P.; Hess, J.

    2013-07-01

    The decommissioning of the twin 1040 MWe PWRs at Zion, near Chicago USA is a ground breaking programme. The original owner, Exelon Nuclear Corporation, transferred the full responsibility for reactor dismantling and site license termination to a subsidiary of EnergySolutions. The target end state of the Zion site for return to Exelon will be a green field with the exception of the dry fuel storage pad. In return, ZionSolutions has access to the full value of the decommissioning trust fund. There are two potential attractions of this model: lower overall cost and significant schedule acceleration. The Zion programme which commenced in September 2010 is designed to return the cleared site with an Independent Spent Fuel Storage Installation (ISFSI) pad in 2020, 12 years earlier than planned by Exelon. The overall cost, at $500 M per full size power reactor is significantly below the long run trend of $750 M+ per PWR. Implementation of the accelerated programme has been underway for nearly three years and is making good progress. The programme is characterised by numerous projects proceeding in parallel. The critical path is defined by the inspection and removal of fuel from the pond and transfer into dry fuel storage casks on the ISFSI pad and completion of RPV segmentation. Fuel loading is expected to commence in mid- 2013 with completion in late 2014. In parallel, ZionSolutions is proceeding with the segmentation of the Reactor Vessel (RV) and internals in both Units. Removal of large components from Unit 1 is underway. Numerous other projects are underway or have been completed to date. They include access openings into both containments, installation of heavy lift crane capacity, rail upgrades to support waste removal from the site, radiological characterization of facilities and equipment and numerous related tasks. As at February 2013, the programme is just ahead of schedule and within the latest budget. The paper will provide a fuller update. The first two

  15. Development of Standard Station Interface for Comprehensive Nuclear Test Ban Treaty Organistation Monitoring Networks

    NASA Astrophysics Data System (ADS)

    Dricker, I. G.; Friberg, P.; Hellman, S.

    2001-12-01

    Under the contract with the CTBTO, Instrumental Software Technologies Inc., (ISTI) has designed and developed a Standard Station Interface (SSI) - a set of executable programs and application programming interface libraries for acquisition, authentication, archiving and telemetry of seismic and infrasound data for stations of the CTBTO nuclear monitoring network. SSI (written in C) is fully supported under both the Solaris and Linux operating systems and will be shipped with fully documented source code. SSI consists of several interconnected modules. The Digitizer Interface Module maintains a near-real-time data flow between multiple digitizers and the SSI. The Disk Buffer Module is responsible for local data archival. The Station Key Management Module is a low-level tool for data authentication and verification of incoming signatures. The Data Transmission Module supports packetized near-real-time data transmission from the primary CTBTO stations to the designated Data Center. The AutoDRM module allows transport of seismic and infrasound signed data via electronic mail (auxiliary station mode). The Command Interface Module is used to pass the remote commands to the digitizers and other modules of SSI. A station operator has access to the state-of-health information and waveforms via an the Operator Interface Module. Modular design of SSI will allow painless extension of the software system within and outside the boundaries of CTBTO station requirements. Currently an alpha version of SSI undergoes extensive tests in the lab and onsite.

  16. License Amendment Request for Storing Exelon Sister Nuclear Stations Class B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620

    SciTech Connect

    Azar, Miguel; Gardner, Donald A.; Taylor, Edward R.

    2013-07-01

    Exelon Nuclear (Exelon) designed and constructed an Interim Radwaste Storage Facility (IRSF) in the mid-1980's at LaSalle County Nuclear Station (LaSalle). The facility was designed to store low-level radioactive waste (LLRW) on an interim basis, i.e., up to five years. The primary reason for the IRSF was to offset lack of disposal in case existing disposal facilities, such as the Southeast Compact's Barnwell Disposal Facility in Barnwell, South Carolina, ceased accepting radioactive waste from utilities not in the Southeast Compact. Approximately ninety percent of the Radwaste projected to be stored in the LaSalle IRSF in that period of time was Class A, with the balance being Class B/C waste. On July 1, 2008 the Barnwell Disposal Facility in the Southeast Compact closed its doors to out of- compact Radwaste, which precluded LaSalle from shipping Class B/C Radwaste to an outside disposal facility. Class A waste generated by LaSalle is still able to be disposed at the 'Envirocare of Utah LLRW Disposal Complex' in Clive, Utah. Thus the need for utilizing the LaSalle IRSF for storing Class B/C Radwaste for an extended period, perhaps life-of-plant or more became apparent. Additionally, other Exelon Midwest nuclear stations located in Illinois that did not build an IRSF heretofore also needed extended Radwaste storage. In early 2009, Exelon made a decision to forward Radwaste from the Byron Nuclear Station (Byron), Braidwood Nuclear Station (Braidwood), and Clinton Nuclear Station (Clinton) to LaSalle's IRSF. As only Class B/C Radwaste would need to be forwarded to LaSalle, the original volumetric capacity of the LaSalle IRSF was capable of handling the small number of additional expected shipments annually from the Exelon sister nuclear stations in Illinois. Forwarding Class B/C Radwaste from the Exelon sister nuclear stations in Illinois to LaSalle would require an amendment to the LaSalle Station operating license. Exelon submitted the License Amendment Request

  17. Environmental Assessment of Installation Development at McGuire Air Force Base, New Jersey

    DTIC Science & Technology

    2008-02-01

    support McGuire AFB. In addition, morale and welfare projects that are a critical part of supporting the warfighter are included. Continued development... critical elements of the human environment that are mandated for review by Executive Order (EO), regulation, or policy. Appendix B contains examples of...layers that are isolated for short distances by interbedded silt and clay (MAFB 2001, MAFB 2002). The PRM has received a critical rating by the NJDEP

  18. 78 FR 6839 - Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3 Denial of Amendment to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-31

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3 Denial of Amendment to Facility Operating License AGENCY: Nuclear Regulatory Commission. ACTION: Denial; opportunity to request...

  19. 78 FR 41425 - In the Matter of Duke Energy Carolinas, LLC; (Oconee Nuclear Station, Units 1, 2, and 3...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-10

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY...; EA-13-010] In the Matter of Duke Energy Carolinas, LLC; (Oconee Nuclear Station, Units 1, 2, and 3... Facility Operating License Nos. DPR-38, DPR-47, and DPR-55 issued by the U.S. Nuclear Regulatory...

  20. 78 FR 47795 - In the Matter of Entergy Nuclear Generation Company Pilgrim Power Station Independent Spent Fuel...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-06

    .... Licensees whose ISFSI is collocated with a power reactor may choose to comply with the U.S. Nuclear... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION In the Matter of Entergy Nuclear Generation Company Pilgrim Power Station Independent Spent...

  1. 78 FR 41805 - In the Matter of FirstEnergy Nuclear Operating Company; Beaver Valley Power Station; Independent...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-11

    ... COMMISSION In the Matter of FirstEnergy Nuclear Operating Company; Beaver Valley Power Station; Independent... fingerprinting for unescorted access to FirstEnergy Nuclear Operating Company. FOR FURTHER INFORMATION CONTACT: L..., the NRC is providing notice in the matter of FirstEnergy Nuclear Operating Company, Beaver Valley...

  2. 78 FR 45987 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-30

    ... COMMISSION Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to the Primary Sampling System AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and combined... COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe...

  3. 78 FR 45989 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-30

    ... COMMISSION Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to the Primary Sampling System AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and combined... COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe...

  4. 78 FR 11904 - Zion Nuclear Power Station, Units 1 and 2; ZionSolutions, LLC; Consideration of Indirect Transfer

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-20

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Zion Nuclear Power Station, Units 1 and 2; ZionSolutions, LLC; Consideration of Indirect Transfer... the indirect transfer of Facility Operating License Nos. DPR-39 and DPR-48 for Zion Nuclear...

  5. Benefits of 20 kHz PMAD in a nuclear space station

    NASA Technical Reports Server (NTRS)

    Sundberg, Gale R.

    1987-01-01

    Compared to existing systems, high frequency ac power provides higher efficiency, lower cost, and improved safety benefits. The 20 kHz power system has exceptional flexibility, is inherently user friendly, and is compatible with all types of energy sources; photovoltaic, solar dynamic, rotating machines and nuclear. A 25 kW, 20 kHz ac power distribution system testbed was recently (1986) developed. The testbed possesses maximum flexibility, versatility, and transparency to user technology while maintaining high efficiency, low mass, and reduced volume. Several aspects of the 20 kHz power management and distribution (PMAD) system that have particular benefits for a nuclear power Space Station are discussed.

  6. Benefits of 20 kHz PMAD in a nuclear space station

    NASA Technical Reports Server (NTRS)

    Sundberg, Gale R.

    1987-01-01

    Compared to existing systems, high frequency ac power provides higher efficiency, lower cost, and improved safety benefits. The 20 kHz power system has exceptional flexibility, is inherently user friendly, and is compatible with all types of energy sources; photovoltaic, solar dynamic, rotating machines and nuclear. A 25 kW, 20 kHz ac power distribution system testbed was recently (1986) developed. The testbed possesses maximum flexibility, versatility, and transparency to user technology while maintaining high efficiency, low mass, and reduced volume. Several aspects of the 20 kHz power management and distribution (PMAD) system that have particular benefits for a nuclear power Space Station are discussed.

  7. Chernobyl Doses. Volume 3. Habitat and Vegetation Near the Chernobyl Nuclear Reactor Station

    DTIC Science & Technology

    1993-01-01

    AD-A260 167 A lexandria, VA 22310-3398 l,* Defense Nuclear Agency Alexandria, VA 22310-.3398 DNA-TR-92-37-V3 Chernobyl Doses, Volume 3-Habitat and...Vegetation Near the Chernobyl Nuclear Reactor Station DTIC~ ELECTF. Elizabeth L. Painter i IN•9 199EIF F. Ward Whicker JAN % 93f Pacific-Sierra...930101 Technical 870929- 920228 4. TITLE AND SUBTITLE 5. FUNDING NUMBERS Chernobyl Doses C - DNA 001-87-C-0104 Volume 3-Habitat and Vegetation Near the

  8. Implicit attitudes toward nuclear power and mobile phone base stations: support for the affect heuristic.

    PubMed

    Siegrist, Michael; Keller, Carmen; Cousin, Marie-Eve

    2006-08-01

    The implicit association test (IAT) measures automatic associations. In the present research, the IAT was adapted to measure implicit attitudes toward technological hazards. In Study 1, implicit and explicit attitudes toward nuclear power were examined. Implicit measures (i.e., the IAT) revealed negative attitudes toward nuclear power that were not detected by explicit measures (i.e., a questionnaire). In Study 2, implicit attitudes toward EMF (electro-magnetic field) hazards were examined. Results showed that cell phone base stations and power lines are judged to be similarly risky and, further, that base stations are more closely related to risk concepts than home appliances are. No differences between experts and lay people were observed. Results of the present studies are in line with the affect heuristic proposed by Slovic and colleagues. Affect seems to be an important factor in risk perception.

  9. Accumulation of /sup 137/Cs in commercial fish of the Belyarsk nuclear power station cooling supply

    SciTech Connect

    Trapeznikova, V.N.; Kulikov, N.V.; Trapeznikov, A.V.

    1984-07-01

    Results are presented of a comparative study of the accumulation of /sup 137/Cs in basic species of commercial fish of the Beloyarsk reservoir which is used as the cooling supply for the Beloyarsk nuclear power station. Possible reasons for interspecies differences in accumulation of the radionuclide are indicated, and the increased accumulation of /sup 137/Cs by free-living fish in the zone of heated water effluent from the station and the reduced accumulation of the emitter in carp, which are cultivated on artificial food in cages, are noted. Levels of the content of the radionuclide are compared in roach and farm carp from the cooling supplies of the Beloyarsk station and the Reftinsk power plant in the Urals.

  10. Confirmatory Survey Results for the Reactor Building Dome Upper Surfaces, Rancho Saco Nuclear Generating Station

    SciTech Connect

    Wade C. Adams

    2006-10-25

    Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006.

  11. [Evaluating psychophysiologic adaptation state in operators of Bilibino nuclear power station].

    PubMed

    Isaeva, N A; Torubarov, F S; Denisova, E A; Zvereva, Z F; Koronotova, M A

    2014-01-01

    The study revealed that 60% operators of Bilibino nuclear power station suffer from psychosomatic diseases, 41.7% of them are assigned to occupational group of workers, and major part of the examinees with psychosomatic diseases (45.82%) are aged 41-50, high integral level ofpsychophysiologic adaptation is revealed in 5 examinees (12.5%), medium integral level--in 12 examinees (30%). Lower integral level of psychophysiologic adaptation manifested in decrease in psychophysiologic and physiologic levels.

  12. Science in Flux: NASA's Nuclear Program at Plum Brook Station 1955-2005

    NASA Technical Reports Server (NTRS)

    Bowles, Mark D.

    2006-01-01

    Science in Flux traces the history of one of the most powerful nuclear test reactors in the United States and the only nuclear facility ever built by NASA. In the late 1950's NASA constructed Plum Brook Station on a vast tract of undeveloped land near Sandusky, Ohio. Once fully operational in 1963, it supported basic research for NASA's nuclear rocket program (NERVA). Plum Brook represents a significant, if largely forgotten, story of nuclear research, political change, and the professional culture of the scientists and engineers who devoted their lives to construct and operate the facility. In 1973, after only a decade of research, the government shut Plum Brook down before many of its experiments could be completed. Even the valiant attempt to redefine the reactor as an environmental analysis tool failed, and the facility went silent. The reactors lay in costly, but quiet standby for nearly a quarter-century before the Nuclear Regulatory Commission decided to decommission the reactors and clean up the site. The history of Plum Brook reveals the perils and potentials of that nuclear technology. As NASA, Congress, and space enthusiasts all begin looking once again at the nuclear option for sending humans to Mars, the echoes of Plum Brook's past will resonate with current policy and space initiatives.

  13. Modeling of a horizontal steam generator for the submerged nuclear power station concept

    SciTech Connect

    Palmrose, D.E.; Herring, J.S.

    1993-01-01

    A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube's inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

  14. Modeling of a horizontal steam generator for the submerged nuclear power station concept

    SciTech Connect

    Palmrose, D.E.; Herring, J.S.

    1993-05-01

    A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube`s inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

  15. The effects of solar-geomagnetically induced currents on electrical systems in nuclear power stations

    SciTech Connect

    Subudhi, M.; Carroll, D.P.; Kasturi, S.

    1994-01-01

    This report presents the results of a study to evaluate the potential effects of geomagnetically induced currents (GICs) caused by the solar disturbances on the in-plant electrical distribution system and equipment in nuclear power stations. The plant-specific electrical distribution system for a typical nuclear plant is modeled using the ElectroMagnetic Transient Program (EMTP). The computer model simulates online equipment and loads from the station transformer in the switchyard of the power station to the safety-buses at 120 volts to which all electronic devices are connected for plant monitoring. The analytical model of the plant`s electrical distribution system is studied to identify the transient effects caused by the half-cycle saturation of the station transformers due to GIC. This study provides results of the voltage harmonics levels that have been noted at various electrical buses inside the plant. The emergency circuits appear to be more susceptible to high harmonics due to the normally light load conditions. In addition to steady-state analysis, this model was further analyzed simulating various plant transient conditions (e.g., loss of load or large motor start-up) occurring during GIC events. Detail models of the plant`s protective relaying system employed in bus transfer application were included in this model to study the effects of the harmonic distortion of the voltage input. Potential harmonic effects on the uniterruptable power system (UPS) are qualitatively discussed as well.

  16. International remote monitoring project Argentina Nuclear Power Station Spent Fuel Transfer Remote Monitoring System

    SciTech Connect

    Schneider, S.; Lucero, R.; Glidewell, D.

    1997-08-01

    The Autoridad Regulataria Nuclear (ARN) and the United States Department of Energy (DOE) are cooperating on the development of a Remote Monitoring System for nuclear nonproliferation efforts. A Remote Monitoring System for spent fuel transfer will be installed at the Argentina Nuclear Power Station in Embalse, Argentina. The system has been designed by Sandia National Laboratories (SNL), with Los Alamos National Laboratory (LANL) and Oak Ridge National Laboratory (ORNL) providing gamma and neutron sensors. This project will test and evaluate the fundamental design and implementation of the Remote Monitoring System in its application to regional and international safeguards efficiency. This paper provides a description of the monitoring system and its functions. The Remote Monitoring System consists of gamma and neutron radiation sensors, RF systems, and video systems integrated into a coherent functioning whole. All sensor data communicate over an Echelon LonWorks Network to a single data logger. The Neumann DCM 14 video module is integrated into the Remote Monitoring System. All sensor and image data are stored on a Data Acquisition System (DAS) and archived and reviewed on a Data and Image Review Station (DIRS). Conventional phone lines are used as the telecommunications link to transmit on-site collected data and images to remote locations. The data and images are authenticated before transmission. Data review stations will be installed at ARN in Buenos Aires, Argentina, ABACC in Rio De Janeiro, IAEA Headquarters in Vienna, and Sandia National Laboratories in Albuquerque, New Mexico. 2 refs., 2 figs.

  17. Evaluating the thermodynamic efficiency of hydrogen cycles at wet-steam nuclear power stations

    NASA Astrophysics Data System (ADS)

    Aminov, R. Z.; Egorov, A. N.

    2013-04-01

    Various schematic solutions for implementing a hydrogen cycle on the basis of thermal and nuclear power stations are discussed. Different approaches to construction of cooling systems for the combustion chambers used in hydrogen-oxygen steam generators are described. An example of solution is given in which the combustion chamber is cooled by steam, which is the most efficient one in the thermodynamic respect. Results from an assessment of the thermodynamic efficiency of hydrogen cycles organized on the basis of the power unit of a wet-steam nuclear power station equipped with a K-1000-60/1500 turbine are presented. The thermodynamic efficiency of different schematic and parametric versions of implementing a hydrogen cycle, including those with a satellite turbine operating on displaced steam, is carried out. It is shown that the use of satellite turbines allows the power output and efficiency of the power unit of a wet-steam nuclear power station to be upgraded in a reliable and effective manner.

  18. [Water-soluble anions of atmosphere on Tianwan nuclear power station].

    PubMed

    Zhao, Heng-Qiang; He, Ying; Zheng, Xiao-Ling; Chen, Fa-Rong; Pang, Shi-Ping; Wang, Cai-Xia; Wang, Xiao-Ru

    2010-11-01

    Three major water-soluble anions (Cl-, SO4(2-) and NO3-) in the atmosphere of the Tianwan nuclear power station in Lianyungang were determined by ion chromatography from June 2005 to May 2006. The results showed that the annual average concentration of Cl-, SO4(2-) and NO3- in the atmosphere of Tianwan nuclear power station was (33.12 +/- 53.63) microg x m(-3), (53.34 +/- 30.34) microg x m(-3) and (8.34 +/- 4.47) microg x m(-3), respectively. The concentrations of the three water-soluble anions showed evident trend of seasonal variation. The concentrations of Cl-, SO4(2-) reached the highest level in summer and the lowest level in winter, while the concentration of NO3- in autumn and winter was higher than those in summer and spring. Meteorological parameters such as wind direction, wind speed, temperature and relative humidity were studied and showed definite influence to the anions concentration of the atmosphere. This is the first simultaneous monitoring of corrosive anions in the atmosphere of Chinese coastal nuclear power plant, and it will provide basis for the prevention of marine atmospheric corrosion, which will ensure the safely operating of our nuclear power industry.

  19. The Satellite Nuclear Power Station - An option for future power generation.

    NASA Technical Reports Server (NTRS)

    Williams, J. R.; Clement, J. D.

    1973-01-01

    A new concept in nuclear power generation is being explored which essentially eliminates major objections to nuclear power. The Satellite Nuclear Power Station, remotely operated in synchronous orbit, would transmit power safely to the ground by a microwave beam. Fuel reprocessing would take place in space and no radioactive materials would ever be returned to earth. Even the worst possible accident to such a plant should have negligible effect on the earth. An exploratory study of a satellite nuclear power station to provide 10,000 MWe to the earth has shown that the system could weigh about 20 million pounds and cost less than $1000/KWe. An advanced breeder reactor operating with an MHD power cycle could achieve an efficiency of about 50% with a 1100 K radiator temperature. If a hydrogen moderated gas core reactor is used, its breeding ratio of 1.10 would result in a fuel doubling time of a few years. A rotating fluidized bed or NERVA type reactor might also be used. The efficiency of power transmission from synchronous orbit would range from 70% to 80%.

  20. The Satellite Nuclear Power Station - An option for future power generation.

    NASA Technical Reports Server (NTRS)

    Williams, J. R.; Clement, J. D.

    1973-01-01

    A new concept in nuclear power generation is being explored which essentially eliminates major objections to nuclear power. The Satellite Nuclear Power Station, remotely operated in synchronous orbit, would transmit power safely to the ground by a microwave beam. Fuel reprocessing would take place in space and no radioactive materials would ever be returned to earth. Even the worst possible accident to such a plant should have negligible effect on the earth. An exploratory study of a satellite nuclear power station to provide 10,000 MWe to the earth has shown that the system could weigh about 20 million pounds and cost less than $1000/KWe. An advanced breeder reactor operating with an MHD power cycle could achieve an efficiency of about 50% with a 1100 K radiator temperature. If a hydrogen moderated gas core reactor is used, its breeding ratio of 1.10 would result in a fuel doubling time of a few years. A rotating fluidized bed or NERVA type reactor might also be used. The efficiency of power transmission from synchronous orbit would range from 70% to 80%.

  1. Mathematical modelling of thermal-plume interaction at Waterford Nuclear Power Station

    SciTech Connect

    Tsai, S.Y.H.

    1981-01-01

    The Waldrop plume model was used to analyze the mixing and interaction of thermal effluents in the Mississippi River resulting from heated-water discharges from the Waterford Nuclear Power Station Unit 3 and from two nearby fossil-fueled power stations. The computer program of the model was modified and expanded to accommodate the multiple intake and discharge boundary conditions at the Waterford site. Numerical results of thermal-plume temperatures for individual and combined operation of the three power stations were obtained for typical low river flow (200,000 cfs) and maximum station operating conditions. The predicted temperature distributions indicated that the surface jet discharge from Waterford Unit 3 would interact with the thermal plumes produced by the two fossil-fueled stations. The results also showed that heat recirculation between the discharge of an upstream fossil-fueled plant and the intake of Waterford Unit 3 is to be expected. However, the resulting combined temperature distributions were found to be well within the thermal standards established by the state of Louisiana.

  2. International Remote Monitoring Project Embalse Nuclear Power Station, Argentina Embalse Remote Monitoring System

    SciTech Connect

    Schneider, Sigfried L.; Glidewell, Donnie D.; Bonino, Anibal; Bosler, Gene; Mercer, David; Maxey, Curt; Vones, Jaromir; Martelle, Guy; Busse, James; Kadner, Steve; White, Mike; Rovere, Luis

    1999-07-21

    The Autoridad Regulatoria Nuclear of Argentina (ARN), the International Atomic Energy Agency (IAEA), ABACC, the US Department of Energy, and the US Support Program POTAS, cooperated in the development of a Remote Monitoring System for nuclear nonproliferation efforts. This system was installed at the Embalse Nuclear Power Station last year to evaluate the feasibility of using radiation sensors in monitoring the transfer of spent fuel from the spent fuel pond to dry storage. The key element in this process is to maintain continuity of knowledge throughout the entire transfer process. This project evaluated the fundamental design and implementation of the Remote Monitoring System in its application to regional and international safeguard efficiency. New technology has been developed to enhance the design of the system to include storage capability on board sensor platforms. This evaluation has led to design enhancements that will assure that no data loss will occur during loss of RF transmission of the sensors.

  3. 75 FR 7628 - Davis-Besse Nuclear Power Station; Notice of Consideration of Issuance of Amendment to Facility...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-22

    ... COMMISSION Davis-Besse Nuclear Power Station; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a... determination that the amendment request involves no significant hazards consideration. Under the...

  4. Determining the power performance effect from modernization of power equipment and process systems at a nuclear power station

    NASA Astrophysics Data System (ADS)

    Khomenok, L. A.; Kruglikov, P. A.; Smolkin, Yu. V.; Sokolov, K. V.

    2012-05-01

    The main stages of a calculation and experimental analysis of measures aimed at achieving better power performance of a nuclear power station and a procedure for carrying out such analysis are considered. The results of a calculated and experimental assessment of the power-performance effect from modernization of the moisture separators-steam superheaters used in turbine generators Nos. 7 and 8 of Unit 4 at the Leningrad nuclear power station are presented.

  5. Characteristics of neurological status and the electroencephalogram in nuclear power station control operators.

    PubMed

    Laskova, I V; Tret'yakova, E E

    2010-05-01

    A total of 105 control operators at the Kursk nuclear power station were studied: 45 after working shifts (study group) and 60 on rest days (reference group). These investigations showed that operators' work shifts had significant influences on the functional state of the nervous system, promoting the appearance or exacerbation of autonomic dysfunction. In some cases, work shifts increased arterial blood pressure to risk levels for the development of cerebrovascular disease. The effects of nuclear power station operators' work shifts on brain bioelectrical activity included a decrease in the proportion of unaltered EEG traces, along with increases in the spectral power densities of the alpha rhythm in the parietal leads and the theta rhythm in the posterior temporal and parietal leads. The origin of these changes may be related to both fatigue and the effects of adverse industrial factors. It is suggested that clinical observation of power station operators should be supplemented by assessments of autonomic dysfunction and measurement of the spectral power densities of the alpha and theta rhythms in the parietal and posterior temporal leads.

  6. A radiological assessment of nuclear power and propulsion operations near Space Station Freedom

    NASA Technical Reports Server (NTRS)

    Bolch, Wesley E.; Thomas, J. Kelly; Peddicord, K. Lee; Nelson, Paul; Marshall, David T.; Busche, Donna M.

    1990-01-01

    Scenarios were identified which involve the use of nuclear power systems in the vicinity of Space Station Freedom (SSF) and their radiological impact on the SSF crew was quantified. Several of the developed scenarios relate to the use of SSF as an evolutionary transportation node for lunar and Mars missions. In particular, radiation doses delivered to SSF crew were calculated for both the launch and subsequent return of a Nuclear Electric Propulsion (NEP) cargo vehicle and a Nuclear Thermal Rocket (NTR) personnel vehicle to low earth orbit. The use of nuclear power on co-orbiting platforms and the storage and handling issues associated with radioisotope power systems were also explored as they relate to SSF. A central philosophy in these analyses was the utilization of a radiation dose budget, defined as the difference between recommended dose limits from all radiation sources and estimated doses received by crew members from natural space radiations. Consequently, for each scenario examined, the dose budget concept was used to identify and quantify constraints on operational parameters such as launch separation distances, returned vehicle parking distances, and reactor shutdown times prior to vehicle approach. The results indicate that realistic scenarios do not exist which would preclude the use of nuclear power sources in the vicinity of SSF. The radiation dose to the SSF crew can be maintained at safe levels solely by implementing proper and reasonable operating procedures.

  7. Environmental radiological studies in 1989 near the Rancho Seco Nuclear Power Generating Station

    SciTech Connect

    Robison, W.L.; Wong, Kai M.; Jones, H.E.

    1990-11-01

    In December 1988, the Sacramento Municipal Utilities District (SMUD) asked the Lawrence Livermore National Laboratory's (LLNL) Environmental Sciences Division (ENV) to collect sediment, water,and fish samples downstream from the Rancho Seco Nuclear Power Generating Station for analysis of radionuclides to compare with results from earlier surveys in 1984 through 1987 (1--8). ENV was, however, asked to reduce the total number of sample collections to a minimum in this study because of financial constraints. The proposal ENV submitted for the 1989 Environmental Radiological Studies downstream of the Rancho Seco Nuclear Power Generating Station reflected this reduction, but we believe, nevertheless, the 1989 efforts do allow us to make some meaningful comparisons with the previous studies. Cesium-137 is the most significant radionuclide still observed downstream from the Rancho Seco Nuclear Power Plant. Only occasionally is {sup 134}Cs or {sup 60}CO observed. In 1989, the concentration of {sup 137}Cs in the water and fish decreased with distance from the plant to the same level that is was in 1987, and was lower than it had been from 1984 through 1986. The concentration ratio (CR) for {sup 137}Cs in fish is between 1000 and 1500, which is below the NRC default value of 2000. Physical mixing in the creek environment has moved the {sup 137}Cs deeper into the sediment column, thereby reducing the concentration in the top 12 cm relative to that in previous years. 8 refs., 18 figs., 9 tabs.

  8. 77 FR 11168 - In the Matter of Exelon Corporation; Constellation Energy Group, Inc.; Nine Mile Nuclear Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-24

    ... Exelon Corporation; Constellation Energy Group, Inc.; Nine Mile Nuclear Station, LLC; Nine Mile Point... Ventures), and Constellation Energy Nuclear Group, LLC (CENG), acting on behalf of itself, and the licensee..., Constellation Energy Group, Inc. (CEG), whereby CEG would be merged into Exelon and ownership of CEG's...

  9. 78 FR 47426 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-05

    ... shield building in order to support the current electrical loads required within containment. This... COMMISSION Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the Containment Structure for Additional Electrical Penetration Assemblies AGENCY: Nuclear Regulatory...

  10. 75 FR 14211 - Southern California Edison, San Onofre Nuclear Generating Station, Unit 2 and Unit 3; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern California Edison, San Onofre Nuclear Generating Station, Unit 2 and Unit 3; Exemption 1.0 Background Southern California Edison (SCE, the licensee) is the holder of the Facility...

  11. 75 FR 71152 - Southern California Edison; San Onofre Nuclear Generating Station, Unit 2 and Unit 3; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-22

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern California Edison; San Onofre Nuclear Generating Station, Unit 2 and Unit 3; Exemption 1.0 Background Southern California Edison (SCE, the licensee) is the holder of the Facility...

  12. 75 FR 9623 - Arizona Public Service Company, et al.; Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-03

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Arizona Public Service Company, et al.; Palo Verde Nuclear Generating Station, Units 1, 2, and 3... Facility Operating License Nos. NPF-41, NPF-51, and NPF- 74, which authorize operation of the Palo...

  13. 75 FR 15745 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-30

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3... Operating License Nos. NPF-41, NPF-51, and NPF-74, which authorize operation of the Palo Verde...

  14. Safety research of insulating materials of cable for nuclear power generating station

    NASA Technical Reports Server (NTRS)

    Lee, C. K.; Choi, J. H.; Kong, Y. K.; Chang, H. S.

    1988-01-01

    The polymers PE, EPR, PVC, Neoprene, CSP, CLPE, EP and other similar substances are frequently used as insulation and protective covering for cables used in nuclear power generating stations. In order to test these materials for flame retardation, environmental resistance, and cable specifications, they were given the cable normal test, flame test, chemical tests, and subjected to design analysis and loss of coolant accident tests. Material was collected on spark tests and actual experience standards were established through these contributions and technology was accumulated.

  15. Investigation on Main Radiation Source at Operation Floor of Fukushima Daiichi Nuclear Power Station Unit 4

    NASA Astrophysics Data System (ADS)

    Hirayama, Hideo; Kondo, Kenjiro; Suzuki, Seishiro; Hamamoto, Shimpei; Iwanaga, Kohei

    2017-09-01

    Pulse height distributions were measured using a LaBr3 detector set in a 1 cm lead collimator to investigate main radiation source at the operation floor of Fukushima Daiichi Nuclear Power Station Unit 4. It was confirmed that main radiation source above the reactor well was Co-60 from the activated steam dryer in the DS pool (Dryer-Separator pool) and that at the standby area was Cs-134 and Cs-137 from contaminated buildings and debris at the lower floor. Full energy peak count rate of Co-60 was reduced about 1/3 by 12mm lead sheet placed on the floor of the fuel handling machine.

  16. Estimating the efficiency from using hydrogen toppings at nuclear power stations

    NASA Astrophysics Data System (ADS)

    Portyankin, A. V.; Khrustalev, V. A.

    2011-09-01

    A low-cost version of modernizing a nuclear power station is considered in which the main profile (standard size) of the power unit is retained and insignificant changes are made in the turbine unit's operational parameters. These changes consist in that steam supplied to the high-pressure cylinder is subjected to slight initial superheating, and that that the design superheating of steam upstream of the low-pressure cylinder is increased to some extent. In addition, different versions that can be used for heating the working steam to the required temperatures in the H2/O2 steam generator's mixing chamber are analyzed.

  17. Radiation exposure to the orbiting lunar station and lunar surface related to reusable nuclear shuttle operations

    NASA Technical Reports Server (NTRS)

    Hutchinson, P. I.

    1972-01-01

    The radiation environment created by the Reusable Nuclear Vehicle (RNS) in performing its normal mission functions while in the lunar vicinity and the impact of that environment on the Orbiting Lunar Station (OLS) and/or the lunar surface are examined. Lunar surface exposures from the operating reactor were evaluated for both the arrival and departure burns and while there is little probability that manned bases would lie along the paths in which measurable exposures would be recorded, the analyses do indicate the need to consider this possibility in planning such operations. Conclusions supported by the analyses and recommended operational constraints for the RNS are presented.

  18. Safety research of insulating materials of cable for nuclear power generating station

    NASA Technical Reports Server (NTRS)

    Lee, C. K.; Choi, J. H.; Kong, Y. K.; Chang, H. S.

    1988-01-01

    The polymers PE, EPR, PVC, Neoprene, CSP, CLPE, EP and other similar substances are frequently used as insulation and protective covering for cables used in nuclear power generating stations. In order to test these materials for flame retardation, environmental resistance, and cable specifications, they were given the cable normal test, flame test, chemical tests, and subjected to design analysis and loss of coolant accident tests. Material was collected on spark tests and actual experience standards were established through these contributions and technology was accumulated.

  19. The {open_quotes}Dragon of Kovachitsa{close_quotes}: Local perceptions of radioactive pollution near the Kozlodui Nuclear Power Station (Bulgaria)

    SciTech Connect

    Konstantinov, Y.

    1995-03-01

    There is continuing uncertainty surrounding the safety of nuclear power stations in Eastern Europe, among them the one at Kozlodui, Bulgaria. It is argued in this paper that attempts on the part of the state to assert the safety of nuclear power stations are expressed in terms of an official {open_quotes}nuclear-safe{close_quotes} discourse, while the local inhabitants near the Kozlodui nuclear power station employ a vernacular mode of expression to explain possible radioactive pollution.

  20. The counter effects of the accident at Fukushima Dai-ichi nuclear power station

    NASA Astrophysics Data System (ADS)

    Murakami, Kenta

    2017-01-01

    The counter effects of the accident at the Fukushima Dai-ichi Nuclear Power Station are discussed in this paper. Though decommission and remediation have been conducted in the facility and surrounding area, ninety thousand residences near the facility are still under the evacuation order. Four nuclear power units have already restarted under the new regulatory framework, but two of them in Fukui prefecture stop the operation due to the provisional disposition declared by Ohtsu district court in Shiga prefecture. Reinforcement of the latter layer of the defense in depth has been improved in many ways. The improvement of decision-making process is very important in latter layers of the defense in depth, in contrast the plant behaviors are automatically decided based on their design in the prior layers.

  1. The AP1000{sup R} nuclear power plant innovative features for extended station blackout mitigation

    SciTech Connect

    Vereb, F.; Winters, J.; Schulz, T.; Cummins, E.; Oriani, L.

    2012-07-01

    Station Blackout (SBO) is defined as 'a condition wherein a nuclear power plant sustains a loss of all offsite electric power system concurrent with turbine trip and unavailability of all onsite emergency alternating current (AC) power system. Station blackout does not include the loss of available AC power to buses fed by station batteries through inverters or by alternate AC sources as defined in this section, nor does it assume a concurrent single failure or design basis accident...' in accordance with Reference 1. In this paper, the innovative features of the AP1000 plant design are described with their operation in the scenario of an extended station blackout event. General operation of the passive safety systems are described as well as the unique features which allow the AP1000 plant to cope for at least 7 days during station blackout. Points of emphasis will include: - Passive safety system operation during SBO - 'Fail-safe' nature of key passive safety system valves; automatically places the valve in a conservatively safe alignment even in case of multiple failures in all power supply systems, including normal AC and battery backup - Passive Spent Fuel Pool cooling and makeup water supply during SBO - Robustness of AP1000 plant due to the location of key systems, structures and components required for Safe Shutdown - Diverse means of supplying makeup water to the Passive Containment Cooling System (PCS) and the Spent Fuel Pool (SFP) through use of an engineered, safety-related piping interface and portable equipment, as well as with permanently installed onsite ancillary equipment. (authors)

  2. Elimination of redundant thermoluminescent dosemeter monitoring at Oyster Creek nuclear generating station

    SciTech Connect

    Schwartz, P.E.

    1989-01-01

    The Oyster Creek direct radiation monitoring network has long been operating using several time-scale measurements. This network is used to assess the radiation levels during normal plant operations as well as to set the background radiation levels used to determine the radiological impact of a nonroutine release of radioactivity from the plant. Through analysis of the behavior of the monthly and quarterly activity of several types of direct radiation monitoring, the successful elimination of redundant and artificially high measurement techniques has been done in concert with providing the community with most efficient direct radiation monitoring methods. Dose rates from external radiation sources are measured around licensed U.S. Nuclear Regulatory Commission (NRC) facilities using passive detectors known as thermoluminescent dosimeters (TLDs). These detectors provide a quantitative measurement of the radiation levels in the are in which they are placed. The detected radiation could be the result of cosmic or naturally occurring origin in the air and on the ground, prior nuclear weapons testing, and activity from a nuclear facility. This paper describes the TLD network placed around the Oyster Creek nuclear generating station (OCNGS) and the comparisons between TLDs of different manufacturers and of different resident times and the successful elimination of the less accurate monthly TLD for the purpose of cost containment.

  3. A Muon Tomography Station with GEM Detectors for Nuclear Threat Detection

    NASA Astrophysics Data System (ADS)

    Staib, Michael; Gnanvo, Kondo; Grasso, Leonard; Hohlmann, Marcus; Locke, Judson; Costa, Filippo; Martoiu, Sorin; Muller, Hans

    2011-10-01

    Muon tomography for homeland security aims at detecting well-shielded nuclear contraband in cargo and imaging it in 3D. The technique exploits multiple scattering of atmospheric cosmic ray muons, which is stronger in dense, high-Z nuclear materials, e.g. enriched uranium, than in low-Z and medium-Z shielding materials. We have constructed and operated a compact Muon Tomography Station (MTS) that tracks muons with six to ten 30 cm x 30 cm Triple Gas Electron Multiplier (GEM) detectors placed on the sides of a 27-liter cubic imaging volume. The 2D strip readouts of the GEMs achieve a spatial resolution of ˜130 μm in both dimensions and the station is operated at a muon trigger rate of ˜20 Hz. The 1,536 strips per GEM detector are read out with the first medium-size implementation of the Scalable Readout System (SRS) developed specifically for Micro-Pattern Gas Detectors by the RD51 collaboration at CERN. We discuss the performance of this MTS prototype and present experimental results on tomographic imaging of high-Z objects with and without shielding.

  4. Satellite Remote Sensing of the Thermal Plume from the Daya Bay Nuclear Power Station, China

    NASA Astrophysics Data System (ADS)

    Tang, D.; Kester, D.; Wang, Z.; Lian, J.

    The 1800 megawatt Daya Bay Nuclear Power Station (DBNPS), China's first nuclear power station, is located on the coast of the South China Sea. DBNPS discharges 29 million m3 y -1 of warm water from its cooling system into Daya Bay, which could have ecological consequences. This study examines satellite sea surface temperature data and shipboard water column measure ments from Daya Bay. Sea surface temperatures were derived from the Advanced Very High Resolution Radiometer (AVHRR) onboard National Oceanic and Atmospheric Administration (NOAA) polar orbiting satellites during November 1997 to February 1999. A total of 2,905 images were examined. Among those images, 342 have sufficient quality for quantitative analysis. Water temperature, salinity, dissolved oxygen, ammonia, and chlorophyll data from ship surveys were also examined. The AVHRR data show a seasonal pattern of thermal plumes in Daya Bay. During the winter months (December to March), the thermal plume is localized to an area within a few km of the power plant, and the temperature difference between the plume and non-plume areas is about 1.5 oC. During the summer and fall months (May to November), there is a larger thermal plume extending 8 10 km south along the coast from DBNPS, and the temperature- change is about 1.0 oC. These results are consistent with field observations at 12 sampling stations in Daya Bay. The strong seasonal difference in the thermal plume is related to vertical mixing of the water column in winter and stratification in summer. Further investigations are needed to determine if there are biological effects of the Daya Bay thermal plume.

  5. The May 18, 1998 Indian Nuclear Test Seismograms at station NIL

    SciTech Connect

    Walter, W R; Rodgers, A J; Bowers, D; Selby, N

    2005-04-11

    The last underground nuclear tests were conducted by India and Pakistan in May 1998. Although the Comprehensive Test Ban Treaty has not entered force, an International Monitoring System (IMS), established by the treaty is nearing completion. This system includes 170 seismic stations, a number of them originally established by IRIS. The station IRIS station NIL (Nilore, Pakistan) is close to a planned IMS primary station and recorded some very interesting seismograms from the May 18, 1998 Indian test. We carefully calibrated the path to NIL using a prior Mw 4.4 that occurred on April 4, 1995 about 110 km north of the Indian test site. We used joint epicentral location techniques along with teleseismic P waves and regional surface waves to fix the epicenter, depth, mechanism and moment of this event. From these we obtained a velocity model for the path to NIL and created explosion synthetic seismograms to compare with the data. Interestingly the observed Rayleigh waves are reversed, consistent with an implosion rather than an explosion source. The preferred explanation is that the explosion released tectonic stress near the source region, which can be modeled as a thrust earthquake of approximate Mw 4.0 plus a pure explosion. This tectonic release is sufficient to completely dominate the Rayleigh waves and produce the observed signal (Walter et al. 2005). We also examined the explosion at high frequencies of 6 6-8 Hz where many studies have shown that relative P/S amplitudes can discriminate explosions from a background of earthquakes (Rodgers and Walter, 2002). Comparing with the April 4 1995 earthquake we see the classic difference of relatively large P/S values for the explosion compared to the earthquakes despite the complication of the large tectonic release during the explosion.

  6. A radiological assessment of space nuclear power operations near Space Station Freedom

    NASA Technical Reports Server (NTRS)

    Stevenson, Steve

    1990-01-01

    In order to accomplish NASA's more ambitious exploration goals, nuclear reactors may be used in the vicinity of Space Station Freedom (SSF) either as power sources for coorbiting platforms or as part of the propulsion system for departing and returning personnel or cargo vehicles. This study identifies ranges of operational parameters, such as parking distances and reactor cooldown times, which would reasonably guarantee that doses to the SSF crew from all radiation sources would be below guidelines recently recommended by the National Council of Radiation Protection and Measurements. The specific scenarios considered include: (1) the launch and return of a nuclear electric propulsion vehicle, (2) the launch and return of a nuclear thermal rocket vehicle, (3) the operation of an SP-100 class reactor on a coorbiting platform, (4) the activation of materials near operating reactors, (5) the storage and handling of radioisotope thermal generator units, and (6) the storage and handling of fresh and previously operated reactors. Portable reactor shield concepts were examined for relaxing the operational constraints imposed by unshielded (for human proximity operations) reactors and that might also be used to provide additional SSF crew protection from natural background radiation.

  7. Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report

    SciTech Connect

    Hebdon, F.J.

    1993-03-01

    On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

  8. [Cytogenetic characteristics of seed offspring of leafy tree plants from one-kilometer zone of Novovoronezh nuclear power station].

    PubMed

    Artiukhov, V G; Kalaev, V N; Sen'kevich, E V; Vakhtel', V M; Savko, A D

    2004-01-01

    Cytogenetic characteristics (mitotic activity, level and spectrum of pathological mitoses, nucleoly characteristics) of seed offspring of Quercus robur L. and Betula pendula Roth from Novovoronezh nuclear power station's 1-kilometer zone have been studied. It has been shown the change of time of passing though mitotic stages by cells, the increasing of bridges frequency occur in spectrum of mitotic aberrations (that shows activation of reparation systems), the change in nucleoly characteristics (the part of polynucleolaris cells increase in case of oak and decrease in case of birch, the rase of surface square of single nucleolies). The phenomena, mean above, probably, induced by synergic effects of Novovoronezh nuclear power station and environment pollutants. The most contaminated territories of 1-kilometer zone of Novovoronezh nuclear power station have been discovered by means of methods of cluster analysis of total cytogenetic characteristics of tree plants seed offspring.

  9. Temporal variation of dose rate distribution around the Fukushima Daiichi nuclear power station using unmanned helicopter.

    PubMed

    Sanada, Yukihisa; Orita, Tadashi; Torii, Tatsuo

    2016-12-01

    Aerial radiological survey using an unmanned aerial vehicle (UAV) was applied to measurement surface contamination around the Fukushima Daiichi nuclear power station (FDNPS). An unmanned helicopter monitoring system (UHMS) was developed to survey the environmental effect of radioactive cesium scattered as a result of the FDNPS accident. The UHMS was used to monitor the area surrounding the FDNPS six times from 2012 to 2015. Quantitative changes in the radioactivity distribution trend were revealed from the results of these monitoring runs. With this information, we found that the actual reduction of dose rate was faster than the one calculated with radiocesium physical half-life. It is indicated that the attenuation effect of radiation by radiocesium penetration in soil is dominant as for reason of reduction of dose rate. Copyright © 2016 Elsevier Ltd. All rights reserved.

  10. Indian Point Nuclear Power Station: verification analysis of County Radiological Emergency-Response Plans

    SciTech Connect

    Nagle, J.; Whitfield, R.

    1983-05-01

    This report was developed as a management tool for use by the Federal Emergency Management Agency (FEMA) Region II staff. The analysis summarized in this report was undertaken to verify the extent to which procedures, training programs, and resources set forth in the County Radiological Emergency Response Plans (CRERPs) for Orange, Putnam, and Westchester counties in New York had been realized prior to the March 9, 1983, exercise of the Indian Point Nuclear Power Station near Buchanan, New York. To this end, a telephone survey of county emergency response organizations was conducted between January 19 and February 22, 1983. This report presents the results of responses obtained from this survey of county emergency response organizations.

  11. Model simulations of the radioactive material plumes in the Fukushima nuclear power station accident

    NASA Astrophysics Data System (ADS)

    Nakajima, Teruyuki; Goto, Daisuke; Morino, Yu; Misawa, Shota; Tsuruta, Haruo; Uchida, Junya; Takemura, Toshihiko; Ohara, Toshimasa; Oura, Yasuji; Ebihara, Mitsuru; Satoh, Masaki

    2017-04-01

    We like to present an analysis of a model-simulated and observed data comparison for depiction of the atmospheric transportation of the 137Cs emitted from the Fukushima Daiichi Nuclear Power Station accident. This method employs a combination of the results of two aerosol model ensembles and the hourly observed atmospheric 137Cs concentration during 14-23 March 2011 at 90 sites in the Suspended Particulate Matter monitoring network. The result elucidates accurate transport routes and the distribution of the surface-level atmospheric 137Cs relevant to eight plume events that were previously identified. The model ensemble simulates the main features of the observed distribution of surface-level atmospheric 137Cs. However, significant differences were found in some cases. Through the analysis we discuss the important processes to control the characteristic shape and movement of each plume. We also report the status of the 2nd international model intercomparison in progress.

  12. Review of DNA(Defense Nuclear Agency) Remote Security Station (RSS) Project. Phase 1

    SciTech Connect

    Pletta, J.B.; Workhoven, R.M.

    1988-08-01

    This report reviews the progress made during FY87 on the Defense Nuclear Agency (DNA) sponsored Remote Security Station (RSS). During this time frame, Sandia National Laboratories was tasked to develop a Phase 1 proof-of-principle system consisting of readily available hardware. The primary emphasis was placed upon development of software and sensor fusion techniques and, as a result, the Phase 1 hardware is not suitable for field deployment. The RSS consists of a portable (non-mobile) sensor platform and an intelligent controller. The paper includes descriptions of the sensor platform and control console hardware, as well as the software that runs the intelligent controller. The sensor fusion techniques originally considered are discussed, and the methods used in the current system are explained in detail. Phase 2 development of the RSS is scheduled for FY88, and a discussion of the planned improvements is included.

  13. Current status of radiological protection at nuclear power stations in Japan.

    PubMed

    Suzuki, Akira; Hori, Shunsuke

    2011-07-01

    The radiation dose to workers at nuclear power stations (NPSs) in Japan was drastically reduced between the late-1970s and the early-1990s by continuous dose-reduction programmes. The total collective dose of radiation workers in FY 2008 was 84.04 person Sv, while the average collective dose was 1.5 person Sv per reactor. The average annual individual dose was 1.1 mSv and the maximum annual individual dose was 19.5 mSv. These values are sufficiently lower than the regulatory dose limits. Radioactive effluent released from NPSs is already so trivial that additional protective measures will not be necessary. Experience in radiation protection at NPSs has been accumulated over 40 y and will be very useful in establishing a rational radiation control system in the future.

  14. Concentration of (3)H in plants around Fukushima Dai-ichi Nuclear Power Station.

    PubMed

    Kakiuchi, Hideki; Akata, Naofumi; Hasegawa, Hidenao; Ueda, Shinji; Tokonami, Shinji; Yamada, Masatoshi; Hosoda, Masahiro; Sorimachi, Atsuyuki; Tazoe, Hirofumi; Noda, Kaori; Hisamatsu, Shun'ichi

    2012-01-01

    A large amount of radionuclides was released from the Fukushima Dai-ichi Nuclear Power Station (FDNPS) following the damage caused by the tsunami due to the Great East Japan Earthquake on 11 March 2011. Although many radionuclides in various environmental samples around the FDNPS have been measured, (3)H in the terrestrial environment has not yet been reported. We present here the first survey results of (3)H concentrations in plant samples collected around the FDNPS in 2011 from shortly after the accident. The free-water (3)H concentrations in herbaceous plant shoots and evergreen tree leaves were considerably higher than the previous background concentration, and diminished with distance from the FDNPS. Although reconstruction of atmospheric (3)H concentrations after the accident is difficult, a rough estimate of the radiation dose due to (3)H inhalation about 20 km from the FDNPS is on the order of a few microsieverts (μSv).

  15. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

    SciTech Connect

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Dawson, J.W.; Brunk, J.L.; Jokela, T.A.

    1985-03-22

    This report summarizes the information compiled in 1984 while assessing the environmental impact of radionuclides in aquatic releases from the Rancho Seco Nuclear Power Generating Station. Gamma-emitting radionuclides discharged since 1981 are found in many of the dietary components derived from the creeks receiving the effluent wastewater. Some soils and crops are found to contain radionuclides that originate from the contaminated water that was transferred to land during the irrigation season. /sup 134/Cs and /sup 137/Cs are the primary gamma-emitting radionuclides detected in the edible flesh of fish from the creeks. Concentrations in the flesh of fish decreased exponentially with distance from the plant. No significant differences in the /sup 137/Cs activity were found between male and female fish of equal size, but concentrations may vary in fish of different size, with the season and diet. 21% of the total /sup 137/Cs and /sup 134/Cs discharged between 1981 and 1984 is associated with the creek sediments to a distance of 27 km from the plant. Fractions of the missing inventory have been transferred to land during the irrigation season or to downstream regions more distant than 27 km from the plant. The radiocesium content of the sediments in 1984 decreased significantly in a downstream direction, much in the same manner as concentrations decreased in fish. Radioactivity originating from the plant was not above detection limits in any terrestrial food item sampled beyond 6.5 km from the plant. Based on the usage factors provided by individuals interviewed in a 1984 survey, the fish and aquatic-organism ingestion pathway contributed the largest radiological dose to humans utilizing products contaminated with the radionuclides in the liquid wastes discharged from the Rancho Seco Nuclear Power Generating Station in 1984.

  16. A modernized high-pressure heater protection system for nuclear and thermal power stations

    NASA Astrophysics Data System (ADS)

    Svyatkin, F. A.; Trifonov, N. N.; Ukhanova, M. G.; Tren'kin, V. B.; Koltunov, V. A.; Borovkov, A. I.; Klyavin, O. I.

    2013-09-01

    Experience gained from operation of high-pressure heaters and their protection systems serving to exclude ingress of water into the turbine is analyzed. A formula for determining the time for which the high-pressure heater shell steam space is filled when a rupture of tubes in it occurs is analyzed, and conclusions regarding the high-pressure heater design most advisable from this point of view are drawn. A typical structure of protection from increase of water level in the shell of high-pressure heaters used in domestically produced turbines for thermal and nuclear power stations is described, and examples illustrating this structure are given. Shortcomings of components used in the existing protection systems that may lead to an accident at the power station are considered. A modernized protection system intended to exclude the above-mentioned shortcomings was developed at the NPO Central Boiler-Turbine Institute and ZioMAR Engineering Company, and the design solutions used in this system are described. A mathematical model of the protection system's main elements (the admission and check valves) has been developed with participation of specialists from the St. Petersburg Polytechnic University, and a numerical investigation of these elements is carried out. The design version of surge tanks developed by specialists of the Central Boiler-Turbine Institute for excluding false operation of the high-pressure heater protection system is proposed.

  17. Reconfigurable Assembly Station for Precision Manufacture of Nuclear Fusion Ignition Targets

    SciTech Connect

    Castro, C; Montesanti, R C; Taylor, J S; Hamza, A V; Dzenitis, E G

    2009-08-11

    This paper explores the design and testing of a reconfigurable assembly station developed for assembling the inertial confinement nuclear fusion ignition targets that will be fielded in the National Ignition Facility (NIF) laser [1]. The assembly station, referred to as the Flexible Final Assembly Machine (FlexFAM) and shown in Figure 1, is a companion system to the earlier Final Assembly Machine (FAM) [2]. Both machines consist of a manipulator system integrated with an optical coordinate measuring machine (OCMM). The manipulator system has six groups of stacked axis used to manipulate the millimeter-sized target components with submicron precision, and utilizes the same force and torque feedback sensing as the FAM. Real-time dimensional metrology is provided by the OCMM's vision system and through-the-lens (TTL) laser-based height measuring probe. The manually actuated manipulator system of the FlexFAM provides a total of thirty degrees-of-freedom to the target components being assembled predominantly in a cubic centimeter work zone.

  18. A feasibility assessment of nuclear reactor power system concepts for the NASA Growth Space Station

    NASA Technical Reports Server (NTRS)

    Bloomfield, H. S.; Heller, J. A.

    1986-01-01

    A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth Space Station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of Space Station - attached concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination.

  19. A feasibility assessment of nuclear reactor power system concepts for the NASA Growth Space Station

    NASA Technical Reports Server (NTRS)

    Bloomfield, H. S.; Heller, J. A.

    1986-01-01

    A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth Space Station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of Space Station - attached concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination.

  20. An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area

    SciTech Connect

    Vojtech, R.J.

    1994-03-01

    An aerial radiological survey was conducted during the period of September 10 to 18, 1990, over a 40-square-mile (104-square-kilometer) area surrounding the Millstone Nuclear Power Station (MNPS). The MNPS is located on the Long Island Sound shoreline, three kilometers south of Waterford, Connecticut. The purpose of the survey was to measure and document the terrestrial gamma ray environment of the plant and surrounding areas. A contour map showing radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on an aerial photograph and a United States Geological Survey map of the area. The exposure rates within the survey region are quite uniform. The area is characterized by an exposure rate of 10-12 microroentgens per hour including an estimated cosmic ray contribution of 3.6 {mu}R/h. This is typical of natural background. The only exception to the natural background readings is the Millstone station itself, which is characterized by an exposure rate consistent with the standard operation of the reactor units. Radionuclide assays of soil samples and pressurized-ion-chamber gamma ray measurements were obtained at five locations within the survey boundaries. These measurements were taken in support of, and are in agreement with, the aerial data. The radiological environment near the plant is consistent with normal plant operation.

  1. Christine McGuire: at the heart of the maverick measurement maven.

    PubMed

    Harris, Ilene B; Simpson, Deborah

    2005-01-01

    In this article, part of the Exemplar series in Advances in Health Sciences Education, we profile the career of Christine McGuire, and capture her perspectives on the status of medical education practice and research. Her career was prototypical of other exemplars in the series--a pathway characterized by serendipity. As an exemplar, her contributions of leadership, scholarship, and innovations have changed the face of medical education. We describe our methods of data collection--literature reviews and in-depth interviews. We provide a portrayal of her career and accomplishments. Finally, we characterize her perspectives on medical eduction, including her views of significant innovations, contributions of professional educators, lessons learned, and needed future efforts.

  2. Environmental impact assessment for nuclear and coal-fired power stations in Czechoslovakia

    SciTech Connect

    Lapcik, V.

    1994-12-31

    Czechoslovakia has had legislation requiring environmental impact assessment since 1992. A methodology for complex evaluation of areas with thermal and nuclear energy sources, as related to ecology and environment, was developed by the staff of the Department of Ecology in accordance with the environmental Protection act (No. 17/1992) for use by the Czech Energy Company (Prague). This methodology will serve as a handbook of environmental impact assessment for the energy industry. Chapter 1 of the handbook describes the project, including information on the site, design, and size of the thermal or nuclear power station. Chapter 2 includes the data necessary to identify and assess the main effects that the project is likely to have on the environment. Chapter 3 describes aspects of the environment likely to be affected significantly by a proposed project, including population, fauna, flora, soil, water, air, climatic factors, material assets (such as architectural and archeological heritage), landscape, and the interrelationship between the above factors. Chapter 4 summarizes the measures envisaged to prevent, reduce, and where possible, offer any significant adverse effects on the environment.

  3. The Role of Open Stations in Underground Nuclear Test Treaty Monitoring

    NASA Astrophysics Data System (ADS)

    van der Vink, G. E.; van der Vink, G. E.

    2001-05-01

    Although the International Monitoring System is fixed by the treaty, seismic stations will continue to be installed around the world in regional networks designed for earthquake hazard assessment and scientific research. For many areas of the world, the high-density coverage of these regional networks will inevitably provide a capability that far surpasses that of the official treaty monitoring system. It is quite likely, therefore, that if evidence of a clandestine nuclear weapon test is discovered, it will be with data collection facilities that were never specifically intended for nuclear monitoring. Global communication networks will provide open access to thousands of resources that can be used to monitor environmental factors and help characterize a suspicious seismic event. When such events occur, Internet sites containing the relevant (and irrelevant) data are likely to appear long before intelligence information can be digested by governments or before memos can work their way through official channels. Competitive news organizations will not wait for the carefully crafted prose of official press releases before pursuing alternative technical judgments and scientific opinions. The future challenge for treaty monitoring may no longer be the acquisition of data, but rather the integration of the vast and continually evolving array of global information sources into their analytical systems. The new challenge for seismology is to maintain the culture of free and open data exchange within this new environment, despite the inevitable controversies and misuse.

  4. Structural integrity analysis of the degraded drywell containment at the Oyster Creek Nuclear generating station.

    SciTech Connect

    Petti, Jason P.

    2007-01-01

    This study examines the effects of the degradation experienced in the steel drywell containment at the Oyster Creek Nuclear Generating Station. Specifically, the structural integrity of the containment shell is examined in terms of the stress limits using the ASME Boiler and Pressure Vessel (B&PV) Code, Section III, Division I, Subsection NE, and examined in terms of buckling (stability) using the ASME B&PV Code Case N-284. Degradation of the steel containment shell (drywell) at Oyster Creek was first observed during an outage in the mid-1980s. Subsequent inspections discovered reductions in the shell thickness due to corrosion throughout the containment. Specifically, significant corrosion occurred in the sandbed region of the lower sphere. Since the presence of the wet sand provided an environment which supported corrosion, a series of analyses were conducted by GE Nuclear Energy in the early 1990s. These analyses examined the effects of the degradation on the structural integrity. The current study adopts many of the same assumptions and data used in the previous GE study. However, the additional computational recourses available today enable the construction of a larger and more sophisticated structural model.

  5. Segmentation of the reactor internals at the Yankee Nuclear Power Station

    SciTech Connect

    Child, C.L.

    1995-10-01

    The Yankee Nuclear Power Station (YNPS) first achieved criticality on August 19, 1960. Located in Rowe, Massachusetts, Yankee was the third commercial power plant licensed in the US. During its lifetime, this 185 MWe plant had a capacity factor of 74%--over ten points higher than the US nuclear industry average at that time. On February 26, 1992, faced with escalating costs and a general decline in power demands in the Northeast, the Yankee Atomic Electric Company announced the permanent shut down of Yankee Rowe. Even after shutdown, the Yankee tradition of pioneering and innovation has continued. Prompted by South Carolina`s decision to extend access to the Barnwell, South Carolina, waste management facility through June 1994 to out-of compact states, Yankee initiated an innovative program to remove reactor internals, steam generators, and the pressurizer. Yankee realized that removal of these components could be completed safely using existing programs and procedures. The project would save the ratepayers several millions of dollars compared to deferring removal until after the year 2000. Yankee management approved execution of the Component Removal Program in March, 1993.

  6. Monitoring the critical radiation exposure pathways at a BWR nuclear power station.

    PubMed

    Golden, J C; Chandrasekaran, E S; Kahn, B

    1982-06-01

    Iodine-131 in milk and gamma radiation from radionuclides in air in the environment of a 3-unit nuclear power station were measured at the levels predicted for airborne effluent. These measurements were part of a modified environmental radiological monitoring program to confirm the population doses computed from radionuclide release rates and environmental transfer models. The limits of detection were lowered relative to conventional monitoring programs by analyzing 21 L samples of milk for 131I and by determining external gamma radiation with a system that combined use of thermoluminescent dosimeters, pressurized ionization chambers, and NaI(T1) survey meters. For monitoring periods slightly longer than 6 months, during a time when fallout from atmospheric nuclear tests contributed very little, the average measured 131I concentration in milk was 0.1 pCi/L for cows on a nearby pasture and 0.02 pCi/L for cows at a more distant control location, compared to predicted values of 0.07 and 0.02 pCi/L, respectively; the average radiation exposure from airborne radionuclides measured at 16 nearby dosimeter locations was 7 mR, compared to the average of predicted values of 4 mR.

  7. Biofouling monitoring and control program at the Boston Edison Pilgrim Nuclear Station: A twelve year history

    SciTech Connect

    McDonald, D.J.; Armstrong, W.J.; Carucci, C.A.

    1996-08-01

    This paper reviews the history of the Biofouling Monitoring and Control Program at the Boston Edison Company Pilgrim Nuclear Power Station. The program was initially developed in 1982 in response to serious operations, maintenance and performance related problems due to biofouling in both the circulating and service water systems. Although implemented seven years prior to federal mandates under GL 89-13, this program also satisfies regulatory criteria for biofouling monitoring and control of nuclear service water systems. Since its inception, the impact of macrofouling on plant operation and availability has been significantly reduced. Stringent monitoring for blue mussels, installation of mechanical barriers to horseshoe crabs, improvements in screens, screenwash and debris removal systems, and an on-going commitment to biofouling control have reduced the number of condenser backwashes per year from > 40 (1989) to < 10. Depending on conditions and timing of a backwash, the resulting economic gain from this improvement alone can be 1.5 to more than 4 million dollars a year. Other improvements in related components and the service water system have also resulted in reduced maintenance related problems and an additional cost benefit to the plant. 13 refs., 6 figs., 1 tab.

  8. 75 FR 67784 - STP Nuclear Operating Company South Texas Project Electric Generating Station, Units 3 and 4...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-03

    ... Water Act Section 402(p) Texas Pollutant Discharge Elimination System (TPDES) general permit for... surface water quality. BMPs would be ] described in a Stormwater Pollution Prevention Plan (SWPPP) that... COMMISSION STP Nuclear Operating Company South Texas Project Electric Generating Station, Units 3 and...

  9. [Radiation injury of the plants in the zone of influence of the accident on Chernobyl Nuclear Power Station (NPS)].

    PubMed

    Grodzinskiĭ, D M; Gudkov, I N

    2006-01-01

    Were considered the radiobiological effects in some species of agricultural and wild growing plants in 30-kilometer zone of alienation of Chernobyl nuclear power station and other radionuclide contaminated territories. The particular attention was given to the distance plant reactions: immunity decreasing, genetic consequences, changes in phytocenosis. Was discussed the question of possibility of plant adaptation to conditions of high radiation influence.

  10. [Influence of working shift on nervous system functional state in operators of control unit in nuclear power station].

    PubMed

    Laskova, I V

    2009-01-01

    Operators of control unit in nuclear power station, if after the working shift, were diagnosed as having changes of cerebral functions and vegetative regulation, with sometimes increased blood pressure up to the level of cerebrovascular disease risk, and with higher spectral density of main EEG rhythms intensity.

  11. A comprehensive approach to selecting the water chemistry of the secondary coolant circuit in the projects of nuclear power stations equipped with VVER-1200 reactors

    NASA Astrophysics Data System (ADS)

    Tyapkov, V. F.

    2011-05-01

    The paper presents the results obtained from studies on selecting the water chemistry of the secondary coolant circuit carried out for the project of a nuclear power station equipped with a new-generation VVER-1200 reactor on the basis of case calculations and an analysis of field experience gained at operating nuclear power stations.

  12. Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

    PubMed Central

    TANAKA, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others. PMID:23138450

  13. Reactor Vessel and Reactor Vessel Internals Segmentation at Zion Nuclear Power Station - 13230

    SciTech Connect

    Cooke, Conrad; Spann, Holger

    2013-07-01

    Zion Nuclear Power Station (ZNPS) is a dual-unit Pressurized Water Reactor (PWR) nuclear power plant located on the Lake Michigan shoreline, in the city of Zion, Illinois approximately 64 km (40 miles) north of Chicago, Illinois and 67 km (42 miles) south of Milwaukee, Wisconsin. Each PWR is of the Westinghouse design and had a generation capacity of 1040 MW. Exelon Corporation operated both reactors with the first unit starting production of power in 1973 and the second unit coming on line in 1974. The operation of both reactors ceased in 1996/1997. In 2010 the Nuclear Regulatory Commission approved the transfer of Exelon Corporation's license to ZionSolutions, the Long Term Stewardship subsidiary of EnergySolutions responsible for the decommissioning of ZNPS. In October 2010, ZionSolutions awarded Siempelkamp Nuclear Services, Inc. (SNS) the contract to plan, segment, remove, and package both reactor vessels and their respective internals. This presentation discusses the tools employed by SNS to remove and segment the Reactor Vessel Internals (RVI) and Reactor Vessels (RV) and conveys the recent progress. SNS's mechanical segmentation tooling includes the C-HORCE (Circumferential Hydraulically Operated Cutting Equipment), BMT (Bolt Milling Tool), FaST (Former Attachment Severing Tool) and the VRS (Volume Reduction Station). Thermal segmentation of the reactor vessels will be accomplished using an Oxygen- Propane cutting system. The tools for internals segmentation were designed by SNS using their experience from other successful reactor and large component decommissioning and demolition (D and D) projects in the US. All of the designs allow for the mechanical segmentation of the internals remotely in the water-filled reactor cavities. The C-HORCE is designed to saw seven circumferential cuts through the Core Barrel and Thermal Shield walls with individual thicknesses up to 100 mm (4 inches). The BMT is designed to remove the bolts that fasten the Baffle Plates to

  14. Steam Dryer Segmentation and Packaging at Grand Gulf Nuclear Station - 13577

    SciTech Connect

    Kreitman, Paul J.; Sirianni, Steve R.; Pillard, Mark M.

    2013-07-01

    Entergy recently performed an Extended Power Up-rate (EPU) on their Grand Gulf Nuclear Station, near Port Gibson, Mississippi. To support the EPU, a new Steam Dryer Assembly was installed during the last refueling outage. Due to limited access into the containment, the large Replacement Steam Dryer (RSD) had to be brought into the containment in pieces and then final assembly was completed on the refueling floor before installation into the reactor. Likewise, the highly contaminated Original Steam Dryer (OSD) had to be segmented into manageable sections, loaded into specially designed shielded containers, and rigged out of containment where they will be safely stored until final disposal is accomplished at an acceptable waste repository. Westinghouse Nuclear Services was contracted by Entergy to segment, package and remove the OSD from containment. This work was performed on critical path during the most recent refueling outage. The segmentation was performed underwater to minimize radiation exposure to the workers. Special hydraulic saws were developed for the cutting operations based on Westinghouse designs previously used in Sweden to segment ABB Reactor Internals. The mechanical cutting method was selected because of its proven reliability and the minimal cutting debris that is generated by the process. Maintaining stability of the large OSD sections during cutting was accomplished using a custom built support stand that was installed into the Moisture Separator Pool after the Moisture Separator was installed back in the reactor vessel. The OSD was then moved from the Steam Dryer Pool to the Moisture Separator Pool for segmentation. This scenario resolved the logistical challenge of having two steam dryers and a moisture separator in containment simultaneously. A water filtration/vacuum unit was supplied to maintain water clarity during the cutting and handling operations and to collect the cutting chips. (authors)

  15. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report Sep-Nov 81

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1982-06-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the fall of 1981, Teredo bartschi remained in Oyster Creek despite continuous prolonged outages of the Oyster Creek Nuclear Generating Station.

  16. HT to HTO conversion and field experiments near Darlington Nuclear Power Generating Station (DNPGS) site.

    PubMed

    Kim, S B; Stuart, M; Bredlaw, M; Festarini, A; Beaton, D

    2014-06-01

    The Canadian input parameters related to tritiated hydrogen gas (HT) used in tritium dose models are currently based on experiments performed at the Chalk River Laboratories (CRL) site in 1986, 1987 and 1994. There is uncertainty in how well other sites experiencing atmospheric HT releases are represented by these data. In order to address this uncertainty, HT to HTO conversion factors were evaluated at different locations near the Darlington Nuclear Power Generating Station (DNPGS) site using various experimental approaches. These were D2 gas exposure chamber experiments, atmospheric tritium measurements, and HTO and OBT measurements in vegetation and soil. In addition to these field experiments, chamber experiments were conducted using HT gas on field soil samples. The suggested Canadian input parameters for atmospheric tritium releases estimate the total fraction of HT oxidized in air and in soil, at the site, to be up to a maximum of 2.4%. Based on the more limited data obtained near DNPGS in early spring, this fraction would likely be closer to 0.5%. The result suggests that current parameters provide a conservative estimate for the DNPGS site.

  17. An aerial radiological survey of the Pilgrim Station Nuclear Power Plant and surrounding area, Plymouth, Massachusetts

    SciTech Connect

    Proctor, A.E.

    1997-06-01

    Terrestrial radioactivity surrounding the Pilgrim Station Nuclear Power Plant was measured using aerial radiolog- ical survey techniques. The purpose of this survey was to document exposure rates near the plant and to identify unexpected, man-made radiation sources within the survey area. The surveyed area included land areas within a three-mile radius of the plant site. Data were acquired using an airborne detection system that employs sodium iodide, thallium-activated detectors. Exposure rate and photopeak counts were computed from these data and plotted on aerial photographs of the survey area. Several ground-based exposure measurements were made for comparison with the,aerial survey results. Exposure rates in areas surrounding the plant site varied from 6 to 10 microroentgens per hour, with exposure rates below 6 microroentgens per hour occurring over bogs and marshy areas. Man-made radiation was found to be higher than background levels at the plant site. Radation due to nitrogen-1 6, which is produced in the steam cycle of a boiling-water reactor, was the primaty source of activity found at the plant site. Cesium-137 activity at levels slightly above those expected from natural fallout was found at isolated locations inland from the plant site. No other detectable sources of man-made radioactivity were found.

  18. Radiation dose reduction efficiency of buildings after the accident at the Fukushima Daiichi Nuclear Power Station.

    PubMed

    Monzen, Satoru; Hosoda, Masahiro; Osanai, Minoru; Tokonami, Shinji

    2014-01-01

    Numerous radionuclides were released from the Fukushima Daiichi Nuclear Power Station (F1-NPS) in Japan following the magnitude 9.0 earthquake and tsunami on March 11, 2011. Local residents have been eager to calculate their individual radiation exposure. Thus, absorbed dose rates in the indoor and outdoor air at evacuation sites in the Fukushima Prefecture were measured using a gamma-ray measuring devices, and individual radiation exposure was calculated by assessing the radiation dose reduction efficiency (defined as the ratio of absorbed dose rate in the indoor air to the absorbed dose rate in the outdoor air) of wood, aluminum, and reinforced concrete buildings. Between March 2011 and July 2011, dose reduction efficiencies of wood, aluminum, and reinforced concrete buildings were 0.55 ± 0.04, 0.15 ± 0.02, and 0.19 ± 0.04, respectively. The reduction efficiency of wood structures was 1.4 times higher than that reported by the International Atomic Energy Agency. The efficiency of reinforced concrete was similar to previously reported values, whereas that of aluminum structures has not been previously reported. Dose reduction efficiency increased in proportion to the distance from F1-NPS at 8 of the 18 evacuation sites. Time variations did not reflect dose reduction efficiencies at evacuation sites although absorbed dose rates in the outdoor air decreased. These data suggest that dose reduction efficiency depends on structure types, levels of contamination, and evacuee behaviors at evacuation sites.

  19. International Remote Monitoring Project Argentina nuclear power station remote monitoring system

    SciTech Connect

    Schneider, S.L.; Lucero, R.; Glidewell, D.

    1998-08-01

    A remote monitoring system, designed to monitor spent fuel transfers from wet to dry storage, was installed at the Embalse Nuclear Power Station at Embalse, Argentina. The system consists of 6 gamma and one neutron radiation sensors. Five gamma sensors utilize RF transmission to communicate with Echelon nodes connected to a Local Operating Network (LON). One gamma and one neutron sensor are hardwired to the LON network. Each sensor Echelon node is bound to a single Datalogger that stores data until it receives an acquisition command to download to the Data Acquisition Software (DASW) database. The data from the Datalogger are transferred and stored in the Data Acquisition Software database, which resides on the IAEA MOS-MUX server. At a pre-determined interval, data from the DASW database are converted into Excel files and transferred to the IAEA database every 24 hours. At an predetermined interval all data are transferred to the distribution server located at the ARN laboratory at Ezeiza, Argentina. Remote access to data from the distribution server will be made from IAEA headquarters, Vienna, Austria, from ABACC in Rio de Janeiro, Brazil, from the IAEA field office in Buenos Aires, from ARN, and from Sandia National Laboratories, Albuquerque, New Mexico.

  20. Nuclear Simulation and Radiation Physics Investigations of the Target Station of the European Spallation Neutron Source

    SciTech Connect

    Filges, Detlef; Neef, Ralf-Dieter; Schaal, Hartwig

    2000-10-15

    The European Spallation Neutron Source (ESS) delivers high-intensity pulsed particle beams with 5-MW average beam power at 1.3-GeV incident proton energy. This causes sophisticated demands on material and geometry choices and a very careful optimization of the whole target system. Therefore, complex and detailed particle transport models and computer code systems have been developed and used to study the nuclear assessment of the ESS target system. The purpose here is to describe the methods of calculation mainly based on the Monte Carlo code to show the performance of the ESS target station. The interesting results of the simulations of the mercury target system are as follows: time-dependent neutron flux densities, energy deposition and heating, radioactivity and afterheat, materials damage by radiation, and high-energy source shielding. The results are discussed in great detail. The validity of codes and models, further requirements to improve the methods of calculation, and the status of running and planned experiments are given also.

  1. ASSESSMENT OF RADIONUCLIDE RELEASE FROM CONTAMINATED CONCRETE AT THE YANKEE NUCLEAR POWER STATION.

    SciTech Connect

    SULLIVAN, T.

    2004-03-01

    Yankee Atomic Energy Company (YAEC) is considering allowing portions of existing structures at the Yankee Nuclear Power Station (YNPS) to remain on site at the time of license termination. Accordingly, release of residual radioactive contaminants (i.e., H-3, C-14, Co-60, Ni-63, Sr-90, and Cs-137) from remaining subsurface concrete structures (Darman, 2004) and dose due to that release must be evaluated. Analyses were performed using DUST-MS to assess the rate of release for each radionuclide from the concrete, based upon an assumed concentration of 1 pCi/g and a concrete density of 2.5 g/cm{sup 3}. Using the same assumptions that were applied to the soil DCGL calculation (and where appropriate, the same input parameters), RESRAD was used to calculate the dose from water pathways. Values for selected RESRAD input parameters were chosen to match the release rate calculated by DUST-MS. The results indicated that Cs-137 yielded the highest dose.

  2. Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station

    SciTech Connect

    Yano, Kimihiko; Kitagaki, Toru; Ikeuchi, Hirotomo; Wakui, Ryohei; Higuchi, Hidetoshi; Kaji, Naoya; Koizumi, Kenji; Washiya, Tadahiro

    2013-07-01

    For the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), defueling of the fuel debris in the reactor core of Units 1-3 is planned to start within 10 years. Preferential items in the characterization of the fuel debris were identified for this work, in which the procedure and handling tools were assumed on the basis of information on 1F and experience after the Three Mile Island Unit 2 (TMI-2) accident. The candidates for defueling tools for 1F were selected from among the TMI- 2 defueling tools. It was found that they could be categorized into six groups according to their operating principles. The important properties of the fuel debris for defueling were selected considering the effect of the target materials on the tool performance. The selected properties are shape, size, density, thermal conductivity, heat capacity, melting point, hardness, elastic modulus, and fracture toughness. Of these properties, the mechanical properties (hardness, elastic modulus, fracture toughness) were identified as preferential items, because too few data on these characteristics of fuel debris are available in past severe accident studies. (authors)

  3. Radiation situation in Kamchatka after the Fukushima nuclear power station accident

    NASA Astrophysics Data System (ADS)

    Sidorin, A. I.

    2013-12-01

    The chronology of events in Kamchatka related to the threat of radioactive contamination of the territory as a result of the Fukushima-1 nuclear power station (NPS) accident in Japan is briefly reviewed based on the published data. The accident happened on March 11, 2011, after a strong earthquake near the coast of Japan and the giant tsunami followed by the earthquake. The power supply was damaged and, as a result, the cooling system of NPS reactors was destroyed. Although the reactors did not explode, radioactive emissions from the damaged NPS discharged into the atmosphere and spread over large areas by the air flows. Information about the radiation situation in Kamchatka is controversial. Therefore, the author carried out regular monitoring of the radiation background during a hiking trip in Kamchatka in August 2011. The data are presented in this paper. It was concluded that the radiation background along the route of the trip was consistent (within the accuracy of measurement methods) with the normal values of a natural background. A thorough analysis of air, soil, food samples, etc., is required for a more detailed study to identify the presence of radionuclides in the atmospheric emissions from the damaged NPS in Japan.

  4. Radiation Dose Reduction Efficiency of Buildings after the Accident at the Fukushima Daiichi Nuclear Power Station

    PubMed Central

    Monzen, Satoru; Hosoda, Masahiro; Osanai, Minoru; Tokonami, Shinji

    2014-01-01

    Numerous radionuclides were released from the Fukushima Daiichi Nuclear Power Station (F1-NPS) in Japan following the magnitude 9.0 earthquake and tsunami on March 11, 2011. Local residents have been eager to calculate their individual radiation exposure. Thus, absorbed dose rates in the indoor and outdoor air at evacuation sites in the Fukushima Prefecture were measured using a gamma-ray measuring devices, and individual radiation exposure was calculated by assessing the radiation dose reduction efficiency (defined as the ratio of absorbed dose rate in the indoor air to the absorbed dose rate in the outdoor air) of wood, aluminum, and reinforced concrete buildings. Between March 2011 and July 2011, dose reduction efficiencies of wood, aluminum, and reinforced concrete buildings were 0.55±0.04, 0.15±0.02, and 0.19±0.04, respectively. The reduction efficiency of wood structures was 1.4 times higher than that reported by the International Atomic Energy Agency. The efficiency of reinforced concrete was similar to previously reported values, whereas that of aluminum structures has not been previously reported. Dose reduction efficiency increased in proportion to the distance from F1-NPS at 8 of the 18 evacuation sites. Time variations did not reflect dose reduction efficiencies at evacuation sites although absorbed dose rates in the outdoor air decreased. These data suggest that dose reduction efficiency depends on structure types, levels of contamination, and evacuee behaviors at evacuation sites. PMID:24999992

  5. Status of the nuclear measurement stations for the process control of spent fuel reprocessing at AREVA NC/La Hague

    SciTech Connect

    Eleon, Cyrille; Passard, Christian; Hupont, Nicolas; Estre, Nicolas; Battel, Benjamin; Doumerc, Philippe; Dupuy, Thierry; Batifol, Marc; Grassi, Gabriele

    2015-07-01

    Nuclear measurements are used at AREVA NC/La Hague for the monitoring of spent fuel reprocessing. The process control is based on gamma-ray spectroscopy, passive neutron counting and active neutron interrogation, and gamma transmission measurements. The main objectives are criticality and safety, online process monitoring, and the determination of the residual fissile mass and activities in the metallic waste remained after fuel shearing and dissolution (empty hulls, grids, end pieces), which are put in radioactive waste drums before compaction. The whole monitoring system is composed of eight measurement stations which will be described in this paper. The main measurement stations no. 1, 3 and 7 are needed for criticality control. Before fuel element shearing for dissolution, station no. 1 allows determining the burn-up of the irradiated fuel by gamma-ray spectroscopy with HP Ge (high purity germanium) detectors. The burn-up is correlated to the {sup 137}Cs and {sup 134}Cs gamma emission rates. The fuel maximal mass which can be loaded in one bucket of the dissolver is estimated from the lowest burn-up fraction of the fuel element. Station no. 3 is dedicated to the control of the correct fuel dissolution, which is performed with a {sup 137}Cs gamma ray measurement with a HP Ge detector. Station no. 7 allows estimating the residual fissile mass in the drums filled with the metallic residues, especially in the hulls, from passive neutron counting (spontaneous fission and alpha-n reactions) and active interrogation (fission prompt neutrons induced by a pulsed neutron generator) with proportional {sup 3}He detectors. The measurement stations have been validated for the reprocessing of Uranium Oxide (UOX) fuels with a burn-up rate up to 60 GWd/t. This paper presents a brief overview of the current status of the nuclear measurement stations. (authors)

  6. Overview of insoluble radioactive cesium particles emitted from the Fukushima Dai-ichi Nuclear Power Station

    NASA Astrophysics Data System (ADS)

    Satou, Yukihiko

    2017-04-01

    In the early stage of the Fukushima Dai-ichi Nuclear Power Station (F1NPS) accident, number of spot type contamination has been observed in computed autoradiography (Kashimura 2013, Shibata 2013, Satou 2014). It's means presence of radioactive particles, however, insoluble cesium particle was overlooked because cesium, which is dominant radioactive element in the accident, becomes ionized in the environment. Adachi et al. (2013) showed presence of cesium (Cs)-bearing particles within air dust sample collected at Tsukuba, 170 km south from the Fukushima site, in midnight of 14 to morning of 15 March 2011. These particles were micrometer order small particles and Cs was could be detectable as element using an energy dispersive X-ray spectroscopy (EDX). However, other radioactive elements such as Co-60, Ru-103 and uranium, which were dominant element of radioactive particles delivered from Chernobyl accident, could not detected. Abe et al. (2014) employed a synchrotron radiation (SR)-micro(μ)-X-ray analysis to the Cs-bearing particles, and they were concluded that (1) contained elements derived from nuclear fission processes and from nuclear reactor and fuel materials; (2) were amorphous; (3) were highly oxidized; and (4) consisted of glassy spherules formed from a molten mixture of nuclear fuel and reactor material. In addition, Satou et al. (2016) and Yamaguchi et al. (2016) disclosed that silicate is main component of Cs-bearing particles. Satou et al. (2015) discovered two types of radioactive particles from soil samples collected in the vicinity of the F1NPS. These particles were remained in the natural environment more than four years, silicate is main component in common of each group particles. Group A particles were very similar to Cs-bearing particles reported by Adachi et al. except particle shape. On the other hand, group B is big particles found in north area from the F1NPS, and the strongest particles contained 20 kBq of Cs-137 within a particle

  7. Comparison of MELCOR modeling techniques and effects of vessel water injection on a low-pressure, short-term, station blackout at the Grand Gulf Nuclear Station

    SciTech Connect

    Carbajo, J.J.

    1995-06-01

    A fully qualified, best-estimate MELCOR deck has been prepared for the Grand Gulf Nuclear Station and has been run using MELCOR 1.8.3 (1.8 PN) for a low-pressure, short-term, station blackout severe accident. The same severe accident sequence has been run with the same MELCOR version for the same plant using the deck prepared during the NUREG-1150 study. A third run was also completed with the best-estimate deck but without the Lower Plenum Debris Bed (BH) Package to model the lower plenum. The results from the three runs have been compared, and substantial differences have been found. The timing of important events is shorter, and the calculated source terms are in most cases larger for the NUREG-1150 deck results. However, some of the source terms calculated by the NUREG-1150 deck are not conservative when compared to the best-estimate deck results. These results identified some deficiencies in the NUREG-1150 model of the Grand Gulf Nuclear Station. Injection recovery sequences have also been simulated by injecting water into the vessel after core relocation started. This marks the first use of the new BH Package of MELCOR to investigate the effects of water addition to a lower plenum debris bed. The calculated results indicate that vessel failure can be prevented by injecting water at a sufficiently early stage. No pressure spikes in the vessel were predicted during the water injection. The MELCOR code has proven to be a useful tool for severe accident management strategies.

  8. The TACIS Nuclear Programme: Assistance in Upgrading Russian Nuclear Power Stations - An Overview of the Individual Projects in the Internet

    SciTech Connect

    Bieth, Michel; Schoels, Hubert

    2006-07-01

    The European Union' TACIS1 programme has been established for the New Independent States (NIS), among them in the Russian Federation since 1991. One priority of TACIS funding is Nuclear Safety. The European Commission has made available a total of 944 Million Euros for nuclear safety programmes covering the period 1991-2003. The TACIS nuclear safety programme is devoted to the improvement of the safety of Soviet designed nuclear installations in providing technology and safety culture transfer. JRC is carrying out works in the following areas: On-Site Assistance for TACIS operating Nuclear Power Plants; Design Safety and Dissemination of TACIS results; Reactor Pressure Vessel Embrittlement for VVER; Regulatory Assistance; Industrial Waste Management; Nuclear Safeguards; All TACIS projects, dealing with these areas of activity are now available in so called Project Description Sheets (PDS) or Project Results Sheets (PRS) in the Internet for everybody. JRC has created in the Internet an easy to open and to browse database which contains the result of works in relation to the above mentioned nuclear activities. This presentation gives an on-line overview of the app. 430 projects which have been implemented so far since the outset of the TACIS Nuclear Programme in the Russian Federation, which is representative to the other CIS countries, benefiting from the TACIS. The presentation will mainly consist of an on-line-demonstration of the TACIS Nuclear WEB Page, created by JRC. (authors)

  9. Sorption (Kd) measurements in support of dose assessments for Zion Nuclear Station Decommissioning

    SciTech Connect

    Yim S. P.; Sullivan T.; Milian, L.

    2012-12-12

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with “clean” concrete demolition debris from the above grade parts of the facility. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) was performed to provide site-specific data for performance assessment calculations to support the request to terminate the NRC license and allow unrestricted use of the facility. Specifically, this study measured the distribution coefficient for five radionuclides of concern using site-specific soils and groundwater. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the soil or concrete that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides of concern are Fe-55, Co-60, Ni-63, Sr-90, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90. Site-specific soils included disturbed sand (sand removed during construction and used as backfill), native sand, silt/clay and silt. In addition, concrete cores from the Unit-1 Containment Building and the Crib House were broken into particles less than 2 mm in size and tested to obtain distribution coefficients for the five nuclides.

  10. 77 FR 64834 - Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-23

    ... information. ] FOR FURTHER INFORMATION CONTACT: John G. Lamb, Office of Nuclear Reactor Regulation, U.S.... For the Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. BILLING CODE 7590-01-P...

  11. Comparison between the results of calculation and experimental aerodynamic studies of the exhaust hoods used in the low-pressure cylinders of steam turbines of nuclear power stations

    NASA Astrophysics Data System (ADS)

    Gudkov, E. I.; Mikhailov, V. E.; Lisyanskii, A. S.; Nazarov, V. V.; Epifanov, V. K.; Baranovskaya, L. V.

    2012-03-01

    Results from calculation and experimental aerodynamic studies of the exhaust hood used in the low-pressure cylinder of a prospective steam turbine for a nuclear power station are presented, and their comparison is given.

  12. Main Generator Seal Oil Supply Reliability Improvements at Southern California Edison's San Onofre Nuclear Generating Station

    SciTech Connect

    Simma, Fred Y.; Chetwynd, Russell J.; Rowe, Stuart A.

    2006-07-01

    This paper presents the justification for the approach, details and results of the Main Generator Seal Oil System reliability enhancements on the San Onofre Nuclear Generating Station, SONGS. The SONGS, Unit 3 experienced substantial turbine damage in early 2001 after the turbine bearings lubrication oil supply failed. During a loss of off-site power incident, power was lost to the two AC powered turbine lubrication oil pumps due to a breaker failure in the switchgear and the DC powered emergency bearing lubricating oil pump failed to start due to a breaker trip. The SONGS turbine generators coasted down from full speed to a full stop without lubricating oil. This resulted in significant bearing, journal and steam path damage that required a four-month duration repair outage during a time period where electricity was in short supply in the State of California. The generator hydrogen sealing system remained operable during this event, however it was recognized during the event follow up investigation that this system had vulnerabilities to failure similar to the bearing lubrication system. In order to prevent a reoccurrence of this extremely costly event, SONGS has taken actions to modify both of these critical turbine generator systems by adding additional, continuously operating pumps with a new, independent power source and independently routed cables. The main challenge was to integrate the additional equipment into the existing lubrication and seal oil systems. The lubrication Oil System was the first system to be retro-fitted and these results already have been presented. Reference 2. This paper provides the result of the reliability enhancements for the Main Generator Seal Oil System, which concludes the turbine/generator critical oil systems reliability improvements, performed by SONGS. It is worth noting that the design team discovered and corrected a number of other significant operational issues, which had been present from the early days and also learned

  13. Water supply for the Nuclear Rocket Development Station at the U.S. Atomic Energy Commission's Nevada Test Site

    USGS Publications Warehouse

    Young, Richard Arden

    1972-01-01

    The Nuclear Rocket Development Station, in Jackass Flats, occupies about 123 square miles in the southwestern part of the U.S. Atomic Energy Commission's Nevada Test Site. Jackass Flats, an intermontane valley bordered by highlands on all sides except for a drainage outlet in the southwestern corner, has an average annual rainfall of 4 inches. Jackass Flats is underlain by alluvium, colluvium, and volcanic rocks of Cenozoic age and, at greater depth, by sedimentary rocks of Paleozoic age. The alluvium and the colluvium lie above the saturated zone throughout nearly all of Jackass Flats. The Paleozoic sedimentary rocks contain limestone and dolomite units that are excellent water producers elsewhere ; however, these units are too deep in Jackass Flats to be economic sources of water. The only important water-producing unit known in the vicinity of the Nuclear Rocket Development Station is a welded-tuff aquifer, the Topopah Spring Member of the Paintbrush Tuff, which receives no significant recharge. This member contains about 500 feet of highly fractured rock underlying an area 11 miles long and 3 miles wide in western Jackass Flats. Permeability of the aquifer is derived mostly from joints and fractures; however, some permeability may be derived from gas bubbles in the upper part of the unit. Transmissivity, obtained from pumping tests, ranges from 68,000 to 488,000 gallons per day per foot. Volume of the saturated part of the aquifer is about 3.5 cubic miles, and the average specific yield probably ranges from 1 to 5 percent. The volume of ground water in storage is probably within the range of 37-187 billion gallons. This large amount of water should be sufficient to supply the needs of the Nuclear Rocket Development Station for many years. Water at the Nuclear Rocket Development Station is used for public supply, construction, test-cell coolant, exhaust cooling, and thermal shielding during nuclear reactor and engine testing, and washdown. Present (1967) average

  14. Analysis of Digitized Seismograms from Russian Geophysical Survey Stations of Soviet Peaceful Nuclear Explosions

    DTIC Science & Technology

    2009-09-30

    and Chukotka regions. The Magadan region profile indicates velocities slower than those found from Kimberlite -4. the closest of the old PNE profiles...Figure 7) indicates velocities essentially identical to those from the Kimberlite -4 profile in the Siberian Platform, which includes stations Yakutsk...and Khandyga. The Siberian Platform portion of the Magadan profile intersects the Kimberlite -4 profile between the Neva site and station Yakutsk, thus

  15. Formation of a nuclear reactor's molten core bath in a crucible-type corium catcher for a nuclear power station equipped with VVER reactors

    NASA Astrophysics Data System (ADS)

    Beshta, S. V.; Vitol', S. A.; Granovskii, V. S.; Kalyago, E. K.; Kovtunova, S. V.; Krushinov, E. V.; Sulatskaya, M. B.; Sulatskii, A. A.; Khabenskii, V. B.; Al'Myashev, V. I.; Gusarov, V. V.

    2011-05-01

    Results from a calculation study on analyzing the formation of a melt bath in a crucible-type catcher for the conditions of a severe accident at a nuclear power station equipped with VVER-1000 reactors are presented. It is shown that the heat loads exerted on the water-cooled walls of the corium catcher shell are limited to a permissible level at which the necessary margins to nucleate boiling crisis and to destruction are ensured under the conditions of thermal and mechanical loading of the shell. An important role of sacrificial material in the efficient operation of the corium catcher is pointed out.

  16. Signature energetic analysis of accelerate electron beam after first acceleration station by accelerating stand of Joint Institute for Nuclear Research

    NASA Astrophysics Data System (ADS)

    Sledneva, A. S.; Kobets, V. V.

    2017-06-01

    The linear electron accelerator based on the LINAC - 800 accelerator imported from the Netherland is created at Joint Institute for Nuclear Research in the framework of the project on creation of the Testbed with an electron beam of a linear accelerator with an energy up to 250 MV. Currently two accelerator stations with a 60 MV energy of a beam are put in operation and the work is to put the beam through accelerating section of the third accelerator station. The electron beam with an energy of 23 MeV is used for testing the crystals (BaF2, CsI (native), and LYSO) in order to explore the opportunity to use them in particle detectors in experiments: Muon g-2, Mu2e, Comet, whose preparation requires a detailed study of the detectors properties such as their irradiation by the accelerator beams.

  17. 78 FR 71675 - License Amendment Application for Vermont Yankee Nuclear Power Station

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-29

    ... 20852. FOR FURTHER INFORMATION CONTACT: Douglas Pickett, Office of Nuclear Reactor Regulation, U.S...) to reduce reactor pressure associated with the fuel cladding integrity safety limits (SLs) from 800..., Office of Nuclear Reactor Regulation. BILLING CODE 7590-01-P ...

  18. Assessment of the efficiency of hydrogen cycles on the basis of off-peak electric energy produced at a nuclear power station

    NASA Astrophysics Data System (ADS)

    Aminov, R. Z.; Bairamov, A. N.; Shatskova, O. V.

    2009-11-01

    The main factors influencing the efficiency of using off-peak electric energy to run hydrogen cycles at a nuclear power station are considered. Indicators characterizing the efficiency of using a hydrogen cycle at a nuclear power station during its operation with superheating live steam in a steam-hydrogen mode are presented. A comparison between the steam-turbine hydrogen cycle and a pumped-storage hydraulic power station in the efficiency of generating peak electric energy (power) and capital investments is given.

  19. Constellation nuclear instrument analysis required in support of the Extended Power Up-rate for Ginna Station

    SciTech Connect

    Guider, J.; Quinn, E. L.

    2006-07-01

    The purpose of this paper is to provide an overview of the Instrumentation and Control design changes required for the Extended Power Up-rate (EPU) at the R.E. Ginna Nuclear Station in Ontario, N.Y. Ginna is a pressurized-water reactor (PWR) plant of the Westinghouse 2-loop design. The request for the EPU was filed on July 7, 2005 and approved by NRC on July 11, 2006 and included an increase in the maximum steady-state reactor core power level from 1520 megawatts thermal to 1775 MWt, which is an increase of approximately 17%. (authors)

  20. A pilot application of risk-based methods to establish in-service inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station

    SciTech Connect

    Vo, T.; Gore, B.; Simonen, F.; Doctor, S.

    1994-08-01

    As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory Commission, the Pacific Northwest Laboratory is developing a method that uses risk-based approaches to establish in-service inspection plans for nuclear power plant components. This method uses probabilistic risk assessment (PRA) results and Failure Modes and Effects Analysis (FEMA) techniques to identify and prioritize the most risk-important systems and components for inspection. The Surry Nuclear Power Station Unit 1 was selected for pilot applications of this method. The specific systems addressed in this report are the reactor pressure vessel, the reactor coolant, the low-pressure injection, and the auxiliary feedwater. The results provide a risk-based ranking of components within these systems and relate the target risk to target failure probability values for individual components. These results will be used to guide the development of improved inspection plans for nuclear power plants. To develop inspection plans, the acceptable level of risk from structural failure for important systems and components will be apportioned as a small fraction (i.e., 5%) of the total PRA-estimated risk for core damage. This process will determine target (acceptable) risk and target failure probability values for individual components. Inspection requirements will be set at levels to assure that acceptable failure probabilistics are maintained.

  1. Thyroid consequences of the Chernobyl nuclear power station accident on the Turkish population.

    PubMed

    Emral, Rifat; Baştemir, Mehmet; Güllü, Sevim; Erdoğan, Gürbüz

    2003-05-01

    The Chernobyl accident caused widespread effects across Europe and huge areas were radiocontaminated. The major impact of the accident on human health was a sharp increase in childhood thyroid carcinoma and autoimmune thyroid diseases in exposed populations. The thyroidal effects of the Chernobyl accident have been investigated in most European countries, except Turkey. The aim of the current study was therefore to determine the thyroidal consequences of the Chernobyl nuclear power station accident in a selected Turkish population. This study was designed as a sectional, area study, between October 2000 and March 2001, in two different regions of Turkey. According to the data of the Turkish Atomic Energy Authority, the eastern part of the Black Sea region was the most radiocontaminated area in Turkey at the time of Chernobyl accident, while Middle Anatolia was not seriously affected. Thus, Rize city, which is located in the eastern Black Sea region, served as a study area, and 970 adolescents, living in this region, comprised our study group (group R). On the other hand, Beypazari, which is located in Middle Anatolia, was chosen as the control region, and 710 adolescents living in this location were enrolled into the study as controls (group B). During the study, thyroid ultrasounds were performed in all subjects and thyroid volumes were calculated. World Health Organization and International Council for Control of Iodine Deficiency Disorders criteria were used for the determination of goiter. Thyroid fine-needle aspiration biopsy with ultrasound guidance was performed when a nodule was detected. Blood samples for thyroid function tests and thyroid autoantibodies, and urine samples for urinary iodine excretion were collected from all subjects. Thyroid function tests were similar in both groups, but thyroid volumes were found to be higher in group B (13.93+/-5.04 vs 17.66+/-5.58 ml; P<0.001). The prevalence of goiter was found to be 28.25% in group R and 61.95% in

  2. XOQDOQ: computer program for the meteorological evaluation of routine effluent releases at nuclear power stations. Final report

    SciTech Connect

    Sagendorf, J.F.; Goll, J.T.; Sandusky, W.F.

    1982-09-01

    Provided is a user's guide for the US Nuclear Regulatory Commission's (NRC) computer program X0QDOQ which implements Regulatory Guide 1.111. This NUREG supercedes NUREG-0324 which was published as a draft in September 1977. This program is used by the NRC meteorology staff in their independent meteorological evaluation of routine or anticipated intermittent releases at nuclear power stations. It operates in a batch input mode and has various options a user may select. Relative atmospheric dispersion and deposition factors are computed for 22 specific distances out to 50 miles from the site for each directional sector. From these results, values for 10 distance segments are computed. The user may also select other locations for which atmospheric dispersion deposition factors are computed. Program features, including required input data and output results, are described. A program listing and test case data input and resulting output are provided.

  3. Biodosimetry of restoration workers for the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi nuclear power station accident.

    PubMed

    Suto, Yumiko; Hirai, Momoki; Akiyama, Miho; Kobashi, Gen; Itokawa, Masanari; Akashi, Makoto; Sugiura, Nobuyuki

    2013-10-01

    The biological dose of nuclear workers engaged in emergency response tasks at Tokyo Electric Power Company (TEPCO) Fukushima Daiichi Nuclear Power Station was estimated in the present study. As the national core center for radiation emergency medical preparedness in Japan, the National Institute of Radiological Sciences (NIRS) received all individuals who were suspected of being overexposed to acute radiation. In the course of health examinations at NIRS, biological dosimetry was performed by the dicentric chromosome assay (DCA). Twelve individuals were examined from 21 March-1 July 2011. The results indicated that the estimated exposure doses for all individuals were lower than 30 mGy, with the mean value of about 101 mGy. These results by DCA were in accordance with those obtained by physical dosimetry based on personal dosimeter recording assessment. The results corroborate the fact that no acute radiation syndrome was observed among the workers examined.

  4. How Space Radiation Risk from Galactic Cosmic Rays at the International Space Station Relates to Nuclear Cross Sections

    NASA Technical Reports Server (NTRS)

    Lin, Zi-Wei; Adams, J. H., Jr.

    2005-01-01

    Space radiation risk to astronauts is a major obstacle for long term human space explorations. Space radiation transport codes have thus been developed to evaluate radiation effects at the International Space Station (ISS) and in missions to the Moon or Mars. We study how nuclear fragmentation processes in such radiation transport affect predictions on the radiation risk from galactic cosmic rays. Taking into account effects of the geomagnetic field on the cosmic ray spectra, we investigate the effects of fragmentation cross sections at different energies on the radiation risk (represented by dose-equivalent) from galactic cosmic rays behind typical spacecraft materials. These results tell us how the radiation risk at the ISS is related to nuclear cross sections at different energies, and consequently how to most efficiently reduce the physical uncertainty in our predictions on the radiation risk at the ISS.

  5. Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams

    SciTech Connect

    Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

    1993-02-01

    Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., {sup 108m}Ag, {sup 93}Mo, {sup 36}Cl, {sup 10}Be, {sup 113m}Cd, {sup 121m}Sn, {sup 126}Sn, {sup 93m}Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., {sup 14}C, {sup 129}I, and {sup 99}Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC`s understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments.

  6. Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams

    SciTech Connect

    Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

    1993-02-01

    Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., [sup 108m]Ag, [sup 93]Mo, [sup 36]Cl, [sup 10]Be, [sup 113m]Cd, [sup 121m]Sn, [sup 126]Sn, [sup 93m]Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., [sup 14]C, [sup 129]I, and [sup 99]Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC's understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments.

  7. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Workshop

    SciTech Connect

    Hoopingarner, K.R.; Vause, J.W.

    1987-08-01

    Pacific Northwest Laboratory (PNL) evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume II, reports the results of an industry-wide workshop held on May 28 and 29, 1986, to discuss the technical issues associated with aging of nuclear service emergency diesel generators. The technical issues discussed most extensively were: man/machine interfaces, component interfaces, thermal gradients of startup and cooldown and the need for an accurate industry database for trend analysis of the diesel generator system.

  8. Analysis of data from sensitive U.S. monitoring stations for the Fukushima Dai-ichi nuclear reactor accident

    SciTech Connect

    Biegalski, Steven R.; Bowyer, Ted W.; Eslinger, Paul W.; Friese, Judah I.; Greenwood, Lawrence R.; Haas, Derek A.; Hayes, James C.; Hoffman, Ian; Keillor, Martin E.; Miley, Harry S.; Morin, Marc P.

    2012-12-01

    The March 11, 2011 9.0 magnitude undersea megathrust earthquake off the coast of Japan and subsequent tsunami waves triggered a major nuclear event at the Fukushima Dai-ichi nuclear power station. At the time of the event, units 1, 2, and 3 were operating and units 4, 5, and 6 were in a shutdown condition for maintenance. Loss of cooling capacity to the plants along with structural damage caused by the earthquake and tsunami resulted in a breach of the nuclear fuel integrity and release of radioactive fission products to the environment. Fission products started to arrive in the United States via atmospheric transport on March 15, 2011 and peaked by March 23, 2011. Atmospheric activity concentrations of 131I reached levels of 3.0 * 10*2 Bqm*3 in Melbourne, FL. The noble gas 133Xe reached atmospheric activity concentrations in Ashland, KS of 17 Bqm*3. While these levels are not health concerns, they were well above the detection capability of the radionuclide monitoring systems within the International Monitoring System of the Comprehensive Nuclear-Test-Ban Treaty.

  9. Analysis of data from sensitive U.S. monitoring stations for the Fukushima Dai-ichi nuclear reactor accident.

    PubMed

    Biegalski, S R; Bowyer, T W; Eslinger, P W; Friese, J A; Greenwood, L R; Haas, D A; Hayes, J C; Hoffman, I; Keillor, M; Miley, H S; Moring, M

    2012-12-01

    The March 11, 2011 9.0 magnitude undersea megathrust earthquake off the coast of Japan and subsequent tsunami waves triggered a major nuclear event at the Fukushima Dai-ichi nuclear power station. At the time of the event, units 1, 2, and 3 were operating and units 4, 5, and 6 were in a shutdown condition for maintenance. Loss of cooling capacity to the plants along with structural damage caused by the earthquake and tsunami resulted in a breach of the nuclear fuel integrity and release of radioactive fission products to the environment. Fission products started to arrive in the United States via atmospheric transport on March 15, 2011 and peaked by March 23, 2011. Atmospheric activity concentrations of (131)I reached levels of 3.0×10(-2) Bqm(-3) in Melbourne, FL. The noble gas (133)Xe reached atmospheric activity concentrations in Ashland, KS of 17 Bqm(-3). While these levels are not health concerns, they were well above the detection capability of the radionuclide monitoring systems within the International Monitoring System of the Comprehensive Nuclear-Test-Ban Treaty.

  10. Evaluation of the prompt alerting systems at four nuclear power stations

    SciTech Connect

    Towers, D.A.; Anderson, G.S.; Keast, D.N.; Kenoyer, J.L.; Desrosiers, A.E.

    1982-09-01

    This report presents evaluations of the prompt notification siren systems at the following four US nuclear power facilities: Trojan, Three Mile Island, Indian Point, and Zion. The objective of these evaluations was to provide examples of an analytical procedure for predicting siren-system effectiveness under specific conditions in the 10-mile emergency planning zone (EPZ) surrounding nuclear power plants. This analytical procedure is discussed in report No. PNL-4227.

  11. Removal of the steam generators and pressurizer at the Yankee Nuclear Power Station

    SciTech Connect

    Holmgren, B.W.; Parker, J.E.

    1995-10-01

    Nuclear Steam Supply System (NSSS) components can be safely and economically removed from shutdown nuclear facilities. In many cases, intact removal of contaminated components is less costly and results in less radiation exposure to personnel than segmented removal. Component removal activities can be conducted prior to Decommissioning Plan approval, provided that the activities are within the bounds of the 10CFR50 operating license and 10CFR50.59, the removal work does not increase the total cost of decommissioning, and does not foreclose the release of the site for unrestricted use. The average citizen appears to be comfortable with the decommissioning process for nuclear power plants, provided the facts are made known. Many anti-nuclear activists, however, do not want nuclear plants to be dismantled right away. Their preference is to place these plants in a SAFSTOR mode for 50 years or more to lower exposure risks to workers and the public. In the case of Yankee Rowe, SAFSTOR will do little to reduce worker and public risk. It could, however, dramatically drive up the cost of decommissioning -- costs which the public pays. The commercial nuclear industry must continue to address the public`s legitimate concerns and respond to misleading antinuclear attacks with facts and information. State and local governments are becoming more interested in nuclear plant decommissioning planning. This trend is likely to continue as more nuclear plants face the end of operation. As several states move toward construction of low-level waste disposal facilities, this may have a positive effect on that process. The need exists for consensus on these facilities which must include provisions for large waste forms such as NSSS components.

  12. Underground nuclear power station using self-regulating heat-pipe controlled reactors

    DOEpatents

    Hampel, Viktor E.

    1989-01-01

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

  13. An underground nuclear power station using self-regulating heat-pipe controlled reactors

    DOEpatents

    Hampel, V.E.

    1988-05-17

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast- acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor. 5 figs.

  14. A new universal formula for efficiency: sensitivity to cooling conditions of nuclear and conventional power stations

    SciTech Connect

    Haidar, N.H.

    1984-10-01

    A new approximate formula is derived for the sensitivity of the net efficiency of fissile- and fossil-fueled condensing power stations to incremental variations in the design temperature of the cooling water or air. It is universal for the three basic modes (open circuit, wet tower, and dry tower) of turbine condenser cooling and incorporates nearly all of the decisive design parameters involved.

  15. Meet the Maximally Exposed Member of the Public: The Service Station Attendant for Spent Nuclear Fuel Going to Yucca Mountain

    SciTech Connect

    Collins, H. E.; Gathers, R.; Halstead, R. J.

    2002-02-28

    According to the 1999 Draft Environmental Impact Statement (DEIS) for the proposed Yucca Mountain repository site, members of the public along transportation routes by which spent nuclear fuel (SNF) and high-level radioactive waste (HLW) is shipped will receive annual radiation doses less than 100 mrem/yr, the international (ICRP) and national (Department of Energy, Nuclear Regulatory Commission) radiation limit for members of the public. For the ''Mostly Truck'' national transportation scenario, the DEIS specifically concludes that the maximally exposed member of the public, a service station attendant along the primary shipping route will receive no more than 100 mrem/yr, or 2.4 rem over 24 years. Based on the assumptions in the DEIS scenarios, however, it is highly likely that service station attendants along shipping routes will be called upon to fuel and service the rigs carrying SNF and HLW to Yucca Mountain. After reevaluating the DEIS, and making realistic alternative assumptions where necessary, the authors conclude that these attendants are likely to receive substantially more than 100 mrem/yr external dose, and perhaps several times that dose (up to 500 mrem/yr), unless mitigating measures are adopted. This is particularly true in Western states where refueling opportunities are limited, and the distances between fuel sources in rural areas may be up to 100 miles.

  16. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study

    SciTech Connect

    Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

    1987-08-01

    Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators.

  17. Nuclear and in-source laser spectroscopy with the ISAC yield station

    SciTech Connect

    Kunz, Peter Bricault, Pierre; Dombsky, Marik; Lassen, Jens; Teigelhöfer, Andrea; Heggen, Henning; Andreoiu, Corina; Wong, Fiona

    2014-05-15

    A new decay station has been built for the ISAC facility at TRIUMF for the rapid and reliable characterization of radioactive ion beam (RIB) compositions and intensities with the capability of simultaneously collecting α, β, and γ decay data from RIB with intensities between a few and ≈10{sup 11} ions per second. It features user-friendly control, data acquisition, and analysis software. The analysis of individual decay time structures allows the unambiguous assignment of α and γ lines even with substantial isobaric contamination present. The capability for accurate half-life measurements is demonstrated with the example of {sup 46}K. The coupling of the yield station to the laser ion source, TRILIS, allows the correlation of radiometric data with automated laser frequency scans. First results of in-source laser spectroscopy measurements on astatine are discussed.

  18. Nuclear and in-source laser spectroscopy with the ISAC yield station

    NASA Astrophysics Data System (ADS)

    Kunz, Peter; Andreoiu, Corina; Bricault, Pierre; Dombsky, Marik; Lassen, Jens; Teigelhöfer, Andrea; Heggen, Henning; Wong, Fiona

    2014-05-01

    A new decay station has been built for the ISAC facility at TRIUMF for the rapid and reliable characterization of radioactive ion beam (RIB) compositions and intensities with the capability of simultaneously collecting α, β, and γ decay data from RIB with intensities between a few and ≈1011 ions per second. It features user-friendly control, data acquisition, and analysis software. The analysis of individual decay time structures allows the unambiguous assignment of α and γ lines even with substantial isobaric contamination present. The capability for accurate half-life measurements is demonstrated with the example of 46K. The coupling of the yield station to the laser ion source, TRILIS, allows the correlation of radiometric data with automated laser frequency scans. First results of in-source laser spectroscopy measurements on astatine are discussed.

  19. [Transport processes of low-level radioactive liquid effluent of nuclear power station in closed water body].

    PubMed

    Wu, Guo-Zheng; Xu, Zong-Xue

    2012-07-01

    The transport processes of low-level radioactive liquid effluent of Xianning nuclear power station in the closed water body Fushui Reservoir are simulated using the EFDC model. Six nuclides concentration distribution with different half-lives in the reservoir are analyzed under the condition of 97% guarantee rate incoming water and four-running nuclear power units. The results show that the nuclides concentration distribution is mainly affected by the flow field of the reservoir and the concentration is decided by the half-lives of nuclide and the volume of incoming water. In addition, the influence region is enlarged as increasing of half-life and tends to be stable when the half-life is longer than 5 years. Moreover, the waste water discharged from the outlet of the nuclear power plant has no effect on the water-intake for the outlet located at the upstream of the water-intake and the flow field flows to the dam of the reservoir.

  20. 77 FR 27804 - Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-11

    ... with only minor plant changes. EPUs typically involve extensive modifications to the nuclear steam... to generate and/or accommodate the increased feedwater and steam flow rates to achieve EPU power... FES to perform its EA for the proposed EPU. There will be extensive changes made to the steam...

  1. 77 FR 41814 - Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-16

    ... changes. EPUs typically involve extensive modifications to the nuclear steam supply system. The licensee... accommodate the increased feedwater and steam flow rates to achieve EPU power levels during a refueling outage... the proposed EPU. There will be extensive changes made to the steam supply system of GGNS Unit...

  2. 75 FR 67406 - Exelon Nuclear Texas Holdings, LLC; Victoria County Station Early Site Permit Application; Notice...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-02

    .... Terry or Ms. Alicia Williamson by telephone at 1-800-368-5642, extension 1488 or 1878, respectively. In... process may be obtained from Ms. Tomeka L. Terry or Ms. Alicia Williamson at U.S. Nuclear Regulatory..., respectively, or via e-mail at Tomeka.Terry@nrc.gov or Alicia.Williamson@nrc.gov . Dated at Rockville, Maryland...

  3. 75 FR 33656 - Exelon Generation Company, LLC Oyster Creek Nuclear Generating Station Environmental Assessment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-14

    ... permit are needed. No effects on the aquatic or terrestrial habitat in the vicinity or the plant, or to... Guide 1.189, ``Fire Protection for Nuclear Power Plants,'' some of the operator manual actions included... procedural direction to take actions proscribed for response to a fire-related event at the plant and...

  4. A Radiological Assessment Skills Training Program for the Radiation Worker at Shoreham Nuclear Power Station.

    ERIC Educational Resources Information Center

    Engel, Leonard, Jr.

    Radiation workers, by law, have the responsibility to maintain their exposure to radiation levels as low as possible. This responsibility has not been accepted. Instead, they have relied solely on the policing action of health physics (HP) technicians, thereby delegating their lawful responsibility. Continued overexposure in the U.S. nuclear power…

  5. A Radiological Assessment Skills Training Program for the Radiation Worker at Shoreham Nuclear Power Station.

    ERIC Educational Resources Information Center

    Engel, Leonard, Jr.

    Radiation workers, by law, have the responsibility to maintain their exposure to radiation levels as low as possible. This responsibility has not been accepted. Instead, they have relied solely on the policing action of health physics (HP) technicians, thereby delegating their lawful responsibility. Continued overexposure in the U.S. nuclear power…

  6. Performance testing of the environmental TLD system for the Three Mile Island Nuclear Station.

    PubMed

    Toke, L F; Carson, B H; Baker, G G; McBride, M H; Plato, P A; Miklos, J A

    1984-05-01

    Panasonic UD-801 thermoluminescent dosimeters ( TLDs ) containing two calcium sulfate phosphors were tested under Performance Specification 3.1 established by the American National Standard Institute ( ANSI75 ) and in the U.S. Nuclear Regulatory Commission's Regulatory Guide 4.13 ( NRC77 ). The specific qualifying tests included TLD uniformity, reproducibility, energy dependence and directional dependence. The overall measurement uncertainties and associated confidence levels are within the prescribed guidelines defined in the qualifying requirements for environmental TLDs .

  7. Establishing an effective dose equivalent monitoring program for a commercial nuclear power station

    NASA Astrophysics Data System (ADS)

    Thompson, Barbara Jane

    The purpose of this thesis is to determine whether monitoring personnel with multiple dosimeter badges to determine effective dose equivalent (EDE) is both acceptable to the Nuclear Regulatory Commission (NRC) and practical for the nuclear power industry. Until now, most nuclear power plants have used a single dosimeter or occasionally multiple dosimeters to monitor the "deep dose equivalent (DDE)" as defined by the International Commission on Radiological Units (ICRU). The measurement of EDE, to replace DDE, is now deemed by international and regulatory agencies to better approximate a worker's dose related to long-term risks of occupational radiation exposure. The definition of DDE, and the formulation of EDE for use as a new indicator of occupational exposure, are presented in this thesis. Radiation exposure measurements using multiple dosimeters on each worker for certain tasks were collected for this thesis on workers at a Dominion/Virginia Company nuclear power plant. These multiple dosimeter measurements have been examined to determine how such a new personnel monitoring system compares to the former one at the Dominion plant, in which only one dosimeter reading was used predominately to calculated deep dose equivalent. This is based on the assumption that most workers were exposed to uniform radiation fields and that the single dosimeter reading was representative of the highest average exposure for the worker's task. These multiple dosimetry measurements show that it is both feasible and advantageous to provide such dosimetry in situations where exposures may be non-uniform and significant enough to approach yearly exposure limits in a single day, such as in the tasks required during refueling outages.

  8. Wastewater treatment plant evaluation, McGuire AFB, New Jersey. Final report, 3-17 November 1986

    SciTech Connect

    Slavich, F.E.

    1987-03-01

    The USAFOEHL conducted a survey evaluating the wastewater treatment facility at McGuire AFB, New Jersey. The scope of the survey included the evaluation of: (1) individual-treatment-plant unit processes, (2) influent and effluent sewage quality, (3) treatment plant flow rates, and (4) operational and maintenance practices. Results of the survey showed that the plant was not meeting the 7-day NJPDES effluent standard for Total Phenols, Total Suspended Solids (TSS), and removal efficiency for TSS. Overall, the unit processes of the plant are performing adequately; notwithstanding correctable operation and maintenance difficulties. Recommendation: (1) Perform daily jar testing at the plant. (2) Clean the chlorine contact chamber. (3) Substitute EPA method 604 for EPA method 423 in determining effluent phenol concentration, if possible. (4) Repair the gaps between the clarifier walls and the overflow weirs. (5) Increase the trickling filter recirculation during periods of low influent flow. (6) Consider construction of an aerate wastewater equalization basin.

  9. Evaluation on the environmental radioactivity in Shanghai city during the normal operational condition of Qinshan nuclear power station.

    PubMed

    Lu, Heqing; Wang, Qiang

    2013-08-01

    The objective of this work was to evaluate the impact of environmental radioactivity in Shanghai from the operation of Qinshan Nuclear Power Station (QNPS). The levels of terrestrial gamma radiation and radioactivities in the drinking water, main food and soils in the Jinshan area where is only 38 km far away from the QNPS were continuously measured in the past 19 y. Both the levels of terrestrial gamma radiation and the radioactivities in the samples were on the normal background levels. No significant changes were found before and after the running of QNPS. The annual public exposure to the terrestrial gamma radiation was estimated to be ∼0.1 mSv, and the annual exposure from intakes of (90)Sr and (137)Cs in food was ∼0.5 μSv. In the past 19 y, no significant impact on the environmental radioactivity in Shanghai was observed due to the operation of QNPS.

  10. Risk-based evaluation of technical specification problems at the La Salle County Nuclear Station: Final report

    SciTech Connect

    Bizzak, D.J.; Trainer, J.E.; McClymont, A.S.

    1987-06-01

    Probabilistic risk assessment (PRA) methods are used to evaluate alternatives to existing requirements for three operationally burdensome technical specifications at La Salle Nuclear Station. The study employs a decision logic to minimize the detailed analysis necessary to show compliance with given acceptance criteria; in this case, no risk increase resulting from a proposed change. The analyses provide insights to choose from among alternative options. The SOCRATES computer code was used for the probabilistic analysis. Results support a change to less frequent diesel generator testing, eliminations of one reactor scram setpoint, and establishing an allowed out-of-service time for valves in a reactor scram system. In each case, the change would result in a safety improvement.

  11. Seismic structural fragility investigation for the San Onofre Nuclear Generating Station, Unit 1 (Project I); SONGS-1 AFWS Project

    SciTech Connect

    Wesley, D.A.; Hashimoto, P.S.

    1982-04-01

    An evaluation of the seismic capacities of several of the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1) structures was conducted to determine input to the overall probabilistic methodology developed by Lawrence Livermore National Laboratory. Seismic structural fragilities to be used as input consist of median seismic capacities and their variabilities due to randomness and uncertainty. Potential failure modes were identified for each of the SONGS-1 structures included in this study by establishing the seismic load-paths and comparing expected load distributions to available capacities for the elements of each load-path. Particular attention was given to possible weak links and details. The more likely failure modes were screened for more detailed investigation.

  12. Investigation of Main Radiation Source above Shield Plug of Unit 3 at Fukushima Daiichi Nuclear Power Station

    NASA Astrophysics Data System (ADS)

    Hiratama, Hideo; Kondo, Kenjiro; Suzuki, Seishiro; Tanimura, Yoshihiko; Iwanaga, Kohei; Nagata, Hiroshi

    2017-09-01

    Pulse height distributions were measured using a CdZnTe detector inside a lead collimator to investigate main source producing high dose rates above the shield plugs of Unit 3 at Fukushima Daiichi Nuclear Power Station. It was confirmed that low energy photons are dominant. Concentrations of Cs-137 under 60 cm concrete of the shield plug were estimated to be between 8.1E+9 and 5.7E+10 Bq/cm2 from the measured peak count rate of 0.662 MeV photons. If Cs-137 was distributed on the surfaces of the gaps with radius 6m and with the averaged concentration of 5 points, 2.6E+10 Bq/cm2, total amount of Cs-137 is estimated to be 30 PBq.

  13. Effects of the Chernobyl and Fukushima nuclear accidents on atmospheric electricity parameters recorded at Polish observation stations

    NASA Astrophysics Data System (ADS)

    Kubicki, Marek; Baranski, Piotr; Odzimek, Anna; Michnowski, Stanislaw; Myslek-Laurikainen, Bogna

    2013-04-01

    We analyse the atmospheric electricity parameters, measured at Polish geophysical stations in Swider, Poland, and Hornsund, Spitsbergen, in connection with the radioactive incident in Fukushima, Japan, beginning on 11 March 2011, following the 9.0 earthquake and tsunami. We compare our results with the situation during and after the Chernobyl disaster on April 26, 1986, when the radioactive fallout detected at Swider increased in the last week of April 1986, from 4.111 to 238.7 Bq/m2 and up to 967.0 Bq/m2 in the second week of May 1986 - what was more than 235 times greater than the values measured prior to that accident. Besides the electric field especially the electric conductivity is very sensitive to the radioactive contamination of the air. Thus we postulate that these two measurements should be run at geophysical stations over the world and used as a relatively simple and low-cost tool for continuous monitoring of possible hazard caused by nuclear power plant accidents.

  14. The key to superior water chemistry at a PWR nuclear station

    SciTech Connect

    Dolan, R.; Miller, L.K.; Olejar, L.L.; Salem, E.

    1983-01-01

    This paper demonstrates how a condensate polishing unit can be successfully used to treat the feedwater for circulating-type pressurized water reactors (PWRs). Water chemistry at the Salem Generating Station, a two-unit, four-loop Westinghouse PWR located in New Jersey, is discussed. Topics considered include a plant description and the history of early operation, the role of constant surveillance, makeup water quality, the effect of freezing on gel-type anion exchange resin, a total organic carbon (TOC) survey, steam generator chemistry, steam generator inspection, condensate polisher operation, and management philosophy. The SEPREX condensate polishing process, in which the complete separation of the anion exchange resin from the cation exchange resin is achieved by flotation separation, is examined. It is concluded that the utilization of a condensate polishing process such as SEPREX provides the operating personnel at the plant with the necessary means to maintain the minimum desired level of contaminants within the steam generator.

  15. Technical evaluation of RETS-required reports for Fort St. Vrain Nuclear Generating Station

    SciTech Connect

    Young, T E; Magleby, E H

    1985-06-14

    A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 6 refs.

  16. Comparison and evaluation of nuclear power plant options for geosynchronous power stations

    NASA Technical Reports Server (NTRS)

    Williams, J. R.

    1975-01-01

    The suitability of eleven types of nuclear fission reactors in combination with five potential energy conversion systems for use in geosynchronous power plants is evaluated. Gas turbine, potassium Rankine liquid metal MHD, and thermionic energy conversion systems are considered. The existing technology of reactors in near-term, intermediate-term, and long-term classes is discussed, together with modifications for use in large-scale power production in space. Unless the temperature is high enough for MHD, reactors which heat gases are generally more suitable for use with gas turbines. Those which heat liquid metals will be more useful for potassium Rankine or liquid metal MHD conversion systems.

  17. Comparison and evaluation of nuclear power plant options for geosynchronous power stations

    NASA Technical Reports Server (NTRS)

    Williams, J. R.

    1975-01-01

    The suitability of eleven types of nuclear fission reactors in combination with five potential energy conversion systems for use in geosynchronous power plants is evaluated. Gas turbine, potassium Rankine liquid metal MHD, and thermionic energy conversion systems are considered. The existing technology of reactors in near-term, intermediate-term, and long-term classes is discussed, together with modifications for use in large-scale power production in space. Unless the temperature is high enough for MHD, reactors which heat gases are generally more suitable for use with gas turbines. Those which heat liquid metals will be more useful for potassium Rankine or liquid metal MHD conversion systems.

  18. [Discirculatory encephalopathy in liquidators of the Chernobyl nuclear power station: a twenty-year study].

    PubMed

    Podsonnaia, I V; Shumakher, G I; Golovin, V A

    2009-01-01

    A comparative twenty-year study of 536 liquidators of the Chernobyl nuclear disaster and 436 patients without radiation anamnesis has been carried out. Discirculatory encephalopathy (DE) was more often developed in subjects exposed to radiation at the age 30 years. Compared to individuals from the general population, it is characterized by the earlier onset, malignant progression, rapid increase of signs of cerebral affection during the first two years after exposure to radiation, stability of clinical symptoms during the following 5-6 years and further progressive cerebral decompensation with early autonomic dysfunction, psychoorganic syndrome, epilepsy. Moreover, severe stroke is a common complication of DE in liquidators.

  19. Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Pilgrim Nuclear Power Station

    SciTech Connect

    Selan, J.C.

    1982-04-29

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Pilgrim Nuclear Power Station. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources.

  20. Magnetic Surveys for Mapping of Ultramafic Bodies on the Site of the Ohi Nuclear Power Station, Central Japan

    NASA Astrophysics Data System (ADS)

    Okuma, S.; Makino, M.; Miyakawa, A.; Nakatsuka, T.; Iwamori, A.; Tanaka, Y.; Kudo, S.; Yanagida, M.; Sasaki, T.; Sugimori, T.; Kitao, H.; Asahi, N.; Shiomi, T.; Higashida, Y.

    2016-12-01

    The Ohi nuclear power station is located at the northern Oshima Peninsula in the Wakasa Bay on the coast of Japan Sea, central Japan. The geology of the site of the power station is composed mainly of shales, diabases, gabbros and ultramafic rocks of the Paleozoic Yakuno Ophiolite. An evaluation of the power station on conformity to the new regulatory requirements for nuclear power plants has been conducted. Various surveys such as tectonic geomorphological, trenching and drilling were conducted to better understand the fracture zones in the gabbro and ultramafic complex. As a result, the fracture zones can be classified into two types: faults found only in the complex and landslides seen in the upper parts of the ultramafic bodies. Whereas, magnetic susceptibilities were measured for whole cores from drilling and the upper parts of the ultramafic bodies showed high magnetic susceptibilities (> 10-2 SI). To map the distribution of ultramafic bodies, we conducted magnetic surveys on ground and at sea around Daibahama beach in December 2015. A ground magnetic survey was carried out on a grid and along a specified line on a small peninsula and some reeves by using a proton magnetometer. A seaborne magnetic survey was also conducted by a small rubber boat on which a Cesium magnetometer was mounted. Both observed data were merged and an IGRF residual magnetic anomaly map was compiled. According to the map, several positive magnetic anomalies lie over the southeastern edge of the estimated distribution area of ultramafic bodies on land, while negative magnetic anomalies are dominant at the northwestern edge. Magnetic susceptibility and NRM measurements were carried out for columnar specimens sampled from drill cores. As a preliminary analysis, we conducted 2D modeling of the specific survey line on a basis of the rock magnetic measurements. A thin dipping-dike with a reverse magnetization can account for the observed magnetic anomalies. However there still remain

  1. Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations

    SciTech Connect

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W.; Morcos, N.

    1992-08-01

    The effects of varying pH and leachant compositions on the physical stability and leachability of radionuclides and chelating agents were determined for cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small scale waste-form specimens were collected during waste solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station. The collected specimens were leach tested, and their compressive strength was measured in accordance with the Nuclear Regulatory Commission`s ``Technical Position on Waste Form`` (Revision 1), from the Low-Level Waste Management Branch. Leachates from these studies were analyzed for radionuclides, selected transition metals, and chelating agents to assess the leachability of these waste form constituents. Leachants used for the study were deionized water, simulated seawater, and groundwater compositions similar to those found at Barnwell, South Carolina and Hanford, Washington. Results of this study indicate that initial leachant pH does not affect leachate pH or releases from cement-solidified decontamination ion-exchange resin waste forms. However, differences in leachant composition and the presence of chelating agents may affect the releases of radionuclides and chelating agents. In addition, results from this study indicate that the cumulative releases of radionuclides and chelating agents observed for forms that disintegrated were similar to those for forms that maintained their general physical integrity.

  2. Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations

    SciTech Connect

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W.; Morcos, N.

    1992-01-01

    The effects of varying pH and leachant compositions on the physical stability and leachability of radionuclides and chelating agents were determined for cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small scale waste-form specimens were collected during waste solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station. The collected specimens were leach tested, and their compressive strength was measured in accordance with the Nuclear Regulatory Commission's Technical Position on Waste Form'' (Revision 1), from the Low-Level Waste Management Branch. Leachates from these studies were analyzed for radionuclides, selected transition metals, and chelating agents to assess the leachability of these waste form constituents. Leachants used for the study were deionized water, simulated seawater, and groundwater compositions similar to those found at Barnwell, South Carolina and Hanford, Washington. Results of this study indicate that initial leachant pH does not affect leachate pH or releases from cement-solidified decontamination ion-exchange resin waste forms. However, differences in leachant composition and the presence of chelating agents may affect the releases of radionuclides and chelating agents. In addition, results from this study indicate that the cumulative releases of radionuclides and chelating agents observed for forms that disintegrated were similar to those for forms that maintained their general physical integrity.

  3. 78 FR 48724 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-09

    ...The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and issuing License Amendment No. 7 to Combined Licenses (COL), NPF-93 and NPF-94. The COLs were issued to South Carolina Electric and Gas (SCE&G) and South Carolina Public Service Authority (Santee Cooper) (the licensee), for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3 located in Fairfield County, South Carolina. The amendment changes requested revise the design of the bracing used to support the Turbine Building structure. This request requires changing Tier 1 information found in the Design Description portion of Updated Final Safety Analysis Report (UFSAR) section 3.3, ``Buildings.'' The granting of the exemption allows the changes to Tier 1 information asked for in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.

  4. The accident at TEPCO's Fukushima-Daiichi Nuclear Power Station: What went wrong and what lessons are universal?

    NASA Astrophysics Data System (ADS)

    Omoto, Akira

    2013-12-01

    After a short summary of the nuclear accident at the Fukushima Daiichi Nuclear Power Station, this paper discusses “what went wrong” by illustrating the problems of the specific layers of defense-in-depth (basic strategy for assuring nuclear safety) and “what lessons are universal.” Breaches in the multiple layers of defense were particularly significant in respective protection (a) against natural disasters (first layer of defense) as well as (b) against severe conditions, specifically in this case, a complete loss of AC/DC power and isolation from the primary heat sink (fourth layer of defense). Confusion in crisis management by the government and insufficient implementation of offsite emergency plans revealed problems in the fifth layer of defense. By taking into consideration managerial and safety culture that might have relevance to this accident, in the author's view, universal lessons are as follows: Resilience: the need to enhance organizational capabilities to respond, monitor, anticipate, and learn in changing conditions, especially to prepare for the unexpected. This includes increasing distance to cliff edge by knowing where it exists and how to increase safety margin. Responsibility: the operator is primarily responsible for safety, and the government is responsible for protecting public health and environment. For both, their right decisions are supported by competence, knowledge, and an understanding of the technology, as well as humble attitudes toward the limitations of what we know and what we can learn from others. Social license to operate: the need to avoid, as much as possible regardless of its probability of occurrence, the reasonably anticipated environmental impact (such as land contamination), as well as to build public confidence/trust and a renewed liability scheme.

  5. The Communication of Information Such as Evacuation Orders at the Time of a Nuclear Power Station Accident

    PubMed Central

    HATANAKA, Takashi; YOSHIDA, Sumito; OJINO, Mayo; ISHII, Masami

    2014-01-01

    This research was carried out from the perspective that the damage to the people of Fukushima and others from the Fukushima Daiichi Nuclear Power Station (NPS) accident was an “information disaster.” It evaluated the critical problems raised by and actual condition analysis on the process of events in the Fukushima Daiichi NPS disaster and responses of the governments and others, notification of the occurrence of the accident and evacuation order by the national and local governments and the evacuation of residents, and guidance for distribution and intake of stable iodine tablets. The research aimed to provide a basis for the implementation of effective distribution and intake of stable iodine tablets and responses to the “information disaster” in the nuclear power disaster. On March 15 at the time that the most radioactive substances were dispersed, even when the average wind speed at the site area was 1.6 m/s, the radioactive substances had reached the outer boundary of Urgent Protective action planning Zone (UPZ, the region with a radius of 30 km) within about five hours. Because of this, every second counted in the provision of information about the accident and the issuance of evacuation orders. This study evaluated the actual condition of information provision by the national government and others from the perspective of this awareness of the importance of time. On the basis of the results of this kind of consideration, we come to the following recommendations: The Nuclear Emergency Response Guidelines and the system for communication of information to medical providers should be revised. The national government should make preparations for the effective advance distribution and intake of stable iodine tablets. PMID:26557446

  6. Optimization of the calibration graph for the determination of anions in the heat carrier of a nuclear power station by two-column ion chromatography

    SciTech Connect

    Bragina, N.V.; Karpyuk, A.D.

    1995-10-01

    Methods upgrading the reliability of analyzing Cl{sup -} and SO{sub 4}{sup 2-} ions in the heat carrier of a nuclear power station are considered. The use of a multilevel calibration plot and eluent-modifying additives is shown to provide reliable determination of the above-mentioned ions in the range of 0.5-20 {mu}g/liter.

  7. [Features of cardiovascular diseases in cleaners-up of consequences of the Chernobyl Nuclear Power Station accident and in residents of territories polluted by radionuclides].

    PubMed

    Babkin, A P; Choporov, O N; Kuralesin, N A

    2002-01-01

    The authors discuss features of cardiovascular diseases in liquidators of Chernobyl nuclear power station accident consequences and in residents of territories polluted with radionuclides, present recommendations on correction of risk factors leading to atherosclerosis--the main cause of cardiovascular complications.

  8. Improving the high-pressure cylinder of the K-220-44-2M turbine at the Loviisa nuclear power station

    NASA Astrophysics Data System (ADS)

    Shvetsov, V. L.; Kozheshkurt, I. I.; Konev, V. A.; Boiko, A. V.; Usatyi, A. P.; Solodov, V. G.; Khandrimailov, A. A.

    2013-02-01

    Results from calculation and design elaborations and numerical investigations aimed at improving the high-pressure cylinder's flow path and steam admission system's stop valves of the K-220-44-2M turbine installed at the Loviisa nuclear power station are discussed.

  9. Environmental radiological studies downstream from the Rancho Seco Nuclear Power Generating Station, 1985

    SciTech Connect

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Brunk, J.L.; Jokela, T.A.

    1986-02-06

    Information compiled in 1985 while assessing the environmental impact of radionuclides previously discharged with aqueous releases from the Rancho Seco Nuclear Power Generating Plant is presented. In October 1984, the quantities of gamma-emitting radionuclides in water discharged to Clay Creek from the plant were reduced below operationally defined detection limits for liquid effluents. However, radionuclides previously discharged persist in the downstream environment and are found in many aquatic dietary components. /sup 134/Cs and /sup 137/Cs are the primary gamma-emitting radionuclides detected in the edible flesh of different fish, crayfish, and frogs. Coefficients for exponential equations are generated, from a least square analysis, that relate the change in concentration of /sup 137/Cs in fish to distance downstream and time between March and October 1985. Concentrations of /sup 137/Cs in surface creek sediments also decreased in the downstream direction much in the same manner as concentrations decreased in fish. However, there was no significant difference in the radiocesium concentrations in surface sediements collected from comparable locations during both 1984 and 1985.

  10. Water chemistry of the secondary circuit at a nuclear power station with a VVER power reactor

    NASA Astrophysics Data System (ADS)

    Tyapkov, V. F.; Erpyleva, S. F.

    2017-05-01

    Results of implementation of the secondary circuit organic amine water chemistry at Russian nuclear power plant (NPP) with VVER-1000 reactors are presented. The requirements for improving the reliability, safety, and efficiency of NPPs and for prolonging the service life of main equipment items necessitate the implementation of new technologies, such as new water chemistries. Data are analyzed on the chemical control of power unit coolant for quality after the changeover to operation with the feed of higher amines, such as morpholine and ethanolamine. Power units having equipment containing copper alloy components were converted from the all-volatile water chemistry to the ethanolamine or morpholine water chemistry with no increase in pH of the steam generator feedwater. This enables the iron content in the steam generator feedwater to be decreased from 6-12 to 2.0-2.5 μg/dm3. It is demonstrated that pH of high-temperature water is among the basic factors controlling erosion and corrosion wear of the piping and the ingress of corrosion products into NPP steam generators. For NPP power units having equipment whose construction material does not include copper alloys, the water chemistries with elevated pH of the secondary coolant are adopted. Stable dosing of correction chemicals at these power units maintains pH25 of 9.5 to 9.7 in the steam generator feedwater with a maximum iron content of 2 μg/dm3 in the steam generator feedwater.

  11. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    SciTech Connect

    GREENE,G.A.; GUPPY,J.G.

    1998-08-01

    This is the final report on the INSP project entitled, ``Kola Confinement Leaktightness'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.1. This project was initiated in February 1993 to assist the Russians to reduce risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Units 1 and 2, through upgrades in the confinement performance to reduce the uncontrolled leakage rate. The major technical objective of this-project was to improve the leaktightness of the Kola NPP VVER confinement boundaries, through the application of a variety of sealants to penetrations, doors and hatches, seams and surfaces, to the extent that current technology permitted. A related objective was the transfer, through training of Russian staff, of the materials application procedures to the staff of the Kola NPP. This project was part of an overall approach to minimizing uncontrolled releases from the Kola NPP VVER440/230s in the event of a serious accident, and to thereby significantly mitigate the consequences of such an accident. The US provided materials, application technology, and applications equipment for application of sealant materials, surface coatings, potting materials and gaskets, to improve the confinement leaktightness of the Kola VVER-440/23Os. The US provided for training of Russian personnel in the applications technology.

  12. Organohalogen products from chlorination of cooling water at nuclear power stations

    SciTech Connect

    Bean, R.M.

    1983-10-01

    Eight nuclear power units at seven locations in the US were studied to determine the effects of chlorine, added as a biocide, on the composition of cooling water discharge. Water, sediment and biota samples from the sites were analyzed for total organic halogen and for a variety of organohalogen compounds. Haloforms were discharged from all plants studied, at concentrations of a few ..mu..g/L (parts-per-billion). Evidence was obtained that power plants with cooling towers discharge a significant portion of the haloforms formed during chlorination to the atmosphere. A complex mixture of halogenated phenols was found in the cooling water discharges of the power units. Cooling towers can act to concentrate halogenated phenols to levels approaching those of the haloforms. Examination of samples by capillary gas chromatography/mass spectrometry did not result in identification of any significant concentrations of lipophilic base-neutral compounds that could be shown to be formed by the chlorination process. Total concentrations of lipophilic (Bioabsorbable) and volatile organohalogen material discharged ranged from about 2 to 4 ..mu..g/L. Analysis of sediment samples for organohalogen material suggests that certain chlorination products may accumulate in sediments, although no tissue bioaccumulation could be demonstrated from analysis of a limited number of samples. 58 references, 25 figures, 31 tables.

  13. Pu isotopes in the western North Pacific Ocean before the accident at Fukushima Dai-ichi Nuclear Power Station

    NASA Astrophysics Data System (ADS)

    Yamada, M.; Zheng, J.; Aono, T.

    2011-12-01

    Anthropogenic radionuclides such as Pu-239 (half-life: 24100 yr), Pu-240 (half-life: 6560 yr) and Pu-241 (half-life: 14.325 yr) mainly have been released into the environment as the result of atmospheric nuclear weapons testing. In the North Pacific Ocean, two distinct sources of Pu isotopes can be identified; i.e., the global stratospheric fallout and close-in tropospheric fallout from nuclear weapons testing at the Pacific Proving Grounds in the Marshall Islands. The atom ratio of Pu-240/Pu-239 is a powerful fingerprint to identify the sources of Pu in the ocean. The Pu-240/Pu-239 atom ratios in seawater and marine sediment samples collected in the western North Pacific before the accident at Fukushima Dai-ichi Nuclear Power Station will provide useful background data for understanding the process controlling Pu transport and for distinguishing future Pu sources. The atom ratios of Pu-240/Pu-239 in water columns from the Yamato and Tsushima Basins in the Japan Sea were significantly higher than the mean global fallout ratio of 0.18; however, there were no temporal variation of atom ratios during the period from 1984 to 1993 in the Japan Sea. The total Pu-239+240 inventories in the whole water columns were approximately doubled during the period from 1984 to 1993 in the two basins. The atom ratio of Pu-240/Pu-239 in surface water from Sagami Bay, western North Pacific Ocean, was 0.224 and showed no notable variation from the surface to the bottom with the mean atom ratio being 0.234. The atom ratios for the Pacific coast, near the Rokkasho nuclear fuel reprocessing plant, were approximately the same as the 0.224 ratio obtained from Sagami Bay, western North Pacific margin. The atom ratios in the surficial sediments from Sagami Bay ranged from 0.229 to 0.247. The mean atom ratio in the sediment columns in the East China Sea ranged from 0.248 for the Changjiang estuary to 0.268 for the shelf edge. The observed atom ratios were significantly higher than the mean

  14. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, December 1981-February 1982

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1982-08-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the winter of 1981, the generating station experienced a prolonged outage. The reproductive cycle of the shipworms was not extended. Teredo bartschi was very abundant at one station in Oyster Creek and moderately abundant at a second, but did not exist elsewhere in Barnegat Bay. Some specimens of Teredo bartschi contained larvae in the gills in February. According to laboratory experiments, Teredo navalis is able to remain active at temperatures as low as 4/sup 0/C, whereas T. bartschi ceases activity (withdraws its siphons) at about 13/sup 0/C. 12 tables.

  15. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, March-May 1982

    SciTech Connect

    Hoagland, K.E.

    1982-11-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. The adult population of Teredo bartschi survived the winter and spring of 1981-1982 better than it did previous cold periods without a thermal effluent. Lack of an effluent was due to a prolonged outage of the generating station. There was no spring outbreak of shipworms. The introduced species appears established at one station near but outside of Oyster Creek. Three teredinid species coexist in Oyster Creek. Larvae of T. bartschi and T. navalis have similar responses to reduced salinity. Bankia gouldi is the fastest-growing of the teredinids found in New Jersey, and as the lowest annual mortality.

  16. Hazardous Waste Staff Assistance Survey, McGuire AFB, New Jersey.

    DTIC Science & Technology

    1987-04-01

    direct requests for copies of this report to: Defense Technical Information Center (DTIC), Cameron Station, Alexandria VA 22314. Non-Government agencies...may purchase copies of this report from: National Technical Information Service (NTIS), 5285 Port Royal Road, Springfield VA 22161 The Public Affairs...Office has reviewed this report, and it is releasable to the National Technical Information Service, where it will be available to the general public

  17. ASSESSMENT OF RADIONUCLIDE RELEASE FROM INTACT STRUCTURES BACKFILLED WITH CONTAMINATED CONCRETE AT THE YANKEE NUCLEAR POWER STATION.

    SciTech Connect

    SULLIVAN, T.

    2004-09-30

    This calculation determines the release of residual radioactivity (including H-3, C-14, Co-60, Ni-63, Sr-90, and Cs-137), from subsurface structures filled with concrete debris at the Yankee Nuclear Power Station. Analyses were performed to assess the rate of release from the source of contamination and the resulting dose in the groundwater pathway. Two mechanisms were considered, diffusive release from the concrete structures (walls and floors) that remain intact and sorption onto concrete backfill placed within these structures. RESRAD was used to calculate the predicted maximum dose assuming a unit loading of 1 pCi/g on the intact structures. To the extent possible, the same assumptions in the soil DCGL calculations performed for Yankee Atomic were used in the calculation. However, modifications to some input parameter values were needed to represent the geometry of the subsurface facilities, flow through these facilities, and releases from the backfill and intact structures. Input parameters specific to these calculations included the leach rate, disposal geometry, pumping rate, porosity and bulk density. The dose results for a unit loading of 1 pCi/g on intact structures showed that Sr-90 had the highest dose (3.67E-02 mrem/yr).

  18. Updating source term and atmospheric dispersion simulations for the dose reconstruction in Fukushima Daiichi Nuclear Power Station Accident

    NASA Astrophysics Data System (ADS)

    Nagai, Haruyasu; Terada, Hiroaki; Tsuduki, Katsunori; Katata, Genki; Ota, Masakazu; Furuno, Akiko; Akari, Shusaku

    2017-09-01

    In order to assess the radiological dose to the public resulting from the Fukushima Daiichi Nuclear Power Station (FDNPS) accident in Japan, especially for the early phase of the accident when no measured data are available for that purpose, the spatial and temporal distribution of radioactive materials in the environment are reconstructed by computer simulations. In this study, by refining the source term of radioactive materials discharged into the atmosphere and modifying the atmospheric transport, dispersion and deposition model (ATDM), the atmospheric dispersion simulation of radioactive materials is improved. Then, a database of spatiotemporal distribution of radioactive materials in the air and on the ground surface is developed from the output of the simulation. This database is used in other studies for the dose assessment by coupling with the behavioral pattern of evacuees from the FDNPS accident. By the improvement of the ATDM simulation to use a new meteorological model and sophisticated deposition scheme, the ATDM simulations reproduced well the 137Cs and 131I deposition patterns. For the better reproducibility of dispersion processes, further refinement of the source term was carried out by optimizing it to the improved ATDM simulation by using new monitoring data.

  19. [Peculiarities of the neurological status and electroencephalogram in operators of the control unit of nuclear power station].

    PubMed

    Laskova, I V; Tret'iakova, E E

    2008-01-01

    One hundred and five operators of the control unit of the Kursk nuclear power station (NPS) have been studied: 45 people after the shift (main group) and 60 - in the day off. The shift was found to exert a significant influence on the functional state of the nervous system promoting the development or aggravation of autonomous dysfunction. In some cases, it causes an elevation of blood pressure to the level of risk for cerebral vascular disease. The effect of shift on the cerebral bioelectric activity of NPS operators manifests itself in the decrease of percentage of unchanged EEG, increase of alpha-rhythm spectral power density in the parietal leads and theta-rhythm in the posterior temporal and parietal leads. These changes may be caused by weariness as well as the effects of adverse factors the operators were exposed to at the NPS. The authors suggest to include the methods of evaluating of autonomous dysfunction and recording of alpha-rhythm spectral power density in the parietal leads and theta-rhythm in the posterior temporal and parietal leads in a special clinical examination of NPS operators.

  20. The activity of superoxide dismutase in animal liver and erythrocyte at Sea Area nearby Dayawan Nuclear Power Station

    SciTech Connect

    Cheng, Ge; Cai, Yana; Chen, Huizhen

    1995-11-01

    Many tests, the effect of ionizing radiation on SOD in vivo and vitro, had proved that the irradiation can cause the SOD activity to decrease with the increase of irradiation dose, change some physicochemical properties and structure. This artical was to study the activity of SOD in Fish (Thearpon jorbua) and Toad(Bufo melanostictus) liver erythrocyte at sea area nearby Dayawan Nuclear Power Station (Nps). We found that the SOD activity in fish liver, after NPS revolved one year, was higher than that of before revoling (7.30 {plus_minus} 1.35U/mg protein, 5.49 {plus_minus}1.56 U/mg protein respectively). The SOD activity in the toad liver at NPS revolving one year after was decreased (4.54 {plus_minus} 0.75 U/mg protein 5.68{plus_minus} 1.49U/mg protein P < 0.001) but in erythrocyte increased (2.32 {plus_minus} 0.75 U/mg Hb, 0.70 {plus_minus} 0.33 U/mg Hb P < 0.001). These results indicated that the SOD activity was changed in different with the animal variety. The effect of irradiation on fish at present was absent, on toad need to research in the future.

  1. Chernobyl doses. Volume 3. Habitat and vegetation near the Chernobyl Nuclear Reactor Station. Technical report, 29 September 1987-28 February 1992

    SciTech Connect

    Painter, E.L.; Whicker, F.W.

    1993-01-01

    This volume presents a detailed exposition on the soils, climate, and vegetation of the Poles'ye region of Ukraine and Belorussia with emphasis on the area around the Chernobyl Nuclear Reactor Station. This data provides background for interpretation of multispectral satellite imagery of the area. Volume 1 uses these images and the information of this report to analyze the radiation response of the canopy of the coniferous forests in the immediate vicinity of the reactor station after the accident of 26 April 1986.... Chernobyl, Forest damage, Landsat, Change detection, Conifer stress, Fallout, Ionizing radiation, Multispectral imagery.

  2. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Quarterly report, 1 September-30 November 1980

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1981-04-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Relative destructiveness and competition among the species are being analyzed. The native species Teredo navalis and Bankia gouldi coexist with the introduced T. bartschi in Oyster Creek and at the mouth of Forked River.

  3. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report 1 Jun-31 Aug 80

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1981-02-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Relative destructiveness and competition among the species are being analyzed. The native species Teredo navalis and Bankia gouldi coexist with the introduced T. bartschi in Oyster Creek. Teredo bartschi can withstand higher temperatures than the native species, but all species suffer osmotic stress at 6 parts per thousand by weight.

  4. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Quarterly progress report 1 Dec 80-28 Feb 81

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1981-08-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Relative destructiveness and competition among the species are being analyzed. The native species Teredo navalis and Bankia gouldi coexist with the introduced T. bartschi in Oyster Creek and at the mouth of Forked River. An increase in mortality occurred in January. By February, Teredo bartschi was found only at Bayside.

  5. Superfund Record of Decision (EPA Region 1): Baird and McGuire, Holbrook, Massachusetts (Third remedial action), September 1989

    SciTech Connect

    Not Available

    1989-09-14

    The Baird McGuire site is a former chemical manufacturing facility in northwest Holbrook, Massachusetts, approximately 14 miles south of Boston. From 1912 to 1983 the company operated a chemical manufacturing and batching facility on the property. Manufactured products included herbicides, pesticides, disinfectants, soaps, floor waxes and solvents. Waste disposal methods at the site included direct discharge into the soil, nearby brook and wetlands, and a former gravel pit (now covered) in the eastern portion of the site. Underground disposal systems were also used. EPA also conducted an Initial Remedial Measure at the site from 1985 through 1987 which involved constructing a new water main to direct water away from the site, removing building structures, and installing a temporary cap. In 1986 a Record of Decision (ROD) was signed to address onsite ground water treatment and incineration of contaminated soil. This ROD addresses the Cochato River sediment contamination. The primary contaminants of concern affecting the sediment are organics including PAHs and pesticides, and metals including arsenic. The selected remedial action for the site are included.

  6. Superfund Record of Decision (EPA Region 1): Baird and McGuire, MA. (Third remedial action), September 1989

    SciTech Connect

    Not Available

    1989-09-14

    The Baird and McGuire site is a former chemical manufacturing facility in northwest Holbrook, Massachusetts, approximately 14 miles south of Boston. From 1912 to 1983 the company operated a chemical manufacturing and batching facility on the property. Manufactured products included herbicides, pesticides, disinfectants, soaps, floor waxes and solvents. Waste disposal methods at the site included direct discharge into the soil, nearby brook and wetlands, and a former gravel pit (now covered) in the eastern portion of the site. EPA conducted a removal action at the site in 1983 after a waste lagoon overflowed spreading contaminants into the Cochato River. The company ceased operating shortly thereafter. A second removal action was conducted in 1985, following the discovery of dioxin in site soils. EPA also conducted an Initial Remedial Measure at the site from 1985 through 1987 which involved constructing a new water main to direct water away from the site, removing building structures, and installing a temporary cap. The primary contaminants of concern affecting the sediment are organics including PAHs and pesticides, and metals including arsenic.

  7. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, 1 March-31 May 1980

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1980-12-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. The native species Teredo navalis and Bankia gouldi coexist with the introduced T. bartschi in Oyster Creek, at the mouth of Forked River and on the coast of the bay between the two creeks. Heavy mortality occurred in all species during winter and spring when the generating station was not operating. Temperature and salinity tolerance tests begun during April and May, 1980, were not completed by the end of May because the adult shipworms proved to be very resistant to drastic changes in these physical parameters.

  8. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Interim report 1 Sep 79-28 Feb 80

    SciTech Connect

    Hoagland, K.E.; Crocket, L.; Turner, R.D.

    1980-11-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Relative destructiveness and competition among the species are being analyzed. Teredo bartschi caused almost complete destruction of panels in Oyster Creek during the summer of 1979. Reproduction and settlement of this species continued into October. The native species Teredo navalis and Bankia gouldi coexist with T. bartschi in Oyster Creek. The greatest shipworm damage is in Oyster Creek. Heavy mortality occurs in all species during winter, especially in winters such as 1979-80 when the generating station is not operating. Adults of all three species can survive for at least 30 days at salinities from 5 to 45 parts per thousand by weight. They can withstand abrupt salinity changes.

  9. Technical evaluation of the proposed design modifications and technical specification changes on grid voltage degradation (Part A) for the Pilgrim Nuclear Power Station, Unit 1

    SciTech Connect

    White, R.L.

    1980-01-01

    This report documents the technical evaluation of the proposed design modifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Pilgrim Nuclear Power Station. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system.

  10. Solid radioactive waste management facility design for managing CANDU{sup R} 600 MW nuclear generating station re-tube/refurbishment Waste Streams

    SciTech Connect

    Pontikakis, N.; Hopkins, J.; Scott, D.; Bajaj, V.; Nosella, L.

    2007-07-01

    The main design features of the re-tube canisters, waste handling equipment and waste containers designed by Atomic Energy of Canada Limited (AECL{sup R}) and implemented in support of the re-tube/refurbishment activities for Candu 600 MW nuclear generating stations are described in this paper. The re-tube/refurbishment waste characterization and the waste management principles, which form the basis of the design activities, are also briefly outlined. (authors)

  11. Evaluation of the Submerged Demineralizer System (SDS) flowsheet for decontamination of high-activity-level water at the Three Mile Island Unit 2 Nuclear Power Station

    SciTech Connect

    Campbell, D. O.; Collins, E. D.; King, L. J.; Knauer, J. B.

    1980-07-01

    This report discusses the Submerged Demineralizer System (SDS) flowsheet for decontamination of the high-activity-level water at the Three Mile Island Unit 2 Nuclear Power Station was evaluated at Oak Ridge National Laboratory in a study that included filtration tests, ion exchange column tests, and ion exchange distribution tests. The contaminated waters, the SDS flowsheet, and the experiments made are described. The experimental results were used to predict the SDS performance and to indicate potential improvements.

  12. Improved sampling and analytical techniques for characterization of very-low-level radwaste materials from commercial nuclear power stations

    SciTech Connect

    Robertson, D.E.; Robinson, P.J.

    1989-11-01

    This paper summarizes the unique sampling methods that were utilized in a recently completed project sponsored by the Electric Power Research Institute (EPRI) to perform accurate and precise radiological characterizations of several very-low-level radwaste materials from commercial nuclear power stations. The waste types characterized during this project included dry active waste (DAW), oil, secondary-side ion exchange resin, and soil. Special precautions were taken to insure representative sampling of the DAW. This involved the initial direct, quantitative gamma spectrometric analyses of bulk quantities (208-liter drums) of DAW utilizing a specially constructed barrel scanner employing a collimated intrinsic germanium detector assembly. Subsamples of the DAW for destructive radiochemical analyses of the difficult-to-measure 10CF61 radionuclides were then selected which had the same isotopic composition (to within {+-}25%) as that measured for the entire drum of DAW. The techniques for accomplishing this sampling are described. Oil samples were collected from the top, middle and bottom sections of 208-liter drums for radiochemical analyses. These samples were composited to represent the entire drum of oil. The accuracy of this type of sampling was evaluated by comparisons with direct, quantitative assays of a number of the drums using the barrel scanning gamma-ray spectrometer. The accuracy of sampling drums of spent secondary-side ion exchange resin was evaluated by comparing the radionuclide contents of grab samples taken from the tops of the drums with direct assays performed with the barrel scanner. The results of these sampling evaluations indicated that the sampling methods used were generally adequate for providing a reasonably representative subsample from bulk quantities of DAW, oil, and resin. The study also identified a number of potential pitfalls, in sampling of these materials.

  13. Estimating cancer risk in relation to tritium exposure from routine operation of a nuclear-generating station in Pickering, Ontario.

    PubMed

    Wanigaratne, S; Holowaty, E; Jiang, H; Norwood, T A; Pietrusiak, M A; Brown, P

    2013-09-01

    Evidence suggests that current levels of tritium emissions from CANDU reactors in Canada are not related to adverse health effects. However, these studies lack tritium-specific dose data and have small numbers of cases. The purpose of our study was to determine whether tritium emitted from a nuclear-generating station during routine operation is associated with risk of cancer in Pickering, Ontario. A retrospective cohort was formed through linkage of Pickering and north Oshawa residents (1985) to incident cancer cases (1985-2005). We examined all sites combined, leukemia, lung, thyroid and childhood cancers (6-19 years) for males and females as well as female breast cancer. Tritium estimates were based on an atmospheric dispersion model, incorporating characteristics of annual tritium emissions and meteorology. Tritium concentration estimates were assigned to each cohort member based on exact location of residence. Person-years analysis was used to determine whether observed cancer cases were higher than expected. Cox proportional hazards regression was used to determine whether tritium was associated with radiation-sensitive cancers in Pickering. Person-years analysis showed female childhood cancer cases to be significantly higher than expected (standardized incidence ratio [SIR] = 1.99, 95% confidence interval [CI]: 1.08-3.38). The issue of multiple comparisons is the most likely explanation for this finding. Cox models revealed that female lung cancer was significantly higher in Pickering versus north Oshawa (HR = 2.34, 95% CI: 1.23-4.46) and that tritium was not associated with increased risk. The improved methodology used in this study adds to our understanding of cancer risks associated with low-dose tritium exposure. Tritium estimates were not associated with increased risk of radiationsensitive cancers in Pickering.

  14. Sorption (Kd) measurements on cinder block and grout in support of dose assessments for Zion Nuclear Station decommissioning

    SciTech Connect

    Milian L.; Sullivan T.

    2014-06-24

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with a backfill to provide structural support. Backfills under consideration include “clean” concrete demolition debris from the above grade parts of the facility, a flowable grout, cinder block construction debris and sand. A previous study (Yim, 2012) examined the sorption behavior of five nuclides (Fe-55, Co-60, Ni-63, Sr-85, and Cs-137) on concrete and local soils. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) examines the sorption behavior on cinder block and grout materials. Specifically, this study measured the distribution coefficient for four radionuclides of concern using site-groundwater and cinder block from the Zion site and a flowable grout. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the solid material that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides examined in this set of tests were Co-60, Ni-63, Sr-85, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90.

  15. "Life without nuclear power": A nuclear plant retirement formulation model and guide based on economics. San Onofre Nuclear Generating Station case: Economic impacts and reliability considerations leading to plant retirement

    NASA Astrophysics Data System (ADS)

    Wasko, Frank

    Traditionally, electric utilities have been slow to change and very bureaucratic in nature. This culture, in and of itself, has now contributed to a high percentage of United States electric utilities operating uneconomical nuclear plants (Crooks, 2014). The economic picture behind owning and operating United States nuclear plants is less than favorable for many reasons including rising fuel, capital and operating costs (EUCG, 2012). This doctoral dissertation is specifically focused on life without nuclear power. The purpose of this dissertation is to create a model and guide that will provide electric utilities who currently operate or will operate uneconomical nuclear plants the opportunity to economically assess whether or not their nuclear plant should be retired. This economic assessment and stakeholder analysis will provide local government, academia and communities the opportunity to understand how Southern California Edison (SCE) embraced system upgrade import and "voltage support" opportunities to replace "base load" generation from San Onofre Nuclear Generating Station (SONGS) versus building new replacement generation facilities. This model and guide will help eliminate the need to build large replacement generation units as demonstrated in the SONGS case analysis. The application of The Nuclear Power Retirement Model and Guide will provide electric utilities with economic assessment parameters and an evaluation assessment progression needed to better evaluate when an uneconomical nuclear plant should be retired. It will provide electric utilities the opportunity to utilize sound policy, planning and development skill sets when making this difficult decision. There are currently 62 nuclear power plants (with 100 nuclear reactors) operating in the United States (EIA, 2014). From this group, 38 are at risk of early retirement based on the work of Cooper (2013). As demonstrated in my model, 35 of the 38 nuclear power plants qualify to move to the economic

  16. Multiscale Speciation of U and Pu at Chernobyl, Hanford, Los Alamos, McGuire AFB, Mayak, and Rocky Flats.

    PubMed

    Batuk, Olga N; Conradson, Steven D; Aleksandrova, Olga N; Boukhalfa, Hakim; Burakov, Boris E; Clark, David L; Czerwinski, Ken R; Felmy, Andrew R; Lezama-Pacheco, Juan S; Kalmykov, Stepan N; Moore, Dean A; Myasoedov, Boris F; Reed, Donald T; Reilly, Dallas D; Roback, Robert C; Vlasova, Irina E; Webb, Samuel M; Wilkerson, Marianne P

    2015-06-02

    The speciation of U and Pu in soil and concrete from Rocky Flats and in particles from soils from Chernobyl, Hanford, Los Alamos, and McGuire Air Force Base and bottom sediments from Mayak was determined by a combination of X-ray absorption fine structure (XAFS) spectroscopy and X-ray fluorescence (XRF) element maps. These experiments identify four types of speciation that sometimes may and other times do not exhibit an association with the source terms and histories of these samples: relatively well ordered PuO2+x and UO2+x that had equilibrated with O2 and H2O under both ambient conditions and in fires or explosions; instances of small, isolated particles of U as UO2+x, U3O8, and U(VI) species coexisting in close proximity after decades in the environment; alteration phases of uranyl with other elements including ones that would not have come from soils; and mononuclear Pu-O species and novel PuO2+x-type compounds incorporating additional elements that may have occurred because the Pu was exposed to extreme chemical conditions such as acidic solutions released directly into soil or concrete. Our results therefore directly demonstrate instances of novel complexity in the Å and μm-scale chemical speciation and reactivity of U and Pu in their initial formation and after environmental exposure as well as occasions of unexpected behavior in the reaction pathways over short geological but significant sociological times. They also show that incorporating the actual disposal and site conditions and resultant novel materials such as those reported here may be necessary to develop the most accurate predictive models for Pu and U in the environment.

  17. 77 FR 21815 - South Carolina Electric And Gas Company (Virgil C. Summer Nuclear Station Units 2 and 3); Order...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-11

    ... after about 70 hours, and in the Unit 3 reactor after about 36 hours, resulting in damage to the nuclear... the general design criteria (GDC) for nuclear power plants. All currently operating reactors were... hearing must be made in writing to the Director, Office of New Reactors, U.S. Nuclear...

  18. International challenge to predict the impact of radioxenon releases from medical isotope production on a comprehensive nuclear test ban treaty sampling station

    SciTech Connect

    Eslinger, Paul W.; Bowyer, Ted W.; Achim, Pascal; Chai, Tianfeng; Deconninck, Benoit; Freeman, Katie; Generoso, Sylvia; Hayes, Philip; Heidmann, Verena; Hoffman, Ian; Kijima, Yuichi; Krysta, Monika; Malo, Alain; Maurer, Christian; Ngan, Fantine; Robins, Peter; Ross, J. Ole; Saunier, Olivier; Schlosser, Clemens; Schöppner, Michael; Schrom, Brian T.; Seibert, Petra; Stein, Ariel F.; Ungar, Kurt; Yi, Jing

    2016-06-01

    Abstract The International Monitoring System (IMS) is part of the verification regime for the Comprehensive Nuclear-Test-Ban-Treaty Organization (CTBTO). At entry-into-force, half of the 80 radionuclide stations will be able to measure concentrations of several radioactive xenon isotopes produced in nuclear explosions, and then the full network may be populated with xenon monitoring afterward (Bowyer et al., 2013). Fission-based production of 99Mo for medical purposes also releases radioxenon isotopes to the atmosphere (Saey, 2009). One of the ways to mitigate the effect of emissions from medical isotope production is the use of stack monitoring data, if it were available, so that the effect of radioactive xenon emissions could be subtracted from the effect from a presumed nuclear explosion, when detected at an IMS station location. To date, no studies have addressed the impacts the time resolution or data accuracy of stack monitoring data have on predicted concentrations at an IMS station location. Recently, participants from seven nations used atmospheric transport modeling to predict the time-history of 133Xe concentration measurements at an IMS station in Germany using stack monitoring data from a medical isotope production facility in Belgium. Participants received only stack monitoring data and used the atmospheric transport model and meteorological data of their choice. Some of the models predicted the highest measured concentrations quite well (a high composite statistical model comparison rank or a small mean square error with the measured values). The results suggest release data on a 15 min time spacing is best. The model comparison rank and ensemble analysis suggests that combining multiple models may provide more accurate predicted concentrations than any single model. Further research is needed to identify optimal methods for selecting ensemble members and those methods may depend on the specific transport problem. None of the submissions based only

  19. Assessing the possible radiological impact of routine radiological discharges from proposed nuclear power stations in England and Wales.

    PubMed

    Jones, Alison; Jones, Kelly; Holmes, Sheila; Ewers, Leon; Cabianca, Tiberio

    2013-03-01

    The aim of this work is to assess the possible radiological impact on the population of the United Kingdom (UK) from new nuclear power stations proposed for up to eight sites in England and Wales. The radiological impact was measured in terms of collective dose to the UK, European and world populations from a single year's discharge integrated to 500 and 100 000 years and the annual dose to an average member of the UK population (known as the per-caput dose). The doses were calculated for two reactor types, UK EPR™ and AP1000™, using the annual expected discharges estimated by the designers of the reactors and assuming two reactors per site. In addition, typical individual doses to adults living close to the sites were calculated on the basis of continuous discharges for 60 years (the assumed lifetime of the reactors). The dose to a representative person (previously known as the critical group) was not calculated, as this has been done elsewhere. The assessments were carried out using the software program PC-CREAM 08(®) which implements the updated European Commission methodology for assessing the radiological impact of routine releases of radionuclides to the environment. The collective dose truncated to 500 years to the UK population was estimated to be 0.5 manSv assuming UK EPR reactors on all sites and 0.6 manSv assuming AP1000s on three sites with UK EPRs on the other sites. The most significant contribution to the collective dose to the UK population is due to the global circulation of carbon-14 released to the atmosphere. The annual dose to an average member of the UK population from all sites was calculated to be around 10 nSv y(-1) and would therefore contribute little to an individual's total radiation dose. All the calculated doses to a typical adult living near the sites assuming continuous discharges for 60 years were found to be below 1 μSv y(-1).

  20. The risk of leukaemia in young children from exposure to tritium and carbon-14 in the discharges of German nuclear power stations and in the fallout from atmospheric nuclear weapons testing.

    PubMed

    Wakeford, Richard

    2014-05-01

    Towards the end of 2007, the results were published from a case-control study (the "KiKK Study") of cancer in young children, diagnosed <5 years of age during 1980-2003 while resident near nuclear power stations in western Germany. The study found a tendency for cases of leukaemia to live closer to the nearest nuclear power station than their matched controls, producing an odds ratio that was raised to a statistically significant extent for residence within 5 km of a nuclear power station. The findings of the study received much publicity, but a detailed radiological risk assessment demonstrated that the radiation doses received by young children from discharges of radioactive material from the nuclear reactors were much lower than those received from natural background radiation and far too small to be responsible for the statistical association reported in the KiKK Study. This has led to speculation that conventional radiological risk assessments have grossly underestimated the risk of leukaemia in young children posed by exposure to man-made radionuclides, and particular attention has been drawn to the possible role of tritium and carbon-14 discharges in this supposedly severe underestimation of risk. Both (3)H and (14)C are generated naturally in the upper atmosphere, and substantial increases in these radionuclides in the environment occurred as a result of their production by atmospheric testing of nuclear weapons during the late 1950s and early 1960s. If the leukaemogenic effect of these radionuclides has been seriously underestimated to the degree necessary to explain the KiKK Study findings, then a pronounced increase in the worldwide incidence of leukaemia among young children should have followed the notably elevated exposure to (3)H and (14)C from nuclear weapons testing fallout. To investigate this hypothesis, the time series of incidence rates of leukaemia among young children <5 years of age at diagnosis has been examined from ten cancer registries

  1. Microbial effects on sorption and transport of actinides in tuff samples from the Nevada Test Site and soils from McGuire AFB, NJ

    NASA Astrophysics Data System (ADS)

    Fisher, J. C.; Gostic, R.; Gostic, J.; Czerwinski, K.; Moser, D. P.

    2009-12-01

    The sorption and behavior of various actinides were examined for two sets of environmental samples. The Nevada Test Site (NTS) harbors a variety of radionuclides resulting from atomic weapons testing from the 1950s-1990s. Modeling the transport of radionuclides at the NTS is difficult because each detonation cavity is a unique environment with distinct hydrologic characteristics, chemical composition, and microbial community structure. McGuire AFB was the site of an explosion that resulted in the burning of a BOMARC nuclear missile and deposition of particles containing high-fired oxides of Am, Pu, and U in soils on the base. Analysis of the NTS samples focused on sorption/desorption of 233-U and 241-Am in the presence/absence of bacteria, and work on the BOMARC cores addressed the potential role of microorganisms in mediating particle degradation and movement. Batch experiments with various NTS tuff samples and strains of bacteria showed that sorption of actinides may be enhanced by >25% under certain conditions by bacteria. Sorption of 233-U was highly dependent on carbonate concentrations in the liquid matrix, while 241-Am was unaffected. Different bacterial species also affected sorption differently. Sorption kinetics for both actinides were rapid, with maximum sorption usually occurring within 4 hours. Actinides bound tightly to tuff and little desorption occurred in carbonate-free batch experiments. Column experiments showed that bacterial cultures in minimal salts buffer desorbed significantly more 233-U from tuff than low carbonate NTS water, but less than 30 mM bicarbonate buffer. Hot particles in the BOMARC cores were located using CT mapping and were extracted from the soil prior to analysis of core sections by gamma spectroscopy. Subcores for DNA extraction and culturing were collected from soil in direct contact with hot particles. The extracted particles consisted of a mixture of weapons-grade Pu, 241-Am and 235-U and ranged in activity from 5-66 k

  2. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, September-November 1981

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1982-06-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the fall of 1981, Teredo bartschi remained in Oyster Creek despite continuous prolonged outages of the Oyster Creek Nuclear Generating Station. It did not spread to Forked River or Waretown as it had done in other years when the effluent was present. The peak in larval production and settlement of T. bartschi occurred between September and October. Settlement of shipworms occurred on no monthly panels except those in Oyster Creek during the period of this report. Laboratory experiments revealed that T. bartschi becomes inactive at 5/sup 0/C (24/sup 0///sub 00/) and T. navalis shows signs of osmotic stress below 10/sup 0///sub 00/ at 18/sup 0/C. The shipworms in Barnegat Bay do not show a preference for settling at the mudline when the substrate is not limited.

  3. Oconee Nuclear Station Unit {number_sign}2 Alloy 600 reactor vessel head CRD penetration inspection: Planning strategies and lessons learned

    SciTech Connect

    Arey, M.L. Jr.; Whitaker, D.E.

    1996-12-01

    Leakage from an Electricite de France (EdF) PWR reactor vessel head penetration at Bugey Unit {number_sign}3 was discovered during a hydrostatic test in 1991. The penetration material is Inconel 600 and is common to many other reactor vessel penetrations throughout the world. EdF has reported the cause of the leakage to be a throughwall crack resulting from Primary Water Stress Corrosion Cracking (PWSCC) as determined by metallurgical evaluation. Utilities in Sweden, Japan, Switzerland, Belgium and Spain have also completed inspections of penetrations in the reactor vessel heads. Cracking has been identified in approximately four percent of the additional EdF penetrations inspected and two percent of worldwide penetrations inspected to date. Five US nuclear plants have completed inspections of the control rod drive (CRD) penetrations with two plants finding indications. D.C. Cook and Oconee Nuclear Stations completed inspections in 1994 with each utility identifying one penetration with multiple indications. Point Beach, Palisades, and North Anna Nuclear Stations have completed penetration inspections without identifying any indications. This paper discusses the planning and preparation for the inspection of the CRD penetrations at ONS Unit {number_sign}2.

  4. 78 FR 49551 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-14

    ...The U.S. Nuclear Regulatory Commission (NRC) is granting both an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment No. 7 to Combined Licenses (COL), NPF-91 and NPF-92. The COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation,......

  5. 78 FR 5511 - Virgil C. Summer Nuclear Station, Units 2 and 3; Application and Amendment to Facility Combined...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-25

    ... issuance of the proposed license amendment, the Commission will have made findings required by the Atomic... the nuclear island structures and the supporting soil or rock. The basemat transfers the load of nuclear island structures to the supporting soil or rock and transmits seismic motions from the supporting...

  6. 78 FR 6145 - Virgil C. Summer Nuclear Station, Units 2 and 3; Application and Amendment to Facility Combined...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-29

    ... proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of... interface between the nuclear island structures and the supporting soil or rock. The basemat transfers the load of nuclear island structures to the supporting soil or rock. The basemat transmits seismic...

  7. 78 FR 32278 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-29

    ... Information in Tier 1, Table 3.3-1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and Combined... information located in Table 3.3-1, ``Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine... change the Tier 1 information located in Table 3.3-1 of its Updated Final Safety Analysis Report (UFSAR...

  8. The thermal circuit of a nuclear power station's unit built around a supercritical-pressure water-cooled reactor

    NASA Astrophysics Data System (ADS)

    Silin, V. A.; Zorin, V. M.; Tagirov, A. M.; Tregubova, O. I.; Belov, I. V.; Povarov, P. V.

    2010-12-01

    Main results obtained from calculations of the steam generator and thermal circuit of the steam turbine unit for a nuclear power unit with supercritical-pressure water coolant and integral layout are presented. The obtained characteristics point to the advisability of carrying out further developments of this promising nuclear power technology.

  9. Technical evaluation of the noise and isolation testing of the reactor protection system for the Davis Besse Nuclear Power Station, Unit 1

    SciTech Connect

    Selan, J.C.

    1980-01-01

    This report documents the technical evaluation of the noise and isolation testing of the reactor protection system (RPS) for the Davis Besse Nuclear Power Station, Unit 1. The testing was performed in accordance to Section 4.6.11, Susceptibility, of MIL-N-19900B, and NRC approved plant test methods. Analysis of the test results shows that the reactor protection system did not degrade below acceptable levels when subjected to electromagnetic, electrostatic, isolation and noise level tests, nor was the system's ability to perform its Class 1E protective functions affected.

  10. THREE-YEAR RETENTION OF RADIOACTIVE CAESIUM IN THE BODY OF TEPCO WORKERS INVOLVED IN THE FUKUSHIMA DAIICHI NUCLEAR POWER STATION ACCIDENT.

    PubMed

    Nakano, T; Tani, K; Kim, E; Kurihara, O; Sakai, K; Akashi, M

    2016-09-01

    Direct measurements of seven highly exposed workers at the Tokyo Electric Power Company Fukushima Daiichi Nuclear Power Station accident have been performed continuously since June 2011. Caesium clearance in the monitored workers is in agreement with the biokinetic models proposed by the International Commission on Radiological Protection. After 500 d from the initial measurement, however, the caesium clearance slowed. It was thought to be unlikely that additional Cs intake had occurred after the initial intake, as activity in foods was kept low. And, the contribution from the detector over the chest was enhanced with time. This indicates that insoluble Cs particles were inhaled and a long metabolic rate showed.

  11. Radiocesium distribution in the tissues of Japanese Black beef heifers fed fallout-contaminated roughage due to the Fukushima Daiichi Nuclear Power Station accident.

    PubMed

    Sasaki, Keisuke; Hayashi, Masayuki; Narita, Takumi; Motoyama, Michiyo; Oe, Mika; Ojima, Koichi; Nakajima, Ikuyo; Muroya, Susumu; Chikuni, Koichi; Aikawa, Katsuhiro; Ide, Yasuyuki; Nakanishi, Naoto; Suzuki, Nobuaki; Shioya, Shigeru; Takenaka, Akio

    2012-01-01

    This study examined the accumulation and tissue distribution of radioactive cesium nuclides in Japanese Black beef heifers raised on roughage contaminated with radioactive fallout due to the accident at the Fukushima Daiichi Nuclear Power Station on March 2011. Radiocesium feeding increased both (134)Cs and (137)Cs levels in all tissues tested. The kidney had the highest level and subcutaneous adipose had the lowest of radioactive cesium in the tissues. Different radioactive cesium levels were not found among parts of the muscles. These results indicate that radiocesium accumulated highly in the kidney and homogenously in the skeletal muscles in the heifers.

  12. Environmental radionuclide concentrations in the vicinity of the Calvert Cliffs Nuclear Power Plant and the Peach Bottom Atomic Power station: 1995

    SciTech Connect

    Jones, T.S.; Frithsen, J.B.; McLean, R.I.

    1997-02-01

    The Maryland Power Plant Research Program monitors concentrations of natural, weapons, and power plant produced radionuclides in environmental samples collected from the Chesapeake Bay in the vicinity of the Calvert Cliffs Nuclear Power Plant (CCNPP) and from the Susquehanna River-Chesapeake Bay system in the vicinity of Peach Bottom Atomic Power Station (PBAPS). The purpose of this monitoring is to determine the fate, transport, and potential effects of power plant produced radionuclides. Radionuclide concentrations in shellfish, finfish, aquatic vegetation, and sediment were measured using high-resolution gamma spectrometry. Radionuclides in environmental samples originated from natural sources, atmospheric weapons testing, and normal operations of CCNPP and PBAPS.

  13. Development and investigations of compact heat-transfer equipment for a nuclear power station equipped with a high-temperature gas-cooled reactor

    NASA Astrophysics Data System (ADS)

    Golovko, V. F.; Dmitrieva, I. V.; Kodochigov, N. G.; Bykh, O. A.

    2013-07-01

    The project of a nuclear power station the reactor coolant system of which includes a high-temperature gas-cooled reactor combined with a gas-turbine energy conversion unit supposes the use of high-efficient gas-cycle-based heat-transfer equipment. An analysis aimed at selecting the optimal heat-transfer surfaces is presented together with the results from their calculated and experimental investigation. The design features of recuperators arranged integrally with end and intermediate coolers and placed in a vertical sealed high-pressure vessel of limited sizes are considered.

  14. International challenge to predict the impact of radioxenon releases from medical isotope production on a comprehensive nuclear test ban treaty sampling station.

    PubMed

    Eslinger, Paul W; Bowyer, Ted W; Achim, Pascal; Chai, Tianfeng; Deconninck, Benoit; Freeman, Katie; Generoso, Sylvia; Hayes, Philip; Heidmann, Verena; Hoffman, Ian; Kijima, Yuichi; Krysta, Monika; Malo, Alain; Maurer, Christian; Ngan, Fantine; Robins, Peter; Ross, J Ole; Saunier, Olivier; Schlosser, Clemens; Schöppner, Michael; Schrom, Brian T; Seibert, Petra; Stein, Ariel F; Ungar, Kurt; Yi, Jing

    2016-06-01

    The International Monitoring System (IMS) is part of the verification regime for the Comprehensive Nuclear-Test-Ban-Treaty Organization (CTBTO). At entry-into-force, half of the 80 radionuclide stations will be able to measure concentrations of several radioactive xenon isotopes produced in nuclear explosions, and then the full network may be populated with xenon monitoring afterward. An understanding of natural and man-made radionuclide backgrounds can be used in accordance with the provisions of the treaty (such as event screening criteria in Annex 2 to the Protocol of the Treaty) for the effective implementation of the verification regime. Fission-based production of (99)Mo for medical purposes also generates nuisance radioxenon isotopes that are usually vented to the atmosphere. One of the ways to account for the effect emissions from medical isotope production has on radionuclide samples from the IMS is to use stack monitoring data, if they are available, and atmospheric transport modeling. Recently, individuals from seven nations participated in a challenge exercise that used atmospheric transport modeling to predict the time-history of (133)Xe concentration measurements at the IMS radionuclide station in Germany using stack monitoring data from a medical isotope production facility in Belgium. Participants received only stack monitoring data and used the atmospheric transport model and meteorological data of their choice. Some of the models predicted the highest measured concentrations quite well. A model comparison rank and ensemble analysis suggests that combining multiple models may provide more accurate predicted concentrations than any single model. None of the submissions based only on the stack monitoring data predicted the small measured concentrations very well. Modeling of sources by other nuclear facilities with smaller releases than medical isotope production facilities may be important in understanding how to discriminate those releases from

  15. Nuclear techniques for the on-line bulk analysis of carbon in coal-fired power stations.

    PubMed

    Sowerby, B D

    2009-09-01

    Carbon trading schemes usually require large emitters of CO(2), such as coal-fired power stations, to monitor, report and be audited on their CO(2) emissions. The emission price provides a significant additional incentive for power stations to improve efficiency. In the present paper, previous work on the bulk determination of carbon in coal is reviewed and assessed. The most favourable method is that based on neutron inelastic scattering. The potential role of on-line carbon analysers in improving boiler efficiency and in carbon accounting is discussed.

  16. Experience in Organization of Urgent Medical Care in Large-Scale Accident Conditions at Nuclear Power Stations

    DTIC Science & Technology

    2001-05-01

    approximately 340 Gwt) which is 17% of the worldwide electricity production level. The Chernobyl Nuclear Disaster with its long-term medico-biological...population to avoid or minimize the risk of their exposure. In October 1986, after the Chernobyl Nuclear Disaster the Federal Center of Radiation...period of their cooperation the Urgent Medical Care Department and the Rapid Response Teams visited the following sites of accidents: "* Chernobyl (a fire

  17. Spatial assessment of radiocaesium in the largest lagoon in Fukushima after the TEPCO Fukushima Dai-ichi Nuclear Power Station accident.

    PubMed

    Kambayashi, Shota; Zhang, Jing; Narita, Hisashi

    2017-09-15

    Radionuclides deposited on land by global fallouts and nuclear power station accidents spread over coastal environments through estuarine areas connecting land to ocean. In this study, we monitored activity concentration of radiocaesium in surface sediment and re-suspended particles in Matsukawa-ura lagoon, the largest lagoon in Fukushima, after the TEPCO Fukushima Dai-ichi Nuclear Power Station accident. Radiocaesium distribution in surface sediment varied spatiotemporally and irregularly due to the effect of tidal waves. The effective half-life was significantly shorter than physical half-life, suggesting some system of radiocaesium discharge in the lagoon. Sediment trap observation revealed re-suspended particles from sediment were transported to the ocean. For these reasons, it is suggested that re-suspension of particles in the lagoon and their transportation to the ocean by the seawater exchange process are important processes of radiocaesium discharge. Moreover, our results show that seawater exchange process contributes to the dispersion of radiocaesium in the ocean. Copyright © 2017 Elsevier Ltd. All rights reserved.

  18. Nuclear privatization

    SciTech Connect

    Jeffs, E.

    1995-11-01

    The United Kingdom government announced in May 1995 plans to privatize the country`s two nuclear generating companies, Nuclear Electric and Scottish Nuclear. Under the plan, the two companies will become operating divisions of a unified holding company, to be called British Electric, with headquarters in Scotland. Britain`s nuclear plants were left out of the initial privatization in 1989 because the government believed the financial community would be unwilling to accept the open-ended liability of decommissioning the original nine stations based on the Magnox gas-cooled reactor. Six years later, the government has found a way around this by retaining these power stations in state ownership, leaving the new nuclear company with the eight Advanced Gas-cooled Reactor (AGR) stations and the recently completed Sizewell B PWR stations. The operating Magnox stations are to be transferred to BNFL, which operates two Magnox stations of their own at Calder Hall and Chapelcross.

  19. Effects of welding fumes on nuclear air cleaning system carbon adsorber banks

    SciTech Connect

    Roberson, P.W.

    1997-08-01

    Standard Technical Specifications for nuclear air cleaning systems include requirements for surveillance tests following fire, painting, or chemical release in areas communicating with the affected system. To conservatively implement this requirement, many plants categorize welding as a chemical release process, and institute controls to ensure that welding fumes do not interact with carbon adsorbers in a filter system. After reviewing research data that indicated welding had a minimal impact on adsorber iodine removal efficiency, further testing was performed with the goal of establishing a welding threshold. It was anticipated that some quantity of weld electrodes could be determined that had a corresponding detrimental impact on iodine removal efficiency for the exposed adsorber. This value could be used to determine a conservative sampling schedule that would allow the station to perform laboratory testing to ensure system degradation did not occur without a full battery of surveillance tests. A series of tests was designed to demonstrate carbon efficiency versus cumulative welding fume exposure. Three series of tests were performed, one for each of three different types of commonly used weld electrodes. Carbon sampling was performed at baseline conditions, and every five pounds of electrode thereafter. Two different laboratory tests were performed for each sample; one in accordance with ASTM 3803/1989 at 95% relative humidity and 30 degrees C, and another using the less rigorous conditions of 70% relative humidity and 80 degrees C. Review of the test data for all three types of electrodes failed to show a significant correlation between carbon efficiency degradation and welding fume exposure. Accordingly, welding is no longer categorized as a `chemical release process` at McGuire Nuclear Station, and limits on welding fume interaction with ventilation systems have been eliminated. 4 refs., 3 figs., 1 tab.

  20. Remote sensing monitoring of thermal discharge in Daya Bay Nuclear Power Station based on HJ-1 infrared camera

    NASA Astrophysics Data System (ADS)

    Zhu, Li; Yin, Shoujing; Wu, Chuanqing; Ma, Wandong; Hou, Haiqian; Xu, Jing

    2014-11-01

    In this paper, the method of monitoring coastal areas affected by thermal discharge of nuclear plant by using remote sensing techniques was introduced. The proposed approach was demonstrated in Daya Bay nuclear plant based on HJ-B IRS data. A single channel water temperature inversion algorithm was detailed, considering the satellite zenith angle and water vapor. Moreover the reference background temperature was obtained using the average environmental temperature method. In the case study of Daya Bay nuclear plant, the spatial distribution of thermal pollution was analyzed by taking into account the influence of tidal, wind and so on. According to the findings of this study, the speed and direction of the ebb tide, is not conducive to the diffusion of thermal discharge of DNNP. The vertically thermal diffusion was limited by the shallow water depth near the outlet.

  1. Radiocesium concentrations in wild mushrooms after the accident at the Fukushima Daiichi Nuclear Power Station: Follow-up study in Kawauchi village.

    PubMed

    Orita, Makiko; Nakashima, Kanami; Taira, Yasuyuki; Fukuda, Toshiki; Fukushima, Yoshiko; Kudo, Takashi; Endo, Yuko; Yamashita, Shunichi; Takamura, Noboru

    2017-07-27

    Since the accident at the Chernobyl Nuclear Power Plant, it has become well known that radiocesium tends to concentrate in wild mushrooms. During the recovery process after the accident at the Fukushima Daiichi Nuclear Power Station (FDNPS), it is important to perform follow-up measurements of the activity concentrations of radiocesium in mushrooms. We evaluated the activity concentrations of the detected artificial radionuclides (radiocesium) in wild mushrooms collected from Kawauchi village, which is within 30 km of the FDNPS, in 2015, four years after the accident. We found that the radiocesium was determined in 147 of 159 mushroom samples (92.4%). Based on the average mushroom consumption of Japanese citizens (6.28 kg per year), we calculated committed effective doses ranging from <0.001 to 0.6 mSv. Although committed effective doses are relatively limited, even if residents have consumed mushrooms several times, continuous monitoring of the radiocesium in mushrooms in Fukushima is needed for sustained recovery from the nuclear disaster.

  2. 78 FR 41117 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-09

    ... Information in Tier 1 Table 3.3-1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and Combined... to allow a departure from the certification information of Tier 1 of the generic design control... clarity and accuracy of the Tier 1 information located in Table 3.3-1, ``Definition of Wall...

  3. 78 FR 63504 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Changes to the...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-24

    ... Primary Sampling System AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and combined license... Sampling System (PSS) design, including changes to Tier 1 information located in Tables 2.2.1-2, 2.3.13-1, and 2.3.13-3, Figures 2.2.1-1 ``Containment System'' and 2.3.13-1 ``Primary Sampling System,'' and...

  4. Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

    SciTech Connect

    Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.; Cuta, Judith M.; Collins, Brian A.; Siciliano, Edward R.

    2012-10-01

    As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Station’s Independent Spent Fuel Storage Installation (ISFSI). Detailed thermal models models were developed to obtain realistic temperature predictions for actual storage systems, in contrast to conservative and bounding design basis calculations.

  5. High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station

    SciTech Connect

    Wong, S.; DiBiasio, A.; Gunther, W.

    1993-09-01

    The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant.

  6. Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project

    SciTech Connect

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  7. Environmental radionuclide concentrations in the vicinity of the Calvert Cliffs Nuclear Power Plant and the Peach Bottom Atomic Power Station: 1996--1997. Final report

    SciTech Connect

    McLean, R.I.; Jones, T.S.

    1998-11-20

    The Maryland Power Plant Research Program monitors concentrations of natural, weapons, and power plant produced radionuclides in environmental samples collected from the Chesapeake Bay in the vicinity of the Calvert Cliffs Nuclear Power Plant (CCNPP) and from the Susquehanna River-Chesapeake Bay system in the vicinity of Peach Bottom Atomic Power Station (PBAPS). The purpose of this monitoring is to determine the fate, transport, and potential effects of power plant-produced radionuclides. This report contains a description of monitoring activities and data collected during the 1996 and 1997 calendar years. Radionuclide concentrations in shellfish, finfish, aquatic vegetation, and sediment were measured using high-resolution gamma spectrometry. Radionuclides in environmental samples originated from natural sources, historic atmospheric weapons testing, and normal operations of CCNPP and PBAPS.

  8. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station: progress report June-August 1981. Quarterly progress report 1 Jun-31 Aug 81

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1982-01-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the summer of 1981, Teredo bartschi occurred in large numbers at one station in Oyster Creek, but did not appear in significant numbers in Forked River.

  9. Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report, June-August 1982

    SciTech Connect

    Hoagland, K.E.

    1982-12-01

    The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. Adult populations of Teredo bartschi existed in both Oyster Creek and Forked River in the summer of 1982, but the species was rare. There was no large settlement of this or any other teredinid species in Barnegat Bay. Teredo navalis was the most common species in the monthly panels. The fouling community reached its maximum yearly diversity in June-July. There was a thermal effluent causing a ..delta..T of 3 to 4/sup 0/C during most of the summer, and salinity in Oyster Creek and Forked River was similar to that of Barnegat Bay. The lack of a shipworm outbreak in 1982 may be related to the low ..delta..T in summer, plus the lack of a thermal effluent in the preceding winter-spring period.

  10. Ecological studies of wood-boring bivalves and fouling organisms in the vicinity of the Oyster Creek Nuclear Generating Station. Final report, September 1976-December 1982

    SciTech Connect

    Hoagland, K.E.

    1983-10-01

    The species composition, distribution, and population dynamics of wood-boring bivalves were studied using wood test panels at 20 stations in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Physiological tolerances of three teredinid species were investigated in the laboratory and correlated with field values of temperature, salinity, siltation, precipitation, and plant operations. The interaction of boring and fouling organisms was examined. There is a definite correlation between the operation of the power plant and teredinid outbreaks. Increased salinity and water flow as well as temperature are responsible. After 1976, most of the damage in Oyster Creek was done by the introduced subtropical species Teredo bartschi. It can respond faster than native species to environmental change. Although Oyster Creek contributed larvae to neighboring parts of Barnegat Bay, its role as a breeding ground was limited. Some elements of the fouling community may be antagonistic to shipworm growth. Fouling was increased in both biomass and species richness in Oyster Creek when compared with creek controls, but the fouling community in Oyster Creek was less stable than that in other areas. Lower salinity limits for the teredinids were within the salinity range found in Oyster Creek but not within the range found in the control creeks. 71 references, 9 figures, 39 tables.

  11. A feasibility assessment of installation, operation and disposal options for nuclear reactor power system concepts for a NASA growth space station

    NASA Technical Reports Server (NTRS)

    Bloomfield, Harvey S.; Heller, Jack A.

    1987-01-01

    A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth space station architecture was conducted to address a variety of installation, operational disposition, and safety issues. A previous NASA sponsored study, which showed the advantages of space station - attached concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide the feasibility of each combination.

  12. Analysis of populations of boring and fouling organisms in the vicinity of the Oyster Creek Nuclear Generating Station. Quarterly progress report No. 12, Jun-Aug 79

    SciTech Connect

    Hoagland, K.E.; Crocket, L.

    1980-07-01

    The growth, distribution, and species composition of marine borers (primarily shipworms) and fouling organisms are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 18 localities. Our most recent findings covering June-August, 1979, are that at least one subtropical species of the borer family Teredinidae, Teredo bartschi, continues to live in Oyster Creek and can breed in Forked River, although many die off in winter in Forked River and the species may have to recolonize. A few of the subtropical T. furcifera also survive in Oyster Creek but cause negligible damage at present, compared with T. bartschi. The summer, 1979, outbreak of T. bartschi in Oyster Creek was severe, causing nearly total destruction to wood panels. The breeding season for T. bartschi was the same as in 1978. Some fouling organisms were present in Oyster Creek that are absent in control creek stations due to low salinity.

  13. The uptake of iron-55 by marine sediment, macroalgae, and biota following discharge from a nuclear power station.

    PubMed

    Warwick, P E; Cundy, A B; Croudace, I W; Bains, M E; Dale, A A

    2001-06-01

    Significant quantities of 55Fe, an activation product of stable iron, have been released into the environment following the atmospheric testing of nuclear weapons (mainly in the 1950s and 1960s) as well as through authorized discharges of radioactivity from nuclear power and reprocessing sites. Although some studies have been performed on the behavior of weapons' fallout-derived 55Fe in the environment and subsequent impact on humans, little has been published on the behavior of 55Fe released as a point source discharge from nuclear sites. This study presents data on the concentration and temporal variation of 55Fe in fucoid seaweeds, shellfish, crab, and lobster collected from Weymouth Bay and adjacent coastal areas, southern England. These areas have received authorized discharges of radionuclides originating from the operation of a now-decommissioned steam-generating, heavy water-type reactor at AEE Winfrith. The highest activities of 55Fe are found associated with marine sediments collected near the discharge pipeline and a rapid decline occurs away from the pipeline. This is consistent with rapid sorption of 55Fe by the sediment, and the data show there is only limited reworking and remobilization. Activities of 55Fe in biota generally decreased over time, due to a reduction in the amount of 55Fe discharged. The variation of 55Fe activity, revealed from the monthly sampling of seaweed, does not reflect the short-term fluctuations seen in the patterns of discharged 55Fe activity. Although discharges of 55Fe from AEE Winfrith exceeded other radionuclides, the radiological impact on local seafood consumers is considerably less than for other key radionuclides such as 60Co and 65Zn but of comparable magnitude to the global average population dose arising from fallout-derived 55Fe.

  14. 78 FR 45990 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-30

    ...The U.S. Nuclear Regulatory Commission (NRC) is granting both an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment No. 8 to Combined Licenses (COL), NPF-91 and NPF-92. The COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and the City of Dalton, Georgia (the licensee); for construction and operation of the Vogtle Electric Generating Plant (VEGP), Units 3 and 4, located in Burke County, Georgia. The amendment requests to revise the design of the bracing used to support the Turbine Building structure. This request requires changing Tier 1 information found in the Design Description portion of Updated Final Safety Analysis Report (UFSAR) Section 3.3, ``Buildings.'' The granting of the exemption allows the changes to Tier 1 information asked for in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.

  15. Preliminary Thermal Modeling of Hi-Storm 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI

    SciTech Connect

    Cuta, Judith M.; Adkins, Harold E.

    2013-08-30

    This report fulfills the M3 milestone M3FT-13PN0810022, “Report on Inspection 1”, under Work Package FT-13PN081002. Thermal analysis is being undertaken at Pacific Northwest National Laboratory (PNNL) in support of inspections of selected storage modules at various locations around the United States, as part of the Used Fuel Disposition Campaign of the U.S. Department of Energy, Office of Nuclear Energy (DOE-NE) Fuel Cycle Research and Development. This report documents pre-inspection predictions of temperatures for four modules at the Hope Creek Nuclear Generating Station ISFSI that have been identified as candidates for inspection in late summer or early fall/winter of 2013. These are HI-STORM 100S-218 Version B modules storing BWR 8x8 fuel in MPC-68 canisters. The temperature predictions reported in this document were obtained with detailed COBRA-SFS models of these four storage systems, with the following boundary conditions and assumptions.

  16. Effect of pH on the release of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resins collected from operating nuclear power stations

    SciTech Connect

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W. )

    1991-06-01

    Data are presented on the physical stability and leachability of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small-scale waste--form specimens collected during solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station were leach-tested and subjected to compressive strength testing in accordance with the Nuclear Regulatory Commission's Technical Position on Waste Form'' (Revision 1). Samples of untreated resin waste collected from each solidification vessel before the solidification process were analyzed for concentrations of radionuclides, selected transition metals, and chelating agents to determine the quantities of these chemicals in the waste-form specimens. The chelating agents included oxalic, citric, and picolinic acids. In order to determine the effect of leachant chemical composition and pH on the stability and leachability of the waste forms, waste-form specimens were leached in various leachants. Results of this study indicate that differences in pH do not affect releases from cement-solidified decontamination ion-exchange resin waste forms, but that differences in leachant chemistry and the presence of chelating agents may affect the releases of radionuclides and chelating agents. Also, this study indicates that the cumulative releases of radionuclides and chelating agents are similar for waste- form specimens that decomposed and those that retained their general physical form. 36 refs., 60 figs., 28 tabs.

  17. Hybrid radiation background monitoring in operational control and forecasting of environmental contamination by nuclear power station discharges

    SciTech Connect

    Ermeev, I.S.; Eremenko, V.A.; Makarov, Y.A.; Matueev, V.V.; Zhernov, V.S.

    1986-05-01

    Rapid developments in nuclear power have stimulated research on monitoring and forecasting environmental radiation pollution (ERP), and in particular the amounts, compositions, and distributions of radionuclides in the environment. A conceptual model is presented for hybrid environmental radiation pollution monitoring. When there is an emergency, the model operates in a fashion most closely corresponding to the actual meteorological conditions, and the ERP data given by the model enable one to distinguish changes due to the man-made component from random fluctuations in the natural background. The measurement system in general includes mobile and stationary data-acquisition facilities linked by wire or radio to the central point. The system also accumulates and stores data on the radiation environment, which are edited on the basis of radioactive, chemical, and other transformations. The purpose of hybrid monitoring is ultimately to analyze trends in order to detect elevated discharges and thus to output data to the regional monitoring system.

  18. Geothermal Energy Development in the Eastern United States: Technical assistance report No. 6 geothermal space heating and airconditioning -- McGuire Air Force Base, New Jersey

    SciTech Connect

    Hill, F.K.; Briesen R. von

    1980-12-01

    A method of utilizing the geothermal (66 F) water resource for space heating and cooling of 200 of the 1452 housing units at McGuire AFB is suggested. Using projections of future costs of gas, coal and electricity made by DOD and by industry (Westinghouse), the relative costs of the geothermal-water-plus-heat-pump system and the otherwise-planned central gas heating (to be converted to coal in 1984) and air-conditioning (using individual electric units) system are compared. For heating with the geothermal/heat-pump system, an outlet temperature of 130 F is selected, requiring a longer running time than the conventional system (at 180 F) but permitting a COP (coefficient of performance) of the heat pump of about 3.4. For cooling (obtained in this study by changing directions of water flow, not refrigerant cycles), the change in temperature is less, and a COP near 4.5 is obtained. The cost of cooling in the summer months would be significantly less than the cost of using individual electric air-conditioners. Thus, by using nonreversible heat pumps, geothermal water is used to heat and to cool a section of the housing compound, minimizing operating expenditures. It is estimated that, to drill 1000 ft deep production and reinjection wells and to install ten heat pumps, heat exchangers and piping, would require a capital outlay of $643 K. This cost would replace the capital cost of purchasing and installing 200 air-conditioning units and 14% of the cost of the future coal-fired central heating system (which would otherwise serve all 1452 housing units at McGuire). The net additional capital outlay would be $299 K, which could be amortized in 10 years by the lower operating cost of the geothermal system if electricity and coal prices escalate as industry suggests. If the coal and electricity costs rise at the more modest rates that DOD projects, the capital costs would be amortized in a 15 year period.

  19. Low (134)Cs/(137)Cs ratio anomaly in the north-northwest direction from the Fukushima Dai-ichi Nuclear Power Station.

    PubMed

    Kobayashi, Shingo; Shinomiya, Takayuki; Ishikawa, Takahiro; Imaseki, Hitoshi; Iwaoka, Kazuki; Kitamura, Hisashi; Kodaira, Satoshi; Kobayashi, Keisuke; Oikawa, Masakazu; Miyaushiro, Norihiro; Takashima, Yoshio; Uchihori, Yukio

    2017-08-07

    A low (134)Cs/(137)Cs ratio anomaly in the north-northwest (NNW) direction from the Fukushima Dai-ichi Nuclear Power Station (FDNPS) is identified by a new analysis of the (134)Cs/(137)Cs ratio dataset which we had obtained in 2011-2015 by a series of car-borne surveys that employed a germanium gamma-ray spectrometer. We found that the (134)Cs/(137)Cs ratio is slightly lower (0.95, decay-corrected to March 11, 2011) in an area with a length of about 15 km and a width of about 3 km in the NNW direction from the FDNPS than in other directions from the station. Furthermore, the area of this lower (134)Cs/(137)Cs ratio anomaly corresponds to a narrow contamination band that runs NNW from the FDNPS and it is nearly parallel with the major and heaviest contamination band in the west-northwest. The plume trace with a low (134)Cs/(137)Cs ratio previously found by other researchers within the 3-km radius of the FDNPS is in a part of the area with the lower (134)Cs/(137)Cs ratio anomaly that we found. Our result suggests that this lower (134)Cs/(137)Cs ratio anomaly is the area which was contaminated before March 13, 2011 (UTC) in association with the hydrogen explosion of Unit 1 on March 12, 2011 at 06:36 (UTC) and it was less influenced by later subsequent plumes. Copyright © 2017 Elsevier Ltd. All rights reserved.

  20. Environmental radiological studies conducted during 1986 in the vicinity of the Rancho Seco Nuclear Power Generating Station

    SciTech Connect

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Brunk, J.L.; Jokela, T.A.

    1987-03-01

    This report summarizes the information compiled in 1986 for our assessment of the environmental impact of radionuclides discharged with aqueous releases from the Rancho Seco Nuclear Power Generating Plant. In October 1984, a liquid-effluent control program was initiated that significantly reduced the quantities of radionuclides discharged with liquid waste from the plant. However, results from our sampling program in 1986 indicate that previously discharged radionuclides persist in the downstream environment and are found in many aquatic dietary components although at concentrations much lower than those measured in 1984 and 1985. The greatly reduced activities in the dietary components from the aquatic environment attest to the effectiveness of the liquid-effluent control program. Concentrations in the flesh of fish from the creeks have decreased over time and with distance from the plant outfall. The mean concentration of /sup 137/Cs in fish collected from Laguna Creek at locations more than 7.5 km from Rancho Seco is now comparable to the concentration determined in fresh-water fish randomly selected from Chicago, Illinois, markets. By August 1986, the mean concentration of /sup 137/Cs in the flesh of bluegill had fallen to 7% of the concentration measured in fish from comparable locations in 1984 and was 30% of the mean concentration measured in these fish during August 1985. Stable potassium in the water plays a major role in the accumulation of /sup 137/Cs by fish. Concentrations of /sup 137/Cs in the surface sections of creek sediments also declined between the end of 1984 and 1986 with an effective half-life of approximately 2 y. Surface soils collected around a perimeter 11 km from Rancho Seco and from ranchlands closer to the plant showed only concentrations of /sup 137/Cs originating from global fallout. Soils previously irrigated with Clay Creek water retain levels of both /sup 134/Cs and /sup 137/Cs.

  1. An Independent Assessment of Evacuation Time Estimates for A Peak Population Scenario in the Emergency Planning Zone of the Seabrook Nuclear Power Station

    SciTech Connect

    Moeller, M. P.; Urbanik, II, T.; Mclean, M. A.; Desrosiers, A. E.

    1982-11-01

    This study comprises two major tasks. First, it includes an independent assessment of the methods and assumptions used in calculating evacuation time estimates (ETEs) applicable to the general population for a peak population scenario in the emergency planning zone {EPZ) of the Seabrook Nuclear Power Station. This consists of a review and analysis of previous work by Public Service of New Hampshire {PSNH) and the Federal Emergency Management Agency (FEMA), as well as an independent calculation of evacuation times using the CLEAR model for the demographic data reported by PSNH. Secondly, this study includes independent estimations of evacuation time for the peak population scenario developed using demographic data prepared by the U.S. Nuclear Regulatory Commission {NRC). These evacuation time estimates are approximately 60% and 84% greater, respectively, than the estimate provided by PSNH for a simulataneous evacuation of the entire EPZ under peak conditions. The CLEAR model, which was developed by Pacific Northwest Laboratory {PNL) under the sponsorship of the. NRC, was also used for these latter calculations. The results of this study reveal the importance of the assumptions used for calculating evacuation times. Because traffic routings and management plans have not been prepared for the area, the CLEAR calculations utilized indepdently prepared traffic routings and assumptions. A detailed analysis of the results suggests that the ETEs submitted by PSNH are consistent with the methods and assumptions which provide the bases for PSNH•s evacuation time estimates. Differences among evacuation time estimates stem largely from differences jn the assumed size of the evacuating population and the estimated effectiveness of traffic controls.

  2. Concentrations of Radiocesium in Local Foods Collected in Kawauchi Village after the Accident at the Fukushima Dai-ichi Nuclear Power Station

    NASA Astrophysics Data System (ADS)

    Orita, Makiko; Nakashima, Kanami; Hayashida, Naomi; Endo, Yuuko; Yamashita, Shunichi; Takamura, Noboru

    2016-06-01

    We evaluated the current concentrations of radiocesium in local foods collected in Kawauchi Village, which is located less than 30 km from Fukushima Daiichi Nuclear Power Station, to minimize public anxiety regarding internal radiation exposure through the consumption of locally produced foods after the 2011 Fukushima accident. The number of samples exceeding the regulatory radiocesium limit (100 Bq/kg for general foods) was five out of 4,080 vegetables (0.1%), 652 of 1,986 (32.8%) among edible wild plants and fungi, and eight of 647 (1.2%) in fruits. Our study confirmed that the internal radiation doses of ingesting these foods are acceptably low compared to the public dose limit, ranging from 24.4 to 42.7 μSv for males and from 21.7 to 43.4 μSv for females, although the potential for radiation exposure still exists. Long-term comprehensive follow-up should take place to clarify trends in radiocesium concentrations in local foods and the committed effective doses found in Fukushima-area residents. By constructing a system that allows residents to access information on radiocesium concentration in foods, a risk communication model between specialists and residents could be developed in the recovery phase after the Fukushima accident.

  3. INTERNAL DOSES OF THREE PERSONS STAYING 110 KM SOUTH OF THE FUKUSHIMA DAIICHI NUCLEAR POWER STATION DURING THE ARRIVAL OF RADIOACTIVE PLUMES BASED ON DIRECT MEASUREMENTS.

    PubMed

    Kurihara, Osamu; Nakagawa, Takahiro; Takada, Chie; Tani, Kotaro; Kim, Eunjoo; Momose, Takumaro

    2016-09-01

    The authors describe the results of direct measurements made on three persons who stayed in Tokai-mura, a village located ∼110 km south of the Fukushima Daiichi Nuclear Power Station (FDNPS), during the arrival of significant radioactive plumes released from the FDNPS as a consequence of the Tohoku earthquake/tsunami/FDNPS accident in March 2011. These measurements were made using a NaI(Tl) spectrometer and a whole-body counter shortly after the accident. Their thyroid equivalent doses ((131)I) were estimated to be 0.9-1.4 mSv under the assumption of acute intake via inhalation on 15 March, when the first significant release event was observed. Although greatly depending on the physicochemical form of iodine, the intake amount ratios of (131)I to (137)Cs for the three subjects were calculated as 2.7-3.7, which were much smaller than the radioactivity ratio (7.8) found in air sampling at the same site. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  4. Suggestion of typical phases of in-vessel fuel-debris by thermodynamic calculation for decommissioning technology of Fukushima-Daiichi nuclear power station

    SciTech Connect

    Ikeuchi, Hirotomo; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro; Kondo, Yoshikazu; Noguchi, Yoshikazu

    2013-07-01

    For the decommissioning of the Fukushima-Daiichi Nuclear Power Station (1F), the characterization of fuel-debris in cores of Units 1-3 is necessary. In this study, typical phases of the in-vessel fuel-debris were estimated using a thermodynamic equilibrium (TDE) calculation. The FactSage program and NUCLEA database were applied to estimate the phase equilibria of debris. It was confirmed that the TDE calculation using the database can reproduce the phase separation behavior of debris observed in the Three Mile Island accident. In the TDE calculation of 1F, the oxygen potential [G(O{sub 2})] was assumed to be a variable. At low G(O{sub 2}) where metallic zirconium remains, (U,Zr)O{sub 2}, UO{sub 2}, and ZrO{sub 2} were found as oxides, and oxygen-dispersed Zr, Fe{sub 2}(Zr,U), and Fe{sub 3}UZr{sub 2} were found as metals. With an increase in zirconium oxidation, the mass of those metals, especially Fe{sub 3}UZr{sub 2}, decreased, but the other phases of metals hardly changed qualitatively. Consequently, (U,Zr)O{sub 2} is suggested as a typical phase of oxide, and Fe{sub 2}(Zr,U) is suggested as that of metal. However, a more detailed estimation is necessary to consider the distribution of Fe in the reactor pressure vessel through core-melt progression. (authors)

  5. Concentrations of Radiocesium in Local Foods Collected in Kawauchi Village after the Accident at the Fukushima Dai-ichi Nuclear Power Station.

    PubMed

    Orita, Makiko; Nakashima, Kanami; Hayashida, Naomi; Endo, Yuuko; Yamashita, Shunichi; Takamura, Noboru

    2016-06-23

    We evaluated the current concentrations of radiocesium in local foods collected in Kawauchi Village, which is located less than 30 km from Fukushima Daiichi Nuclear Power Station, to minimize public anxiety regarding internal radiation exposure through the consumption of locally produced foods after the 2011 Fukushima accident. The number of samples exceeding the regulatory radiocesium limit (100 Bq/kg for general foods) was five out of 4,080 vegetables (0.1%), 652 of 1,986 (32.8%) among edible wild plants and fungi, and eight of 647 (1.2%) in fruits. Our study confirmed that the internal radiation doses of ingesting these foods are acceptably low compared to the public dose limit, ranging from 24.4 to 42.7 μSv for males and from 21.7 to 43.4 μSv for females, although the potential for radiation exposure still exists. Long-term comprehensive follow-up should take place to clarify trends in radiocesium concentrations in local foods and the committed effective doses found in Fukushima-area residents. By constructing a system that allows residents to access information on radiocesium concentration in foods, a risk communication model between specialists and residents could be developed in the recovery phase after the Fukushima accident.

  6. The Contribution of Sources to the Sustained Elevated Inventory of (137)Cs in Offshore Waters East of Japan after the Fukushima Dai-ichi Nuclear Power Station Accident.

    PubMed

    Takata, Hyoe; Kusakabe, Masashi; Inatomi, Naohiko; Ikenoue, Takahito; Hasegawa, Kazuyuki

    2016-07-05

    We have evaluated the contribution of sources of (137)Cs to the inventory of radiocesium in waters (surface area: 6160 km(2), water volume: 753 km(3)) off Fukushima Prefecture and neighboring prefectures from May 2011 to February 2015. A time-series of the inventory of (137)Cs in the offshore waters revealed a clearly decreasing trend from May 2011 (283.4 TBq) to February 2015 (1.89 TBq). The (137)Cs inventory about four years after the accident was approximately twice the background inventory of 1.1 TBq. The magnitudes of the (137)Cs influxes from sources into offshore waters for periods of 182-183 days were estimated from the first period (1 October 2011 to 31 March 2012: 15.3 TBq) to the last period (1 October 2014 to 31 March 2015: 0.41 TBq). We assumed that three sources contributed (137)Cs: continuous direct discharge from the Fukushima Dai-ichi Nuclear Power Station (FNPS) even after the massive discharge in late March 2011, desorption/dissolution from sediments, and fluvial input. Quantification of these sources indicated that the direct discharge from the FNPS is the principal source of (137)Cs to maintain the relatively high inventory in the offshore area.

  7. Concentrations of Radiocesium in Local Foods Collected in Kawauchi Village after the Accident at the Fukushima Dai-ichi Nuclear Power Station

    PubMed Central

    Orita, Makiko; Nakashima, Kanami; Hayashida, Naomi; Endo, Yuuko; Yamashita, Shunichi; Takamura, Noboru

    2016-01-01

    We evaluated the current concentrations of radiocesium in local foods collected in Kawauchi Village, which is located less than 30 km from Fukushima Daiichi Nuclear Power Station, to minimize public anxiety regarding internal radiation exposure through the consumption of locally produced foods after the 2011 Fukushima accident. The number of samples exceeding the regulatory radiocesium limit (100 Bq/kg for general foods) was five out of 4,080 vegetables (0.1%), 652 of 1,986 (32.8%) among edible wild plants and fungi, and eight of 647 (1.2%) in fruits. Our study confirmed that the internal radiation doses of ingesting these foods are acceptably low compared to the public dose limit, ranging from 24.4 to 42.7 μSv for males and from 21.7 to 43.4 μSv for females, although the potential for radiation exposure still exists. Long-term comprehensive follow-up should take place to clarify trends in radiocesium concentrations in local foods and the committed effective doses found in Fukushima-area residents. By constructing a system that allows residents to access information on radiocesium concentration in foods, a risk communication model between specialists and residents could be developed in the recovery phase after the Fukushima accident. PMID:27334847

  8. Space Station

    NASA Image and Video Library

    1991-01-01

    In 1982, the Space Station Task Force was formed, signaling the initiation of the Space Station Freedom Program, and eventually resulting in the Marshall Space Flight Center's responsibilities for Space Station Work Package 1.

  9. The activity of radiocaesium in sediments around off Fukushima after the accident of TEPCO's Fukushima Dai-ich Nuclear Power Station.

    NASA Astrophysics Data System (ADS)

    Fukuda, Miho; Aono, Tatsuo; Yoshida, Satoshi; Naganuma, Sho; Kubo, Atsushi; Ito, Yukari; Ishimaru, Takashi; Kanda, Jota

    2014-05-01

    The 2011 off the Pacific coast of Tohoku Earthquake and tsunami on March 11, 2011 have led to the accident of TEPCO's Fukushima Dai-ich Nuclear Power Station (FNPS) and large amount of radioactive material were discharged by the hydrogen explosion and leaked from FNPS to the ocean. About three years have passed after the accident, radiocaesium in seawater off Fukushima except for part of area is gradually decreasing to the level before the accident. However, because the decrease of radiocaesium in marine sediment is more slowly than that in seawater, it is worried to influence on marine biota dwelled around the seabed over the long term. The aim of this study was to elucidate the variation and behavior of radiocaesium (134Cs and 137Cs) activities in the marine environment. Sediment and seawater samples were collected from three sites in 5 km-20 km area from FNPS (NP2 site ; 37° 25 N, 141°06 E, water depth 30 m, AN6 site ; 37° 33 N, 141°07 E, water depth 30 m, and M01 site ; 37° 33 N, 141°20 E, water depth 60 m) in May and October 2013 during some cruise of Umitaka-maru and Shinyo-maru (Tokyo University of Marine and Technology) .Vertical changes of 134Cs concentration (Bq/kg-dry) in sediment ranged 17-28, 8.2-53, and 4.2-11 at NP2, AN6 and M01 sites as of May 2013, respectively. At NP2 site, 134Cs inventory (Bq/m2) in seawater in October was about four times higher than that of 134Cs inventory in May. At NP2 and M01 sites in May, 134Cs concentration was higher in the shallow layer (0 cm-1 cm). On the contrary, at AN6 site in May and NP2 site in October, 134Cs concentration was higher in the middle layer (4 cm-5 cm). Trend of organic content at all stations were consistent with that of vertical change of 134Cs concentration. These results suggest that highest radiocaesium layer in the shallow as well as in the middle depth was caused by increase of river input and resedimentation.

  10. Radiation-related anxiety among public health nurses in the Fukushima Prefecture after the accident at the Fukushima Daiichi Nuclear Power Station: a cross-sectional study.

    PubMed

    Yoshida, Koji; Orita, Makiko; Goto, Aya; Kumagai, Atsushi; Yasui, Kiyotaka; Ohtsuru, Akira; Hayashida, Naomi; Kudo, Takashi; Yamashita, Shunichi; Takamura, Noboru

    2016-10-24

    In Japan, public health nurses (PHNs) play important roles in managing the health of local residents, especially after a disaster. In this study, we assessed radiation anxiety and the stress processing capacity of PHNs in the Fukushima Prefecture in Japan, after the accident at the Fukushima Daiichi Nuclear Power Station (FDNPS). We conducted a questionnaire survey among the PHNs (n=430) in July of 2015 via postal mail. The questions included demographic factors (sex, age and employment position), knowledge about radiation, degree of anxiety about radiation at the time of the FDNPS accident (and at present), by asking them to answer questions about radiation and the Sense of Coherence-13 (SOC-13). We classified the low and high levels of anxiety by asking them to answer questions about radiation, and compared the anxiety-negative (-) group with the anxiety-positive (+) group. Of the PHNs, 269 (62.6%) were classified in the anxiety (-) group and 161 (37.4%) were in the anxiety (+) group. When the multivariate logistic regression analysis was conducted, the PHNs at the time of the accident (OR: 2.37, p=0.007), current general anxieties about radiation (OR: 3.56, p<0.001), current possession of materials to obtain knowledge about radiation (OR: 2.11, p=0.006) and knowledge of the childhood thyroid cancer increase after the Chernobyl accident (OR: 1.69, p=0.035) were significantly associated with anxiety after the FDNPS accident. The mean SOC-13 was 43.0±7.7, with no significant difference between the anxiety (-) group and anxiety (+) group (p=0.47). Our study suggested that anxiety about radiation was associated with materials and knowledge about radiation in the PHNs in the Fukushima Prefecture 4 years after the FDNPS accident. It is important for PHNs to obtain knowledge and teaching materials about radiation, and radiation education programmes for PHNs must be established in areas that have nuclear facilities. Published by the BMJ Publishing Group Limited. For

  11. Radiation-related anxiety among public health nurses in the Fukushima Prefecture after the accident at the Fukushima Daiichi Nuclear Power Station: a cross-sectional study

    PubMed Central

    Yoshida, Koji; Orita, Makiko; Goto, Aya; Kumagai, Atsushi; Yasui, Kiyotaka; Ohtsuru, Akira; Hayashida, Naomi; Kudo, Takashi; Yamashita, Shunichi; Takamura, Noboru

    2016-01-01

    Objective In Japan, public health nurses (PHNs) play important roles in managing the health of local residents, especially after a disaster. In this study, we assessed radiation anxiety and the stress processing capacity of PHNs in the Fukushima Prefecture in Japan, after the accident at the Fukushima Daiichi Nuclear Power Station (FDNPS). Methods We conducted a questionnaire survey among the PHNs (n=430) in July of 2015 via postal mail. The questions included demographic factors (sex, age and employment position), knowledge about radiation, degree of anxiety about radiation at the time of the FDNPS accident (and at present), by asking them to answer questions about radiation and the Sense of Coherence-13 (SOC-13). We classified the low and high levels of anxiety by asking them to answer questions about radiation, and compared the anxiety-negative (−) group with the anxiety-positive (+) group. Results Of the PHNs, 269 (62.6%) were classified in the anxiety (−) group and 161 (37.4%) were in the anxiety (+) group. When the multivariate logistic regression analysis was conducted, the PHNs at the time of the accident (OR: 2.37, p=0.007), current general anxieties about radiation (OR: 3.56, p<0.001), current possession of materials to obtain knowledge about radiation (OR: 2.11, p=0.006) and knowledge of the childhood thyroid cancer increase after the Chernobyl accident (OR: 1.69, p=0.035) were significantly associated with anxiety after the FDNPS accident. The mean SOC-13 was 43.0±7.7, with no significant difference between the anxiety (−) group and anxiety (+) group (p=0.47). Conclusions Our study suggested that anxiety about radiation was associated with materials and knowledge about radiation in the PHNs in the Fukushima Prefecture 4 years after the FDNPS accident. It is important for PHNs to obtain knowledge and teaching materials about radiation, and radiation education programmes for PHNs must be established in areas that have nuclear facilities. PMID

  12. Evaluation of a main steam line break with induced, multiple tube ruptures: A comparison of NUREG 1477 (Draft) and transient methodologies Palo Verde Nuclear Generating Station

    SciTech Connect

    Parrish, K.R.

    1995-09-01

    This paper presents the approach taken to analyze the radiological consequences of a postulated main steam line break event, with one or more tube ruptures, for the Palo Verde Nuclear Generating Station. The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on March 14, 1993 and to justify continued operation of Units 1 and 3. During the post-event evaluation, the NRC expressed concern that Unit 2 could have been operating with degraded tubes and that similar conditions could exist in Units 1 and 3. The NRC therefore directed that a safety assessment be performed to evaluate a worst case scenario in which a non-isolable main steam line break occurs inducing one or more tube failures in the faulted steam generator. This assessment was to use the generic approach described in NUREG 1477, Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report. An analysis based on the NUREG approach was performed but produced unacceptable results for off-site and control room thyroid doses. The NUREG methodology, however, does not account for plant thermal-hydraulic transient effects, system performance, or operator actions which could be credited to mitigate dose consequences. To deal with these issues, a more detailed analysis methodology was developed using a modified version of the Combustion Engineering Plant Analysis Code, which examines the dose consequences for a main steam line break transient with induced tube failures for a spectrum equivalent to 1 to 4 double ended guillotine U-tube breaks. By incorporating transient plant system responses and operator actions, the analysis demonstrates that the off-site and control room does consequences for a MSLBGTR can be reduced to acceptable limits. This analysis, in combination with other corrective and recovery actions, provided sufficient justification for continued operation of PVNGS Units 1 and 3, and for the subsequent restart of Unit 2.

  13. The (137)Cs activity concentration of suspended and dissolved fractions in irrigation waters collected from the 80 km zone around TEPCO's Fukushima Daiichi Nuclear Power Station.

    PubMed

    Tsukada, Hirofumi; Nihira, Satoshi; Watanabe, Takashi; Takeda, Satoru

    2017-08-11

    Fifty-four samples of irrigation water were collected in 2014 from agricultural ponds, rivers, and dams within the 80 km zone around TEPCO's Fukushima Daiichi Nuclear Power Station (FDNPS). The samples were filtered with a 0.45 μm pore-size membrane filter to produce suspended and dissolved fractions. The (137)Cs activity concentration of the suspended fraction varied from 1.5 to 300 Bq g(-1) dry weight and was significantly higher than that in the soil around each sampling site. The range of (137)Cs activity concentrations in the dissolved fraction varied over three orders of magnitude at 0.0075-6.7 Bq l(-1), which was a larger range than that of the suspended fraction; the higher values for samples were from within the 20 km zone. In the dissolved fraction 87 ± 9% of the (137)Cs (n = 37) was in a monovalent cationic form (Cs(+)) and therefore potentially mobile. The distribution coefficient (Kd) ranged from 4100 to 2,100,000; the geometric mean value (110,000) was higher than that reported by the IAEA (2010). The geometric mean Kd of samples collected from the 20 km zone was 61,000 (n = 27), which was significantly lower than that collected from 20 to 80 km zone (200,000, n = 27). The Kd-value was negative correlated with the concentration of stable (133)Cs and the electric conductivity in the dissolved fraction. This shows relatively higher mobility of radiocaesium in irrigation waters may occur when there are higher contents of cations present. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Prediction and modeling of the two-dimensional separation characteristic of a steam generator at a nuclear power station with VVER-1000 reactors

    NASA Astrophysics Data System (ADS)

    Parchevsky, V. M.; Guryanova, V. V.

    2017-01-01

    A computational and experimental procedure for construction of the two-dimensional separation curve (TDSC) for a horizontal steam generator (SG) at a nuclear power station (NPS) with VVER-reactors. In contrast to the conventional one-dimensional curve describing the wetness of saturated steam generated in SG as a function of the boiler water level at one, usually rated, load, TDSC is a function of two variables, which are the level and the load of SGB that enables TDSC to be used for wetness control in a wide load range. The procedure is based on two types of experimental data obtained during rated load operation: the nonuniformity factor of the steam load at the outlet from the submerged perforated sheet (SPS) and the dependence of the mass water level in the vicinity of the "hot" header on the water level the "cold" end of SG. The TDSC prediction procedure is presented in the form of an algorithm using SG characteristics, such as steam load and water level as the input and giving the calculated steam wetness at the output. The zoneby-zone calculation method is used. The result is presented in an analytical form (as an empirical correlation) suitable for uploading into controllers or other controls. The predicted TDSC can be used during real-time operation for implementation of different wetness control scenarios (for example, if the effectiveness is a priority, then the minimum water level, minimum wetness, and maximum turbine efficiency should be maintained; if safety is a priority, then the maximum level at the allowable wetness and the maximum water inventory should be kept), for operation of NPS in controlling the frequency and power in a power system, at the design phase (as a part of the simulation complex for verification of design solutions), during construction and erection (in developing software for personnel training simulators), during commissioning tests (to reduce the duration and labor-intensity of experimental activities), and for training.

  15. Measuring the external exposure dose in the contaminated area near the Chernobyl nuclear power station using the thermoluminescence of quartz in bricks.

    PubMed

    Sato, Hitoshi; Takatsuji, Toshihiro; Takada, Jun; Endo, Satoru; Hoshi, Masaharu; Sharifov, Vagif F; Veselkina, Irina I; Pilenko, Irina V; Kalimullin, Wafa A F; Masyakin, Vladimir B; Yoshikawa, Isao; Nagatomo, Tsuneto; Okajima, Syunzo

    2002-08-01

    We collected bricks from buildings in the heavily contaminated evacuated area of Belarus in a 30-km zone around the Chernobyl nuclear power station and the Gomel-Bryansk area of 150-250 km from Chernobyl and estimated the cumulative radiation dose caused by the reactor accident by measuring the thermoluminescence (TL) of the bricks. The annual dose at each location was measured using glass dosimeters and thermoluminescence dosimeters (TLD). The dose rate was measured using an energy-compensated NaI scintillation survey meter. The soil contamination near the location of each brick was measured using a germanium semiconductor detector. The main purpose of the project was to extrapolate the relation between the cumulative external dose and the present dose rate or contamination level to the lower contaminated areas. The results of the glass dosimeter, TLD, and survey meter determinations were almost identical. For a determination of the annual dose higher than 10 mGy y(-1), the cumulative dose by TL (TL dose) was roughly proportional to the annual dose and about 1.5 times larger than the cumulative dose calculated from the annual dose and 137Cs half life. The difference is expected due to the contribution of short-lived nuclides immediately after the accident or localized heavy contamination of the ground surface with 137Cs that migrated afterwards. For annual dose smaller than 10 mGy y(-1), the proportionality was not observed and most of the locations facing indoors showed TL doses very much larger than that expected from the proportionality. The cumulative dose outdoors by TL was also roughly proportional to the regional 137Cs contamination level and the proportional constant is about 10(-1) mGy per GBq km(-2), and is about 250 times larger than the present annual internal dose derived from published results. The correlation between the present dose rate where the brick was sampled and the average 137Cs concentration in the ground soil near the point is not clear

  16. Ecosystem monitoring of radiocesium redistribution dynamics in a forested catchment in Fukushima after the nuclear power station accident in March 2011

    NASA Astrophysics Data System (ADS)

    Ohte, N.; Endo, I.; Ohashi, M.; Murakami, M.; Oda, T.; Hotta, N.; Yamanishi, R.; Sugiyama, Y.; Tanoi, K.; Kobayashi, N. I.; Ishii, N.

    2016-12-01

    The accident at the Fukushima Daiichi Nuclear Power Station (F1NPS) in March 2011 emitted 1.2 × 1016 Bq of cesium-137 (137Cs) into the surrounding environment. Radioactive substances, including 137Cs, were deposited onto forested areas in the northeastern region of Japan. To clarify the mechanisms of dispersion and export of 137Cs, within and from a forest ecosystem, we have conducted intensive field observations on hydrological processes and the 137Cs movement and storage in a forested headwater catchment in an area 50 km from F1NNS. Two major pathways of 137Cs transport were focused: 1) through the hydrological processes with dissolved and particulate or colloidal forms, and 2) by dispersion through the food web in the forest-stream ecological continuum. The 137Cs concentrations of stream waters were monitored. Various aquatic and terrestrial organisms were periodically sampled to measure their 137Cs concentrations. The results indicate that the major form of exported 137Cs is via suspended solid in the streamflow. Thus, high flows generated by a storm event accelerated strongly the transportation of 137Cs from the forested catchments. Estimation of 137Cs export from the forested catchments requires precise evaluation of the high water flow during storm events. On the other hand, dissolved form, especially mineral ion form of 137Cs were dominant in througfall and stemflow. Because the biggest pool of 137Cs in the forested ecosystem was the accumulated litters and detritus on the forest floor, 137Cs dispersion through food web was quicker through the detritus food chain than through the grazing food chain. 137Cs concentration of leaves (1.1k Bq/kg), barks (4.4-22.5 kBq/kg) woods (0.1-0.6 kBq/kg) and litters (1.3 kBq/kg) of a dominant deciduous tree (Quercus serrata) suggested that internal cyccling of 137Cs have aready occurred between surface soils including litter layer and plants.

  17. Distributions of Pu isotopes in seawater and bottom sediments in the coast of the Japanese archipelago before and soon after the Fukushima Dai-ichi Nuclear Power Station accident.

    PubMed

    Oikawa, Shinji; Watabe, Teruhisa; Takata, Hyoe

    2015-04-01

    A radioactivity measurement survey was carried out from 24 April 2008 to 3 June 2011 to determine the levels of plutonium isotopes and (240)Pu/(239)Pu atom ratios in the marine environments off the sites of commercial nuclear power stations around the Japanese islands; the sampling period extended to two months after the Fukushima Dai-ichi Nuclear Power Station accident. In our previous study (Oikawa et al., 2015), data on Pu isotopes and (241)Am in sediments have already been reported. In this study, we report those on Pu isotopes in seawater as well as sediments, and the characteristics of sediments in addition (e.g., ignition loss and biogenic opals). Concentrations of (239+240)Pu in seawater and bottom sediments remained nearly constant at all sampling locations during the survey period. In addition, no regional differences were observed in the (239+240)Pu concentrations in surface waters. Higher (239+240)Pu concentrations were found in bottom waters at deeper sampling locations, but the (240)Pu/(239)Pu atom ratios were nearly constant regardless of the water depth. Higher (239+240)Pu concentrations were also found in bottom sediments at deeper sampling locations, but vice versa for (240)Pu/(239)Pu atom ratios as reported in the previous report. The sediments samples from deeper locations showed the higher percentage of ignition loss as well as the higher content of biogenic opal. There was likely to be some driving force participating in the transfer of Pu isotopes associated with biogenic substances to the deeper seabed. The present survey showed that the accident at the Fukushima Dai-ichi Nuclear Power Station did not contribute much to the inventory of Pu isotopes in the adjacent sea area.

  18. Space Station

    NASA Image and Video Library

    1972-01-01

    This is an artist's concept of a modular space station. In 1970 the Marshall Space Flight Center arnounced the completion of a study concerning a modular space station that could be launched by the planned-for reusable Space Shuttle. The study envisioned a space station composed of cylindrical sections 14 feet in diameter and of varying lengths joined to form any one of a number of possible shapes. The sections were restricted to 14 feet in diameter and 58 feet in length to be consistent with a shuttle cargo bay size of 15 by 60 feet. Center officials said that the first elements of the space station could be in orbit by about 1978 and could be manned by three or six men. This would be an interim space station with sections that could be added later to form a full 12-man station by the early 1980s.

  19. Space station

    NASA Technical Reports Server (NTRS)

    Stewart, Donald F.; Hayes, Judith

    1989-01-01

    The history of American space flight indicates that a space station is the next logical step in the scientific pursuit of greater knowledge of the universe. The Space Station and its complement of space vehicles, developed by NASA, will add new dimensions to an already extensive space program in the United States. The Space Station offers extraordinary benefits for a comparatively modest investment (currently estimated at one-ninth the cost of the Apollo Program). The station will provide a permanent multipurpose facility in orbit necessary for the expansion of space science and technology. It will enable significant advancements in life sciences research, satellite communications, astronomy, and materials processing. Eventually, the station will function in support of the commercialization and industrialization of space. Also, as a prerequisite to manned interplanetary exploration, the long-duration space flights typical of Space Station missions will provide the essential life sciences research to allow progressively longer human staytime in space.

  20. Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-category 1 systems for the Yankee Rowe Nuclear Power Station

    SciTech Connect

    Epps, R.C.

    1980-11-01

    This report documents the technical evaluation of the Maine Yankee Atomic Power Station. The purpose of this evaluation was to determine whether the failure of any non-Class I (seismic) equipment could result in a condition, such as flooding, that might adversely affect the performance of the safety-related equipment required for the safe shutdown of the facility, or to mitigate the consequences of an accident. Criteria developed by the US Nuclear Regulatory Commission were used to evaluate the acceptability of the existing protection system as well as measures taken by Maine Yankee Atomic Power Company (MYAPC) to minimize the danger of flooding and to protect safety-related equipment.

  1. Psychological distress of residents in Kawauchi village, Fukushima Prefecture after the accident at Fukushima Daiichi Nuclear Power Station: the Fukushima Health Management Survey.

    PubMed

    Yoshida, Koji; Shinkawa, Tetsuko; Urata, Hideko; Nakashima, Kanami; Orita, Makiko; Yasui, Kiyotaka; Kumagai, Atsushi; Ohtsuru, Akira; Yabe, Hirooki; Maeda, Masaharu; Hayashida, Naomi; Kudo, Takashi; Yamashita, Shunichi; Takamura, Noboru

    2016-01-01

    To shed light on the mental health of evacuees after the accident at Fukushima Daiichi Nuclear Power Station (FDNPS), we evaluate the results of the Fukushima Health Management Survey (FHMS) of the residents at Kawauchi village in Fukushima, which is located less than 30 km from the FDNPS. We conducted the cross-sectional study within the framework of the FHMS. Exposure values were "anorexia," "subjective feelings about health," "feelings about sleep satisfaction," and "bereavement caused by the disaster," confounding variables were "age" and "sex," and outcome variables were "K6 points." We collected data from the FHMS, and employed the Kessler Psychological Distress Scale (K6) and the posttraumatic stress disorder (PTSD) Checklist Stressor-Specific Version (PCL-S) to carry out the research. A total of 13 or greater was the cut-off for identifying serious mental illness using the K6 scale. The study subjects included residents (n = 542) of over 30 years of age from Kawauchi village, and data were used from the period of January 1, 2012 to October 31, 2012. A total of 474 residents (87.5%) scored less than 13 points in the K6 and 68 (12.6%) scored 13 points or more. The proportion of elderly residents (over 65 years old) among people with K6 score above the cut-off was higher than that among people with K6 score below the cut-off (44.1 vs 31.0%, p < 0.05). In addition, the proportion of residents with anorexia and mental illness among people with K6 score above the cut-off was higher than among people with K6 score below the cut-off (p < 0.001 and p < 0.05, respectively). The amount of residents who scored 44 points or more in the PCL-S among people with K6 score above the cut-off was also considerably higher than among people with K6 score below the cut-off (79.4 vs 12.9%, p < 0.001). Interestingly, the proportion of residents who scored more than among people with K6 score above the cut-off and the among people with PCL-S score above the cut-off in Kawauchi was

  2. Psychological distress of residents in Kawauchi village, Fukushima Prefecture after the accident at Fukushima Daiichi Nuclear Power Station: the Fukushima Health Management Survey

    PubMed Central

    Yoshida, Koji; Shinkawa, Tetsuko; Urata, Hideko; Nakashima, Kanami; Orita, Makiko; Yasui, Kiyotaka; Kumagai, Atsushi; Ohtsuru, Akira; Yabe, Hirooki; Maeda, Masaharu; Hayashida, Naomi; Kudo, Takashi; Yamashita, Shunichi

    2016-01-01

    Background To shed light on the mental health of evacuees after the accident at Fukushima Daiichi Nuclear Power Station (FDNPS), we evaluate the results of the Fukushima Health Management Survey (FHMS) of the residents at Kawauchi village in Fukushima, which is located less than 30 km from the FDNPS. Methods We conducted the cross-sectional study within the framework of the FHMS. Exposure values were “anorexia,” “subjective feelings about health,” “feelings about sleep satisfaction,” and “bereavement caused by the disaster,” confounding variables were “age” and “sex,” and outcome variables were “K6 points.” We collected data from the FHMS, and employed the Kessler Psychological Distress Scale (K6) and the posttraumatic stress disorder (PTSD) Checklist Stressor-Specific Version (PCL-S) to carry out the research. A total of 13 or greater was the cut-off for identifying serious mental illness using the K6 scale. The study subjects included residents (n = 542) of over 30 years of age from Kawauchi village, and data were used from the period of January 1, 2012 to October 31, 2012. Results A total of 474 residents (87.5%) scored less than 13 points in the K6 and 68 (12.6%) scored 13 points or more. The proportion of elderly residents (over 65 years old) among people with K6 score above the cut-off was higher than that among people with K6 score below the cut-off (44.1 vs 31.0%, p < 0.05). In addition, the proportion of residents with anorexia and mental illness among people with K6 score above the cut-off was higher than among people with K6 score below the cut-off (p < 0.001 and p < 0.05, respectively). The amount of residents who scored 44 points or more in the PCL-S among people with K6 score above the cut-off was also considerably higher than among people with K6 score below the cut-off (79.4 vs 12.9%, p < 0.001). Interestingly, the proportion of residents who scored more than among people with K6 score above the cut-off and the among

  3. 78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-19

    ... COMMISSION Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station, Pilgrim Nuclear Power Station, Request for Action AGENCY: Nuclear Regulatory Commission... petitioners'') has requested that the NRC take action with regard to James A. Fitzpatrick Nuclear Power Plant...

  4. Space Station

    NASA Technical Reports Server (NTRS)

    Anderton, D. A.

    1985-01-01

    The official start of a bold new space program, essential to maintain the United States' leadership in space was signaled by a Presidential directive to move aggressively again into space by proceeding with the development of a space station. Development concepts for a permanently manned space station are discussed. Reasons for establishing an inhabited space station are given. Cost estimates and timetables are also cited.

  5. Space Station

    NASA Image and Video Library

    1952-01-01

    This is a von Braun 1952 space station concept. In a 1952 series of articles written in Collier's, Dr. Wernher von Braun, then Technical Director of the Army Ordnance Guided Missiles Development Group at Redstone Arsenal, wrote of a large wheel-like space station in a 1,075-mile orbit. This station, made of flexible nylon, would be carried into space by a fully reusable three-stage launch vehicle. Once in space, the station's collapsible nylon body would be inflated much like an automobile tire. The 250-foot-wide wheel would rotate to provide artificial gravity, an important consideration at the time because little was known about the effects of prolonged zero-gravity on humans. Von Braun's wheel was slated for a number of important missions: a way station for space exploration, a meteorological observatory and a navigation aid. This concept was illustrated by artist Chesley Bonestell.

  6. Space Station

    NASA Image and Video Library

    1969-01-01

    This picture illustrates a concept of a 33-Foot-Diameter Space Station Leading to a Space Base. In-house work of the Marshall Space Flight Center, as well as a Phase B contract with the McDornel Douglas Astronautics Company, resulted in a preliminary design for a space station in 1969 and l970. The Marshall-McDonnel Douglas approach envisioned the use of two common modules as the core configuration of a 12-man space station. Each common module was 33 feet in diameter and 40 feet in length and provided the building blocks, not only for the space station, but also for a 50-man space base. Coupled together, the two modules would form a four-deck facility: two decks for laboratories and two decks for operations and living quarters. Zero-gravity would be the normal mode of operation, although the station would have an artificial gravity capability. This general-purpose orbital facility was to provide wide-ranging research capabilities. The design of the facility was driven by the need to accommodate a broad spectrum of activities in support of astronomy, astrophysics, aerospace medicine, biology, materials processing, space physics, and space manufacturing. To serve the needs of Earth observations, the station was to be placed in a 242-nautical-mile orbit at a 55-degree inclination. An Intermediate-21 vehicle (comprised of Saturn S-IC and S-II stages) would have launched the station in 1977.

  7. Space Station

    NASA Image and Video Library

    1991-01-01

    This artist's concept depicts the Space Station Freedom as it would look orbiting the Earth, illustrated by Marshall Space Flight Center artist, Tom Buzbee. Scheduled to be completed in late 1999, this smaller configuration of the Space Station featured a horizontal truss structure that supported U.S., European, and Japanese Laboratory Modules; the U.S. Habitation Module; and three sets of solar arrays. The Space Station Freedom was an international, permanently marned, orbiting base to be assembled in orbit by a series of Space Shuttle missions that were to begin in the mid-1990's.

  8. Space Station

    NASA Image and Video Library

    1991-01-01

    This artist's concept depicts the Space Station Freedom as it would look orbiting the Earth; illustrated by Marshall Space Flight Center artist, Tom Buzbee. Scheduled to be completed in late 1999, this smaller configuration of the Space Station features a horizontal truss structure that supported U.S., European, and Japanese Laboratory Modules; the U.S. Habitation Module; and three sets of solar arrays. The Space Station Freedom was an international, permanently marned, orbiting base to be assembled in orbit by a series of Space Shuttle missions that were to begin in the mid-1990's.

  9. JPRS Report, Nuclear Developments

    DTIC Science & Technology

    2016-03-24

    development of nuclear power stations. stand that thermal power generation (by coal) and hydropower generation can no longer meet the increas- ing...as quently, no firm decision was made on the construction building thermal power stations. In the first place, the of nuclear power stations, and...year, many thermal He pointed out that China is 20 years behind advanced power and hydropower experts pointed out that the way countries in developing

  10. 75 FR 10508 - Duke Energy Carolinas, LLC; Notice of Consideration of Issuance of Amendment to Facility...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-08

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY... License for McGuire Nuclear Station Units 1 and 2, Proposed No Significant Hazards Consideration... Non-Safeguards Information (SUNSI) AGENCY: Nuclear Regulatory Commission. ACTION: Order, notice of...

  11. Molecular forensic science analysis of nuclear materials

    NASA Astrophysics Data System (ADS)

    Reilly, Dallas David

    Concerns over the proliferation and instances of nuclear material in the environment have increased interest in the expansion of nuclear forensics analysis and attribution programs. A new related field, molecular forensic science (MFS) has helped meet this expansion by applying common scientific analyses to nuclear forensics scenarios. In this work, MFS was applied to three scenarios related to nuclear forensics analysis. In the first, uranium dioxide was synthesized and aged at four sets of static environmental conditions and studied for changes in chemical speciation. The second highlighted the importance of bulk versus particle characterizations by analyzing a heterogeneous industrially prepared sample with similar techniques. In the third, mixed uranium/plutonium hot particles were collected from the McGuire Air Force Base BOMARC Site and analyzed for chemical speciation and elemental surface composition. This work has identified new signatures and has indicated unexpected chemical behavior under various conditions. These findings have lead to an expansion of basic actinide understanding, proof of MFS as a tool for nuclear forensic science, and new areas for expansion in these fields.

  12. Stations Outdoors

    ERIC Educational Resources Information Center

    Madison, John P.; And Others

    1976-01-01

    Described is a program of outdoor education utilizing activity-oriented learning stations. Described are 13 activities including: a pond study, orienteering, nature crafts, outdoor mathematics, linear distance measurement, and area measurement. (SL)

  13. Space Station

    NASA Image and Video Library

    1970-01-01

    This is an illustration of the Space Base concept. In-house work of the Marshall Space Flight Center, as well as a Phase B contract with the McDornel Douglas Astronautics Company, resulted in a preliminary design for a space station in 1969 and l970. The Marshall-McDonnel Douglas approach envisioned the use of two common modules as the core configuration of a 12-man space station. Each common module was 33 feet in diameter and 40 feet in length and provided the building blocks, not only for the space station, but also for a 50-man space base. Coupled together, the two modules would form a four-deck facility: two decks for laboratories and two decks for operations and living quarters. Zero-gravity would be the normal mode of operation, although the station would have an artificial-gravity capability. This general-purpose orbital facility was to provide wide-ranging research capabilities. The design of the facility was driven by the need to accommodate a broad spectrum of activities in support of astronomy, astrophysics, aerospace medicine, biology, materials processing, space physics, and space manufacturing. To serve the needs of Earth observations, the station was to be placed in a 242-nautical-mile orbit at a 55-degree inclination. An Intermediate-21 vehicle (comprised of Saturn S-IC and S-II stages) would have launched the station in 1977.

  14. 76 FR 19148 - Entergy Nuclear Operations, Inc., Entergy Nuclear Vermont Yankee, LLC, Vermont Yankee Nuclear...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-06

    ... Commission (NRC) take action with regard to the Vermont Yankee Nuclear Power Station (VY). Mr. Saporito... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc., Entergy Nuclear Vermont Yankee, LLC, Vermont Yankee Nuclear...

  15. 75 FR 39057 - Entergy Nuclear Operations, Inc.; Entergy Nuclear Vermont Yankee, LLC; Vermont Yankee Nuclear...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-07

    ... Commission (NRC) take action with regard to the Vermont Yankee Nuclear Power Station. Mr. Mulligan requested... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Entergy Nuclear Vermont Yankee, LLC; Vermont Yankee Nuclear...

  16. Completely automated nuclear reactors for long-term operation II: toward a conceptual-level point design of a high-temperature, gas-cooled central power station system

    SciTech Connect

    Teller, E.; Ishikawa, M.; Wood, L.; Hyde, R.; Nuckolls, J.

    1996-06-01

    We discuss a new type of nuclear fission power reactor optimized for the generation of heat for use in obviously safe, economic, and long- duration electricity production in large central power stations. These reactors are fundamentally different in design, implementation, and operation from conventional light-water-cooled and- moderated reactors (LWRs) currently in widespread use. they feature a low- average-enrichment initial fuel loading which lasts the entire 30 year, full-power design life of the power plant, and which is intended never to be removed from the reactor. The reactor contains a cylindrical core comprised of a nuclear ignitor and a much larger nuclear [breeding + burning] wave propagating region containing natural thorium or uranium fuel, a surrounding neutron reflector and radiation shield, distributed means for implementing a thermostating function on the reactivity and local power density, a redundant pressurized gas coolant transport system, and automatic and redundant heat dumping means to obviate concerns regarding all classes of loss-of-coolant accidents during the plants operational and post operational life. These reactors are proposed to be situated at {>=}100 meter depths underground. There operation will be completely automatic, with no powered mechanisms, no operator controls and no provision for human access during or after their operational lifetime, in order to avoid both error and misuse. The power plant`s heat engine and electrical generator sub-systems are located above ground and are connected to the nuclear heat source only with readily sealed coolant conduits. This paper outlines a concept level point design of a 1 GWe member of this type of reactor, one oriented to production of high temperature, high pressure coolant gas and directed towards 60% efficiency, combined-cycle electricity generation.

  17. Report to the NRC on guidance for preparing scenarios for emergency preparedness exercises at nuclear generating stations. Draft report for comment

    SciTech Connect

    Martin, G. F.; Hickey, E. E.; Moeller, M. P.; Schultz, D. H.; Bethke, G. W.

    1986-03-01

    A scenario guidance handbook was prepared to assist emergency planners in developing scenarios for emergency preparedness exercises at nuclear power plants. The handbook provides guidance for the development of the objectives of an exercise, the descriptions of scenario events and responses, and the instructions to the participants. Information concerning implementation of the scenario, critiques and findings, and generation and format of scenario data are also included. Finally, examples of manual calculational techniques for producing radiological data are included as an appendix.

  18. Space Station

    NASA Image and Video Library

    1971-01-01

    This is an artist's concept of the Research and Applications Modules (RAM). Evolutionary growth was an important consideration in space station plarning, and another project was undertaken in 1971 to facilitate such growth. The RAM study, conducted through a Marshall Space Flight Center contract with General Dynamics Convair Aerospace, resulted in the conceptualization of a series of RAM payload carrier-sortie laboratories, pallets, free-flyers, and payload and support modules. The study considered two basic manned systems. The first would use RAM hardware for sortie mission, where laboratories were carried into space and remained attached to the Shuttle for operational periods up to 7 days. The second envisioned a modular space station capability that could be evolved by mating RAM modules to the space station core configuration. The RAM hardware was to be built by Europeans, thus fostering international participation in the space program.

  19. Space Station

    NASA Image and Video Library

    1986-08-01

    In response to President Reagan's directive to NASA to develop a permanent marned Space Station within a decade, part of the State of the Union message to Congress on January 25, 1984, NASA and the Administration adopted a phased approach to Station development. This approach provided an initial capability at reduced costs, to be followed by an enhanced Space Station capability in the future. This illustration depicts a configuration with enhanced capabilities. It builds on the horizontal boom and module pattern of the revised baseline. This configuration would feature dual keels, two vertical spines 105-meters long joined by upper and lower booms. The structure carrying the modules would become a transverse boom of a basically rectangular structure. The two new booms, 45-meters in length, would provide extensive accommodations for attached payloads, and would offer a wide field of view. Power would be increased significantly, with the addition if a 50-kW solar dynamic power system.

  20. Observation Station

    ERIC Educational Resources Information Center

    Rutherford, Heather

    2011-01-01

    This article describes how a teacher integrates science observations into the writing center. At the observation station, students explore new items with a science theme and use their notes and questions for class writings every day. Students are exposed to a variety of different topics and motivated to write in different styles all while…

  1. Space Station

    NASA Image and Video Library

    1989-08-01

    In response to President Reagan's directive to NASA to develop a permanent marned Space Station within a decade, part of the State of the Union message to Congress on January 25, 1984, NASA and the Administration adopted a phased approach to Station development. This approach provided an initial capability at reduced costs, to be followed by an enhanced Space Station capability in the future. This illustration depicts the baseline configuration, which features a 110-meter-long horizontal boom with four pressurized modules attached in the middle. Located at each end are four photovoltaic arrays generating a total of 75-kW of power. Two attachment points for external payloads are provided along this boom. The four pressurized modules include the following: A laboratory and habitation module provided by the United States; two additional laboratories, one each provided by the European Space Agency (ESA) and Japan; and an ESA-provided Man-Tended Free Flyer, a pressurized module capable of operations both attached to and separate from the Space Station core. Canada was expected to provide the first increment of a Mobile Serving System.

  2. Space Station

    NASA Image and Video Library

    1985-12-01

    Skylab's success proved that scientific experimentation in a low gravity environment was essential to scientific progress. A more permanent structure was needed to provide this space laboratory. President Ronald Reagan, on January 25, 1984, during his State of the Union address, claimed that the United States should exploit the new frontier of space, and directed NASA to build a permanent marned space station within a decade. The idea was that the space station would not only be used as a laboratory for the advancement of science and medicine, but would also provide a staging area for building a lunar base and manned expeditions to Mars and elsewhere in the solar system. President Reagan invited the international community to join with the United States in this endeavour. NASA and several countries moved forward with this concept. By December 1985, the first phase of the space station was well underway with the design concept for the crew compartments and laboratories. Pictured are two NASA astronauts, at Marshall Space Flight Center's (MSFC) Neutral Buoyancy Simulator (NBS), practicing construction techniques they later used to construct the space station after it was deployed.

  3. Nuclear Regulatory Commission issuances

    SciTech Connect

    1996-03-01

    This document is the March 1996 listing of NRC issuances. Included are: (1) NRC orders granting Cleveland Electric Illuminating Company`s petition for review of the ASLB order LBP-95-17, (2) NRC orders relating to the potential disqualification of two commissioners in the matter of the decommissioning of Yankee Nuclear Power Station, (3) ASLB orders pertaining to the Oncology Services Corporation, (4) ASLB orders pertaining to the Radiation Oncology Center, (5) ASLB orders pertaining to the Yankee Nuclear Power Station, and (6) Director`s decision pertaining to the Yankee Nuclear Power Station.

  4. Estimation of internal exposure of the thyroid to (131)I on the basis of (134)Cs accumulated in the body among evacuees of the Fukushima Daiichi Nuclear Power Station accident.

    PubMed

    Hosoda, Masahiro; Tokonami, Shinji; Akiba, Suminori; Kurihara, Osamu; Sorimachi, Atsuyuki; Ishikawa, Tetsuo; Momose, Takumaro; Nakano, Takashi; Mariya, Yasushi; Kashiwakura, Ikuo

    2013-11-01

    Namie Town was heavily contaminated by the Fukushima Daiichi Nuclear Power Station accident. The thyroid equivalent dose for residents who lived in Namie was estimated using results of whole body counting examinations which were carried out by the Japan Atomic Energy Agency a few months after the nuclear accident. Photon peaks of (131)I and (134)Cs were previously measured by the authors using a NaI(Tl) scintillation spectrometer and that information was used to estimate the (131)I/(134)Cs activity ratio of total intake in the present study. The maximum values of (131)I/(134)Cs activity ratio corresponding to thyroid uptake factors of 0.3, 0.1 and 0.03 were evaluated to be 0.9, 2.6 and 8.7, respectively. The maximum value of the (131)I/(134)Cs activity ratio was used to obtain the most conservative thyroid equivalent dose estimation. The maximum internal exposure of the thyroid to (131)I on the basis of (134)Cs accumulated in the body measured by the whole body counter was estimated to be 18mSv. This value was much smaller than 50mSv that the International Atomic Energy Agency recommends as the dose at which exposed persons should take stable iodine tablets.

  5. The Communication of Information Such as Evacuation Orders at the Time of a Nuclear Power Station Accident: -Recommendations for responses by the national government and electric power utilities to the "Information Disaster".

    PubMed

    Hatanaka, Takashi; Yoshida, Sumito; Ojino, Mayo; Ishii, Masami

    2014-12-01

    This research was carried out from the perspective that the damage to the people of Fukushima and others from the Fukushima Daiichi Nuclear Power Station (NPS) accident was an "information disaster." It evaluated the critical problems raised by and actual condition analysis on the process of events in the Fukushima Daiichi NPS disaster and responses of the governments and others, notification of the occurrence of the accident and evacuation order by the national and local governments and the evacuation of residents, and guidance for distribution and intake of stable iodine tablets. The research aimed to provide a basis for the implementation of effective distribution and intake of stable iodine tablets and responses to the "information disaster" in the nuclear power disaster. On March 15 at the time that the most radioactive substances were dispersed, even when the average wind speed at the site area was 1.6 m/s, the radioactive substances had reached the outer boundary of Urgent Protective action planning Zone (UPZ, the region with a radius of 30 km) within about five hours. Because of this, every second counted in the provision of information about the accident and the issuance of evacuation orders. This study evaluated the actual condition of information provision by the national government and others from the perspective of this awareness of the importance of time. On the basis of the results of this kind of consideration, we come to the following recommendations: The Nuclear Emergency Response Guidelines and the system for communication of information to medical providers should be revised. The national government should make preparations for the effective advance distribution and intake of stable iodine tablets.

  6. Nuclear Regulatory Commission issuances, June 1996. Volume 43, Number 6

    SciTech Connect

    1996-06-01

    This report covers the issuances received during the specified period form the Commission, the Atomic Safety and licensing Boards, the administrative Law Judges, the Director`s decisions and the Decisions on Petitions for Rulemaking. Included are a memorandum and order on the decommissioning plan for Yankee Nuclear Power Station, a memorandum and order suspending byproduct material license for Eastern Testing and Inspection, Inc., an initial decision of the source materials license for Sequoyah Fuels Corporation, Director`s decisions for Palo Verde Nuclear Generating Station, Indian Point, Peach Bottom Atomic Power Station, Trojan Nuclear Plant, Rancho Seco Nuclear Generating Station, San Onofre Nuclear Generating Station, and Yankee Nuclear Power Station.

  7. Britain`s nuclear quandary

    SciTech Connect

    1994-07-01

    This article is review of energy policy in the United Kingdom, in particular, the British government`s review of the nuclear industry. Major topics of this review include: (1) The economic viability of new nuclear stations, (2) The privitization of the nuclear industry, (3) Nuclear waste disposal, and (4) Liabilities associated with decommissioning.

  8. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    SciTech Connect

    GREENE,G.A.; GUPPY,J.G.

    1998-09-01

    This is the final report on the INSP project entitled, ``Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant.

  9. Compression and immersion tests and leaching of radionuclides, stable metals, and chelating agents from cement-solidified decontamination waste collected from nuclear power stations

    SciTech Connect

    Akers, D.W.; Kraft, N.C.; Mandler, J.W.

    1994-06-01

    A study was performed for the Nuclear Regulatory Commission (NRC) to evaluate structural stability and leachability of radionuclides, stable metals, and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from seven commercial boiling water reactors and one pressurized water reactor. The decontamination methods used at the reactors were the Can-Decon, AP/Citrox, Dow NS-1, and LOMI processes. Samples of untreated resin waste and solidified waste forms were subjected to immersion and compressive strength testing. Some waste-form samples were leach-tested using simulated groundwaters and simulated seawater for comparison with the deionized water tests that are normally performed to assess waste-form leachability. This report presents the results of these tests and assesses the effects of the various decontamination methods, waste form formulations, leachant chemical compositions, and pH of the leachant on the structural stability and leachability of the waste forms. Results indicate that releases from intact and degraded waste forms are similar and that the behavior of some radionuclides such as {sup 55}Fe, {sup 60}Co, and {sup 99}Tc were similar. In addition, the leachability indexes are greater than 6.0, which meets the requirement in the NRC`s ``Technical Position on Waste Form,`` Revision 1.

  10. Independent technical support for the frozen soil barrier installation and operation at the Fukushima Daiichi Nuclear Power Station (F1 Site)

    SciTech Connect

    Looney, Brian B.; Jackson, Dennis G.; Truex, Michael J.; Johnson, Christian D.

    2015-02-23

    TEPCO is implementing a number of water countermeasures to limit the releases and impacts of contaminated water to the surrounding environment. The diverse countermeasures work together in an integrated manner to provide different types, and several levels, of protection. In general, the strategy represents a comprehensive example of a “defense in depth” concept that is used for nuclear facilities around the world. One of the key countermeasures is a frozen soil barrier encircling the damaged reactor facilities. The frozen barrier is intended to limit the flow of water into the area and provide TEPCO the ability to reduce the amount of contaminated water that requires treatment and storage. The National Laboratory team supports the selection of artificial ground freezing and the incorporation of the frozen soil barrier in the contaminated water countermeasures -- the technical characteristics of a frozen barrier are relatively well suited to the Fukushima-specific conditions and the need for inflow reduction. Further, our independent review generally supports the TEPCO/Kajima design, installation strategy and operation plan.

  11. Hourly atmospheric concentrations of Cs-134 and Cs-137 at monitoring stations for suspended particulate matter in and south of Fukushima after the Fukushima Daiichi Nuclear Power Plant accident

    NASA Astrophysics Data System (ADS)

    Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

    2013-04-01

    No data has been found of continuous monitoring of radioactive materials in the atmosphere in Fukushima area after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident on March 11, 2011, although it greatly contributes to accurate evaluation of the internal exposure dose, to reconstruction of emission time series of released radionuclides, and to validation of numerical simulations by atmospheric transport models. Then, we have challenged to retrieve the radioactivity in atmospheric aerosols collected every hour on a filter tape of Suspended Particulate Matter (SPM) monitoring system with beta ray attenuation method used at air pollution monitoring stations in east Japan. A test measurement for hourly atmospheric concentrations of Cs-134 and Cs-137 was successfully performed with a Ge detector for the used filter tapes during March 15-23, 2011, at three stations in Fukushima City 60 km northwest of the FD1NPP and four stations in southwest Ibaraki prefecture more than 150 km southwest of the FD1NPP. The data in Fukushima City revealed high Cs-137 concentrations of 10-30 Bq m-3 from the evening of March 15 to the early morning of March 16, when a large amount of radioactive materials was simultaneously deposited on the land surface by precipitation according to the measurement of radiation dose rate. Higher Cs-137 concentrations of 10-50 Bq m-3 were also found from the afternoon of March 20 to the morning of March 21, and which could not be detected by the radiation dose rate due to no precipitation. In contrast, much higher concentrations with the maximum of 320 Bq m-3 in southwest Ibaraki than in Fukushima City were found on the morning of March 15 and 21 under strong temperature inversion near the surface. The polluted air masses with high radioactive materials were passed away within a few hours as a plume in southwest Ibaraki, while the high Cs-137 concentrations lasted for 10-16 hours in Fukushima City where the polluted air masses after their transport

  12. Nuclear Security for Floating Nuclear Power Plants

    SciTech Connect

    Skiba, James M.; Scherer, Carolynn P.

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  13. Space Station

    NASA Image and Video Library

    1977-01-01

    The Marshall Space Flight Center (MSFC) and the Johnson Space Center (JSC) were each awarded 16-month contracts in April 1976 for the Space Station Systems Analysis Study (SSSAS). Grumman Aerospace Corporation was MSFC's contractor and McDornell Douglas Aerospace Company was JSC's contractor. The goal of this study was to formulate plans for a permanent operational base and laboratory facility in Earth orbit in addition to developing a space construction base design for implementing the program. An expended Space Shuttle external tank was to be the central core platform of the base, and additional pressurized modules could be added to provide laboratory facilities. This artist's concept depicts a space construction base design for implementing the SSSAS.

  14. RadNet Air Quality (Fixed Station) Data

    EPA Pesticide Factsheets

    RadNet is a national network of monitoring stations that regularly collect air for analysis of radioactivity. The RadNet network, which has stations in each State, has been used to track environmental releases of radioactivity from nuclear weapons tests and nuclear accidents. RadNet also documents the status and trends of environmental radioactivity

  15. Nuclear Shuttle Logistics Configuration

    NASA Technical Reports Server (NTRS)

    1971-01-01

    This 1971 artist's concept shows the Nuclear Shuttle in both its lunar logistics configuraton and geosynchronous station configuration. As envisioned by Marshall Space Flight Center Program Development persornel, the Nuclear Shuttle would deliver payloads to lunar orbits or other destinations then return to Earth orbit for refueling and additional missions.

  16. Aerospace crew station design

    NASA Technical Reports Server (NTRS)

    Carr, Gerald P. (Editor); Montemerlo, Melvin D. (Editor)

    1984-01-01

    Consideration is given to spacecraft cockpits and work stations, commercial aircraft cockpits and crew stations, high performance aircraft cockpits and crew stations, and space stations and habitat crew stations. Particular attention is given to an historical review of NASA manned spacecraft crew stations, ESA spacelab crew stations, the evolution of commercial aircraft flight station design, Boeing 757/767 flight deck, a historical review of Concorde flight deck design, trends in the cockpit design of new European fighters, and state-of-the-art applications for Space Station crew interface design.

  17. International Space Station Overview

    NASA Technical Reports Server (NTRS)

    Bates, William V., Jr.

    1999-01-01

    The overview of the International Space Station (ISS) is comprised of the program vision and mission; Space Station uses; definition of program phases; as well as descriptions and status of several scheduled International Space Station Overview assembly flights.

  18. Intelligent Virtual Station (IVS)

    NASA Technical Reports Server (NTRS)

    2002-01-01

    The Intelligent Virtual Station (IVS) is enabling the integration of design, training, and operations capabilities into an intelligent virtual station for the International Space Station (ISS). A viewgraph of the IVS Remote Server is presented.

  19. Space Station Freedom

    NASA Technical Reports Server (NTRS)

    1991-01-01

    In 1982, the Space Station Task Force was formed, signaling the initiation of the Space Station Freedom Program, and eventually resulting in the Marshall Space Flight Center's responsibilities for Space Station Work Package 1.

  20. Intelligent Virtual Station (IVS)

    NASA Technical Reports Server (NTRS)

    2002-01-01

    The Intelligent Virtual Station (IVS) is enabling the integration of design, training, and operations capabilities into an intelligent virtual station for the International Space Station (ISS). A viewgraph of the IVS Remote Server is presented.

  1. Nuclear Propulsion in Space (1968)

    ScienceCinema

    None

    2016-07-12

    Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

  2. Nuclear Propulsion in Space (1968)

    SciTech Connect

    2012-06-23

    Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

  3. Space station user's handbook

    NASA Technical Reports Server (NTRS)

    1972-01-01

    A user's handbook for the modular space station concept is presented. The document is designed to acquaint science personnel with the overall modular space station program, the general nature and capabilities of the station itself, some of the scientific opportunities presented by the station, the general policy governing its operation, and the relationship between the program and participants from the scientific community.

  4. Detailed source term estimation of the atmospheric release for the Fukushima Daiichi Nuclear Power Station accident by coupling simulations of an atmospheric dispersion model with an improved deposition scheme and oceanic dispersion model

    NASA Astrophysics Data System (ADS)

    Katata, G.; Chino, M.; Kobayashi, T.; Terada, H.; Ota, M.; Nagai, H.; Kajino, M.; Draxler, R.; Hort, M. C.; Malo, A.; Torii, T.; Sanada, Y.

    2015-01-01

    Temporal variations in the amount of radionuclides released into the atmosphere during the Fukushima Daiichi Nuclear Power Station (FNPS1) accident and their atmospheric and marine dispersion are essential to evaluate the environmental impacts and resultant radiological doses to the public. In this paper, we estimate the detailed atmospheric releases during the accident using a reverse estimation method which calculates the release rates of radionuclides by comparing measurements of air concentration of a radionuclide or its dose rate in the environment with the ones calculated by atmospheric and oceanic transport, dispersion and deposition models. The atmospheric and oceanic models used are WSPEEDI-II (Worldwide version of System for Prediction of Environmental Emergency Dose Information) and SEA-GEARN-FDM (Finite difference oceanic dispersion model), both developed by the authors. A sophisticated deposition scheme, which deals with dry and fog-water depositions, cloud condensation nuclei (CCN) activation, and subsequent wet scavenging due to mixed-phase cloud microphysics (in-cloud scavenging) for radioactive iodine gas (I2 and CH3I) and other particles (CsI, Cs, and Te), was incorporated into WSPEEDI-II to improve the surface deposition calculations. The results revealed that the major releases of radionuclides due to the FNPS1 accident occurred in the following periods during March 2011: the afternoon of 12 March due to the wet venting and hydrogen explosion at Unit 1, midnight of 14 March when the SRV (safety relief valve) was opened three times at Unit 2, the morning and night of 15 March, and the morning of 16 March. According to the simulation results, the highest radioactive contamination areas around FNPS1 were created from 15 to 16 March by complicated interactions among rainfall, plume movements, and the temporal variation of release rates. The simulation by WSPEEDI-II using the new source term reproduced the local and regional patterns of cumulative

  5. Space Station Spartan study

    NASA Technical Reports Server (NTRS)

    Lane, J. H.; Schulman, J. R.; Neupert, W. M.

    1985-01-01

    The required extension, enhancement, and upgrading of the present Spartan concept are described to conduct operations from the space station using the station's unique facilities and operational features. The space station Spartan (3S), the free flyer will be deployed from and returned to the space station and will conduct scientific missions of much longer duration than possible with the current Spartan. The potential benefits of a space station Spartan are enumerated. The objectives of the study are: (1) to develop a credible concept for a space station Spartan; and (2) to determine the associated requirements and interfaces with the space station to help ensure that the 3S can be properly accommodated.

  6. Nuclear Regulatory Commission issuances

    SciTech Connect

    1996-04-01

    This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services.

  7. Estimating the Duration of Public Concern After the Fukushima Dai-ichi Nuclear Power Station Accident From the Occurrence of Radiation Exposure-Related Terms on Twitter: A Retrospective Data Analysis

    PubMed Central

    2016-01-01

    Background After the Fukushima Dai-ichi Nuclear Power Station accident in Japan on March 11, 2011, a large number of comments, both positive and negative, were posted on social media. Objective The objective of this study was to clarify the characteristics of the trend in the number of tweets posted on Twitter, and to estimate how long public concern regarding the accident continued. We surveyed the attenuation period of the first term occurrence related to radiation exposure as a surrogate endpoint for the duration of concern. Methods We retrieved 18,891,284 tweets from Twitter data between March 11, 2011 and March 10, 2012, containing 143 variables in Japanese. We selected radiation, radioactive, Sievert (Sv), Becquerel (Bq), and gray (Gy) as keywords to estimate the attenuation period of public concern regarding radiation exposure. These data, formatted as comma-separated values, were transferred into a Statistical Analysis System (SAS) dataset for analysis, and survival analysis methodology was followed using the SAS LIFETEST procedure. This study was approved by the institutional review board of Hokkaido University and informed consent was waived. Results A Kaplan-Meier curve was used to show the rate of Twitter users posting a message after the accident that included one or more of the keywords. The term Sv occurred in tweets up to one year after the first tweet. Among the Twitter users studied, 75.32% (880,108/1,168,542) tweeted the word radioactive and 9.20% (107,522/1,168,542) tweeted the term Sv. The first reduction was observed within the first 7 days after March 11, 2011. The means and standard errors (SEs) of the duration from the first tweet on March 11, 2011 were 31.9 days (SE 0.096) for radioactive and 300.6 days (SE 0.181) for Sv. These keywords were still being used at the end of the study period. The mean attenuation period for radioactive was one month, and approximately one year for radiation and radiation units. The difference in mean duration

  8. Estimating the Duration of Public Concern After the Fukushima Dai-ichi Nuclear Power Station Accident From the Occurrence of Radiation Exposure-Related Terms on Twitter: A Retrospective Data Analysis.

    PubMed

    Nishimoto, Naoki; Ota, Mizuki; Yagahara, Ayako; Ogasawara, Katsuhiko

    2016-11-25

    After the Fukushima Dai-ichi Nuclear Power Station accident in Japan on March 11, 2011, a large number of comments, both positive and negative, were posted on social media. The objective of this study was to clarify the characteristics of the trend in the number of tweets posted on Twitter, and to estimate how long public concern regarding the accident continued. We surveyed the attenuation period of the first term occurrence related to radiation exposure as a surrogate endpoint for the duration of concern. We retrieved 18,891,284 tweets from Twitter data between March 11, 2011 and March 10, 2012, containing 143 variables in Japanese. We selected radiation, radioactive, Sievert (Sv), Becquerel (Bq), and gray (Gy) as keywords to estimate the attenuation period of public concern regarding radiation exposure. These data, formatted as comma-separated values, were transferred into a Statistical Analysis System (SAS) dataset for analysis, and survival analysis methodology was followed using the SAS LIFETEST procedure. This study was approved by the institutional review board of Hokkaido University and informed consent was waived. A Kaplan-Meier curve was used to show the rate of Twitter users posting a message after the accident that included one or more of the keywords. The term Sv occurred in tweets up to one year after the first tweet. Among the Twitter users studied, 75.32% (880,108/1,168,542) tweeted the word radioactive and 9.20% (107,522/1,168,542) tweeted the term Sv. The first reduction was observed within the first 7 days after March 11, 2011. The means and standard errors (SEs) of the duration from the first tweet on March 11, 2011 were 31.9 days (SE 0.096) for radioactive and 300.6 days (SE 0.181) for Sv. These keywords were still being used at the end of the study period. The mean attenuation period for radioactive was one month, and approximately one year for radiation and radiation units. The difference in mean duration between the keywords was attributed

  9. Space Station power system issues

    NASA Technical Reports Server (NTRS)

    Giudici, R. J.

    1985-01-01

    Issues governing the selection of power systems for long-term manned Space Stations intended solely for earth orbital missions are covered briefly, drawing on trade study results from both in-house and contracted studies that have been conducted over nearly two decades. An involvement, from the Program Development Office at MSFC, with current Space Station concepts began in late 1982 with the NASA-wide Systems Definition Working Group and continued throughout 1984 in support of various planning activities. The premise for this discussion is that, within the confines of the current Space Station concept, there is good reason to consider photovoltaic power systems to be a venerable technology option for both the initial 75 kW and 300 kW (or much greater) growth stations. The issue of large physical size required by photovoltaic power systems is presented considering mass, atmospheric drag, launch packaging and power transmission voltage as being possible practicality limitations. The validity of searching for a cross-over point necessitating the introduction of solar thermal or nuclear power system options as enabling technologies is considered with reference to programs ranging from the 4.8 kW Skylab to the 9.5 gW Space Power Satellite.

  10. NEW EMPLOYEES ON THE JOB - DONALD E HEGBERG OF THE NUCLEAR REACTOR DIVISION DISCUSSES NUCLEAR ROCKET

    NASA Technical Reports Server (NTRS)

    1963-01-01

    NEW EMPLOYEES ON THE JOB - DONALD E HEGBERG OF THE NUCLEAR REACTOR DIVISION DISCUSSES NUCLEAR ROCKET FUEL ELEMENT EXPERIMENT WITH CHARLES L YOUNGER - THE DISCUSSION IS PREPATORY TO CONDUCTING THE EXPERIMENT AT THE PLUM BROOK STATION REACTOR FACILITY

  11. International Space Station (ISS)

    NASA Image and Video Library

    2002-07-05

    Expedition Five flight engineer Peggy Whitson is shown installing the Solidification Using a Baffle in Sealed Ampoules (SUBSA) experiment in the Microgravity Science Glovebox (MSG) in the Destiny laboratory aboard the International Space Station (ISS). SUBSA examines the solidification of semiconductor crystals from a melted material. Semiconductor crystals are used for many products that touch our everyday lives. They are found in computer chips, integrated circuits, and a multitude of other electronic devices, such as sensors for medical imaging equipment and detectors of nuclear radiation. Materials scientists want to make better semiconductor crystals to be able to further reduce the size of high-tech devices. In the microgravity environment, convection and sedimentation are reduced, so fluids do not remove and deform. Thus, space laboratories provide an ideal environment of studying solidification from the melt. This investigation is expected to determine the mechanism causing fluid motion during production of semiconductors in space. It will provide insight into the role of the melt motion in production of semiconductor crystals, advancing our knowledge of the crystal growth process. This could lead to a reduction of defects in semiconductor crystals produced in space and on Earth.

  12. Single-Station Sigma for the Iranian Strong Motion Stations

    NASA Astrophysics Data System (ADS)

    Zafarani, H.; Soghrat, M. R.

    2017-07-01

    In development of ground motion prediction equations (GMPEs), the residuals are assumed to have a log-normal distribution with a zero mean and a standard deviation, designated as sigma. Sigma has significant effect on evaluation of seismic hazard for designing important infrastructures such as nuclear power plants and dams. Both aleatory and epistemic uncertainties are involved in the sigma parameter. However, ground-motion observations over long time periods are not available at specific sites and the GMPEs have been derived using observed data from multiple sites for a small number of well-recorded earthquakes. Therefore, sigma is dominantly related to the statistics of the spatial variability of ground motion instead of temporal variability at a single point (ergodic assumption). The main purpose of this study is to reduce the variability of the residuals so as to handle it as epistemic uncertainty. In this regard, it is tried to partially apply the non-ergodic assumption by removing repeatable site effects from total variability of six GMPEs driven from the local, Europe-Middle East and worldwide data. For this purpose, we used 1837 acceleration time histories from 374 shallow earthquakes with moment magnitudes ranging from M w 4.0 to 7.3 recorded at 370 stations with at least two recordings per station. According to estimated single-station sigma for the Iranian strong motion stations, the ratio of event-corrected single-station standard deviation (Φ ss) to within-event standard deviation (Φ) is about 0.75. In other words, removing the ergodic assumption on site response resulted in 25% reduction of the within-event standard deviation that reduced the total standard deviation by about 15%.

  13. Modeling Array Stations in SIG-VISA

    NASA Astrophysics Data System (ADS)

    Ding, N.; Moore, D.; Russell, S.

    2013-12-01

    We add support for array stations to SIG-VISA, a system for nuclear monitoring using probabilistic inference on seismic signals. Array stations comprise a large portion of the IMS network; they can provide increased sensitivity and more accurate directional information compared to single-component stations. Our existing model assumed that signals were independent at each station, which is false when lots of stations are close together, as in an array. The new model removes that assumption by jointly modeling signals across array elements. This is done by extending our existing Gaussian process (GP) regression models, also known as kriging, from a 3-dimensional single-component space of events to a 6-dimensional space of station-event pairs. For each array and each event attribute (including coda decay, coda height, amplitude transfer and travel time), we model the joint distribution across array elements using a Gaussian process that learns the correlation lengthscale across the array, thereby incorporating information of array stations into the probabilistic inference framework. To evaluate the effectiveness of our model, we perform ';probabilistic beamforming' on new events using our GP model, i.e., we compute the event azimuth having highest posterior probability under the model, conditioned on the signals at array elements. We compare the results from our probabilistic inference model to the beamforming currently performed by IMS station processing.

  14. Internal contamination in the space station

    NASA Technical Reports Server (NTRS)

    Poythress, C.

    1985-01-01

    Atmosphere trace contaminant control systems used in the past (Lunar Module and Skylab) and present (nuclear submarines and Shuttle) are discussed. Recommendations are made for the future Space Station contaminant control system. The prevention and control methods used are judicious material selection, detection, and specific removal equipment. Sources and effects of contamination relating to crew and equipment are also discussed.

  15. Role definition among public officials and emergency workers in a nuclear evacuation

    SciTech Connect

    Metz, W.C.

    1983-01-01

    How public officials and emergency workers will resolve conflict between their official duties and assigned tasks and their family and conscience responsibilities is discussed in the context of the Indian Point nuclear station, and the Shoreham nuclear station. (ACR)

  16. 47 CFR 73.877 - Station logs for LPFM stations.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 47 Telecommunication 4 2012-10-01 2012-10-01 false Station logs for LPFM stations. 73.877 Section... BROADCAST SERVICES Low Power FM Broadcast Stations (LPFM) § 73.877 Station logs for LPFM stations. The licensee of each LPFM station must maintain a station log. Each log entry must include the time and date...

  17. 47 CFR 73.877 - Station logs for LPFM stations.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 47 Telecommunication 4 2014-10-01 2014-10-01 false Station logs for LPFM stations. 73.877 Section... BROADCAST SERVICES Low Power FM Broadcast Stations (LPFM) § 73.877 Station logs for LPFM stations. The licensee of each LPFM station must maintain a station log. Each log entry must include the time and date...

  18. 47 CFR 73.877 - Station logs for LPFM stations.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 47 Telecommunication 4 2011-10-01 2011-10-01 false Station logs for LPFM stations. 73.877 Section... BROADCAST SERVICES Low Power FM Broadcast Stations (LPFM) § 73.877 Station logs for LPFM stations. The licensee of each LPFM station must maintain a station log. Each log entry must include the time and date...

  19. 47 CFR 73.877 - Station logs for LPFM stations.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 47 Telecommunication 4 2013-10-01 2013-10-01 false Station logs for LPFM stations. 73.877 Section... BROADCAST SERVICES Low Power FM Broadcast Stations (LPFM) § 73.877 Station logs for LPFM stations. The licensee of each LPFM station must maintain a station log. Each log entry must include the time and date...

  20. 47 CFR 73.877 - Station logs for LPFM stations.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Station logs for LPFM stations. 73.877 Section... BROADCAST SERVICES Low Power FM Broadcast Stations (LPFM) § 73.877 Station logs for LPFM stations. The licensee of each LPFM station must maintain a station log. Each log entry must include the time and date...

  1. Station Tour: Russian Segment

    NASA Image and Video Library

    Expedition 33 Commander Suni Williams concludes her tour of the International Space Station with a visit to the Russian segment, which includes Zarya, the first segment of the station launched in 1...

  2. Detailed source term estimation of the atmospheric release for the Fukushima Daiichi Nuclear Power Station accident by coupling simulations of atmospheric dispersion model with improved deposition scheme and oceanic dispersion model

    NASA Astrophysics Data System (ADS)

    Katata, G.; Chino, M.; Kobayashi, T.; Terada, H.; Ota, M.; Nagai, H.; Kajino, M.; Draxler, R.; Hort, M. C.; Malo, A.; Torii, T.; Sanada, Y.

    2014-06-01

    Temporal variations in the amount of radionuclides released into the atmosphere during the Fukushima Dai-ichi Nuclear Power Station (FNPS1) accident and their atmospheric and marine dispersion are essential to evaluate the environmental impacts and resultant radiological doses to the public. In this paper, we estimate a detailed time trend of atmospheric releases during the accident by combining environmental monitoring data with atmospheric model simulations from WSPEEDI-II (Worldwide version of System for Prediction of Environmental Emergency Dose Information), and simulations from the oceanic dispersion model SEA-GEARN-FDM, both developed by the authors. A sophisticated deposition scheme, which deals with dry and fogwater depositions, cloud condensation nuclei (CCN) activation and subsequent wet scavenging due to mixed-phase cloud microphysics (in-cloud scavenging) for radioactive iodine gas (I2 and CH3I) and other particles (CsI, Cs, and Te), was incorporated into WSPEEDI-II to improve the surface deposition calculations. The fallout to the ocean surface calculated by WSPEEDI-II was used as input data for the SEA-GEARN-FDM calculations. Reverse and inverse source-term estimation methods based on coupling the simulations from both models was adopted using air dose rates and concentrations, and sea surface concentrations. The results revealed that the major releases of radionuclides due to FNPS1 accident occurred in the following periods during March 2011: the afternoon of 12 March due to the wet venting and hydrogen explosion at Unit 1, the morning of 13 March after the venting event at Unit 3, midnight of 14 March when the SRV (Safely Relief Valve) at Unit 2 was opened three times, the morning and night of 15 March, and the morning of 16 March. According to the simulation results, the highest radioactive contamination areas around FNPS1 were created from 15 to 16 March by complicated interactions among rainfall, plume movements, and the temporal variation of

  3. Radio spectrum surveillance station

    NASA Technical Reports Server (NTRS)

    Hersey, D. R.

    1979-01-01

    The paper presents a general and functional description of a low-cost surveillance station designed as the first phase of NASA's program to develop a radio spectrum surveillance capability for deep space stations for identifying radio frequency interference sources. The station described has identified several particular interferences and is yielding spectral signature data which, after cataloging, will serve as a library for rapid identification of frequently observed interference. Findings from the use of the station are discussed.

  4. 77 FR 33004 - Exelon Generation Company, LLC; Clinton Power Station, Unit 1

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-04

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Generation Company, LLC; Clinton Power Station, Unit 1 AGENCY: Nuclear Regulatory... request for partial site release to Facility Operating License No. NPF-62 issued to Exelon...

  5. International Space Station (ISS)

    NASA Image and Video Library

    1997-07-20

    Photograph shows the International Space Station Laboratory Module under fabrication at Marshall Space Flight Center (MSFC), Building 4708 West High Bay. Although management of the U.S. elements for the Station were consolidated in 1994, module and node development continued at MSFC by Boeing Company, the prime contractor for the Space Station.

  6. 78 FR 782 - Energy Northwest; Columbia Generating Station; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-04

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Energy Northwest; Columbia Generating Station; Exemption 1.0 Background Energy Northwest (the licensee) is the holder of Renewed Facility Operating License No. NPF-21, which authorizes operation of the Columbia Generating Station. The...

  7. Operate a Nuclear Power Plant.

    ERIC Educational Resources Information Center

    Frimpter, Bonnie J.; And Others

    1983-01-01

    Describes classroom use of a computer program originally published in Creative Computing magazine. "The Nuclear Power Plant" (runs on Apple II with 48K memory) simulates the operating of a nuclear generating station, requiring students to make decisions as they assume the task of managing the plant. (JN)

  8. Operate a Nuclear Power Plant.

    ERIC Educational Resources Information Center

    Frimpter, Bonnie J.; And Others

    1983-01-01

    Describes classroom use of a computer program originally published in Creative Computing magazine. "The Nuclear Power Plant" (runs on Apple II with 48K memory) simulates the operating of a nuclear generating station, requiring students to make decisions as they assume the task of managing the plant. (JN)

  9. Space Station Live: Station Communications Upgrade

    NASA Image and Video Library

    NASA Public Affairs Officer Nicole Cloutier-Lemasters recently spoke with Penny Roberts, one of the leads for the International Space Station Avionics and Software group, about the upgrade of the K...

  10. Space Station attached payloads

    NASA Technical Reports Server (NTRS)

    Clark, Lenwood G.

    1990-01-01

    The Space Station Freedom is being designed and developed with user requirements being used to shape the configuration. Plans include accommodation provisions for a wide variety of attached payloads including the Earth sciences research activities which are the focus of this conference. The station program is even beginning some preliminary payload manifesting which involves planning for accommodation of payload during the station's assembly flights. Potential payload organizations should be aware of the station's plans for payload accommodations so as to guide their own payload activities for future space station use.

  11. Neuroradiology viewing station

    NASA Astrophysics Data System (ADS)

    Lou, Shyhliang A.; Lufkin, Robert B.; Valentino, Daniel J.; Huang, H. K.; Hanafee, William; Jabour, Bradly; Bentsen, John R.; Duckwiler, Gary R.; Dion, Jacques E.

    1990-07-01

    A distributed CT/MR digital viewing station for the neuroradiology section has been developed and is being evaluated in our department. The major components of the station consist of a SUN host computer, a PIXAR II image processor, and four 1K x 1K progressive video monitors. The software modules operating in the station include an image acquisition process, a local database process, and an user image display and processing process. Functions provided by the station are described. Preliminary results obtained from clinical evaluation are reported. Future plans to refine the station are presented.

  12. Optimization of station battery replacement

    NASA Astrophysics Data System (ADS)

    Jancauskas, J. R.; Shook, D. A.

    1994-08-01

    During a loss of ac power at a nuclear generating station (including diesel generators), batteries provide the source of power which is required to operate safety-related components. Because traditional lead-acid batteries have a qualified life of 20 years, the batteries must be replaced a minimum of once during a station's lifetime, twice if license extension is pursued, and more often depending on actual in-service dates and the results of surveillance tests. Replacement of batteries often occurs prior to 20 years as a result of systems changes caused by factors such as Station Blackout Regulations, control system upgrades, incremental load growth, and changes in the operating times of existing equipment. Many of these replacement decisions are based on the predictive capabilities of manual design basis calculations. The inherent conservatism of manual calculations may result in battery replacements occurring before actually required. Computerized analysis of batteries can aid in optimizing the timing of replacements as well as in interpreting service test data. Computerized analysis also provides large benefits in maintaining the as-configured load profile and corresponding design margins, while also providing the capability to quickly analyze proposed modifications and respond to internal and external audits.

  13. Timber Mountain Precipitation Monitoring Station

    SciTech Connect

    Lyles, Brad; McCurdy, Greg; Chapman, Jenny; Miller, Julianne

    2012-01-01

    A precipitation monitoring station was placed on the west flank of Timber Mountain during the year 2010. It is located in an isolated highland area near the western border of the Nevada National Security Site (NNSS), south of Pahute Mesa. The cost of the equipment, permitting, and installation was provided by the Environmental Monitoring Systems Initiative (EMSI) project. Data collection, analysis, and maintenance of the station during fiscal year 2011 was funded by the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office Environmental Restoration, Soils Activity. The station is located near the western headwaters of Forty Mile Wash on the Nevada Test and Training Range (NTTR). Overland flows from precipitation events that occur in the Timber Mountain high elevation area cross several of the contaminated Soils project CAU (Corrective Action Unit) sites located in the Forty Mile Wash watershed. Rain-on-snow events in the early winter and spring around Timber Mountain have contributed to several significant flow events in Forty Mile Wash. The data from the new precipitation gauge at Timber Mountain will provide important information for determining runoff response to precipitation events in this area of the NNSS. Timber Mountain is also a groundwater recharge area, and estimation of recharge from precipitation was important for the EMSI project in determining groundwater flowpaths and designing effective groundwater monitoring for Yucca Mountain. Recharge estimation additionally provides benefit to the Underground Test Area Sub-project analysis of groundwater flow direction and velocity from nuclear test areas on Pahute Mesa. Additionally, this site provides data that has been used during wild fire events and provided a singular monitoring location of the extreme precipitation events during December 2010 (see data section for more details). This letter report provides a summary of the site location, equipment, and data collected in

  14. Automating existing stations

    SciTech Connect

    Little, J.E.

    1986-09-01

    The task was to automate 20 major compressor stations along ANR Pipeline Co.'s Southeastern and Southwestern pipelines in as many months. Meeting this schedule required standardized hardware and software design. Working with Bristol Babcock Co., ANR came up with an off-the-shelf station automation package suitable for a variety of compressor stations. The project involved 148 engines with 488,880-hp in the 20 stations. ANR Pipeline developed software for these engines and compressors, including horsepower prediction and efficiency. The system places processors ''intelligence'' at each station and engine to monitor and control operations. The station processor receives commands from the company's gas dispatch center at Detroit and informs dispatchers of alarms, conditions, and decision it makes. The automation system is controlled by the Detroit center through a central communications network. Operating orders from the center are sent to the station processor, which obeys orders using the most efficient means of operation at the station's disposal. In a malfunction, a control and communications backup system takes over. Commands and information are directly transmitted between the center and the individual compressor stations. Stations receive their orders based on throughput, with suction and discharge pressure overrides. Additionally, a discharge temperature override protects pipeline coatings.

  15. Space station, 1959 to . .

    NASA Astrophysics Data System (ADS)

    Butler, G. V.

    1981-04-01

    Early space station designs are considered, taking into account Herman Oberth's first space station, the London Daily Mail Study, the first major space station design developed during the moon mission, and the Manned Orbiting Laboratory Program of DOD. Attention is given to Skylab, new space station studies, the Shuttle and Spacelab, communication satellites, solar power satellites, a 30 meter diameter radiometer for geological measurements and agricultural assessments, the mining of the moons, and questions of international cooperation. It is thought to be very probable that there will be very large space stations at some time in the future. However, for the more immediate future a step-by-step development that will start with Spacelab stations of 3-4 men is envisaged.

  16. Space Station Freedom Utilization Conference

    NASA Technical Reports Server (NTRS)

    1992-01-01

    The topics addressed in Space Station Freedom Utilization Conference are: (1) space station freedom overview and research capabilities; (2) space station freedom research plans and opportunities; (3) life sciences research on space station freedom; (4) technology research on space station freedom; (5) microgravity research and biotechnology on space station freedom; and (6) closing plenary.

  17. Space station power system

    NASA Technical Reports Server (NTRS)

    Baraona, Cosmo R.

    1987-01-01

    The major requirements and guidelines that affect the space station configuration and power system are explained. The evolution of the space station power system from the NASA program development-feasibility phase through the current preliminary design phase is described. Several early station concepts are described and linked to the present concept. Trade study selections of photovoltaic system technologies are described in detail. A summary of present solar dynamic and power management and distribution systems is also given.

  18. Technology for space station

    NASA Astrophysics Data System (ADS)

    Colladay, R. S.; Carlisle, R. F.

    1984-10-01

    Some of the most significant advances made in the space station discipline technology program are examined. Technological tasks and advances in the areas of systems/operations, environmental control and life support systems, data management, power, thermal considerations, attitude control and stabilization, auxiliary propulsion, human capabilities, communications, and structures, materials, and mechanisms are discussed. An overview of NASA technology planning to support the initial space station and the evolutionary growth of the space station is given.

  19. Space Station operations

    NASA Technical Reports Server (NTRS)

    Gray, R. H.

    1985-01-01

    An evaluation of the success of the Space Station will be based on the service provided to the customers by the Station crew, the productivity of the crew, and the costs of operation. Attention is given to details regarding Space Station operations, a summary of operational philosophies and requirements, logistics and resupply operations, prelaunch processing and launch operations, on-orbit operations, aspects of maintainability and maintenance, habitability, and questions of medical care. A logistics module concept is considered along with a logistics module processing timeline, a habitability module concept, and a Space Station rescue mission.

  20. Control of space stations

    NASA Technical Reports Server (NTRS)

    Lee, K. Y.

    1983-01-01

    A study is made to develop controllers for the NASA-JSC Triangular Space Station and evaluate their performances to make recommendations for structural design and/or control alternatives. The control system design assumes the rigid body of the Space Station and developes the lumped parameter control system by using the Inverse Optimal Control Theory. In order to evaluate the performance of the control system, a Parameter Estimation algorithm is being developed which will be used in modeling an equivalent but simpler Space Station model. Finally, a scaled version of the Space Station is being built for the purpose of physical experiments to evaluate the control system performance.

  1. Space Station fluid resupply

    NASA Astrophysics Data System (ADS)

    Winters, Al

    Viewgraphs on space station fluid resupply are presented. Space Station Freedom is resupplied with supercritical O2 and N2 for the ECLSS and USL on a 180 day resupply cycle. Resupply fluids are stored in the subcarriers on station between resupply cycles and transferred to the users as required. ECLSS contingency fluids (O2 and N2) are supplied and stored on station in a gaseous state. Efficiency and flexibility are major design considerations. Subcarrier approach allows multiple manifest combinations. Growth is achieved by adding modular subcarriers.

  2. Station Crew Celebrates Christmas

    NASA Image and Video Library

    Aboard the orbiting International Space Station, Expedition 34 Commander Kevin Ford, Russian Flight Engineers Oleg Novitskiy, Evgeny Tarelkin and Roman Romanenko, NASA Flight Engineer Tom Marshburn...

  3. Installing a Hydroacoustic Station at the Crozet Islands

    DTIC Science & Technology

    2012-09-01

    Nuclear-Test-Ban Treaty Organization2 Sponsored by the United States State Department Award No. NDF – 288 ABSTRACT The Comprehensive...Nuclear-Test-Ban Treaty (CTBT) International Monitoring System (IMS) includes a network of eleven hydroacoustic stations for monitoring the Earth’s oceans...NNSA). 14. ABSTRACT The Comprehensive Nuclear-Test-Ban Treaty (CTBT) International Monitoring System (IMS) includes a network of eleven hydroacoustic

  4. 78 FR 50454 - Entergy Operations, Inc., River Bend Station, Unit 1

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-19

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Operations, Inc., River Bend Station, Unit 1 AGENCY: Nuclear Regulatory Commission. ACTION...-47, issued to Entergy Operations, Inc. (the licensee), for operation of the River Bend Station, Unit...

  5. Reevaluation of air surveillance station siting

    SciTech Connect

    Abbott, K.; Jannik, T.

    2016-07-06

    DOE Technical Standard HDBK-1216-2015 (DOE 2015) recommends evaluating air-monitoring station placement using the analytical method developed by Waite. The technique utilizes wind rose and population distribution data in order to determine a weighting factor for each directional sector surrounding a nuclear facility. Based on the available resources (number of stations) and a scaling factor, this weighting factor is used to determine the number of stations recommended to be placed in each sector considered. An assessment utilizing this method was performed in 2003 to evaluate the effectiveness of the existing SRS air-monitoring program. The resulting recommended distribution of air-monitoring stations was then compared to that of the existing site perimeter surveillance program. The assessment demonstrated that the distribution of air-monitoring stations at the time generally agreed with the results obtained using the Waite method; however, at the time new stations were established in Barnwell and in Williston in order to meet requirements of DOE guidance document EH-0173T.

  6. "Inventive" Learning Stations

    ERIC Educational Resources Information Center

    Jarrett, Olga

    2010-01-01

    Learning stations can be used for myriad purposes--to teach concepts, integrate subject matter, build interest, and allow for inquiry--the possibilities are limited only by the imagination of the teacher and the supplies available. In this article, the author shares suggestions and a checklist for setting up successful learning stations. In…

  7. International Space Station (ISS)

    NASA Image and Video Library

    2006-07-06

    Though very close to the International Space Station, the majority of Discovery's underside is visible in this frame. The image was captured by one of the Expedition 13 crew members onboard the International Space Station (ISS) during the STS-121 Rotating Pitch Maneuver (RPM) survey prior to docking of the two spacecraft.

  8. Summit Station Skiway Review

    DTIC Science & Technology

    2013-03-01

    delivery of personnel and materials, is by skied airplanes (currently Twin Otters and LC-130s) or by annual traverse. To support aircraft, the station...Station during the first sea - son (2009) of skiway construction at Pegasus Airfield (Haehnel et al. 2013) but consistently lower than densities of

  9. International Space Station (ISS)

    NASA Image and Video Library

    2007-08-13

    Back dropped by the blue and white Earth is a Materials International Space Station Experiment (MISSE) on the exterior of the Station. The photograph was taken during the second bout of STS-118 Extra Vehicular Activity (EVA). MISSE collects information on how different materials weather in the environment of space.

  10. International Space Station (ISS)

    NASA Image and Video Library

    2000-12-01

    This image of the International Space Station in orbit was taken from the Space Shuttle Endeavour prior to docking. Most of the Station's components are clearly visible in this photograph. They are the Node 1 or Unity Module docked with the Functional Cargo Block or Zarya (top) that is linked to the Zvezda Service Module. The Soyuz spacecraft is at the bottom.

  11. "Inventive" Learning Stations

    ERIC Educational Resources Information Center

    Jarrett, Olga

    2010-01-01

    Learning stations can be used for myriad purposes--to teach concepts, integrate subject matter, build interest, and allow for inquiry--the possibilities are limited only by the imagination of the teacher and the supplies available. In this article, the author shares suggestions and a checklist for setting up successful learning stations. In…

  12. Space station dynamics

    NASA Technical Reports Server (NTRS)

    Berka, Reg

    1990-01-01

    Structural dynamic characteristics and responses of the Space Station due to the natural and induced environment are discussed. Problems that are peculiar to the Space Station are also discussed. These factors lead to an overall acceleration environment that users may expect. This acceleration environment can be considered as a loading, as well as a disturbance environment.

  13. Nuclear power and nuclear weapons

    SciTech Connect

    Vaughen, V.C.A.

    1983-01-01

    The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described.

  14. [STEM on Station Education

    NASA Technical Reports Server (NTRS)

    Lundebjerg, Kristen

    2016-01-01

    The STEM on Station team is part of Education which is part of the External Relations organization (ERO). ERO has traditional goals based around BHAG (Big Hairy Audacious Goal). The BHAG model is simplified to a saying: Everything we do stimulates actions by others to advance human space exploration. The STEM on Station education initiate is a project focused on bringing off the earth research and learning into classrooms. Educational resources such as lesson plans, activities to connect with the space station and STEM related contests are available and hosted by the STEM on Station team along with their partners such as Texas Instruments. These educational activities engage teachers and students in the current happenings aboard the international space station, inspiring the next generation of space explorers.

  15. Technocrats and nuclear politics

    SciTech Connect

    Massey, A.

    1988-01-01

    This book arrives in an age of growing unease and dissatisfaction with the reassurances, by the nuclear power industry, of the safety of its power stations. The book's central purpose is to examine the motivations and varied perceptions which have laid the foundation for Britain's contemporary civil nuclear industry. The author pays particular attention to the role and influence of technical experts in the shaping of decisions within their own industry and the implementation of those decisions at the government level. The author shows how, in the British model, ministers and civil servants tend to serve as policy arbiters who set the parameters within which the dynamics of special interest groups provide policy options. This book combines several current themes; the politics of nuclear energy; the role of professional experts; and the impact of and drive for privitization. It examines the process of modern British policy-making and nuclear power politics, and holds implications that reach far beyond Britain.

  16. Nuclear rights - nuclear wrongs

    SciTech Connect

    Paul, E.F.; Miller, F.D.; Paul, J.; Ahrens, J.

    1986-01-01

    This book contains 11 selections. The titles are: Three Ways to Kill Innocent Bystanders: Some Conundrums Concerning the Morality of War; The International Defense of Liberty; Two Concepts of Deterrence; Nuclear Deterrence and Arms Control; Ethical Issues for the 1980s; The Moral Status of Nuclear Deterrent Threats; Optimal Deterrence; Morality and Paradoxical Deterrence; Immoral Risks: A Deontological Critique of Nuclear Deterrence; No War Without Dictatorship, No Peace Without Democracy: Foreign Policy as Domestic Politics; Marxism-Leninism and its Strategic Implications for the United States; Tocqueveille War.

  17. The remote security station (RSS)

    SciTech Connect

    Pletta, J.B. )

    1991-01-01

    This paper reports that, as an outgrowth of research into physical security systems, Sandia is investigating robotic technologies for improving physical security performance and flexibility. Robotic systems have the potential to allow more effective utilization of security personnel, especially in scenarios where they might be exposed to harm. They also can supplement fixed site installations where sensors have failed or where transient assets are present. The Remote Security Station (RSS) program for the defense Nuclear Agency is developing a proof-of-principle robotic system which will be used to evaluate the role, and associated cost, of robotic technologies in exterior physical security systems. The RSS consists of three primary elements: a fixed but quickly moveable tripod with intrusion detection sensors and assessment camera; a mobile robotic platform with a functionally identical security module; and a control console which allows an operator to perform security functions and teleoperate the mobile platform.

  18. Spallation neutron source target station issues

    SciTech Connect

    Gabriel, T.A.; Barnes, J.N.; Charlton, L.A.

    1996-10-01

    In many areas of physics, materials and nuclear engineering, it is extremely valuable to have a very intense source of neutrons so that the structure and function of materials can be studied. One facility proposed for this purpose is the National Spallation Neutron Source (NSNS). This facility will consist of two parts: (1) a high-energy ({approximately}1 GeV) and high powered ({approximately} 1 MW) proton accelerator, and (2) a target station which converts the protons to low-energy ({le} 2 eV) neutrons and delivers them to the neutron scattering instruments. This paper deals with the second part, i.e., the design and development of the NSNS target station and the scientifically challenging issues. Many scientific and technical disciplines are required to produce a successful target station. These include engineering, remote handling, neutronics, materials, thermal hydraulics, and instrumentation. Some of these areas will be discussed.

  19. Comparative analyses of space-to-space central power stations

    NASA Technical Reports Server (NTRS)

    Holloway, P. F.; Garrett, L. B.

    1981-01-01

    The technological and economical impact of a large central power station in Earth orbit on the performance and cost of future spacecraft and their orbital transfer systems are examined. It is shown that beaming power to remote users cannot be cost effective if the central power station uses the same power generation system that is readily available for provision of onboard power and microwave transmission and reception of power through space for use in space is not cost competitive with onboard power or propulsion systems. Laser and receivers are required to make central power stations feasible. Remote power transmission for propulsion of orbital transfer vehicles promises major cost benefits. Direct nuclear pumped or solar pumped laser power station concepts are attractive with laser thermal and laser electric propulsion systems. These power stations are also competitive, on a mass and cost basis, with a photovoltaic power station.

  20. Station set residual : event classification using historical distribution of observing stations.

    SciTech Connect

    Draelos, Timothy John; Procopio, Michael J.; Lewis, Jennifer E.; Young, Christopher John

    2010-04-01

    Analysts working at the International Data Centre in support of treaty monitoring through the Comprehensive Nuclear-Test-Ban Treaty Organization spend a significant amount of time reviewing hypothesized seismic events produced by an automatic processing system. When reviewing these events to determine their legitimacy, analysts take a variety of approaches that rely heavily on training and past experience. One method used by analysts to gauge the validity of an event involves examining the set of stations involved in the detection of an event. In particular, leveraging past experience, an analyst can say that an event located in a certain part of the world is expected to be detected by Stations A, B, and C. Implicit in this statement is that such an event would usually not be detected by Stations X, Y, or Z. For some well understood parts of the world, the absence of one or more 'expected' stations - or the presence of one or more 'unexpected' stations - is correlated with a hypothesized event's legitimacy and to its survival to the event bulletin. The primary objective of this research is to formalize and quantify the difference between the observed set of stations detecting some hypothesized event, versus the expected set of stations historically associated with detecting similar nearby events close in magnitude. This Station Set Residual can be quantified in many ways, some of which are correlated with the analysts determination of whether or not the event is valid. We propose that this Station Set Residual score can be used to screen out certain classes of 'false' events produced by automatic processing with a high degree of confidence, reducing the analyst burden. Moreover, we propose that the visualization of the historically expected distribution of detecting stations can be immediately useful as an analyst aid during their review process.

  1. International Space Station (ISS)

    NASA Image and Video Library

    2002-04-16

    Docked to the International Space Station (ISS), a Soyuz vehicle (foreground) and the Space Shuttle Atlantis were photographed by a crew member in the Pirs docking compartment on the orbital outpost. Atlantis launched on April 8, 2002, carrying the the STS-110 mission which prepared the ISS for future space walks by installing and outfitting the 43-foot-long Starboard side S0 (S-zero) truss and preparing the first railroad in space, the Mobile Transporter. The 27,000 pound S0 truss was the first of 9 segments that will make up the Station's external framework that will eventually stretch 356 feet (109 meters), or approximately the length of a football field. This central truss segment also includes a flatcar called the Mobile Transporter and rails that will become the first "space railroad," which will allow the Station's robotic arm to travel up and down the finished truss for future assembly and maintenance. The completed truss structure will hold solar arrays and radiators to provide power and cooling for additional international research laboratories from Japan and Europe that will be attached to the Station. STS-110 Extravehicular Activity (EVA) marked the first use of the Station's robotic arm to maneuver space walkers around the Station and was the first time all of a shuttle crew's scapulas were based out of the Station's Quest Airlock.

  2. International Space Station (ISS)

    NASA Image and Video Library

    2001-03-13

    Astronaut Paul W. Richards, STS-102 mission specialist, works in the cargo bay of the Space Shuttle Discovery during the second of two scheduled space walks. Richards, along with astronaut Andy Thomas, spent 6.5 hours outside the International Space Station (ISS), continuing work to outfit the station and prepare for delivery of its robotic arm. STS-102 delivered the first Multipurpose Logistics Modules (MPLM) named Leonardo, which was filled with equipment and supplies to outfit the U.S. Destiny Laboratory Module. The Leonardo MPLM is the first of three such pressurized modules that will serve as the ISS' moving vans, carrying laboratory racks filled with equipment, experiments, and supplies to and from the Station aboard the Space Shuttle. The cylindrical module is approximately 21-feet long and 15- feet in diameter, weighing almost 4.5 tons. It can carry up to 10 tons of cargo in 16 standard Space Station equipment racks. Of the 16 racks the module can carry, 5 can be furnished with power, data, and fluid to support refrigerators or freezers. In order to function as an attached station module as well as a cargo transport, the logistics module also includes components that provide life support, fire detection and suppression, electrical distribution, and computer functions. NASA's 103rd overall mission and the 8th Space Station Assembly Flight, STS-102 mission also served as a crew rotation flight. It delivered the Expedition Two crew to the Station and returned the Expedition One crew back to Earth.

  3. White Paper on Nuclear Astrophysics and Low Energy Nuclear Physics - Part 1. Nuclear Astrophysics

    SciTech Connect

    Arcones, Almudena; Escher, Jutta E.; Others, M.

    2016-04-04

    This white paper informs the nuclear astrophysics community and funding agencies about the scientific directions and priorities of the field and provides input from this community for the 2015 Nuclear Science Long Range Plan. It summarizes the outcome of the nuclear astrophysics town meeting that was held on August 21 - 23, 2014 in College Station at the campus of Texas A&M University in preparation of the NSAC Nuclear Science Long Range Plan. It also reflects the outcome of an earlier town meeting of the nuclear astrophysics community organized by the Joint Institute for Nuclear Astrophysics (JINA) on October 9 - 10, 2012 Detroit, Michigan, with the purpose of developing a vision for nuclear astrophysics in light of the recent NRC decadal surveys in nuclear physics (NP2010) and astronomy (ASTRO2010). The white paper is furthermore informed by the town meeting of the Association of Research at University Nuclear Accelerators (ARUNA) that took place at the University of Notre Dame on June 12 - 13, 2014. In summary we find that nuclear astrophysics is a modern and vibrant field addressing fundamental science questions at the intersection of nuclear physics and astrophysics. These questions relate to the origin of the elements, the nuclear engines that drive life and death of stars, and the properties of dense matter. A broad range of nuclear accelerator facilities, astronomical observatories, theory efforts, and computational capabilities are needed. With the developments outlined in this white paper, answers to long-standing key questions are well within reach in the coming decade.

  4. Fast neutron nuclear reactor

    SciTech Connect

    Cabrillat, M. Th.; Lions, N.

    1985-01-08

    The invention relates to a fast neutron nuclear reactor of the integrated type comprising a cylindrical inner vessel. The inner vessel comprises two concentric ferrules and the connection between the hot collector defined within this vessel and the inlet port of the exchangers is brought about by a hot structure forming a heat baffle and supported by the inner ferrule and by a cold structure surrounding the hot structure, supported by the outer ferrule and sealingly connected to the exchanger. Application to the generation of electric power in nuclear power stations.

  5. Overview of guideway, Pratt Street Station, Bridge Street Station and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    Overview of guideway, Pratt Street Station, Bridge Street Station and train yard, looking east. Dyre street in foreground. - Frankford Elevated, 52100-5400 Frankford Avenue (guideway & stations), Philadelphia, Philadelphia County, PA

  6. 4. EASTBOUND VIEW. NORTH TRACK WAITING STATION ON LEFT. STATION ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    4. EASTBOUND VIEW. NORTH TRACK WAITING STATION ON LEFT. STATION ON RIGHT. NOTE TUNNEL IN BACKGROUND. - Baltimore & Ohio Railroad, Harpers Ferry Station, Potomac Street, Harpers Ferry, Jefferson County, WV

  7. Station Climatic Summaries, Asia

    DTIC Science & Technology

    1989-07-01

    MANDALAY 480420 8809 (OCDS) .................................................. .022 MYITKYINA 480080 8809 (OCDS...0 1 0 0 0 2 0 5 2 1 06-20 LST 8 3 # 1 # 1 1 2 4 10 11 13 4 ECR-KRW-7a OZi OPERATIONAL CLIMATIC DATA SUMMARY STATION: MANDALAY , BM STATION #: 480420...18-20 LST # 0 # 0 # 1 0 2 1 # 1 1 1 06-20 LST 1 2 2 1 1 1 2 1 1 1 2 5 1 ECR-KRW-6 oZ3 OPERATIONAL CLIMATIC DATA SUPPLEMENT STATION: MANDALAY , BM

  8. International Space Station (ISS)

    NASA Image and Video Library

    1997-06-01

    Artist's digital concept of the International Space Station (ISS), a gateway to permanent human presence in space, after all assembly is completed in Year 2003. The Station will be powered by almost an acre of solar panels and have a mass of almost one million pounds. Station modules are being provided by the United States, Russia, Japan, and Europe. Canada is providing a mechanical arm and Canada Hand. Sixteen countries are cooperating to provide a multidisciplinary laboratory, technology test bed, and observatory that will provide an unprecedented undertaking in scientific, technological, and international experimentation.

  9. Madrid space station

    NASA Technical Reports Server (NTRS)

    Fahnestock, R. J.; Renzetti, N. A.

    1975-01-01

    The Madrid space station, operated under bilateral agreements between the governments of the United States and Spain, is described in both Spanish and English. The space station utilizes two tracking and data acquisition networks: the Deep Space Network (DSN) of the National Aeronautics and Space Administration and the Spaceflight Tracking and Data Network (STDN) operated under the direction of the Goddard Space Flight Center. The station, which is staffed by Spanish employees, comprises four facilities: Robledo 1, Cebreros, and Fresnedillas-Navalagamella, all with 26-meter-diameter antennas, and Robledo 2, with a 64-meter antenna.

  10. The space station

    NASA Technical Reports Server (NTRS)

    Munoz, Abraham

    1988-01-01

    Conceived since the beginning of time, living in space is no longer a dream but rather a very near reality. The concept of a Space Station is not a new one, but a redefined one. Many investigations on the kinds of experiments and work assignments the Space Station will need to accommodate have been completed, but NASA specialists are constantly talking with potential users of the Station to learn more about the work they, the users, want to do in space. Present configurations are examined along with possible new ones.

  11. Space Station Induced Monitoring

    NASA Technical Reports Server (NTRS)

    Spann, James F. (Editor); Torr, Marsha R. (Editor)

    1988-01-01

    This report contains the results of a conference convened May 10-11, 1988, to review plans for monitoring the Space Station induced environment, to recommend primary components of an induced environment monitoring package, and to make recommendations pertaining to suggested modifications of the Space Station External Contamination Control Requirements Document JSC 30426. The contents of this report are divided as Follows: Monitoring Induced Environment - Space Station Work Packages Requirements, Neutral Environment, Photon Emission Environment, Particulate Environment, Surface Deposition/Contamination; and Contamination Control Requirements.

  12. Space station operations management

    NASA Technical Reports Server (NTRS)

    Cannon, Kathleen V.

    1989-01-01

    Space Station Freedom operations management concepts must be responsive to the unique challenges presented by the permanently manned international laboratory. Space Station Freedom will be assembled over a three year period where the operational environment will change as significant capability plateaus are reached. First Element Launch, Man-Tended Capability, and Permanent Manned Capability, represent milestones in operational capability that is increasing toward mature operations capability. Operations management concepts are being developed to accomodate the varying operational capabilities during assembly, as well as the mature operational environment. This paper describes operations management concepts designed to accomodate the uniqueness of Space Station Freedoom, utilizing tools and processes that seek to control operations costs.

  13. JPRS Report, Nuclear Developments

    DTIC Science & Technology

    2016-03-24

    nuclear power plants with a production capacity of 1 million kilowatts each plus 65 thermal power stations by the year 2031 to meet energy demands...because of the far lower pollution problem than other energy sources. JPRS-TND-89-013 28 June 1989 EAST EUROPE CZECHOSLOVAKIA Austria Demands Halt...balance of payments, and has helped them eliminate atmospheric pollution . The authors also contend that, in pursuing the reduction of sulfur dioxide

  14. JPRS Report Nuclear Developments

    DTIC Science & Technology

    2007-11-02

    BANGLADESH Atomic Energy Commission Chairman Sacked [Delhi Domestic Service 9 Nov] 5 EGYPT West Germans Build Small Nuclear Power Stations...Brazil has geologial uranium reserves calculated at 301,400 metric tons, and the world market allows annual business involving up to $65 million, "a...country. JPRS-TND-88-020 28 November 1988 NEAR EAST & SOUTH ASIA BANGLADESH Atomic Energy Commission Chairman Sacked BK0911075888 Delhi Domestic

  15. Enabler operator station

    NASA Technical Reports Server (NTRS)

    Bailey, Andrea; Kietzman, John; King, Shirlyn; Stover, Rae; Wegner, Torsten

    1992-01-01

    The objective of this project was to design an onboard operator station for the conceptual Lunar Work Vehicle (LWV). The LWV would be used in the colonization of a lunar outpost. The details that follow, however, are for an Earth-bound model. The operator station is designed to be dimensionally correct for an astronaut wearing the current space shuttle EVA suit (which include life support). The proposed operator station will support and restrain an astronaut as well as to provide protection from the hazards of vehicle rollover. The threat of suit puncture is eliminated by rounding all corners and edges. A step-plate, located at the front of the vehicle, provides excellent ease of entry and exit. The operator station weight requirements are met by making efficient use of rigid members, semi-rigid members, and woven fabrics.

  16. Space Station Software Recommendations

    NASA Technical Reports Server (NTRS)

    Voigt, S. (Editor)

    1985-01-01

    Four panels of invited experts and NASA representatives focused on the following topics: software management, software development environment, languages, and software standards. Each panel deliberated in private, held two open sessions with audience participation, and developed recommendations for the NASA Space Station Program. The major thrusts of the recommendations were as follows: (1) The software management plan should establish policies, responsibilities, and decision points for software acquisition; (2) NASA should furnish a uniform modular software support environment and require its use for all space station software acquired (or developed); (3) The language Ada should be selected for space station software, and NASA should begin to address issues related to the effective use of Ada; and (4) The space station software standards should be selected (based upon existing standards where possible), and an organization should be identified to promulgate and enforce them. These and related recommendations are described in detail in the conference proceedings.

  17. Space station data flow

    NASA Technical Reports Server (NTRS)

    1972-01-01

    The results of the space station data flow study are reported. Conceived is a low cost interactive data dissemination system for space station experiment data that includes facility and personnel requirements and locations, phasing requirements and implementation costs. Each of the experiments identified by the operating schedule is analyzed and the support characteristics identified in order to determine data characteristics. Qualitative and quantitative comparison of candidate concepts resulted in a proposed data system configuration baseline concept that includes a data center which combines the responsibility of reprocessing, archiving, and user services according to the various agencies and their responsibility assignments. The primary source of data is the space station complex which provides through the Tracking Data Relay Satellite System (TDRS) and by space shuttle delivery data from experiments in free flying modules and orbiting shuttles as well as from the experiments in the modular space station itself.

  18. The Space Station Chronicles

    NASA Image and Video Library

    As early as the nineteenth century, writers and artists and scientists around the world began to publish their visions of a crewed outpost in space. Learn about the history of space stations, from ...

  19. Station Assembly Animation

    NASA Image and Video Library

    This animation depicts the assembly of the International Space Station since Nov. 20, 1998, with the delivery of the Zarya module, through May 16, 2011, with the delivery of the EXPRESS Logistics C...

  20. Space station propulsion technology

    NASA Technical Reports Server (NTRS)

    Briley, G. L.

    1986-01-01

    The progress on the Space Station Propulsion Technology Program is described. The objectives are to provide a demonstration of hydrogen/oxygen propulsion technology readiness for the Initial Operating Capability (IOC) space station application, specifically gaseous hydrogen/oxygen and warm hydrogen thruster concepts, and to establish a means for evolving from the IOC space station propulsion to that required to support and interface with advanced station functions. The evaluation of concepts was completed. The accumulator module of the test bed was completed and, with the microprocessor controller, delivered to NASA-MSFC. An oxygen/hydrogen thruster was modified for use with the test bed and successfully tested at mixture ratios from 4:1 to 8:1.

  1. Station Commander Praises AMS

    NASA Image and Video Library

    When asked what's the most important International Space Station experiment, Commander Chris Hadfield names the Alpha Magnetic Spectrometer-2, a state-of-the-art particle physics detector that coul...

  2. Multiple Craft Stations.

    ERIC Educational Resources Information Center

    Johns, Mary Sue

    1980-01-01

    Described are three craft stations (claywork, papermaking, and stamp designing) for intermediate grade students, to correlate with their classroom study which focused on Ohio: its history, geography, cities, industries, products and famous natives. (KC)

  3. Space Station Food System

    NASA Technical Reports Server (NTRS)

    Thurmond, Beverly A.; Gillan, Douglas J.; Perchonok, Michele G.; Marcus, Beth A.; Bourland, Charles T.

    1986-01-01

    A team of engineers and food scientists from NASA, the aerospace industry, food companies, and academia are defining the Space Station Food System. The team identified the system requirements based on an analysis of past and current space food systems, food systems from isolated environment communities that resemble Space Station, and the projected Space Station parameters. The team is resolving conflicts among requirements through the use of trade-off analyses. The requirements will give rise to a set of specifications which, in turn, will be used to produce concepts. Concept verification will include testing of prototypes, both in 1-g and microgravity. The end-item specification provides an overall guide for assembling a functional food system for Space Station.

  4. Enabler operator station

    NASA Astrophysics Data System (ADS)

    Bailey, Andrea; Keitzman, John; King, Shirlyn; Stover, Rae; Wegner, Torsten

    The objective of this project was to design an onboard operator station for the conceptual Lunar Work Vehicle (LWV). This LWV would be used in the colonization of a lunar outpost. The details that follow, however, are for an earth-bound model. Several recommendations are made in the appendix as to the changes needed in material selection for the lunar environment. The operator station is designed dimensionally correct for an astronaut wearing the current space shuttle EVA suit (which includes life support). The proposed operator station will support and restrain an astronaut as well as provide protection from the hazards of vehicle rollover. The threat of suit puncture is eliminated by rounding all corners and edges. A step-plate, located at the front of the vehicle, provides excellent ease of entry and exit. The operator station weight requirements are met by making efficient use of grid members, semi-rigid members and woven fabrics.

  5. International Space Station (ISS)

    NASA Image and Video Library

    1995-04-17

    This computer generated scene of the International Space Station (ISS) represents the first addition of hardware following the completion of Phase II. The 8-A Phase shows the addition of the S-9 truss.

  6. International Space Station (ISS)

    NASA Image and Video Library

    1994-04-20

    An artist's concept of a fully deployed International Space Station (ISS) Alpha. The ISS-A is a multidisciplinary laboratory, technology test bed, and observatory that will provide an unprecedented undertaking in scientific, technological, and international experiments.

  7. International Space Station (ISS)

    NASA Image and Video Library

    2000-02-01

    A section of the International Space Station truss assembly arrived at the Marshall Space Flight Center on NASA's Super Guppy cargo plane for structural and design testing as well as installation of critical flight hardware.

  8. International Space Station (ISS)

    NASA Image and Video Library

    2000-12-01

    This image of the International Space Station (ISS) in orbit was taken during a fly-around inspection by the Space Shuttle Endeavour after successfull attachment of the 240-foot-long, 38-foot-wide solar array.

  9. International Space Station (ISS)

    NASA Image and Video Library

    1994-09-21

    Artist's concept of the final configuration of the International Space Station (ISS) Alpha. The ISS is a multidisciplinary laboratory, technology test bed, and observatory that will provide an unprecedented undertaking in scientific, technological, and international experimentation.

  10. Space Station Live! Tour

    NASA Image and Video Library

    NASA is using the Internet and smartphones to provide the public with a new inside look at what happens aboard the International Space Station and in the Mission Control Center. NASA Public Affairs...

  11. Space Station Software Issues

    NASA Technical Reports Server (NTRS)

    Voigt, S. (Editor); Beskenis, S. (Editor)

    1985-01-01

    Issues in the development of software for the Space Station are discussed. Software acquisition and management, software development environment, standards, information system support for software developers, and a future software advisory board are addressed.

  12. Destination Station Atlanta

    NASA Image and Video Library

    Destination Station was recently in Atlanta from April 15 through April 21. During the week, NASA visited schools, hospitals, museums, and the city’s well known Atlanta Science Tavern Meet Up gro...

  13. International Space Station (ISS)

    NASA Image and Video Library

    2000-10-01

    Not long after separation of the Space Shuttle Discovery from the International Space Station (ISS), a crew member was able to use a 70mm handheld camera to grab this image of the station, featuring its newest additions. Backdropped against the blackness of space, the Z1 truss structure and its anterna, as well as the new Pressurized Mating Adapter (PMA-3), are visible in the foreground.

  14. International Space Station (ISS)

    NASA Image and Video Library

    2001-04-28

    A Canadian "handshake" in space occurred on April 28, 2001, as the Canadian-built space station robotic arm (Canadarm-2) transferred its launch cradle over to Endeavor's robotic arm. Marning the controls from the shuttle's aft flight deck, Canadian Mission Specialist Chris A. Hadfield of the Canadian Space Agency (CSA) was instrumental in the activity. The Spacelab pallet that carried the Canadarm2 robotic arm to the station was developed at the Marshall Space Flight Center (MSFC) in Huntsville, Alabama.

  15. International Space Station (ISS)

    NASA Image and Video Library

    2002-04-17

    This close-up view of the International Space Station (ISS), newly equipped with its new 27,000-pound S0 (S-zero) truss, was photographed by an astronaut aboard the Space Shuttle Atlantis STS-110 upon its ISS flyaround mission while pulling away from the ISS. The STS-110 mission prepared the Station for future spacewalks by installing and outfitting the 43-foot-long S0 truss and preparing the first railroad in space, the Mobile Transporter. The 27,000 pound S0 truss was the first of 9 segments that will make up the Station's external framework that will eventually stretch 356 feet (109 meters), or approximately the length of a football field. This central truss segment also includes a flatcar called the Mobile Transporter and rails that will become the first "space railroad," which will allow the Station's robotic arm to travel up and down the finished truss for future assembly and maintenance. The completed truss structure will hold solar arrays and radiators to provide power and cooling for additional international research laboratories from Japan and Europe that will be attached to the Station. STS-110 Extravehicular Activity (EVA) marked the first use of the Station's robotic arm to maneuver spacewalkers around the station and was the first time all of a Shuttle crew's spacewalks were based out of the Station's Quest Airlock. It was also the first Shuttle to use three Block II Main Engines. The Space Shuttle Orbiter Atlantis STS-110 mission, was launched April 8, 2002 and returned to Earth April 19, 2002.

  16. International Space Station (ISS)

    NASA Image and Video Library

    2002-04-14

    STS-110 mission specialist Lee M.E. Morin carries an affixed 35 mm camera to record work which is being performed on the International Space Station (ISS). Working with astronaut Jerry L. Ross (out of frame), the duo completed the structural attachment of the S0 (s-zero) truss, mating two large tripod legs of the 13 1/2 ton structure to the station's main laboratory during a 7-hour, 30-minute space walk. The STS-110 mission prepared the Station for future space walks by installing and outfitting the 43-foot-long S0 truss and preparing the Mobile Transporter. The S0 Truss was the first of 9 segments that will make up the Station's external framework that will eventually stretch 356 feet (109 meters), or approximately the length of a football field. This central truss segment also includes a flatcar called the Mobile Transporter and rails that will become the first "space railroad," which will allow the Station's robotic arm to travel up and down the finished truss for future assembly and maintenance. The completed truss structure will hold solar arrays and radiators to provide power and cooling for additional international research laboratories from Japan and Europe that will be attached to the Station. Milestones of the S-110 mission included the first time the ISS robotic arm was used to maneuver space walkers around the Station and marked the first time all space walks were based out of the Station's Quest Airlock. It was also the first Shuttle to use three Block II Main Engines. The Space Shuttle Orbiter Atlantis, STS-110 mission, was launched April 8, 2002 and returned to Earth April 19, 2002.

  17. International Space Station (ISS)

    NASA Image and Video Library

    2002-04-17

    This close-up view of the International Space Station (ISS), newly equipped with its new 27,000-pound S0 (S-zero) truss, was photographed by an astronaut aboard the Space Shuttle Atlantis STS-110 during its ISS flyaround mission while pulling away from the ISS. The STS-110 mission prepared the Station for future spacewalks by installing and outfitting the 43-foot-long S0 truss and preparing the first railroad in space, the Mobile Transporter. The 27,000 pound S0 truss was the first of 9 segments that will make up the Station's external framework that will eventually stretch 356 feet (109 meters), or approximately the length of a football field. This central truss segment also includes a flatcar called the Mobile Transporter and rails that will become the first "space railroad," which will allow the Station's robotic arm to travel up and down the finished truss for future assembly and maintenance. The completed truss structure will hold solar arrays and radiators to provide power and cooling for additional international research laboratories from Japan and Europe that will be attached to the Station. STS-110 Extravehicular Activity (EVA) marked the first use of the Station's robotic arm to maneuver spacewalkers around the Station and was the first time all of a shuttle crew's spacewalks were based out of the Station's Quest Airlock. It was also the first Shuttle to use three Block II Main Engines. The Space Shuttle Orbiter Atlantis STS-110 mission, was launched April 8, 2002 and returned to Earth April 19, 2002.

  18. International Space Station (ISS)

    NASA Image and Video Library

    2002-04-17

    This close-up view of the International Space Station (ISS), newly equipped with its new 27,000 pound S0 (S-zero) truss, was photographed by an astronaut aboard the Space Shuttle Atlantis STS-110 during its ISS fly-around mission while pulling away from the ISS. The STS-110 mission prepared the Station for future spacewalks by installing and outfitting the 43-foot-long S0 truss and preparing the first railroad in space, the Mobile Transporter. The 27,000 pound S0 truss was the first of 9 segments that will make up the Station's external framework that will eventually stretch 356 feet (109 meters), or approximately the length of a football field. This central truss segment also includes a flatcar called the Mobile Transporter and rails that will become the first "space railroad," which will allow the Station's robotic arm to travel up and down the finished truss for future assembly and maintenance. The completed truss structure will hold solar arrays and radiators to provide power and cooling for additional international research laboratories from Japan and Europe that will be attached to the Station. STS-110 Extravehicular Activity (EVA) marked the first use of the Station's robotic arm to manuever spacewalkers around the Station and was the first time all of a shuttle crew's spacewalks were based out of the Station's Quest Airlock. It was also the first Shuttle to use three Block II Main Engines. The Space Shuttle Orbiter Atlantis STS-110 mission, was launched April 8, 2002 and returned to Earth April 19, 2002.

  19. International Space Station (ISS)

    NASA Image and Video Library

    2002-04-17

    This close-up view of the International Space Station (ISS), newly equipped with its new 27,000- pound S0 (S-zero) truss, was photographed by an astronaut aboard the Space Shuttle Atlantis STS-110 mission following its undocking from the ISS. The STS-110 mission prepared the Station for future spacewalks by installing and outfitting the 43-foot-long S0 truss and preparing the first railroad in space, the Mobile Transporter. The 27,000 pound S0 truss was the first of 9 segments that will make up the Station's external framework that will eventually stretch 356 feet (109 meters), or approximately the length of a football field. This central truss segment also includes a flatcar called the Mobile Transporter and rails that will become the first "space railroad," which will allow the Station's robotic arm to travel up and down the finished truss for future assembly and maintenance. The completed truss structure will hold solar arrays and radiators to provide power and cooling for additional international research laboratories from Japan and Europe that will be attached to the Station. STS-110 Extravehicular Activity (EVA) marked the first use of the Station's robotic arm to maneuver spacewalkers around the Station and was the first time all of a shuttle crew's spacewalks were based out of the Station's Quest Airlock. It was also the first Shuttle to use three Block II Main Engines. The Space Shuttle Orbiter Atlantis STS-110 mission, was launched April 8, 2002 and returned to Earth April 19, 2002.

  20. International Space Station (ISS)

    NASA Image and Video Library

    2002-04-17

    This close-up view of the International Space Station (ISS), newly equipped with its new 27,000-pound S0 (S-zero) truss, was photographed by an astronaut aboard the Space Shuttle Atlantis STS-110 mission following its undocking from the ISS. The STS-110 mission prepared the Station for future spacewalks by installing and outfitting the 43-foot-long S0 truss and preparing the first railroad in space, the Mobile Transporter. The 27,000 pound S0 truss was the first of 9 segments that will make up the Station's external framework that will eventually stretch 356 feet (109 meters), or approximately the length of a football field. This central truss segment also includes a flatcar called the Mobile Transporter and rails that will become the first "space railroad," which will allow the Station's robotic arm to travel up and down the finished truss for future assembly and maintenance. The completed truss structure will hold solar arrays and radiators to provide power and cooling for additional international research laboratories from Japan and Europe that will be attached to the Station. STS-110 Extravehicular Activity (EVA) marked the first use of the Station's robotic arm to maneuver spacewalkers around the Station and was the first time all of a Shuttle crew's spacewalks were based out of the Station's Quest Airlock. It was also the first Shuttle to use three Block II Main Engines. The Space Shuttle Orbiter Atlantis STS-110 mission, was launched April 8, 2002 and returned to Earth April 19, 2002.