Sample records for nuclear operators
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-25
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-255; NRC-2010-0127] Entergy Nuclear Operations, Inc., Palisades Nuclear Plant; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear... Operating License No. DPR-20, issued to Entergy Nuclear Operations, LLC (ENO) (the licensee), for operation...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-01-14
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-293; NRC-2010-0010] Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and Finding of No Significant Impact The U.S... Entergy Nuclear Operations, Inc. (Entergy or the licensee), for operation of Pilgrim Nuclear Power Station...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-26
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-440; NRC-2010-0124] FirstEnergy Nuclear Operating Company; Perry Nuclear Power Plant; Environmental Assessment and Finding of No Significant Impact The U.S...,'' for Facility Operating License No. NPF-58, issued to FirstEnergy Nuclear Operating Company (FENOC, the...
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75 FR 38147 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-07-01
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346; NRC-2010-0240] FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company... of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). The license provides, among other things...
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75 FR 16524 - FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-04-01
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-440; NRC-2010-0124] FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC...: June 4, 2009, letter from R. W. Borchardt, NRC, to M. S. Fertel, Nuclear Energy Institute). The...
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75 FR 80549 - FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-22
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346; NRC-2010-0378] FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company... of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). The license provides, among other things...
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75 FR 16523 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-04-01
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346; NRC-2010-0125] FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company..., letter from R.W. Borchardt, NRC, to M.S. Fertel, Nuclear Energy Institute). The licensee's request for an...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-01-21
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; NRC-2010-0006] Entergy Nuclear Operations, Inc., Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC,: Indian Point Nuclear Generating Unit Nos. 2 and 3; Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity To Request a...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-23
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346; NRC-2010-0121] Firstenergy Nuclear Operating Company and Firstenergy Nuclear Generation Corp.; Notice of Withdrawal of Application for Amendment to Facility Operating License The U.S. Nuclear Regulatory Commission (the Commission) has [[Page 13802
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-10-03
... Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision Notice is hereby... ML102210411, respectively), concerns the operation of Pilgrim Nuclear Power Station (Pilgrim), owned by...) inaccessible cables at Pilgrim Nuclear Power Station (Pilgrim) are capable of performing their required...
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75 FR 77677 - Southern Nuclear Operating Company, Inc.
Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-13
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-366; NRC-2010-0345] Southern Nuclear Operating Company, Inc. Edwin I Hatch Nuclear Plant, Unit No. 2; Exemption 1.0 Background The Southern Nuclear...-5 which authorizes operation of the Edwin I. Hatch Nuclear Plant, Unit No. 2 (HNP-2). The license...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-07-31
... environmental effect of renewing the operating license of a nuclear power plant. This document is necessary to..., Environmental impact statement, Nuclear materials, Nuclear power plants and reactors, Reporting and... Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction AGENCY: Nuclear...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-15
... INFORMATION CONTACT: Michael Mahoney, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission... Licensing Branch III-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346] FirstEnergy Nuclear Operating Company; Notice of...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-09
... NUCLEAR REGULATORY COMMISSION [Docket No. 05000271; License No. DPR-28; EA-10-034; NRC-2010-0089] 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...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-05-18
... New Nuclear Power Plant Units on Operating Units at Multi-Unit Sites AGENCY: Nuclear Regulatory... construct and operate new nuclear power plants (NPPs) on multi-unit sites to provide an evaluation of the... License) of New Nuclear Power Plants on Operating Units at Multi-Unit Sites (Package). ML112630039 Federal...
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10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.
Code of Federal Regulations, 2014 CFR
2014-01-01
... power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear... requirements for immediate notification of the NRC by licensed operating nuclear power reactors are contained...
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75 FR 16520 - James A. Fitzpatrick Nuclear Power Plant; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-04-01
... date for all operating nuclear power plants, but noted that the Commission's regulations provide... Power Plant; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (the licensee) is the holder of Facility Operating License No. DPR-59, which authorizes operation of the James A. FitzPatrick Nuclear Power...
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75 FR 8150 - STP Nuclear Operating Company
Federal Register 2010, 2011, 2012, 2013, 2014
2010-02-23
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-498 and 50-499; NRC-2010-060] STP Nuclear Operating... The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption, pursuant to...,'' for Facility Operating [[Page 8151
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10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 1 2012-01-01 2012-01-01 false Immediate notification requirements for operating nuclear power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear...
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10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 1 2013-01-01 2013-01-01 false Immediate notification requirements for operating nuclear power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-09
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-348 AND 50-364; NRC-2012-0053] Facility Operating License Amendment From Southern Nuclear Operating, Inc., Joseph M. Farley Nuclear Plant, Units 1 and 2...-0053. You may submit comments by the following methods: Federal Rulemaking Web site: Go to http://www...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-08-16
... NUCLEAR REGULATORY COMMISSION [NRC-2011-0184; Docket No. 50-482] Wolf Creek Nuclear Operating... Regulatory Commission (the Commission) has granted the request of Wolf Creek Nuclear Operating Corporation... 22, 2010, for proposed amendment to Renewed Facility Operating License No. NPF-42 for the Wolf Creek...
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Code of Federal Regulations, 2013 CFR
2013-01-01
... nuclear material, facility and operator licenses. (a) If the Director, Office of Nuclear Reactor... repository operations area under parts 60 or 63 of this chapter, the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or...
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Code of Federal Regulations, 2014 CFR
2014-01-01
... nuclear material, facility and operator licenses. (a) If the Director, Office of Nuclear Reactor... repository operations area under parts 60 or 63 of this chapter, the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-11-27
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-247; NRC-2012-0284] Entergy Nuclear Indian Point 2, LLC; Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit No. 2, Request for Action AGENCY: Nuclear Regulatory Commission. ACTION: Request for Action; receipt. SUMMARY: The U.S. Nuclear...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-07-07
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-271; NRC-2010-0243; License No. DPR-28] Entergy Nuclear Operations, Inc.; Entergy Nuclear Vermont Yankee, LLC; Vermont Yankee Nuclear Power Station... action with regard to the Vermont Yankee Nuclear Power Station. Mr. Mulligan requested in his petition...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-08-19
... 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. ACTION: Request... that the NRC take action with regard to James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...
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77 FR 40091 - Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating, Units 2 and 3
Federal Register 2010, 2011, 2012, 2013, 2014
2012-07-06
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; NRC-2008-0672] Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating, Units 2 and 3 AGENCY: Nuclear Regulatory Commission... renewal of nuclear plants; availability. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-10-28
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346; NRC-2010-0298] FirstEnergy Nuclear Operating Company; Notice of Intent To Prepare an Environmental Impact Statement and Conduct the Scoping Process for Davis-Besse Nuclear Power Station, Unit 1 FirstEnergy Nuclear Operating Company (FENOC) has submitted an application for renewal of Facility...
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78 FR 52987 - Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit 3
Federal Register 2010, 2011, 2012, 2013, 2014
2013-08-27
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-286; NRC-2013-0063] Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Environmental assessment and finding of no significant impact; issuance. SUMMARY: The U.S. Nuclear Regulatory Commission...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-04-06
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-271; License No. DPR-28; NRC-2011-0074] Entergy Nuclear Operations, Inc., Entergy Nuclear Vermont Yankee, LLC, Vermont Yankee Nuclear Power Station... regard to the Vermont Yankee Nuclear Power Station (VY). Mr. Saporito requested in his petition that the...
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78 FR 39018 - Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating Unit Nos. 2 and 3
Federal Register 2010, 2011, 2012, 2013, 2014
2013-06-28
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; NRC-2008-0672] Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating Unit Nos. 2 and 3 AGENCY: Nuclear Regulatory Commission... Renewal of Nuclear Plants; issuance. SUMMARY: Notice is hereby given that the U.S. Nuclear Regulatory...
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Code of Federal Regulations, 2011 CFR
2011-01-01
... Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple... construct and operate nuclear power reactors of identical design (“common design”) to be located at multiple...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-05-07
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-286; NRC-2013-0063] Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit No. 3 Extension of Public Comment Period AGENCY: Nuclear Regulatory... FURTHER INFORMATION CONTACT: Douglas V. Pickett, Senior Project Manager, Office of Nuclear Reactor...
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77 FR 76541 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station
Federal Register 2010, 2011, 2012, 2013, 2014
2012-12-28
....; Pilgrim Nuclear Power Station AGENCY: Nuclear Regulatory Commission. ACTION: Environmental assessment and... licensee), for operation of the Pilgrim Nuclear Power Station (Pilgrim), located in Plymouth, Massachusetts... Regarding Pilgrim Nuclear Power Station, Final Report- Appendices,'' published in July 2007 (ADAMS Accession...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-09-20
... NUCLEAR REGULATORY COMMISSION [NRC-2010-0298; Docket No. 50-346] First Energy Nuclear Operating Company; Notice of Receipt and Availability of Application for Renewal of Davis Besse Nuclear Power Station, Unit 1, Facility Operating License No. NPF-003 for an Additional 20-Year Period The U.S. Nuclear Regulatory Commission (NRC or Commission) has...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-26
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346; NRC-2010-0125] FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Environmental Assessment and Finding of No Significant Impact... 14636
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75 FR 29785 - Draft Regulatory Guide: Issuance, Availability
Federal Register 2010, 2011, 2012, 2013, 2014
2010-05-27
... Guide, DG-1248, ``Nuclear Power Plant Simulation Facilities for Use in Operator Training, License..., ``Nuclear Power Plant Simulation Facilities for Use in Operator Training, License Examinations, and... or acceptance of a nuclear power plant simulation facility for use in operator and senior operator...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-08-19
... Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Changes to the Chemical Volume Control System AGENCY: Nuclear Regulatory Commission. ACTION: Exemption and combined license amendment; issuance... Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, Municipal...
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10 CFR 140.72 - Indemnity agreements.
Code of Federal Regulations, 2014 CFR
2014-01-01
... (issued pursuant to part 50 of this chapter) authorizing the licensee to operate the nuclear reactor... the licensee to possess and store special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of an operating license for the reactor...
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10 CFR 140.72 - Indemnity agreements.
Code of Federal Regulations, 2010 CFR
2010-01-01
... (issued pursuant to part 50 of this chapter) authorizing the licensee to operate the nuclear reactor... the licensee to possess and store special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of an operating license for the reactor...
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ERIC Educational Resources Information Center
Center for Occupational Research and Development, Inc., Waco, TX.
This program planning guide for a two-year postsecondary nuclear reactor (plant) operator trainee program is designed for use with courses 1-16 of thirty-five in the Nuclear Technology Series. The purpose of the guide is to describe the nuclear power field and its job categories for specialists, technicians and operators; and to assist planners,…
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-10
...; Pilgrim Nuclear Power Station Environmental Assessment and Finding of No Significant Impact The U.S... licensee), for operation of Pilgrim Nuclear Power Station (Pilgrim), located in Plymouth County, MA. In... License Renewal of Nuclear Plants: Regarding Pilgrim Nuclear Power Station,'' NUREG-1437, Supplement 29...
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78 FR 784 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2013-01-04
....; Pilgrim Nuclear Power Station; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (the licensee) is... Nuclear Power Station (PNPS). The license provides, among other things, that the facility is subject to... participated in two FEMA-evaluated exercises in conjunction with the Vermont Yankee Nuclear Power Plant and...
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10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.
Code of Federal Regulations, 2010 CFR
2010-01-01
... power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear power reactor licensee licensed under §§ 50.21(b) or 50.22 holding an operating license under this part...
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10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.
Code of Federal Regulations, 2011 CFR
2011-01-01
... power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear power reactor licensee licensed under §§ 50.21(b) or 50.22 holding an operating license under this part...
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75 FR 13323 - James A. Fitzpatrick Nuclear Power Plant; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-19
... Power Plant; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (the licensee) is the holder of Facility Operating License No. DPR-59, which authorizes operation of the James A. FitzPatrick Nuclear Power... nuclear power plants that were licensed before January 1, 1979, satisfy the requirements of 10 CFR Part 50...
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75 FR 9958 - Carolina Power & Light Company, Shearon Harris Nuclear Power Plant, Unit 1; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-04
..., Shearon Harris Nuclear Power Plant, Unit 1; Exemption 1.0 Background Carolina Power & Light Company (the... Operating License No. NPF-63, which authorizes operation of the Shearon Harris Nuclear Power Plant, Unit 1... rule's compliance date for all operating nuclear power plants, but noted that the Commission's...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-12-29
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-416; NRC-2011-0262] Entergy Operations, Inc.; Notice... Nuclear Station, Unit 1 AGENCY: Nuclear Regulatory Commission. ACTION: Intent to prepare environmental... years of operation at Grand Gulf Nuclear Station, Unit 1 (GGNS). GGNS is located in Claiborne County...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-02-02
...). Pilgrim is a boiling water nuclear reactor that is owned by Entergy Nuclear and operated by ENO. The... Generating Unit No. 1 (IP1). IP1 is a pressurized water nuclear reactor that is owned by ENIP2 and maintained... nuclear reactors that are owned by ENIP2 and ENIP3, respectively, and operated by ENO. The facilities are...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-11-05
... NUCLEAR REGULATORY COMMISSION [Docket Nos.: 50-003, 50-247, 50-286; NRC-2012-0265: License Nos.: DPR- 5, DPR-26, and DPR-64] Entergy Nuclear Operations, Inc., Entergy Nuclear Indian Point 2, LLC, and Entergy Nuclear Indian Point 3, LLC; Issuance of Director's Decision Notice is hereby given that the Director, Office of Nuclear Reactor Regulation...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-08-09
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-293; License No. DPR-35; NRC-2012-0186] Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station Receipt of Request for Action Notice is hereby... the Commission) take action with regard to the Pilgrim Nuclear Power Station (Pilgrim). The Petitioner...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-06-21
... NUCLEAR REGULATORY COMMISSION [NRC-2012-0284; Docket No. 50-247; License No. DPR-26] Entergy Nuclear Operations, Inc., Entergy Nuclear Indian Point Unit 2, LLC, Issuance of Director's Decision Notice is hereby given that the Deputy Director, Reactor Safety Programs, Office of Nuclear Reactor...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-02-24
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346; NRC-2010-0253] License No. NPF-3; FirstEnergy Nuclear Operating Company Notice of Issuance of Director's Decision Notice is hereby given that the... Petitioner states that FirstEnergy Nuclear Operating Company (the licensee for DBNPS) has violated Federal...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-05-21
... NUCLEAR REGULATORY COMMISSION [Docket No. 52-011; NRC-2008-0252] Southern Nuclear Operating Company; Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Early Site Permit Issued to Southern Nuclear Operating Company et al., for Vogtle Electric Generating Plant ESP Site Located in Burke...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-01-11
... nuclear power plants operating in the USA. II. Effective Date This MOU is effective December 30, 2009. III... requirements at commercial nuclear power plants operating in the United States of America (USA). The NRC's... digital assets at commercial nuclear power plants operating in the USA. This cooperation will ensure that...
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Problems and Delays Overshadow NRC's Initial Success in Improving Reactor Operators' Capabilities.
ERIC Educational Resources Information Center
General Accounting Office, Washington, DC.
The nuclear power plant accident at Three Mile Island raised many questions concerning the safety of nuclear power plant operations and the ability of nuclear plant reactor operators to respond to abnormal or accident conditions. In response, the Nuclear Regulatory Commission (NRC) developed a plan, which included short- and long-term actions to…
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-05-06
... Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone (301..., Office of Nuclear Reactor Regulation. [FR Doc. 2011-11107 Filed 5-5-11; 8:45 am] BILLING CODE 7590-01-P ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0071; Docket No. 50-382] Entergy Operations, Inc...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-05-20
... NUCLEAR REGULATORY COMMISSION [DOCKET NO. 52-016; NRC-2008-0250] Calvert Cliffs 3 Nuclear Project, LLC and Unistar Nuclear Operating Services, LLC; Notice of Availability of the Final Environmental Impact Statement for the Combined License Application for Calvert Cliffs Nuclear Power Plant Unit 3 Notice is hereby given that the U.S. Nuclear...
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Non-Nuclear Testing of Fission Technologies at NASA MSFC
NASA Technical Reports Server (NTRS)
Houts, Robert G.; Pearson, J. Boise; Aschenbrenner, Kenneth C.; Bradley, David E.; Dickens, Ricky E.; Emrich, William J.; Garber, Anne E.; Godfroy, Thomas J.; Harper, Roger T.; Martin, Jim J.;
2011-01-01
Highly realistic non-nuclear testing can be used to investigate and resolve potential issues with space nuclear power and propulsion systems. Non-nuclear testing is particularly useful for systems designed with fuels and materials operating within their demonstrated nuclear performance envelope. Non-nuclear testing also provides an excellent way for screening potential advanced fuels and materials prior to nuclear testing, and for investigating innovative geometries and operating regimes. Non-nuclear testing allows thermal hydraulic, heat transfer, structural, integration, safety, operational, performance, and other potential issues to be investigated and resolved with a greater degree of flexibility and at reduced cost and schedule compared to nuclear testing. The primary limit of non-nuclear testing is that nuclear characteristics and potential nuclear issues cannot be directly investigated. However, non-nuclear testing can be used to augment the potential benefit from any nuclear testing that may be required for space nuclear system design and development. This paper describes previous and ongoing non-nuclear testing related to space nuclear systems at NASA s Marshall Space Flight Center (MSFC).
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-14
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; NRC-2008-0672] Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating Unit Nos. 2 and 3; Notice of Availability of the Final Supplement 38 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Notice is hereby given that the U.S. Nuclear...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-06-25
... NUCLEAR REGULATORY COMMISSION [Docket No. 52-011; NRC-2008-0252] Southern Nuclear Operating Company et al.; Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Early Site Permit Issued to Southern Nuclear Operating Company et al., for Vogtle Electric Generating Plant ESP Site Located i...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-07-08
... NUCLEAR REGULATORY COMMISSION [Docket No. 52-011; NRC-2008-0252] Southern Nuclear Operating Company et al.; Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Early Site Permit Issued to Southern Nuclear Operating Company et al., for Vogtle Electric Generating Plant ESP Site Located I...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-08-27
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-482; NRC-2010-0286] Wolf Creek Nuclear Operating.... Nuclear Regulatory Commission (NRC, the Commission) has granted the request of Wolf Creek Nuclear... the Wolf Creek Generating Station, located in Coffey County, Kansas. The proposed amendment would have...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-08
... Company, Davis-Besse Nuclear Power Station; Environmental Assessment And Finding of No Significant Impact... operation of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS), located in Ottawa County, Ohio. In... the reactor coolant pressure boundary of light-water nuclear power reactors provide adequate margins...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-05-03
... Nuclear Reactor, Renewed Facility Operating License No. R-112 AGENCY: Nuclear Regulatory Commission... Commission (NRC or the Commission) has issued renewed Facility Operating License No. R- 112, held by Reed... License No. R-112 will expire 20 years from its date of issuance. The renewed facility operating license...
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Silver, E G
This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.
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The optimization of nuclear power plants operation modes in emergency situations
NASA Astrophysics Data System (ADS)
Zagrebayev, A. M.; Trifonenkov, A. V.; Ramazanov, R. N.
2018-01-01
An emergency situations resulting in the necessity for temporary reactor trip may occur at the nuclear power plant while normal operating mode. The paper deals with some of the operation c aspects of nuclear power plant operation in emergency situations and during threatened period. The xenon poisoning causes limitations on the variety of statements of the problem of calculating characteristics of a set of optimal reactor power off controls. The article show a possibility and feasibility of new sets of optimization tasks for the operation of nuclear power plants under conditions of xenon poisoning in emergency circumstances.
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JAEA's actions and contributions to the strengthening of nuclear non-proliferation
NASA Astrophysics Data System (ADS)
Suda, Kazunori; Suzuki, Mitsutoshi; Michiji, Toshiro
2012-06-01
Japan, a non-nuclear weapons state, has established a commercial nuclear fuel cycle including LWRs, and now is developing a fast neutron reactor fuel cycle as part of the next generation nuclear energy system, with commercial operation targeted for 2050. Japan Atomic Energy Agency (JAEA) is the independent administrative agency for conducting comprehensive nuclear R&D in Japan after the merger of Japan Atomic Energy Research Institute (JAERI) and Japan Nuclear Cycle Development Institute (JNC). JAEA and its predecessors have extensive experience in R&D, facility operations, and safeguards development and implementation for new types of nuclear facilities for the peaceful use of nuclear energy. As the operator of various nuclear fuel cycle facilities and numerous nuclear materials, JAEA makes international contributions to strengthen nuclear non-proliferation. This paper provides an overview of JAEA's development of nuclear non-proliferation and safeguards technologies, including remote monitoring of nuclear facilities, environmental sample analysis methods and new efforts since the 2010 Nuclear Security Summit in Washington D.C.
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-11-10
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-366; NRC-2010-0345] Southern Nuclear Operating Company Inc. Edwin I. Hatch Nuclear Plant, Unit No. 2 Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering the issuance of an exemption from Title 10 of the Code of Federal Regulations, ...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-11-29
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-348 and 50-364; NRC-2009-0375] Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant, Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an Exemption, pursuant to Title 10 of the Code of Federal...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-01-25
... Nuclear Power Plant, LLC, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Exemption 1.0 Background Calvert Cliffs Nuclear Power Plant, LLC, the licensee, is the holder of Facility Operating License Nos. DPR-53 and DPR-69 which authorizes operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1...
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Code of Federal Regulations, 2011 CFR
2011-01-01
... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites Section 101... nuclear power reactors of essentially the same design to be located at different sites. 1 1 If the design...
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Emergency Support Function 15 Standard Operating Procedures
2013-08-01
learned from numerous incidents to include the BP oil spill, the Fukushima nuclear incident, Hurricane Sandy and the Boston Marathon attack. Guidance is...Staffing Operations Activation Incident Operations Case Study - 2013 Boston Marathon Bombing Case Study - 2011 Fukushima Nuclear Crisis...Quick Summary Radiological Dispersal Device (RDD) Improvised Nuclear Device (IND) Federal Response Case Studies – 2011 Fukushima Nuclear
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Code of Federal Regulations, 2012 CFR
2012-01-01
... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites Section 101... nuclear power reactors of essentially the same design to be located at different sites. 1 1 If the design...
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Code of Federal Regulations, 2013 CFR
2013-01-01
... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites Section 101... nuclear power reactors of essentially the same design to be located at different sites. 1 1 If the design...
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Code of Federal Regulations, 2010 CFR
2010-01-01
... lightwater nuclear power reactors for normal operation. 50.60 Section 50.60 Energy NUCLEAR REGULATORY... lightwater nuclear power reactors for normal operation. (a) Except as provided in paragraph (b) of this section, all light-water nuclear power reactors, other than reactor facilities for which the...
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Code of Federal Regulations, 2011 CFR
2011-01-01
... lightwater nuclear power reactors for normal operation. 50.60 Section 50.60 Energy NUCLEAR REGULATORY... lightwater nuclear power reactors for normal operation. (a) Except as provided in paragraph (b) of this section, all light-water nuclear power reactors, other than reactor facilities for which the...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-15
...; Vermont Yankee Nuclear Power Station Environmental Assessment and Finding of No Significant Impact The U.S... licensee), for operation of Vermont Yankee Nuclear Power Station (Vermont Yankee), located in Windham... Statement for Vermont Yankee Nuclear Power Station, Docket No. 50-271, dated July 1972, as supplemented...
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10 CFR 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
Code of Federal Regulations, 2012 CFR
2012-01-01
... maintenance at nuclear power plants. 50.65 Section 50.65 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC... Construction Permits § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power..., including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power plant...
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10 CFR 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
Code of Federal Regulations, 2013 CFR
2013-01-01
... maintenance at nuclear power plants. 50.65 Section 50.65 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC... Construction Permits § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power..., including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power plant...
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10 CFR 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
Code of Federal Regulations, 2011 CFR
2011-01-01
... maintenance at nuclear power plants. 50.65 Section 50.65 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC... Construction Permits § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power..., including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power plant...
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10 CFR 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
Code of Federal Regulations, 2014 CFR
2014-01-01
... maintenance at nuclear power plants. 50.65 Section 50.65 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC... Construction Permits § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power..., including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power plant...
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78 FR 35989 - Tennessee Valley Authority; Watts Bar Nuclear Plant, Unit 2
Federal Register 2010, 2011, 2012, 2013, 2014
2013-06-14
... Bar Nuclear Plant, Unit 2 AGENCY: Nuclear Regulatory Commission. ACTION: Final environmental statement... Operation of Watts Bar Nuclear Plant (WBN), Unit 2'' (SFES). ADDRESSES: Please refer to Docket ID NRC-2008... option of issuing the operating license for Watts Bar Nuclear Plant, Unit 2. This recommendation is based...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-04-01
... Perry. FOR FURTHER INFORMATION CONTACT: Michael Mahoney, Office of Nuclear Reactor Regulation, U.S... Nuclear Reactor Regulation. [FR Doc. 2010-7331 Filed 3-31-10; 8:45 am] BILLING CODE 7590-01-P ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-440; NRC-2010-0124] FirstEnergy Nuclear Operating...
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NASA Technical Reports Server (NTRS)
1972-01-01
An analysis of the nuclear safety aspects (design and operational considerations) in the transport of nuclear payloads to and from earth orbit by the space shuttle is presented. Three representative nuclear payloads used in the study were: (1) the zirconium hydride reactor Brayton power module, (2) the large isotope Brayton power system and (3) small isotopic heat sources which can be a part of an upper stage or part of a logistics module. Reference data on the space shuttle and nuclear payloads are presented in an appendix. Safety oriented design and operational requirements were identified to integrate the nuclear payloads in the shuttle mission. Contingency situations were discussed and operations and design features were recommended to minimize the nuclear hazards. The study indicates the safety, design and operational advantages in the use of a nuclear payload transfer module. The transfer module can provide many of the safety related support functions (blast and fragmentation protection, environmental control, payload ejection) minimizing the direct impact on the shuttle.
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Nuclear Power Now and in the Near Future
NASA Astrophysics Data System (ADS)
Burchill, William
2006-04-01
The presentation will describe the present status of nuclear power in the United States including its operating, economic, and safety record. This status report will be based on publicly-available records of the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission, and the Institute of Nuclear Power Operations. The report will provide a brief description and state the impact of both the Three Mile Island and Chernobyl accidents. It will list the lessons learned and report significant improvements in U.S. nuclear power plants. The major design differences between Chernobyl and U.S. nuclear reactors will be discussed. The presentation will project the near future of nuclear power considering the 2005 Energy Bill, initiatives by the U.S. Department of Energy and industry, and public opinions. Issues to be considered include plant operating safety, disposition of nuclear waste, protection against proliferation of potential weapons materials, economic performance, environmental impact and protection, and advanced nuclear reactor designs and fuel cycle options. The risk of nuclear power plant operations will be compared to risks presented by other industrial activities.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 60%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to grow by about 24% from 2013 to 2040 . At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license, for a total of 60 years of operation (the oldest commercial plants in the Unitedmore » States reached their 40th anniversary in 2009). Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity for 40- and 60-year license periods. If current operating nuclear power plants do not operate beyond 60 years (and new nuclear plants are not built quickly enough to replace them), the total fraction of generated electrical energy from nuclear power will rapidly decline. That decline will be accelerated if plants are shut down before 60 years of operation. Decisions on extended operation ultimately rely on economic factors; however, economics can often be improved through technical advancements. The U.S. Department of Energy Office of Nuclear Energy's 2010 Research and Development Roadmap (2010 Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: 1. Develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; 2. Develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; 3. Develop sustainable nuclear fuel cycles; and 4. Understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program's plans. For the LWRS Program, sustainability is defined as the ability to maintain safe and economic operation of the existing fleet of nuclear power plants for a longer-than-initially-licensed lifetime. It has two facets with respect to long-term operations: (1) manage the aging of plant systems, structures, and components so that nuclear power plant lifetimes can be extended and the plants can continue to operate safely, efficiently, and economically; and (2) provide science-based solutions to the industry to implement technology to exceed the performance of the current labor-intensive business model.« less
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77 FR 6150 - Notice of Sunshine Act Meeting
Federal Register 2010, 2011, 2012, 2013, 2014
2012-02-07
... Status of Outreach and Educational Efforts with External Stakeholders Related to the Safety Culture...). a. Entergy Nuclear Generation Co. and Entergy Nuclear Operations, Inc (Pilgrim Nuclear Power Station). Docket No. 50-293-LR (Tentative). b. Southern Nuclear Operating Co. (Vogtle Electric Generating Plant...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-01-22
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-321 and 50-366; NRC-2010-0024] Southern Nuclear Operating Company, Inc., Edwin I. Hatch Nuclear Plant, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an Exemption, pursuant to Title 10 of the Code of...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-26
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-003, 50-247, and 50-286; NRC-2010-0137] Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating Unit Nos. 1, 2, and 3; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption, pursuant to Title 10 of...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-02-08
... through Entergy Nuclear Management Manual EN-OP-115, Revision 9, ``Conduct of Operations.'' Specifically... underlying the apparent violation. These actions included: (a) Operations management conducted a briefing for... the timely notification of events; (b) Management conducted a comprehensive assessment during the week...
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Systems and methods for processing irradiation targets through a nuclear reactor
Dayal, Yogeshwar; Saito, Earl F.; Berger, John F.; Brittingham, Martin W.; Morales, Stephen K.; Hare, Jeffrey M.
2016-05-03
Apparatuses and methods produce radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable during operation of commercial nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes or other desired materials at several different origin and termination points accessible outside an access barrier such as a containment building, drywell wall, or other access restriction preventing access to instrumentation tubes during operation of the nuclear plant.
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-03-21
... INFORMATION CONTACT: Nageswaran Kalyanam, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory..., Office of Nuclear Reactor Regulation. [FR Doc. 2013-06510 Filed 3-20-13; 8:45 am] BILLING CODE 7590-01-P ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0012] [Docket Nos. 50-458, 50-155, 72-043, 50-003, 50-247...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-06-15
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247-LR and 50-286-LR; ASLBP No. 07-858-03-LR-BD01] Atomic Safety and Licensing Board; Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3); Notice of Hearing (Application for License Renewal) June 8, 2012. Before Administrative Judges: Lawrence G. McDade, Chairman, Dr....
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-10-03
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-155; 72-43 and NRC-2013-0218] Entergy Nuclear Operations, Inc.; Big Rock Point; Independent Spent Fuel Storage Installation AGENCY: Nuclear Regulatory... the Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). ADDRESSES: Please refer...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-11-29
... NUCLEAR REGULATORY COMMISSION [NRC-2011-0272] Knowledge and Abilities Catalog for Nuclear Power...) is issuing for public comment a draft NUREG, NUREG-2103, Revision 0, ``Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized-Water Reactors. DATES: Submit...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-01-20
... NUCLEAR REGULATORY COMMISSION [NRC-2012-0010] Knowledge and Abilities Catalog for Nuclear Power... comment a draft NUREG, NUREG-2104, Revision 0, ``Knowledge and Abilities Catalog for Nuclear Power Plant... developed using this Catalog along with the Operator Licensing Examination Standards for Power Reactors...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-02-03
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-482; NRC-2010-0032] Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption, pursuant to Title...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-06-20
... Nuclear Power Plants; Generic Environmental Impact Statement and Standard Review Plans for Environmental... for Nuclear Power Plants, Supplement 1: Operating License Renewal'' (ESRP). The ESRP serves as a guide... published a final rule, ``Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating...
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75 FR 14208 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-24
... for all operating nuclear power plants, but noted that the Commission's regulations provide mechanisms...: June 4, 2009, letter from R. W. Borchardt, NRC, to M. S. Fertel, Nuclear Energy Institute). The... hereafter in effect. The facility consists of a boiling-water reactor located in Plymouth County...
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76 FR 20052 - Notice of Issuance of Regulatory Guide
Federal Register 2010, 2011, 2012, 2013, 2014
2011-04-11
... Guide 1.149, ``Nuclear Power Plant Simulation Facilities for Use in Operator Training, License..., ``Nuclear Power Plant Simulation Facilities for Use in Operator Training, License Examinations, and... simulation facility for use in operator and senior operator training, license examination operating tests...
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Light Water Reactor Sustainability Program: Integrated Program Plan
DOE Office of Scientific and Technical Information (OSTI.GOV)
None, None
Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 60%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to grow by about 24% from 2013 to 2040 . At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license, for a total of 60 years of operation (the oldest commercial plants in the Unitedmore » States reached their 40th anniversary in 2009). Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity for 40- and 60-year license periods. If current operating nuclear power plants do not operate beyond 60 years (and new nuclear plants are not built quickly enough to replace them), the total fraction of generated electrical energy from nuclear power will rapidly decline. That decline will be accelerated if plants are shut down before 60 years of operation. Decisions on extended operation ultimately rely on economic factors; however, economics can often be improved through technical advancements. The U.S. Department of Energy Office of Nuclear Energy’s 2010 Research and Development Roadmap (2010 Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: 1. Develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; 2. Develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; 3. Develop sustainable nuclear fuel cycles; and 4. Understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans. For the LWRS Program, sustainability is defined as the ability to maintain safe and economic operation of the existing fleet of nuclear power plants for a longer-than-initially-licensed lifetime. It has two facets with respect to long-term operations: (1) manage the aging of plant systems, structures, and components so that nuclear power plant lifetimes can be extended and the plants can continue to operate safely, efficiently, and economically; and (2) provide science-based solutions to the industry to implement technology to exceed the performance of the current labor-intensive business model.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.
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Operation CASTLE. Operation Plan Number 3-53. March - May 1954,
Nuclear radiation, *Nuclear explosions, *Radiation dosage, *Test methods, *Military operations, *Military planning, Radiobiology, Missions, Marshall Islands , Eniwetok Atoll, Bikini Atoll, Atmospheric physics, Low level, Radiation
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Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 2 2013-01-01 2013-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N to Part 52 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Pt. 52, App. N...
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Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 2 2014-01-01 2014-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N to Part 52 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Pt. 52, App. N...
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NASA Technical Reports Server (NTRS)
Buden, D.
1991-01-01
Topics dealing with nuclear safety are addressed which include the following: general safety requirements; safety design requirements; terrestrial safety; SP-100 Flight System key safety requirements; potential mission accidents and hazards; key safety features; ground operations; launch operations; flight operations; disposal; safety concerns; licensing; the nuclear engine for rocket vehicle application (NERVA) design philosophy; the NERVA flight safety program; and the NERVA safety plan.
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-02-10
..., Beaver Valley Power Station, Unit Nos. 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption, pursuant to... Operating Company (licensee), for operation of the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-22
... NUCLEAR REGULATORY COMMISSION [NRC-2011-0063; Docket Nos. 50-498 And 50-499] STP Nuclear Operating... Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity... on the NRC Web site and on the Federal rulemaking Web site http://www.regulations.gov . Because your...
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Nuclear Propulsion for Space, Understanding the Atom Series.
ERIC Educational Resources Information Center
Corliss, William R.; Schwenk, Francis C.
The operation of nuclear rockets with respect both to rocket theory and to various fuels is described. The development of nuclear reactors for use in nuclear rocket systems is provided, with the Kiwi and NERVA programs highlighted. The theory of fuel element and reactor construction and operation is explained with particular reference to rocket…
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-09-20
... nuclear power plants. In response to a request from the Nuclear Energy Institute (NEI), the NRC is... NUCLEAR REGULATORY COMMISSION [NRC-2011-0191] Draft License Renewal Interim Staff Guidance LR-ISG-2011-05; Ongoing Review of Operating Experience AGENCY: Nuclear Regulatory Commission. ACTION: Draft...
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75 FR 16869 - Entergy Nuclear Operations, LLC; Palisades Nuclear Plant; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-04-02
... generic industry request to extend the rule's compliance date for all operating nuclear power plants, but..., to M. S. Fertel, Nuclear Energy Institute). The licensee's request for an exemption is therefore... exemption will not have a significant effect on the quality of the human environment [75 FR 14473; dated...
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75 FR 14209 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-24
... compliance date for all operating nuclear power plants, but noted that the Commission's regulations provide...: June 4, 2009, letter from R.W. Borchardt, NRC, to M.S. Fertel, Nuclear Energy Institute). The licensee... Commission) now or hereafter in effect. The facility consists of a boiling-water reactor located in Windham...
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75 FR 11947 - STP Nuclear Operating Company, South Texas Project, Units 1 and 2; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-12
... request to extend the rule's compliance date for all operating nuclear power plants, but noted that the..., Nuclear Energy Institute). The licensee's request for an exemption is therefore consistent with the.... Nuclear Regulatory Commission (NRC, the Commission) now or hereafter in effect. The facility consists of...
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10 CFR 140.52 - Indemnity agreements.
Code of Federal Regulations, 2014 CFR
2014-01-01
...) authorizing the licensee to operate the nuclear reactor involved; or (2) The effective date of the license... material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after... 10 Energy 2 2014-01-01 2014-01-01 false Indemnity agreements. 140.52 Section 140.52 Energy NUCLEAR...
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10 CFR 140.52 - Indemnity agreements.
Code of Federal Regulations, 2010 CFR
2010-01-01
...) authorizing the licensee to operate the nuclear reactor involved; or (2) The effective date of the license... material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after... 10 Energy 2 2010-01-01 2010-01-01 false Indemnity agreements. 140.52 Section 140.52 Energy NUCLEAR...
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Mission design considerations for nuclear risk mitigation
NASA Technical Reports Server (NTRS)
Stancati, Mike; Collins, John
1993-01-01
Strategies for the mitigation of the nuclear risk associated with two specific mission operations are discussed. These operations are the safe return of nuclear thermal propulsion reactors to earth orbit and the disposal of lunar/Mars spacecraft reactors.
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Plant maintenance and plant life extension issue, 2008
DOE Office of Scientific and Technical Information (OSTI.GOV)
Agnihotri, Newal
The focus of the March-April issue is on plant maintenance and plant life extension. Major articles include the following: Exciting time to be at the U.S. NRC, by Dale Klein, Nuclear Regulatory Commission; Extraordinary steps to ensure a minimal environmental impact, by George Vanderheyden, UniStar Nuclear Energy, LLC.; Focused on consistent reduction of outages, by Kevin Walsh, GE Hitachi Nuclear Energy; On the path towards operational excellence, by Ricardo Perez, Westinghouse Electric Company; Ability to be refuelled on-line, by Ian Trotman, CANDU Services, Atomic Energy of Canada, Ltd.; ASCA Application for maintenance of SG secondary side, by Patrick Wagner, Wolfmore » Creek Nuclear Operating Corporation, Phillip Battaglia and David Selfridge, Westinghouse Electric Company; and, An integral part of the landscape and lives, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovation article is titled Steam generator bowl drain repairs, by John Makar and Richard Gimple, Wolf Creek Nuclear Operating Corporation.« less
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Counter Action Procedure Generation in an Emergency Situation of Nuclear Power Plants
NASA Astrophysics Data System (ADS)
Gofuku, A.
2018-02-01
Lessons learned from the Fukushima Daiichi accident revealed various weak points in the design and operation of nuclear power plants at the time although there were many resilient activities made by the plant staff under difficult work environment. In order to reinforce the measures to make nuclear power plants more resilient, improvement of hardware and improvement of education and training of nuclear personnel are considered. In addition, considering the advancement of computer technology and artificial intelligence, it is a promising way to develop software tools to support the activities of plant staff.This paper focuses on the software tools to support the operations by human operators and introduces a concept of an intelligent operator support system that is called as co-operator. This paper also describes a counter operation generation technique the authors are studying as a core component of the co-operator.
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Light Water Reactor Sustainability Program Integrated Program Plan
DOE Office of Scientific and Technical Information (OSTI.GOV)
McCarthy, Kathryn A.; Busby, Jeremy; Hallbert, Bruce
2014-04-01
Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution tomore » the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.« less
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-06-12
...., Pilgrim Nuclear Power Station; Record of Decision and Issuance of Renewed Facility Operating License No... as the record of decision for the renewal of facility operating license No. DPR-35, consistent with... referenced. NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21...
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Code of Federal Regulations, 2010 CFR
2010-01-01
... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FACILITIES Pt. 50, App.N Appendix N to Part 50—Standardization of Nuclear Power Plant Designs: Permits To..., apply to construction permits and operating licenses subject to this appendix N. 2. Applications for...
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NASA Astrophysics Data System (ADS)
Kuznetsov, V. M.; Khvostova, M. S.
2016-12-01
After the NPP radiation accidents in Russia and Japan, a safety statu of Russian nuclear power plants causes concern. A repeated life time extension of power unit reactor plants, designed at the dawn of the nuclear power engineering in the Soviet Union, power augmentation of the plants to 104-109%, operation of power units in a daily power mode in the range of 100-70-100%, the use of untypical for NPP remixed nuclear fuel without a careful study of the results of its application (at least after two operating periods of the research nuclear installations), the aging of operating personnel, and many other management actions of the State Corporation "Rosatom", should attract the attention of the Federal Service for Ecological, Technical and Atomic Supervision (RosTekhNadzor), but this doesn't happen. The paper considers safety issues of nuclear power plants operating in the Russian Federation. The authors collected statistical information on violations in NPP operation over the past 25 years, which shows that even after repeated relaxation over this period of time of safety regulation requirements in nuclear industry and highly expensive NPP modernization, the latter have not become more safe, and the statistics confirms this. At a lower utilization factor high-power pressure-tube reactors RBMK-1000, compared to light water reactors VVER-440 and 1000, have a greater number of violations and that after annual overhauls. A number of direct and root causes of NPP mulfunctions is still high and remains stable for decades. The paper reveals bottlenecks in ensuring nuclear and radiation safety of nuclear facilities. Main outstanding issues on the storage of spent nuclear fuel are defined. Information on emissions and discharges of radioactive substances, as well as fullness of storages of solid and liquid radioactive waste, located at the NPP sites are presented. Russian NPPs stress test results are submitted, as well as data on the coming removal from operation of NPP units is analyzed.
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-11-08
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-407, NRC-2011-0153] University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of Renewed Facility Operating License No. R-126 AGENCY... University of Utah (UU, the licensee), which authorizes continued operation of the UU TRIGA Nuclear Reactor...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-03
... industry request to extend the rule's compliance date for all operating nuclear power plants, but noted... M.S. Fertel, Nuclear Energy Institute). The licensee's request for an exemption is therefore... effect. The facility consists of two boiling-water reactors located in Appling County, Georgia. 2.0...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-07
... rule's compliance date for all operating nuclear power plants, but noted that the Commission's... compliance date (Reference: June 4, 2009, letter from R. W. Borchardt, NRC, to M. S. Fertel, Nuclear Energy... significant effect on the quality of the human environment (75 FR 73135, dated November 29, 2010). This...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-22
..., Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption 1.0 Background Carolina Power & Light Company... operation of the Shearon Harris Nuclear Power Plant (HNP), Unit 1. The license provides, among other things... request to generically extend the rule's compliance date for all operating nuclear power plants, but noted...
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Code of Federal Regulations, 2014 CFR
2014-01-01
..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...
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Code of Federal Regulations, 2013 CFR
2013-01-01
..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...
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Code of Federal Regulations, 2010 CFR
2010-01-01
..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...
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Code of Federal Regulations, 2011 CFR
2011-01-01
..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...
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Code of Federal Regulations, 2012 CFR
2012-01-01
..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...
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Non-Nuclear Testing of Space Nuclear Systems at NASA MSFC
NASA Technical Reports Server (NTRS)
Houts, Michael G.; Pearson, Boise J.; Aschenbrenner, Kenneth C.; Bradley, David E.; Dickens, Ricky; Emrich, William J.; Garber, Anne; Godfroy, Thomas J.; Harper, Roger T.; Martin, Jim J.;
2010-01-01
Highly realistic non-nuclear testing can be used to investigate and resolve potential issues with space nuclear power and propulsion systems. Non-nuclear testing is particularly useful for systems designed with fuels and materials operating within their demonstrated nuclear performance envelope. Non-nuclear testing allows thermal hydraulic, heat transfer, structural, integration, safety, operational, performance, and other potential issues to be investigated and resolved with a greater degree of flexibility and at reduced cost and schedule compared to nuclear testing. The primary limit of non-nuclear testing is that nuclear characteristics and potential nuclear issues cannot be directly investigated. However, non-nuclear testing can be used to augment the potential benefit from any nuclear testing that may be required for space nuclear system design and development. This paper describes previous and ongoing non-nuclear testing related to space nuclear systems at NASA's Marshall Space Flight Center (MSFC).
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Intrinsic operators for the electromagnetic nuclear current
DOE Office of Scientific and Technical Information (OSTI.GOV)
J. Adam, Jr.; H. Arenhovel
1996-09-01
The intrinsic electromagnetic nuclear meson exchange charge and current operators arising from a separation of the center-of-mass motion are derived for a one-boson-exchange model for the nuclear interaction with scalar, pseudoscalar and vector meson exchange including leading order relativistic terms. Explicit expressions for the meson exchange operators corresponding to the different meson types are given in detail for a two-nucleon system. These intrinsic operators are to be evaluated between intrinsic wave functions in their center-of-mass frame.
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NASA Astrophysics Data System (ADS)
Tyapkov, V. F.; Chudakova, I. Yu.; Alekseenko, O. A.
2011-08-01
Ways of improving the water chemistry used in the turbine generator stator's cooling systems at Russian nuclear power plants are considered. Data obtained from operational chemical monitoring of indicators characterizing the quality of cooling water in the turbine generator stator cooling systems of operating power units at nuclear power plants are presented.
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Nuclear Engineering Technologists in the Nuclear Power Era
ERIC Educational Resources Information Center
Wang, C. H.; And Others
1974-01-01
Describes manpower needs in nuclear engineering in the areas of research and development, architectural engineering and construction supervision, power reactor operations, and regulatory tasks. Outlines a suitable curriculum to prepare students for the tasks related to construction and operation of power reactors. (GS)
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78 FR 69139 - Physical Security-Design Certification and Operating Reactors
Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-18
... scheduled to close on October 30, 2013. The Nuclear Energy Institute (NEI) submitted a letter on October 9... NUCLEAR REGULATORY COMMISSION [NRC-2013-0225] Physical Security--Design Certification and Operating Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Standard review plan--draft section...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-12-18
... NUCLEAR REGULATORY COMMISSION [Docket Nos.: 50-498 and 50-499; NRC-2010-0375] STP Nuclear Operating Company, South Texas Project; Notice of Availability of Draft Supplement 48 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants and Public Meetings for the License Renewal of South Texas Project Notice is hereby...
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Economic and Market Challenges Facing the U.S. Nuclear Commercial Fleet
DOE Office of Scientific and Technical Information (OSTI.GOV)
Szilard, Ronaldo; Sharpe, Phil; Kee, Edward
This report identifies underlying economic and electricity market factors that have led to early retirements of U.S. operating nuclear power plants, assesses the Gap between operating revenues and operating costs for selected nuclear power plants, and discusses a range of actions that might be taken to stop early retirement of operating nuclear power plants. The Kewaunee and Vermont Yankee nuclear power plants were retired early for economic and financial reasons. Early retirement has been announced or proposed for Clinton and Quad Cities in Illinois, Fitzpatrick and Ginna in New York, Fort Calhoun in Nebraska. Other nuclear power plants, including Palisades,more » Davis-Besse, Prairie Island, and Three Mile Island Unit 1, have been identified as facing financial stress that might lead to early retirement. The early retirement of operating nuclear power plants will mean the loss of a large amount of zero-emission electricity, inconsistent with the goal of reducing carbon emissions in the electricity sector. This report provides a high-level view of the major factors driving early retirement: • The U.S. market and private ownership approach to the electricity sector; • Low electricity market prices resulting from low natural gas prices, low demand growth, increased penetration of renewable generation, and negative electricity market prices; and • No compensation to nuclear power plants for public benefits including zero-emission electricity.« less
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1996 NRC annual report. Volume 13
DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
1997-10-01
This 22nd annual report of the US Nuclear Regulatory Commission (NRC) describes accomplishments, activities, and plans made during Fiscal Year 1996 (FH 1996)--October 1, 1995, through September 30, 1996. Significant activities that occurred early in FY 1997 are also described, particularly changes in the Commission and organization of the NRC. The mission of the NRC is to ensure that civilian uses of nuclear materials in the US are carried out with adequate protection of public health and safety, the environment, and national security. These uses include the operation of nuclear power plants and fuel cycle plants and medical, industrial, andmore » research applications. Additionally, the NRC contributes to combating the proliferation of nuclear weapons material worldwide. The NRC licenses and regulates commercial nuclear reactor operations and research reactors and other activities involving the possession and use of nuclear materials and wastes. It also protects nuclear materials used in operation and facilities from theft or sabotage. To accomplish its statutorily mandated regulatory mission, the NRC issues rules and standards, inspects facilities and operations, and issues any required enforcement actions.« less
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NASA Technical Reports Server (NTRS)
1972-01-01
The design and operations guidelines and requirements developed in the study of space base nuclear system safety are presented. Guidelines and requirements are presented for the space base subsystems, nuclear hardware (reactor, isotope sources, dynamic generator equipment), experiments, interfacing vehicles, ground support systems, range safety and facilities. Cross indices and references are provided which relate guidelines to each other, and to substantiating data in other volumes. The guidelines are intended for the implementation of nuclear safety related design and operational considerations in future space programs.
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NASA Technical Reports Server (NTRS)
1972-01-01
The design and operations guidelines and requirements developed in the study of space shuttle nuclear system transportation are presented. Guidelines and requirements are presented for the shuttle, nuclear payloads (reactor, isotope-Brayton and small isotope sources), ground support systems and facilities. Cross indices and references are provided which relate guidelines to each other, and to substantiating data in other volumes. The guidelines are intended for the implementation of nuclear safety related design and operational considerations in future space programs.
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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)
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10 CFR 75.23 - Operating records.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 2 2011-01-01 2011-01-01 false Operating records. 75.23 Section 75.23 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) SAFEGUARDS ON NUCLEAR MATERIAL-IMPLEMENTATION OF US/IAEA AGREEMENT Material Accounting and Control for Facilities § 75.23 Operating records. The operating records required by § 75.21...
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78 FR 7816 - Quality Assurance Program Requirements (Operations)
Federal Register 2010, 2011, 2012, 2013, 2014
2013-02-04
... NUCLEAR REGULATORY COMMISSION [NRC-2013-0021] Quality Assurance Program Requirements (Operations...), DG-1300, ``Quality Assurance Program Requirements (Operations).'' DATES: Submit comments by April 1... CFR Part 50, Appendix B, ``Quality Assurance Criteria for Nuclear power Plants and Fuel Reprocessing...
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77 FR 14047 - Guidance for Decommissioning Planning During Operations
Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-08
...)-4014, ``Decommissioning Planning During Operations.'' This action is necessary to correct the NRC's... NUCLEAR REGULATORY COMMISSION [NRC-2011-0286] Guidance for Decommissioning Planning During Operations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; correction. SUMMARY: The U...
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Code of Federal Regulations, 2010 CFR
2010-01-01
... Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power Plant... that the applicant wishes to have the application considered under 10 CFR part 52, appendix N, and must...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-05-14
... recent public examples, including those documented in EA-12-240 and EA-12-230, and the impacts when there... and EA-12-230, and the impacts when there is a loss of integrity and trustworthiness. f. By the later...-8; EA-12-145] In the Matter of Southern Nuclear Operating Company, Farley Nuclear Plant, Units 1 and...
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78 FR 58570 - Environmental Assessment; Entergy Nuclear Operations, Inc., Big Rock Point
Federal Register 2010, 2011, 2012, 2013, 2014
2013-09-24
... Assessment; Entergy Nuclear Operations, Inc., Big Rock Point AGENCY: Nuclear Regulatory Commission. ACTION... applicant or the licensee), for the Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI... Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). II. Environmental Assessment (EA...
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Tower of Babel: a special report of the nuclear industry
DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
The southern U.S. region currently maintains 19 operating nuclear reactors, a large number of nuclear-related industries, and numerous radioactive waste storage facilities. To illustrate the greed of nuclear power proponents and the dangers of existing and future nuclear power plant operations, the southern nuclear power industry is surveyed. Detailed are the South's involvement in each phase of the nuclear fuel cycle, from uranium mining to waste disposal; efforts by the region's private electric utility companies to buttress the crumbling supports of the nuclear industry; and the serious threat that nuclear power poses to the region, the nation, and the world.more » The U.S. nuclear power industry can be viewed as a modern Tower of Babel. (4 maps, 20 photos, 2 tables)« less
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Nuclear Physics Made Very, Very Easy
NASA Technical Reports Server (NTRS)
Hanlen, D. F.; Morse, W. J.
1968-01-01
The fundamental approach to nuclear physics was prepared to introduce basic reactor principles to various groups of non-nuclear technical personnel associated with NERVA Test Operations. NERVA Test Operations functions as the field test group for the Nuclear Rocket Engine Program. Nuclear Engine for Rocket Vehicle Application (NERVA) program is the combined efforts of Aerojet-General Corporation as prime contractor, and Westinghouse Astronuclear Laboratory as the major subcontractor, for the assembly and testing of nuclear rocket engines. Development of the NERVA Program is under the direction of the Space Nuclear Propulsion Office, a joint agency of the U.S. Atomic Energy Commission and the National Aeronautics and Space Administration.
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78 FR 37850 - Quality Assurance Program Requirements (Operations)
Federal Register 2010, 2011, 2012, 2013, 2014
2013-06-24
... NUCLEAR REGULATORY COMMISSION [NRC-2013-0021] Quality Assurance Program Requirements (Operations... Regulatory Commission (NRC) is issuing a revision to Regulatory Guide (RG) 1.33, ``Quality Assurance Program... managerial and administrative Quality Assurance (QA) controls for nuclear power plants during operations...
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10 CFR 2.1115 - Designation of issues for adjudicatory hearing.
Code of Federal Regulations, 2010 CFR
2010-01-01
... at Civilian Nuclear Power Reactors § 2.1115 Designation of issues for adjudicatory hearing. (a) After... reactor already licensed to operate at the site, or any civilian nuclear power reactor for which a... the issuance of a construction permit or operating license for a civilian nuclear power reactor at...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-06-28
... University (the licensee, WSU) to operate the Washington State University Modified TRIGA Nuclear Radiation... NUCLEAR REGULATORY COMMISSION [Docket No. 50-27; Facility Operating License No. R-76; NRC-2010... Safeguards Information and Sensitive Unclassified Non-Safeguards Information AGENCY: Nuclear Regulatory...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-08-16
... Limited Work Authorizations AGENCY: Nuclear Regulatory Commission. ACTION: Notice of hearing. SUMMARY: The... Southern Nuclear Operating Company for two combined licenses (COLs) seeking approval to construct and...), as well as for two limited work authorizations (LWAs) to engage in selected construction activities...
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10 CFR 2.400 - Scope of subpart.
Code of Federal Regulations, 2010 CFR
2010-01-01
... to construct and/or operate nuclear power reactors of identical design to be located at multiple... Procedures Applicable to Proceedings for the Issuance of Licenses To Construct and/or Operate Nuclear Power... 10 Energy 1 2010-01-01 2010-01-01 false Scope of subpart. 2.400 Section 2.400 Energy NUCLEAR...
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76 FR 34105 - FirstEnergy Nuclear Operating Company; Notice of Issuance of Director's Decision
Federal Register 2010, 2011, 2012, 2013, 2014
2011-06-10
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-320; License No. DPR-73; NRC-2010-0358] FirstEnergy Nuclear Operating Company; Notice of Issuance of Director's Decision Notice is hereby given that the..., Petition Review Board (PRB) meeting, via teleconference, with the Petitioner and FirstEnergy Corporation...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-10-11
...; Notice of Issuance of Renewed Facility Operating License No. R-76 AGENCY: Nuclear Regulatory Commission. ACTION: Notice of issuance of renewed facility operating license No. R- 76. ADDRESSES: You can access.... Nuclear Regulatory Commission (NRC, the Commission) has issued renewed Facility Operating License No. R-76...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-16
...-05: Ongoing Review of Operating Experience AGENCY: Nuclear Regulatory Commission. ACTION: Interim... License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2011-05, ``Ongoing Review of Operating Experience... industry-wide operating experience as an attribute of aging management programs used at nuclear power...
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Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 1 2014-01-01 2014-01-01 false Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. N Appendix N to Par...
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Autonomous Control of Nuclear Power Plants
DOE Office of Scientific and Technical Information (OSTI.GOV)
Basher, H.
2003-10-20
A nuclear reactor is a complex system that requires highly sophisticated controllers to ensure that desired performance and safety can be achieved and maintained during its operations. Higher-demanding operational requirements such as reliability, lower environmental impacts, and improved performance under adverse conditions in nuclear power plants, coupled with the complexity and uncertainty of the models, necessitate the use of an increased level of autonomy in the control methods. In the opinion of many researchers, the tasks involved during nuclear reactor design and operation (e.g., design optimization, transient diagnosis, and core reload optimization) involve important human cognition and decisions that maymore » be more easily achieved with intelligent methods such as expert systems, fuzzy logic, neural networks, and genetic algorithms. Many experts in the field of control systems share the idea that a higher degree of autonomy in control of complex systems such as nuclear plants is more easily achievable through the integration of conventional control systems and the intelligent components. Researchers have investigated the feasibility of the integration of fuzzy logic, neural networks, genetic algorithms, and expert systems with the conventional control methods to achieve higher degrees of autonomy in different aspects of reactor operations such as reactor startup, shutdown in emergency situations, fault detection and diagnosis, nuclear reactor alarm processing and diagnosis, and reactor load-following operations, to name a few. With the advancement of new technologies and computing power, it is feasible to automate most of the nuclear reactor control and operation, which will result in increased safety and economical benefits. This study surveys current status, practices, and recent advances made towards developing autonomous control systems for nuclear reactors.« less
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Integrated nuclear data utilisation system for innovative reactors.
Yamano, N; Hasegawa, A; Kato, K; Igashira, M
2005-01-01
A five-year research and development project on an integrated nuclear data utilisation system was initiated in 2002, for developing innovative nuclear energy systems such as accelerator-driven systems. The integrated nuclear data utilisation system will be constructed as a modular code system, which consists of two sub-systems: the nuclear data search and plotting sub-system, and the nuclear data processing and utilisation sub-system. The system will be operated with a graphical user interface in order to enable easy utilisation through the Internet by both nuclear design engineers and nuclear data evaluators. This paper presents an overview of the integrated nuclear data utilisation system, describes the development of a prototype system to examine the operability of the user interface and discusses specifications of the two sub-systems.
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Expanded scope of training and education programs at the UFTR
DOE Office of Scientific and Technical Information (OSTI.GOV)
Vernetson, W.G.; Whaley, P.M.
1985-01-01
Historically, the University of Florida Training Reactor (UFTR) has been used to train both hot and cold license reactor operator candidates in intensive two- and three-week training programs consisting of a correlated set of classroom lectures, hands-on reactor operations, and laboratory exercises. These training programs provide nuclear plant operating staff with fundamental operational experience in understanding, controlling, and evaluating subcritical multiplication, reactivity effects, reactivity manipulations, and reactor operations; a sufficient number of startups and shutdowns is also assured. The UDTR is also used in a nuclear engineering course entitled ''Principles of Nuclear Reactor Operations.'' The purpose of this paper ismore » to report the results of efforts to redirect and refine tractor operations educational and training programs at the UFTR.« less
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-29
...] South Texas Project Nuclear Operating Company; Establishment of Atomic Safety and Licensing Board..., 2.318, and 2.321, notice is hereby given that an Atomic Safety and Licensing Board (Board) is being...: Ronald M. Spritzer, Chair, Atomic Safety and Licensing Board Panel, U.S. Nuclear Regulatory Commission...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-01-20
... Nuclear Operating Company; Establishment of Atomic Safety and Licensing Board Pursuant to delegation by... hereby given that an Atomic Safety and Licensing Board (Board) is being established to preside over the... administrative judges: William J. Froehlich, Chair, Atomic Safety and Licensing Board Panel, U.S. Nuclear...
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Deep rock nuclear waste disposal test: design and operation
DOE Office of Scientific and Technical Information (OSTI.GOV)
Klett, Robert D.
1974-09-01
An electrically heated test of nuclear waste simulants in granitic rock was conducted to demonstrate the feasibility of the concept of deep rock nuclear waste disposal and to obtain design data. This report describes the deep rock disposal sytstems study and the design and operation of the first concept feasibility test.
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77 FR 30435 - In-core Thermocouples at Different Elevations and Radial Positions in Reactor Core
Federal Register 2010, 2011, 2012, 2013, 2014
2012-05-23
... NUCLEAR REGULATORY COMMISSION 10 CFR Part 50 [Docket No. PRM-50-105; NRC-2012-0056] In-core Thermocouples at Different Elevations and Radial Positions in Reactor Core AGENCY: Nuclear Regulatory Commission... of operating licenses for nuclear power plants (``NPP'') to operate NPPs with in-core thermocouples...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-12-26
... Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, and Nuclear Energy... 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or... cyber security controls only. The operational and management controls, as described in Nuclear Energy...
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10 CFR 51.95 - Postconstruction environmental impact statements.
Code of Federal Regulations, 2010 CFR
2010-01-01
... determined by the Commission, a supplement on the operation of a nuclear power plant will not include a... the storage of spent fuel for the nuclear power plant within the scope of the generic determination in... the renewal of an operating license or combined license for a nuclear power plant under parts 52 or 54...
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75 FR 15749 - Entergy Operations, Inc., Grand Gulf Nuclear Station, Unit 1; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-30
... request to extend the rule's compliance date for all operating nuclear power plants, but noted that the... (Nuclear Energy Institute) dated June 4, 2009. The licensee's request for an exemption is therefore...) now or hereafter in effect. The facility consists of a boiling-water reactor located in Claiborne...
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DOE Office of Scientific and Technical Information (OSTI.GOV)
None, None
NNSA’s third mission pillar is supporting the U.S. Navy’s ability to protect and defend American interests across the globe. The Naval Reactors Program remains at the forefront of technological developments in naval nuclear propulsion and ensures a commanding edge in warfighting capabilities by advancing new technologies and improvements in naval reactor performance and reliability. In 2015, the Naval Nuclear Propulsion Program pioneered advances in nuclear reactor and warship design – such as increasing reactor lifetimes, improving submarine operational effectiveness, and reducing propulsion plant crewing. The Naval Reactors Program continued its record of operational excellence by providing the technical expertise requiredmore » to resolve emergent issues in the Nation’s nuclear-powered fleet, enabling the Fleet to safely steam more than two million miles. Naval Reactors safely maintains, operates, and oversees the reactors on the Navy’s 82 nuclear-powered warships, constituting more than 45 percent of the Navy’s major combatants.« less
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Wade, Elman E.
1978-01-01
A lifting, rotating and sealing apparatus for nuclear reactors utilizing rotating plugs above the nuclear reactor core. This apparatus permits rotation of the plugs to provide under the plug refueling of a nuclear core. It also provides a means by which positive top core holddown can be utilized. Both of these operations are accomplished by means of the apparatus lifting the top core holddown structure off the nuclear core while stationary, and maintaining this structure in its elevated position during plug rotation. During both of these operations, the interface between the rotating member and its supporting member is sealingly maintained.
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Robotics for Nuclear Material Handling at LANL:Capabilities and Needs
DOE Office of Scientific and Technical Information (OSTI.GOV)
Harden, Troy A; Lloyd, Jane A; Turner, Cameron J
Nuclear material processing operations present numerous challenges for effective automation. Confined spaces, hazardous materials and processes, particulate contamination, radiation sources, and corrosive chemical operations are but a few of the significant hazards. However, automated systems represent a significant safety advance when deployed in place of manual tasks performed by human workers. The replacement of manual operations with automated systems has been desirable for nearly 40 years, yet only recently are automated systems becoming increasingly common for nuclear materials handling applications. This paper reviews several automation systems which are deployed or about to be deployed at Los Alamos National Laboratory formore » nuclear material handling operations. Highlighted are the current social and technological challenges faced in deploying automated systems into hazardous material handling environments and the opportunities for future innovations.« less
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-07-29
... geothermal energy demonstration project and research center. Reduced Operations Alternative The Reduced... DEPARTMENT OF ENERGY National Nuclear Security Administration Draft Site-Wide Environmental Impact Statement for the Continued Operation of the Department of Energy/National Nuclear Security Administration...
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Utility operations review of North Carolina State University BSNE curriculum
DOE Office of Scientific and Technical Information (OSTI.GOV)
Bishop, E.A.; Faggart, E.M.; Jackson, G.D.
1988-01-01
The industry advisors group of the North Carolina State University (NCSU) Department of Nuclear Engineering raised the question of how well the curriculum for a bachelor of science in nuclear engineering (BSNE) meets the needs of educating students to enter the nuclear operations field. The concern was that the nuclear industry has evolved from a design to an operations mode, but that the BSNE curriculum may not have responded to this evolution. To address this issue, a group of four persons qualified as senior reactor operators with operational experience from different utilities was selected. The authors are the members ofmore » this review group. All are degreed personnel, with three BSNE graduates from NCSU, and all have participated in nuclear plant startups and currently work at nuclear plant sites. The group prepared by reviewing the curriculum before arriving on campus, including the report developed for the Accreditation Board for Engineering and Technology. During our two-day campus visit, we reviewed course materials, interviewed professors, and toured laboratory and reactor facilities in order to get more insight into the breadth and thrust of the BSNE curriculum. The observations and recommendations contained in this paper were developed based on these reviews and discussions and represent the opinions of the authors and not necessarily their companies.« less
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Stabin, M; Schlafke-Stelson, A
1991-09-01
Operators of in-vivo counters often encounter unusual photopeaks, some of which may be attributed to nuclear medicine radiopharmaceuticals recently received by the subject. This article lists the most common radiopharmaceuticals used in nuclear medicine, their common uses, their half-lives and principal decay energies, and the half-lives and decay energies of any contaminants or daughter products they may contain. The purpose is to help the in-vivo counter operator track down and eliminate causes of such unusual photopeaks.
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-06-04
... Nuclear Operating Company; Establishment of Atomic Safety and Licensing Board Pursuant to delegation by... 2.104, 2.105, 2.300, 2.309, 2.313, 2.318, and 2.321, notice is hereby given that an Atomic Safety... administrative judges: Paul S. Ryerson, Chairman, Atomic Safety and Licensing Board Panel, U.S. Nuclear...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-03-07
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-302; NRC-2009-0039] Crystal River Nuclear Generating... in ADAMS) is provided the first time that a document is referenced. NRC's PDR: You may examine and... operating license DPR-72, which authorizes Florida Power Corporaton (FPC) to operate the Crystal River...
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A Post Licensing Study of Community Effects at Two Operating Nuclear Power Plants. Final Report.
ERIC Educational Resources Information Center
Purdy, Bruce J.; And Others
In an effort to identify and assess the social, economic, and political effects of nuclear power plant construction and operation upon two host communities (Plymouth, Massachusetts and Waterford, Connecticut), a post-licensing review revealed that the primary impact of the nuclear power plants in both communities was an increase in the property…
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75 FR 15751 - Entergy Operations, Inc., Arkansas Nuclear One, Units 1 And 2; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-30
... compliance date for all operating nuclear power plants, but noted that the Commission's regulations provide...: June 4, 2009, letter from R. W. Borchardt, NRC, to M. S. Fertel, Nuclear Energy Institute). The... have a significant effect on the quality of the human environment (75 FR 13607; dated March 22, 2010...
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Reactor engineering support of operations at the Davis-Besse nuclear power station
DOE Office of Scientific and Technical Information (OSTI.GOV)
Kelley, D.B.
1995-12-31
Reactor engineering functions differ greatly from unit to unit; however, direct support of the reactor operators during reactor startups and operational transients is common to all units. This paper summarizes the support the reactor engineers provide the reactor operators during reactor startups and power changes through the use of automated computer programs at the Davis-Besse nuclear power station.
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Human reliability and plant operating efficiency: Are 12-hour work schedules cause for concern
DOE Office of Scientific and Technical Information (OSTI.GOV)
Baker, T.L.
1992-01-01
Since the introduction of 12-h shifts to the US nuclear power industry only 8 yr ago, compressed workweek schedules have proliferated among operations departments at a phenomenal rate. Many plants that continue to use 8-h shifts during normal operations routinely change to scheduled 12-h shifts during refueling or maintenance outages. The most critical issue in the use of extended work shifts is whether alertness, physical stamina, or mental performance are compromised to the point of reducing safety or efficiency of nuclear power plant operation. Laboratory and field research sponsored by the National Institute of Occupational Safety and Health suggests thatmore » alertness, measured by self-ratings, and mental performance, measured by computer-based performance tests, are impaired on 12-h shifts compared with 8-h shifts. In contrast to these findings, plant operating efficiency and operator performance have been rated as improved in two field studies conducted in operating nuclear power plants (Fast Flux Test Facility, Washington and Ontario Hydro, Canada). A recent Electric Power Research Institute review of nuclear industry experience with 12-h shifts also suggests an overwhelmingly positive rating of 12-h schedules from both control room operators and management.« less
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-02-13
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-264; NRC-2012-0026] Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108 AGENCY: Nuclear Regulatory Commission... Facility Operating License No. R-108 (``Application''), which currently authorizes the Dow Chemical Company...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-11-08
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-020; NRC-2010-0313] Massachusetts Institute of Technology Reactor Notice of Issuance of Renewed Facility Operating; License No. R-37 The U.S. Nuclear... Institute of Technology (the licensee), which authorizes continued operation of the Massachusetts Institute...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-29
... correspondence to addressees and subscribers through a computer-based email distribution system. Since then, the... Electronic Operating Reactor Correspondence The U.S. Nuclear Regulatory Commission (NRC) is issuing this... available operating reactor licensing correspondence, effective December 9, 2013. Official agency records...
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
1994-06-01
The U.S. Department of Energy, Nevada Operations Office (DOE/NV), Completion Report provides a summary of activities conducted at the Nevada Test Site (NTS) between October 1, 1992, and September 30, 1993, associated with Operation KLAXON. (In the past, each annual Completion Report dealt with a series of underground nuclear detonations; however, because no nuclear tests were conducted during FY 1993, this Report summarizes continuing nonnuclear and nuclear test readiness activities at the NTS sponsored by DOE/NV.) The report serves as a reference for those involved with the planning and execution of Operation KLAXON and also serves as a planning guidemore » for future operations. Information in the report covers the logistics and management of activities. Scientific information and data associated with NTS activities are presented in technical documents published by participating agencies. In September 1992, Congress legislated a nine-month moratorium on the testing of nuclear weapons. The bill also provided for a resumption of testing (with no more than five tests per year, or a total of 15 during the next three years) in July 1993, and mandated an end to nuclear testing, entirely, by 1996. President Bush signed the bill into law in October 1992.« less
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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 assessment review and then on to the stakeholder cost benefit analysis (if model qualifications are met) leading to a final plant retirement decision. This application via the model and guide, in turn, will lead electric utilities to explore system upgrade import opportunities and mitigation measures versus building new replacement generation facilities. United States nuclear reactors are licensed for 40 years with a 20 year extension available prior to the expiration date (EIA, 2013). Since late 2012, electric power companies have announced the early retirement of four uneconomical nuclear power plants while other studies have indicated that as many as 70 percent of United States nuclear power plants are potentially at risk for early retirement (Crooks, 2014 and Cooper, 2013). A high percentage of these aforementioned nuclear plants have operating licenses that will not expire until 2030 and beyond. Thus, for the most part, replacement power contingency planning has not been initiated for these plants or is still in preliminary stages. The recent nuclear plant retirements are the first since 1998 (EIA, 2013). Decisions to retire the plants involved concerns over maintenance and repair costs as well as declining profitability (EIA, 2013). In addition, the Energy Information Administration (2010-2012) released data that demonstrated that the worst 25 percent of United States nuclear plants are far more expensive to operate and generate electricity than new gas plants. It is equally important to understand and explain the economic and power replacement implications to both ratepayers and end-users. A SONGS case study analysis will review the economic, operational and political challenges that SCE faced leading to the retirement decision of SONGS. As preface to the case study, replacement steam generators (RSGs) were installed in Unit 2 in 2009 and in Unit 3 in 2010. In January 2012, while Unit 2 was down for routine maintenance, a small leak was discovered inside a steam generator in Unit 3. Because of the situation, both units remained shut down to evaluate the cause of the leakage and to make repairs. SCE submitted plans to the Nuclear Regulatory Commission (NRC) to re-start Unit 2 at reduced power. However, concerns over the length of the review process and the high costs associated with steam generator repairs led SCE to retire both reactors (SCE SONGS Fact Sheets, 2012-2013). Finally, collaborative resource power replacement planning is needed more than ever as nuclear facilities in the United States are now being retired for economic related reasons (Crooks, 2014). This collaborative power replacement process and implementation must encompass all relevant stakeholders including state grid operators, ratepayers, shareholders and the electric utility company.
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U.S. Nuclear Power Plants: Continued Life or Replacement After 60? (released in AEO2010)
2010-01-01
Nuclear power plants generate approximately 20% of U.S. electricity, and the plants in operation today are often seen as attractive assets in the current environment of uncertainty about future fossil fuel prices, high construction costs for new power plants (particularly nuclear plants), and the potential enactment of greenhouse gas regulations. Existing nuclear power plants have low fuel costs and relatively high power output. However, there is uncertainty about how long they will be allowed to continue operating.
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-22
..., Inc., Arkansas Nuclear One, Units 1 and 2; Environmental Assessment and Finding of No Significant... licensee), for operation of the Arkansas Nuclear One, Units 1 and 2 (ANO-1 and 2), located in Pope County... required implementation date of March 31, 2010, for three new requirements of 10 CFR Part 73 for ANO-1 and...
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Evaluation of Radiation Impacts of Spent Nuclear Fuel Storage (SNFS-2) of Chernobyl NPP - 13495
DOE Office of Scientific and Technical Information (OSTI.GOV)
Paskevych, Sergiy; Batiy, Valiriy; Sizov, Andriy
2013-07-01
Radiation effects are estimated for the operation of a new dry storage facility for spent nuclear fuel (SNFS-2) of Chernobyl NPP RBMK reactors. It is shown that radiation exposure during normal operation, design and beyond design basis accidents are minor and meet the criteria for safe use of radiation and nuclear facilities in Ukraine. (authors)
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Appraisal of Scientific Resources for Emergency Management.
1983-09-01
water, communications, computers, and oil refineries or storage facilities. In addition, the growth of the number of operative nuclear power plants ...one from a nuclear power plant accident); one involved hazardous waste disposal problems; and finally two involved wartime scenarios, one focusing on...pro- tection research, radiological protection from nuclear power plant accidents, concepts and operation of public shelters, and post attack
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10 CFR 140.11 - Amounts of financial protection for certain reactors.
Code of Federal Regulations, 2014 CFR
2014-01-01
...,000,000 for each nuclear reactor he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear reactor he is authorized to operate at... amount of $2,500,000 for each nuclear reactor other than a testing reactor or a reactor licensed under...
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10 CFR 140.11 - Amounts of financial protection for certain reactors.
Code of Federal Regulations, 2012 CFR
2012-01-01
...,000,000 for each nuclear reactor he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear reactor he is authorized to operate at... amount of $2,500,000 for each nuclear reactor other than a testing reactor or a reactor licensed under...
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10 CFR 140.11 - Amounts of financial protection for certain reactors.
Code of Federal Regulations, 2013 CFR
2013-01-01
...,000,000 for each nuclear reactor he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear reactor he is authorized to operate at... amount of $2,500,000 for each nuclear reactor other than a testing reactor or a reactor licensed under...
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Hyun Seok Ko; Yong Min Kim; Young Wook Lee
2006-07-01
In Korea, the nuclear power generation is grown technically well. Already, 20 nuclear reactors are operated, and approximate they supply the 40% of whole the consumption of electric power. This is the driving force of Korean industrial development. Besides, Korean Standard Nuclear Power Plant that was developed by Korean self-technique with nuclear plant technique independence, Ul-Chin 6 has started the commercial operation. Advanced Korean Standard Nuclear Power Plant, new Gori 1, 2 constructions are commenced. But, past days Korean situation is that intention of residents is neglected in the decision making process of nuclear power plant construction and operation. Inmore » existing decision making process, it is regarded as the role of public opinion is secondary, and the problem of decision making process is that public is persuaded and believed. So, in decision making process, the public opinion is considered restrictively, there is not the actual public participation. Therefore the dissatisfaction of public is increased continuously, and in Korea, bad recognition about nuclear power is getting full. The method of public participation for complement of this problem is public hearing or ombudsman system. The public hearing is ensuring public participation before decision of a case, and ombudsman is the system that elevates the public satisfaction through continuous feedback of public requirement to occur in deciding and performing the matters. In Korean situation, that present 20 nuclear reactors are operated and also the place of radioactive waste repository has been decided, not only the introduction of public hearing to decide the coming matter but also the operation of ombudsman system to continuously correct and collect the public requirements about the matter to already decided and operated is necessary. In Korea, administration type ombudsman is operated now. But, it has operated without basic element at the aspect of organization, function and phase. So it is not established a firm phase as right relief body to be believed by public with lack of independence, authority and specialty. Therefore the establishment of organization that can be the role as special ombudsman organization about sensitive and special matter like nuclear matter is necessary. Definite establishment element of ombudsman system is to introduce of congress type ombudsman element, to be permanent standing system ombudsman, to limit jurisdiction extent and have strong authority, to be able to access easily, to be composed of legal and nuclear specialist. One of important requirements of resident is compensation. So, based on the resident compensation theory about aversion equipment, ombudsman system should be established introducing the insurance theory through risk management as functional background for appropriate compensation. (authors)« less
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Carbide fuels for nuclear thermal propulsion
NASA Astrophysics Data System (ADS)
Matthews, R. B.; Blair, H. T.; Chidester, K. M.; Davidson, K. V.; Stark, W. E.; Storms, E. K.
1991-09-01
A renewed interest in manned exploration of space has revitalized interest in the potential for advancing nuclear rocket technology developed during the 1960's. Carbide fuel performance, melting point, stability, fabricability and compatibility are key technology issues for advanced Nuclear Thermal Propulsion reactors. The Rover fuels development ended with proven carbide fuel forms with demonstrated operating temperatures up to 2700 K for over 100 minutes. The next generation of nuclear rockets will start where the Rover technology ended, but with a more rigorous set of operating requirements including operating lifetime to 10 hours, operating temperatures greater that 3000 K, low fission product release, and compatibility. A brief overview of Rover/NERVA carbide fuel development is presented. A new fuel form with the highest potential combination of operating temperature and lifetime is proposed that consists of a coated uranium carbide fuel sphere with built-in porosity to contain fission products. The particles are dispersed in a fiber reinforced ZrC matrix to increase thermal shock resistance.
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A Nuclear Ramjet Flyer for Exploration of Jovian Atmosphere
NASA Astrophysics Data System (ADS)
Maise, G.; Powell, J.; Paniagua, J.; Lecat, R.
2001-01-01
We investigated the design, operation, and data gathering possibilities of a nuclear-powered ramjet flyer in the Jovian atmosphere. The MITEE nuclear rocket engine can be modified to operate as a ramjet in planetary atmospheres. (Note: MITEE is a compact, ultra-light-weight thermal nuclear rocket which uses hydrogen as the propellant.) To operate as a ramjet, MITEE requires a suitable inlet and diffuser to substitute for the propellant that is pumped from the supply tanks in a nuclear rocket engine. Such a ramjet would fly in the upper Jovian atmosphere, mapping in detail temperatures, pressures, compositions, lightning activity, and wind speeds in the highly turbulent equatorial zone and the Great Red Spot. The nuclear ramjet could operate for months because: (1) the Jovian atmosphere has unlimited propellant, (2) the MITEE nuclear reactor is a (nearly) unlimited power source, and (3) with few moving parts, mechanical wear should be minimal. This paper presents a conceptual design of a ramjet flyer and its nuclear engine. The flyer incorporates a swept-wing design with instruments located in the twin wing-tip pods (away from the radiation source and readily shielded, if necessary). The vehicle is 2 m long with a 2 m wingspan. Its mass is 220 kg, and its nominal flight Mach number is 1.5. Based on combined neutronic and thermal/hydraulic analyses, we calculated that the ambient pressure range over which the flyer can operate to be from about 0.04 to 4 (terrestrial) atmospheres. This altitude range encompasses the three uppermost cloud layers in the Jovian atmosphere: (1) the entire uppermost visible NH3 ice cloud layer (where lightning has been observed), (2) the entire NH4HS ice cloud layer, and (3) the upper portion of the H2O ice cloud layer.
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Comparison of ENDF/B-VII.1 and JEFF-3.2 in VVER-1000 operational data calculation
NASA Astrophysics Data System (ADS)
Frybort, Jan
2017-09-01
Safe operation of a nuclear reactor requires an extensive calculational support. Operational data are determined by full-core calculations during the design phase of a fuel loading. Loading pattern and design of fuel assemblies are adjusted to meet safety requirements and optimize reactor operation. Nodal diffusion code ANDREA is used for this task in case of Czech VVER-1000 reactors. Nuclear data for this diffusion code are prepared regularly by lattice code HELIOS. These calculations are conducted in 2D on fuel assembly level. There is also possibility to calculate these macroscopic data by Monte-Carlo Serpent code. It can make use of alternative evaluated libraries. All calculations are affected by inherent uncertainties in nuclear data. It is useful to see results of full-core calculations based on two sets of diffusion data obtained by Serpent code calculations with ENDF/B-VII.1 and JEFF-3.2 nuclear data including also decay data library and fission yields data. The comparison is based directly on fuel assembly level macroscopic data and resulting operational data. This study illustrates effect of evaluated nuclear data library on full-core calculations of a large PWR reactor core. The level of difference which results exclusively from nuclear data selection can help to understand the level of inherent uncertainties of such full-core calculations.
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NASA Technical Reports Server (NTRS)
Emrich, William J., Jr.
2014-01-01
To support the on-going nuclear thermal propulsion effort, a state-of-the-art non nuclear experimental test setup has been constructed to evaluate the performance characteristics of candidate fuel element materials and geometries in representative environments. The facility to perform this testing is referred to as the Nuclear Thermal Rocket Element Environment Simulator (NTREES). This device can simulate the environmental conditions (minus the radiation) to which nuclear rocket fuel components will be subjected during reactor operation. Prototypical fuel elements mounted in the simulator are inductively heated in such a manner so as to accurately reproduce the temperatures and heat fluxes which would normally occur as a result of nuclear fission in addition to being exposed to flowing hydrogen. Recent upgrades to NTREES now allow power levels 24 times greater than those achievable in the previous facility configuration. This higher power operation will allow near prototypical power densities and flows to finally be achieved in most prototypical fuel elements.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Jonathan Gray; Robert Anderson; Julio G. Rodriguez
Abstract: Identifying and understanding digital instrumentation and control (I&C) cyber vulnerabilities within nuclear power plants and other nuclear facilities, is critical if nation states desire to operate nuclear facilities safely, reliably, and securely. In order to demonstrate objective evidence that cyber vulnerabilities have been adequately identified and mitigated, a testbed representing a facility’s critical nuclear equipment must be replicated. Idaho National Laboratory (INL) has built and operated similar testbeds for common critical infrastructure I&C for over ten years. This experience developing, operating, and maintaining an I&C testbed in support of research identifying cyber vulnerabilities has led the Korean Atomic Energymore » Research Institute of the Republic of Korea to solicit the experiences of INL to help mitigate problems early in the design, development, operation, and maintenance of a similar testbed. The following information will discuss I&C testbed lessons learned and the impact of these experiences to KAERI.« less
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Operations research applications in nuclear energy
NASA Astrophysics Data System (ADS)
Johnson, Benjamin Lloyd
This dissertation consists of three papers; the first is published in Annals of Operations Research, the second is nearing submission to INFORMS Journal on Computing, and the third is the predecessor of a paper nearing submission to Progress in Nuclear Energy. We apply operations research techniques to nuclear waste disposal and nuclear safeguards. Although these fields are different, they allow us to showcase some benefits of using operations research techniques to enhance nuclear energy applications. The first paper, "Optimizing High-Level Nuclear Waste Disposal within a Deep Geologic Repository," presents a mixed-integer programming model that determines where to place high-level nuclear waste packages in a deep geologic repository to minimize heat load concentration. We develop a heuristic that increases the size of solvable model instances. The second paper, "Optimally Configuring a Measurement System to Detect Diversions from a Nuclear Fuel Cycle," introduces a simulation-optimization algorithm and an integer-programming model to find the best, or near-best, resource-limited nuclear fuel cycle measurement system with a high degree of confidence. Given location-dependent measurement method precisions, we (i) optimize the configuration of n methods at n locations of a hypothetical nuclear fuel cycle facility, (ii) find the most important location at which to improve method precision, and (iii) determine the effect of measurement frequency on near-optimal configurations and objective values. Our results correspond to existing outcomes but we obtain them at least an order of magnitude faster. The third paper, "Optimizing Nuclear Material Control and Accountability Measurement Systems," extends the integer program from the second paper to locate measurement methods in a larger, hypothetical nuclear fuel cycle scenario given fixed purchase and utilization budgets. This paper also presents two mixed-integer quadratic programming models to increase the precision of existing methods given a fixed improvement budget and to reduce the measurement uncertainty in the system while limiting improvement costs. We quickly obtain similar or better solutions compared to several intuitive analyses that take much longer to perform.
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78 FR 49262 - Sunshine Act Meeting
Federal Register 2010, 2011, 2012, 2013, 2014
2013-08-13
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting AGENCY: Defense Nuclear Facilities... given of the Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing described... associated with continued operation of aging defense nuclear [[Page 49263
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Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 2 2013-01-01 2013-01-01 false Environmental Effect of Renewing the Operating License of a Nuclear Power Plant B Appendix B to Subpart A of Part 51 Energy NUCLEAR REGULATORY COMMISSION... near these plants could be of moderate significance in some situations. See § 51.53(c)(3)(ii)(A...
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Code of Federal Regulations, 2013 CFR
2013-01-01
... operating licenses for nuclear power reactors, if the Commission has not found that a hearing is in the public interest, the Commission, the Director, Office of New Reactors or Director, Office of Nuclear... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...
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Code of Federal Regulations, 2012 CFR
2012-01-01
... this chapter for operating licenses for nuclear power reactors, if the Commission has not found that a..., Office of Nuclear Reactor Regulation, as appropriate will, prior to acting thereon, cause to be published... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...
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Code of Federal Regulations, 2010 CFR
2010-01-01
... this chapter for operating licenses for nuclear power reactors, if the Commission has not found that a..., Office of Nuclear Reactor Regulation, as appropriate will, prior to acting thereon, cause to be published... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...
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Code of Federal Regulations, 2014 CFR
2014-01-01
... operating licenses for nuclear power reactors, if the Commission has not found that a hearing is in the public interest, the Commission, the Director, Office of New Reactors or Director, Office of Nuclear... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...
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Code of Federal Regulations, 2011 CFR
2011-01-01
... this chapter for operating licenses for nuclear power reactors, if the Commission has not found that a..., Office of Nuclear Reactor Regulation, as appropriate will, prior to acting thereon, cause to be published... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...
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Nuclear Technology Series. Course 7: Reactor Operations.
ERIC Educational Resources Information Center
Center for Occupational Research and Development, Inc., Waco, TX.
This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…
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Detection of Nuclear Sources by UAV Teleoperation Using a Visuo-Haptic Augmented Reality Interface
Micconi, Giorgio; Caselli, Stefano; Benassi, Giacomo; Zambelli, Nicola; Bettelli, Manuele
2017-01-01
A visuo-haptic augmented reality (VHAR) interface is presented enabling an operator to teleoperate an unmanned aerial vehicle (UAV) equipped with a custom CdZnTe-based spectroscopic gamma-ray detector in outdoor environments. The task is to localize nuclear radiation sources, whose location is unknown to the user, without the close exposure of the operator. The developed detector also enables identification of the localized nuclear sources. The aim of the VHAR interface is to increase the situation awareness of the operator. The user teleoperates the UAV using a 3DOF haptic device that provides an attractive force feedback around the location of the most intense detected radiation source. Moreover, a fixed camera on the ground observes the environment where the UAV is flying. A 3D augmented reality scene is displayed on a computer screen accessible to the operator. Multiple types of graphical overlays are shown, including sensor data acquired by the nuclear radiation detector, a virtual cursor that tracks the UAV and geographical information, such as buildings. Experiments performed in a real environment are reported using an intense nuclear source. PMID:28961198
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Detection of Nuclear Sources by UAV Teleoperation Using a Visuo-Haptic Augmented Reality Interface.
Aleotti, Jacopo; Micconi, Giorgio; Caselli, Stefano; Benassi, Giacomo; Zambelli, Nicola; Bettelli, Manuele; Zappettini, Andrea
2017-09-29
A visuo-haptic augmented reality (VHAR) interface is presented enabling an operator to teleoperate an unmanned aerial vehicle (UAV) equipped with a custom CdZnTe-based spectroscopic gamma-ray detector in outdoor environments. The task is to localize nuclear radiation sources, whose location is unknown to the user, without the close exposure of the operator. The developed detector also enables identification of the localized nuclear sources. The aim of the VHAR interface is to increase the situation awareness of the operator. The user teleoperates the UAV using a 3DOF haptic device that provides an attractive force feedback around the location of the most intense detected radiation source. Moreover, a fixed camera on the ground observes the environment where the UAV is flying. A 3D augmented reality scene is displayed on a computer screen accessible to the operator. Multiple types of graphical overlays are shown, including sensor data acquired by the nuclear radiation detector, a virtual cursor that tracks the UAV and geographical information, such as buildings. Experiments performed in a real environment are reported using an intense nuclear source.
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Space nuclear reactors — A post-operational disposal strategy
NASA Astrophysics Data System (ADS)
Angelo, Joseph A.; Buden, David
If 100-kWe and multimegawatt-electric class space nuclear reactors are to play a significant role in humanity's push into cislunar and heliocentric space in the next millennium, the obvious advantages of space nuclear power plants should not be denied to space mission planners due to a failure to develop internationally-acceptable post-operational disposal strategies for spent reactor cores. This is true whether the space reactor has shut down at the end of its normal mission lifetime or in response to an onboard system failure/emergency which causes a premature mission termination. Up until now the great majority of aerospace nuclear safety efforts have concentrated on prelaunch, launch and reactor startup activities. In fact, with the exception of the development of the "nuclear safe orbit" (NSO) concept, little technical attention has yet been given to the post-operational disposal of future space reactors. This paper describes the technical alternatives available for the safe, acceptable disposal of space reactors that could be used in a wide variety of space applications in the 21st Century. Post-operational core radioactivity levels for typical advanced design (hundred kWe-class) space reactors are presented as a function of decay time and contrasted to the spent core radionuclide inventory of the SNAP-10A system, the only nuclear reactor operated in space by the United States. The role of a permanent space station, smart robotic systems, and an operating lunar base in support of spent core disposal strategies is also presented, including use of a selected portion of the lunar surface as an internationally-designated spent reactor core repository.
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ERIC Educational Resources Information Center
Hull, Daniel M.
A study was conducted to assist two-year postsecondary educational institutions in providing technical specialty courses for preparing nuclear technicians. As a result of project activities, curricula have been developed for five categories of nuclear technicians and operators: (1) radiation protection technician, (2) nuclear instrumentation and…
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-20
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; NRC-2008-0672] License Renewal Application for Indian Point Nuclear Generating Units 2 and 3; Entergy Nuclear Operations, Inc. AGENCY: Nuclear Regulatory Commission. ACTION: License renewal application; intent to prepare supplement to final...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-02
..., Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001..., Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2011-4557 Filed 3-1... NUCLEAR REGULATORY COMMISSION [Docket No. 50-282; NRC-2011-0040] Prairie Island Nuclear Generating...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-07-13
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; NRC-2012-0168] Entergy Nuclear Indian Point Unit 2, LLC, Entergy Nuclear Indian Point Unit 3, LLC, Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Units 2 and 3; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC...
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
This standard presents program criteria and implementation guidance for an operational configuration management program for DOE nuclear and non-nuclear facilities in the operational phase. Portions of this standard are also useful for other DOE processes, activities, and programs. This Part 1 contains foreword, glossary, acronyms, bibliography, and Chapter 1 on operational configuration management program principles. Appendices are included on configuration management program interfaces, and background material and concepts for operational configuration management.
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Nuclear Hybrid Energy Systems Initial Integrated Case Study Development and Analysis
DOE Office of Scientific and Technical Information (OSTI.GOV)
Harrison, Thomas J.; Greenwood, Michael Scott
The US Department of Energy Office of Nuclear Energy established the Nuclear Hybrid Energy System (NHES) project to develop a systematic, rigorous, technically accurate set of methods to model, analyze, and optimize the integration of dispatchable nuclear, fossil, and electric storage with an industrial customer. Ideally, the optimized integration of these systems will provide economic and operational benefits to the overall system compared to independent operation, and it will enhance the stability and responsiveness of the grid as intermittent, nondispatchable, renewable resources provide a greater share of grid power.
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NASA Technical Reports Server (NTRS)
Emrich, William J., Jr.
2017-01-01
To satisfy the Nuclear Cryogenic Propulsion Stage (NCPS) testing milestone, a graphite composite fuel element using a uranium simulant was received from the Oakridge National Lab and tested in the Nuclear Thermal Rocket Element Environmental Simulator (NTREES) at various operating conditions. The nominal operating conditions required to satisfy the milestone consisted of running the fuel element for a few minutes at a temperature of at least 2000 K with flowing hydrogen. This milestone test was successfully accomplished without incident.
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Multi-unit Operations in Non-Nuclear Systems: Lessons Learned for Small Modular Reactors
DOE Office of Scientific and Technical Information (OSTI.GOV)
OHara J. M.; Higgins, J.; DAgostino, A.
2012-01-17
The nuclear-power community has reached the stage of proposing advanced reactor designs to support power generation for decades to come. Small modular reactors (SMRs) are one approach to meet these energy needs. While the power output of individual reactor modules is relatively small, they can be grouped to produce reactor sites with different outputs. Also, they can be designed to generate hydrogen, or to process heat. Many characteristics of SMRs are quite different from those of current plants and may be operated quite differently. One difference is that multiple units may be operated by a single crew (or a singlemore » operator) from one control room. The U.S. Nuclear Regulatory Commission (NRC) is examining the human factors engineering (HFE) aspects of SMRs to support licensing reviews. While we reviewed information on SMR designs to obtain information, the designs are not completed and all of the design and operational information is not yet available. Nor is there information on multi-unit operations as envisioned for SMRs available in operating experience. Thus, to gain a better understanding of multi-unit operations we sought the lesson learned from non-nuclear systems that have experience in multi-unit operations, specifically refineries, unmanned aerial vehicles and tele-intensive care units. In this paper we report the lessons learned from these systems and the implications for SMRs.« less
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10 CFR 1.32 - Office of the Executive Director for Operations.
Code of Federal Regulations, 2014 CFR
2014-01-01
... of Nuclear Reactor Regulation, the Office of New Reactors, the Office of Nuclear Material Safety and... Section 1.32 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION... Nuclear Regulatory Research, the Office of Nuclear Security and Incident Response, and the NRC Regional...
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10 CFR 1.32 - Office of the Executive Director for Operations.
Code of Federal Regulations, 2012 CFR
2012-01-01
... of Nuclear Reactor Regulation, the Office of New Reactors, the Office of Nuclear Material Safety and... Section 1.32 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION... Nuclear Regulatory Research, the Office of Nuclear Security and Incident Response, and the NRC Regional...
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10 CFR 1.32 - Office of the Executive Director for Operations.
Code of Federal Regulations, 2011 CFR
2011-01-01
... of Nuclear Reactor Regulation, the Office of New Reactors, the Office of Nuclear Material Safety and... Section 1.32 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION... Nuclear Regulatory Research, the Office of Nuclear Security and Incident Response, and the NRC Regional...
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10 CFR 1.32 - Office of the Executive Director for Operations.
Code of Federal Regulations, 2013 CFR
2013-01-01
... of Nuclear Reactor Regulation, the Office of New Reactors, the Office of Nuclear Material Safety and... Section 1.32 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION... Nuclear Regulatory Research, the Office of Nuclear Security and Incident Response, and the NRC Regional...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-07-12
... NUCLEAR REGULATORY COMMISSION [NRC-2011-0150; Docket Nos. 50-003, 50-247, and 50-286; License Nos. DPR-5, DPR-26, and DPR-64] Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, Entergy Nuclear Operations, Inc.; Receipt of Request for Action Notice is hereby given that by petition...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-01-10
... Impact Statement for License Renewal of Nuclear Plants, Calvert Cliffs Nuclear Power Plant (NUREG-1437... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Environmental Assessment... Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...
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Psychology in nuclear power plants: an integrative approach to safety - general statement
DOE Office of Scientific and Technical Information (OSTI.GOV)
Shikiar, R.
Since the accident at the Three Mile Island nuclear power plant on March 28, 1979, the commercial nuclear industry in the United States has paid increasing attention to the role of humans in overall plant safety. As the regulatory body with primary responsibility for ensuring public health and safety involving nuclear operations, the United States Nuclear Regulatory Commission (NRC) has also become increasingly involved with the ''human'' side of nuclear operations. The purpose of this symposium is to describe a major program of research and technical assistance that the Pacific Northwest Laboratory is performing for the NRC that deals withmore » the issues of safety at nuclear power plants (NPPs). This program addresses safety from several different levels of analysis, which are all important within the context of an integrative approach to system safety.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Sklenka, L.; Rataj, J.; Frybort, J.
Research reactors play an important role in providing key personnel of nuclear power plants a hands-on experience from operation and experiments at nuclear facilities. Training of NPP (Nuclear Power Plant) staff is usually deeply theoretical with an extensive utilisation of simulators and computer visualisation. But a direct sensing of the reactor response to various actions can only improve the personnel awareness of important aspects of reactor operation. Training Reactor VR-1 and its utilization for training of NPP operators and other professionals from Czech Republic and Slovakia is described. Typical experimental exercises and good practices in organization of a training programmore » are demonstrated. (authors)« less
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NASA Astrophysics Data System (ADS)
Arkadov, G. V.; Zhukavin, A. P.; Kroshilin, A. E.; Parshikov, I. A.; Solov'ev, S. L.; Shishov, A. V.
2014-10-01
The article describes the "Virtual Digital VVER-Based Nuclear Power Plant" computerized system comprising a totality of verified initial data (sets of input data for a model intended for describing the behavior of nuclear power plant (NPP) systems in design and emergency modes of their operation) and a unified system of new-generation computation codes intended for carrying out coordinated computation of the variety of physical processes in the reactor core and NPP equipment. Experiments with the demonstration version of the "Virtual Digital VVER-Based NPP" computerized system has shown that it is in principle possible to set up a unified system of computation codes in a common software environment for carrying out interconnected calculations of various physical phenomena at NPPs constructed according to the standard AES-2006 project. With the full-scale version of the "Virtual Digital VVER-Based NPP" computerized system put in operation, the concerned engineering, design, construction, and operating organizations will have access to all necessary information relating to the NPP power unit project throughout its entire lifecycle. The domestically developed commercial-grade software product set to operate as an independently operating application to the project will bring about additional competitive advantages in the modern market of nuclear power technologies.
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77 FR 18873 - Sunshine Act Meeting
Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-28
.... Entergy Nuclear Generation Co. and Entergy Nuclear Operations, Inc. (Pilgrim Nuclear Power Station... will be made on a case-by-case basis. * * * * * This notice is distributed electronically to...
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Nuclear Data Evaluation Co-operation (WPEC) Nuclear Reaction Data Centers, NRDC (IAEA Vienna) EMPIRE , Nuclear Reaction Model Code Atlas of Neutron Resonances The Cross Section Evaluation Working Group (CSEWG
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10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 2 2010-01-01 2010-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...
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10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 2 2013-01-01 2013-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...
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10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.
Code of Federal Regulations, 2014 CFR
2014-01-01
... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...
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10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 2 2014-01-01 2014-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...
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10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 2 2011-01-01 2011-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...
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10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.
Code of Federal Regulations, 2013 CFR
2013-01-01
... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...
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10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.
Code of Federal Regulations, 2010 CFR
2010-01-01
... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...
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10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 2 2012-01-01 2012-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...
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10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.
Code of Federal Regulations, 2012 CFR
2012-01-01
... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...
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10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.
Code of Federal Regulations, 2011 CFR
2011-01-01
... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-16
..., University of Wisconsin Nuclear Reactor; Notice of Issuance of Environmental Assessment and Finding of No... operation of the University of Wisconsin Nuclear Reactor. This action is necessary to add supplemental... of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001...
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Integrating Nuclear Energy to Oilfield Operations – Two Case Studies
DOE Office of Scientific and Technical Information (OSTI.GOV)
Eric P. Robertson; Lee O. Nelson; Michael G. McKellar
2011-11-01
Fossil fuel resources that require large energy inputs for extraction, such as the Canadian oil sands and the Green River oil shale resource in the western USA, could benefit from the use of nuclear power instead of power generated by natural gas combustion. This paper discusses the technical and economic aspects of integrating nuclear energy with oil sands operations and the development of oil shale resources. A high temperature gas reactor (HTGR) that produces heat in the form of high pressure steam (no electricity production) was selected as the nuclear power source for both fossil fuel resources. Both cases weremore » based on 50,000 bbl/day output. The oil sands case was a steam-assisted, gravity-drainage (SAGD) operation located in the Canadian oil sands belt. The oil shale development was an in-situ oil shale retorting operation located in western Colorado, USA. The technical feasibility of the integrating nuclear power was assessed. The economic feasibility of each case was evaluated using a discounted cash flow, rate of return analysis. Integrating an HTGR to both the SAGD oil sands operation and the oil shale development was found to be technically feasible for both cases. In the oil sands case, integrating an HTGR eliminated natural gas combustion and associated CO2 emissions, although there were still some emissions associated with imported electrical power. In the in situ oil shale case, integrating an HTGR reduced CO2 emissions by 88% and increased natural gas production by 100%. Economic viabilities of both nuclear integrated cases were poorer than the non-nuclear-integrated cases when CO2 emissions were not taxed. However, taxing the CO2 emissions had a significant effect on the economics of the non-nuclear base cases, bringing them in line with the economics of the nuclear-integrated cases. As we move toward limiting CO2 emissions, integrating non-CO2-emitting energy sources to the development of energy-intense fossil fuel resources is becoming increasingly important. This paper attempts to reduce the barriers that have traditionally separated fossil fuel development and application of nuclear power and to promote serious discussion of ideas about hybrid energy systems.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Spudeck, R.E.
1983-01-01
Two weeks prior to the Three Mile Island accident, March 15, 1979, the Nuclear Regulatory Commission ordered five operating nuclear plants shut down in order to reexamine safety standards in these plants. Reports in the popular and trade press during this time suggested that these events, particularly the accident at Three Mile Island, caused investors in the securities of electric utilities that had nuclear-generation facilities to revise their risk perceptions. This study was designed to examine the impact of both the Nuclear Regulatory Commission order and the accident at Three Mile Island on investor risk perceptions. Selected categories of electricmore » utilities were chosen to examine any differential risk effects resulting from these events. An asset pricing model devoid of many of the restrictive assumptions of more familiar models was used to model investor behavior. The findings suggest that the events described did cause investors to revise upward their perceptions of systematic risk regarding different categories of electric utilities. More specifically, those electric utilities that were operating nuclear plants in 1979 experienced the largest and most sustained increase in systematic risk. However, electric utilities that in 1979 had no operating nuclear plants, but had planned and committed funds for nuclear plants in the future, also experienced increases in systematic risk.« less
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-01-22
... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3, Exemption 1.0 Background UniStar Nuclear Energy (UNE), on behalf of Calvert Cliffs Nuclear Project, LLC and UniStar Nuclear Operating Services...
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Simultaneous Thermal and Gamma Radiation Aging of Electrical Cable Polymers
DOE Office of Scientific and Technical Information (OSTI.GOV)
Fifield, Leonard S.
The polymers used for insulation in nuclear power plant electrical cables are susceptible to aging during long term operation. Elevated temperature is the primary contributor to changes in polymer structure that result loss of mechanical and electrical properties, but gamma radiation is also a significant source of degradation for polymers used within relevant plant locations. Despite many years of polymer degradation research, the combined effects of simultaneous exposure to thermal and radiation stress are not well understood. As nuclear operators contemplate and prepare for extended operations beyond initial license periods, a predictive understanding of exposure-based cable material degradation is becomingmore » an increasingly important input to safety, licensing, operations and economic decisions. We are focusing on carefully-controlled simultaneous thermal and gamma radiation accelerating aging and characterization of the most common nuclear cable polymers to understand the relative contributions of temperature, time, dose and dose rate to changes in cable polymer material structure and properties. Improved understanding of cable performance in long term operation will help support continued sustainable nuclear power generation.« less
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French Atomic Energy Commission Decommissioning Programme and Feedback Experience - 12230
DOE Office of Scientific and Technical Information (OSTI.GOV)
Guiberteau, Ph.; Nokhamzon, J.G.
Since the French Atomic and Alternatives Energy Commission (CEA) was founded in 1945 to carry out research programmes on use of nuclear, and its application France has set up and run various types of installations: research or prototypes reactors, process study or examination laboratories, pilot installations, accelerators, nuclear power plants and processing facilities. Some of these are currently being dismantled or must be dismantled soon so that the DEN, the Nuclear Energy Division, can construct new equipment and thus have available a range of R and D facilities in line with the issues of the nuclear industry of the future.more » Since the 1960's and 1970's in all its centres, the CEA has acquired experience and know-how through dismantling various nuclear facilities. The dismantling techniques are nowadays operational, even if sometimes certain specific developments are necessary to reduce the cost of operations. Thanks to availability of techniques and guarantees of dismantling programme financing now from two dedicated funds, close to euro 15,000 M for the next thirty years, for current or projected dismantling operations, the CEA's Nuclear Energy Division has been able to develop, when necessary, its immediate dismantling strategy. Currently, nearly thirty facilities are being dismantled by the CEA's Nuclear Energy Division operational units with industrial partners. Thus the next decade will see completion of the dismantling and radioactive clean-up of the Grenoble site and of the facilities on the Fontenay-aux-Roses site. By 2016, the dismantling of the UP1 plant at Marcoule, the largest dismantling work in France, will be well advanced, with all the process equipment dismantled. After an overview of the French regulatory framework, the paper will describe the DD and R (Decontamination Decommissioning and Remediation) strategy, programme and feedback experience inside the CEA's Nuclear Energy Division. A special feature of dismantling operations at the CEA comes from the diversity of facilities to be dismantled, which are predominantly research facilities and therefore have no series advantage. There is tremendous operating feedback, however. For more than twenty years in all its centres, the CEA has acquired experience and know-how through dismantling research reactors or critical models and laboratories or plants. The dismantling techniques are nowadays operational, even if sometimes certain specific developments are necessary to reduce the cost of operations. Thanks to availability of techniques and guarantees of dismantling programme financing from two dedicated funds, close to euro 15,000 Millions for the next thirty years, for current or projected dismantling operations, the Nuclear Energy Division has been able to develop, when necessary, its immediate dismantling strategy. Currently, nearly thirty facilities are being dismantled by the CEA's Nuclear Energy Division operational units with industrial partners. Thus the next decade will see completion of the dismantling and radioactive clean-up of the Grenoble site and of the facilities on the Fontenay-aux-Roses site. By 2020, the dismantling of the UP1 plant at Marcoule, one of the largest dismantling works in the world, will be well advanced, with all the process equipment dismantled. (authors)« less
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75 FR 33855 - Sunshine Federal Register Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2010-06-15
.... Entergy Nuclear Generation Co. and Entergy Nuclear Operations, Inc. (Pilgrim Nuclear Power Station) Remaining Issues from Pilgrim Watch Petition for Review (Tentative). b. Entergy Nuclear Generation Co. and...-case basis. * * * * * This notice is distributed electronically to subscribers. If you no longer wish...
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77 FR 17102 - Sunshine Federal Register Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-23
...) (Tentative). a. FirstEnergy Nuclear Operating Co. (Davis-Besse Nuclear Power Station, Unit 1), Appeal of LBP... NUCLEAR REGULATORY COMMISSION Sunshine Federal Register Notice AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission, [NRC-2012- 0002]. DATE: Week of March 26, 2012. PLACE: Commissioners...
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Chickamauga Reservoir 1992 fisheries monitoring cove rotenone results
DOE Office of Scientific and Technical Information (OSTI.GOV)
Kerley, B.L.
1993-06-01
The Tennessee Valley Authority (TVA) is required by the National Pollutant Discharge Elimination System (NPDES) Permit for Sequoyah Nuclear Plant (SQN) to conduct and report annually a nonradiological operational monitoring program to evaluate potential effects of SQN on Chickamauga Reservoir. This monitoring program was initially designed to identify potential changes in water quality and biological communities in Chickamauga Reservoir resulting from operation of SQU. Chickamauga Reservoir cove rotenone sampling has also been conducted as part of the preoperational monitoring program for Watts Bar Nuclear Plant (WBN) to evaluate the combined effects of operating two nuclear facilities on one reservoir oncemore » WBU becomes operational. The purpose of this report is to present results of cove rotenone sampling conducted on Chickamauga Reservoir in 1992.« less
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Radionuclide metrology research for nuclear site decommissioning
NASA Astrophysics Data System (ADS)
Judge, S. M.; Regan, P. H.
2017-11-01
The safe and cost-effective decommissioning of legacy nuclear sites relies on accurate measurement of the radioactivity content of the waste materials, so that the waste can be assigned to the most appropriate disposal route. Such measurements are a new challenge for the science of radionuclide metrology which was established largely to support routine measurements on operating nuclear sites and other applications such as nuclear medicine. In this paper, we provide a brief summary of the international measurement system that is established to enable nuclear site operators to demonstrate that measurements are accurate, independent and fit for purpose, and highlight some of the projects that are underway to adapt the measurement system to meet the changing demands from the industry.
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Tackling the nuclear manpower shortage: industry, educators must work together
DOE Office of Scientific and Technical Information (OSTI.GOV)
Witzig, W.
1981-10-01
A 50% decline in graduate enrollment and an increase to 50% of foreign nationals among the nuclear engineering students since 1973 at Pennsylvania State University is typical of national trends, which have led to the closing of 13 undergraduate programs across the country. Penn State's proximity to Three Mile Island had less effect than its interactions with high schools and utilities in keeping the nuclear program as strong as it is. Penn State operates three separate career programs to interest high school students in a nuclear career. Institute of Nuclear Power Operations (INPO) educational assistance reflects industry interest, but moremore » scholarships are needed to broaden student awareness. (DCK)« less
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75 FR 68630 - Sunshine Federal Register Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2010-11-08
...) (Tentative). a. Entergy Nuclear Generation Co. and Entergy Nuclear Operations, Inc. (Pilgrim Nuclear Power... reasonable accommodation will be made on a case-by-case basis. * * * * * This notice is distributed...
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Digital computer operation of a nuclear reactor
Colley, R.W.
1982-06-29
A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.
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Digital computer operation of a nuclear reactor
Colley, Robert W.
1984-01-01
A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.
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NASA Astrophysics Data System (ADS)
Simola, Kaisa; Laakso, Kari
1992-01-01
Eight years of operating experiences of 104 motor operated closing valves in different safety systems in nuclear power units were analyzed in a systematic way. The qualitative methods used were Failure Mode and Effect Analysis (FMEA) and Maintenance Effects and Criticality Analysis (MECA). These reliability engineering methods are commonly used in the design stage of equipment. The successful application of these methods for analysis and utilization of operating experiences was demonstrated.
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Economic Conditions and Factors Affecting New Nuclear Power Deployment
DOE Office of Scientific and Technical Information (OSTI.GOV)
Harrison, Thomas J.
2014-10-01
This report documents work performed in support of the US Department of Energy Office of Nuclear Energy’s Advanced Small Modular Reactor (AdvSMR) program. The report presents information and results from economic analyses to describe current electricity market conditions and those key factors that may impact the deployment of AdvSMRs or any other new nuclear power plants. Thus, this report serves as a reference document for DOE as it moves forward with its plans to develop advanced reactors, including AdvSMRs. For the purpose of this analysis, information on electricity markets and nuclear power plant operating costs will be combined to examinemore » the current state of the nuclear industry and the process required to successfully move forward with new nuclear power in general and AdvSMRs in particular. The current electricity market is generally unfavorable to new nuclear construction, especially in deregulated markets with heavy competition from natural gas and subsidized renewables. The successful and profitable operation of a nuclear power plant (or any power plant) requires the rate at which the electricity is sold to be sufficiently greater than the cost to operate. The wholesale rates in most US markets have settled into values that provide profits for most operating nuclear power plants but are too low to support the added cost of capital recovery for new nuclear construction. There is a strong geographic dependence on the wholesale rate, with some markets currently able to support new nuclear construction. However, there is also a strong geographic dependence on pronuclear public opinion; the areas where power prices are high tend to have unfavorable views on the construction of new nuclear power plants. The use of government-backed incentives, such as subsidies, can help provide a margin to help justify construction projects that otherwise may not seem viable. Similarly, low interest rates for the project will also add a positive margin to the economic analysis. In both cases, the profitable price point is decreased, making more markets open to profitable entry. Overall, the economic attractiveness of a nuclear power construction project is not only a function of its own costs, but a function of the market into which it is deployed. Many of the market characteristics are out of the control of the potential nuclear power plant operators. The decision-making process for the power industry in general is complicated by the short-term market volatility in both the wholesale electricity market and the commodity (natural gas) market. Decisions based on market conditions today may be rendered null and void in six months. With a multiple-year lead time, nuclear power plants are acutely vulnerable to market corrections.« less
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Proceedings of the Oak Ridge Electron Linear Accelerator (ORELA) Workshop
DOE Office of Scientific and Technical Information (OSTI.GOV)
Dunn, M.E.
2006-02-27
The Oak Ridge National Laboratory (ORNL) organized a workshop at ORNL July 14-15, 2005, to highlight the unique measurement capabilities of the Oak Ridge Electron Linear Accelerator (ORELA) facility and to emphasize the important role of ORELA for performing differential cross-section measurements in the low-energy resonance region that is important for nuclear applications such as nuclear criticality safety, nuclear reactor and fuel cycle analysis, stockpile stewardship, weapons research, medical diagnosis, and nuclear astrophysics. The ORELA workshop (hereafter referred to as the Workshop) provided the opportunity to exchange ideas and information pertaining to nuclear cross-section measurements and their importance for nuclearmore » applications from a variety of perspectives throughout the U.S. Department of Energy (DOE). Approximately 50 people, representing DOE, universities, and seven U.S. national laboratories, attended the Workshop. The objective of the Workshop was to emphasize the technical community endorsement for ORELA in meeting nuclear data challenges in the years to come. The Workshop further emphasized the need for a better understanding of the gaps in basic differential nuclear measurements and identified the efforts needed to return ORELA to a reliable functional measurement facility. To accomplish the Workshop objective, nuclear data experts from national laboratories and universities were invited to provide talks emphasizing the unique and vital role of the ORELA facility for addressing nuclear data needs. ORELA is operated on a full cost-recovery basis with no single sponsor providing complete base funding for the facility. Consequently, different programmatic sponsors benefit by receiving accurate cross-section data measurements at a reduced cost to their respective programs; however, leveraging support for a complex facility such as ORELA has a distinct disadvantage in that the programmatic funds are only used to support program-specific measurements. As a result, ORELA has not received base funding to support major upgrades and significant maintenance operations that are essential to keep the facility in a state of readiness over the long term. As a result, ORELA has operated on a ''sub-bare-minimum'' budget for the past 10 to 15 years, and the facility has not been maintained at a level for continued reliable operation for the long term. During the Workshop, Jerry McKamy (NNSA/NA-117) used a hospital patient metaphor that accurately depicts the facility status. ORELA is currently in the intensive care unit (ICU) on life support, and refurbishment efforts are needed to get the ''patient'' off life support and out to an ordinary hospital room. McKamy further noted that the DOE NCSP is planning to fund immediate refurbishment tasks ($1.5 M over three years) to help reestablish reliable ORELA operation (i.e., move ORELA from ICU to an ordinary hospital room). Furthermore, the NCSP will work to identify and carry out the actions needed to discharge ORELA from the ''hospital'' over the next five to seven years. In accordance with the Workshop objectives, the technical community publicly endorsed the need for a reliable ORELA facility that can meet current and future nuclear data needs. These Workshop proceedings provide the formal documentation of the technical community endorsement for ORELA. Furthermore, the proceedings highlight the past and current contributions that ORELA has made to the nuclear industry. The Workshop further emphasized the operational and funding problems that currently plague the facility, thereby limiting ORELA's operational reliability. Despite the recent operational problems, ORELA is a uniquely capable measurement facility that must be part of the overall U.S. nuclear data measurement portfolio in order to support current and emerging nuclear applications. The Workshop proceedings further emphasize that ORNL, the technical community, and programmatic sponsors are eager to see ORELA reestablish reliable measurement operation and be readily available to address nuclear data challenges in the United States.« less
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-07-07
... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Calvert Cliffs.... DPR-53 and DPR-69, for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (CCNPP), respectively... (ISFSI), currently held by Calvert Cliffs Nuclear Power Plant, LLC as owner and licensed operator...
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Emerging nuclear programs in Asia: The Phillipines, Thailand, Indonesia, and Pakistan
DOE Office of Scientific and Technical Information (OSTI.GOV)
Williams, M.L.
This article is a review of the potential for nuclear energy development in the developing nations of Pakistan, Indonesia, Thailand, and the Philippines. In each country, there is a substantial need for new generating capacity, and each is exploring the idea of having nuclear energy supply a meaningful portion of this new capacity. Of the four countries, only Pakistan is currently a nuclear operator, and one vintage CANDU plant in operation and the Chashma unit under construction. Thailand and Indonesia have ambitious plans to have 12 reactors in service by the year 2015.
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NASA Astrophysics Data System (ADS)
Ivanov, Yu. A.
2007-12-01
An analytical review is given of Russian and foreign measurement instruments employed in a system for automatically monitoring the water chemistry of the reactor coolant circuit and used in the development of projects of nuclear power stations equipped with VVER-1000 reactors and the nuclear station project AES 2006. The results of experience gained from the use of such measurement instruments at nuclear power stations operating in Russia and abroad are presented.
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75 FR 39057 - Sunshine Federal Register Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2010-07-07
... NUCLEAR REGULATORY COMMISSION [NRC-2010-0002] Sunshine Federal Register Notice Agency Holding the Meetings: Nuclear Regulatory Commission. Date: Weeks of July 5, 12, 19, 26, August 2, 9, 2010. Place... Licensing Board Initial Decision (Tentative). b. Entergy Nuclear Operations, Inc. (Indian Point Nuclear...
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77 FR 62539 - Sunshine Federal Register Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2012-10-15
... NUCLEAR REGULATORY COMMISSION Sunshine Federal Register Notice AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission [NRC-2012- 0002]. DATE: Weeks of October 8, 15, 22, 29, November 5, 12, 19... Meeting) (Tentative) a. Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-05-24
... Power Station, Unit 1; Exemption From Certain Security Requirements 1.0 Background Exelon Nuclear is the licensee and holder of Facility Operating License No. DPR-2 issued for Dresden Nuclear Power Station (DNPS... protection of licensed activities in nuclear power reactors against radiological sabotage,'' paragraph (b)(1...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-07-25
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-271, NRC-2011-0168] Vermont Yankee Nuclear Power... Regulatory Commission (NRC or the Commission) has granted the request of Vermont Yankee Nuclear Power Station... Operating License No. DPR-28 for the Vermont Yankee Nuclear Power Station, located in Vernon, Vermont. The...
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Code of Federal Regulations, 2011 CFR
2011-01-01
..., Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Federal and..., Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear... of this chapter, see § 2.106(d). (b) If the Director, Office of Nuclear Reactor Regulation, Director...
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Code of Federal Regulations, 2012 CFR
2012-01-01
..., Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Federal and..., Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear... of this chapter, see § 2.106(d). (b) If the Director, Office of Nuclear Reactor Regulation, Director...
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Kartashov,V.V.; Pratt,W.; Romanov, Y.A.
The Material Protection, Control and Accounting (MPC&A) Operations Monitoring (MOM) systems handling at the International Intergovernmental Organization - Joint Institute for Nuclear Research (JINR) is described in this paper. Category I nuclear material (plutonium and uranium) is used in JINR research reactors, facilities and for scientific and research activities. A monitoring system (MOM) was installed at JINR in April 2003. The system design was based on a vulnerability analysis, which took into account the specifics of the Institute. The design and installation of the MOM system was a collaborative effort between JINR, Brookhaven National Laboratory (BNL) and the U.S. Departmentmore » of Energy (DOE). Financial support was provided by DOE through BNL. The installed MOM system provides facility management with additional assurance that operations involving nuclear material (NM) are correctly followed by the facility personnel. The MOM system also provides additional confidence that the MPC&A systems continue to perform effectively.« less
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Intermediate-range nuclear forces (INF) treaty: an operational error
DOE Office of Scientific and Technical Information (OSTI.GOV)
Caldwell, W.B.
1988-05-12
The purpose of this paper is to examine the operational impact of the INF treaty and what it means for the future of NATO. At this writing, there is considerable debate going on as to whether or not the US Congress should ratify the INF treaty. The political issues are well known and under careful examination. A critical element that still needs to be addressed is the operational impact of the INF treaty. This area may have been neglected because nuclear weapons are viewed primarily as an element of deterrence. Therefore, their warfighting potential is given only minimal consideration. Thismore » paper begins with a discussion of the historical use of nuclear weapons in NATO's defensive Alliance. It follows through to the decision in 1979 to modernize NATO's nuclear force. This decision resulted in the deployment of the Pershing II and ground-launched cruise missile (GLCM) systems in Europe. The Soviet warfighting concept for Europe is addressed next to place the intermediate-range nuclear forces in their proper perspective. This is followed by a discussion on the operational implications of the INF treaty. The paper concludes by briefly mentioning a few of the defensive proposals for the post-INF period.« less
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Agarwal, Vivek; Buttles, John W.; Beaty, Lawrence H.; ...
2016-10-05
In the current competitive energy market, the nuclear industry is committed to lower the operations and maintenance cost; increase productivity and efficiency while maintaining safe and reliable operation. The present operating model of nuclear power plants is dependent on large technical staffs that put the nuclear industry at long-term economic disadvantage. Technology can play a key role in nuclear power plant configuration management in offsetting labor costs by automating manually performed plant activities. The technology being developed, tested, and demonstrated in this paper will enable the continued safe operation of today’s fleet of light water reactors by providing the technicalmore » means to monitor components in plants today that are only routinely monitored through manual activities. The wireless enabled valve position indicators that are the subject of this paper are able to provide a valid position indication available continuously, rather than only periodically. As a result, a real-time (online) availability of valve positions using an affordable technologies are vital to plant configuration when compared with long-term labor rates, and provide information that can be used for a variety of plant engineering, maintenance, and management applications.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Agarwal, Vivek; Buttles, John W.; Beaty, Lawrence H.
In the current competitive energy market, the nuclear industry is committed to lower the operations and maintenance cost; increase productivity and efficiency while maintaining safe and reliable operation. The present operating model of nuclear power plants is dependent on large technical staffs that put the nuclear industry at long-term economic disadvantage. Technology can play a key role in nuclear power plant configuration management in offsetting labor costs by automating manually performed plant activities. The technology being developed, tested, and demonstrated in this paper will enable the continued safe operation of today’s fleet of light water reactors by providing the technicalmore » means to monitor components in plants today that are only routinely monitored through manual activities. The wireless enabled valve position indicators that are the subject of this paper are able to provide a valid position indication available continuously, rather than only periodically. As a result, a real-time (online) availability of valve positions using an affordable technologies are vital to plant configuration when compared with long-term labor rates, and provide information that can be used for a variety of plant engineering, maintenance, and management applications.« less
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77 FR 18271 - Notice of Sunshine Act Meeting
Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-27
.... Affirmation Session (Public Meeting) (Tentative) a. FirstEnergy Nuclear Operating Co. (Davis-Besse Nuclear... NUCLEAR REGULATORY COMMISSION [NRC-2012-0002] Notice of Sunshine Act Meeting DATE: Weeks of March....m. Briefing on the Final Report of the Blue Ribbon Commission on America's Nuclear Future (Public...
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77 FR 13158 - Sunshine Act Meeting Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-05
... NUCLEAR REGULATORY COMMISSION [NRC-2012-0002] Sunshine Act Meeting Notice DATE: Weeks of March 5...-11-2 (Feb. 15, 2011), Docket No. 50-443-LR (Tentative) b. Entergy Nuclear Generation Co. and Entergy Nuclear Operations, Inc. (Pilgrim Nuclear Power Station), Commonwealth of Massachusetts' Notice of Appeal...
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48 CFR 970.4402-4 - Nuclear material transfers.
Code of Federal Regulations, 2014 CFR
2014-10-01
... 48 Federal Acquisition Regulations System 5 2014-10-01 2014-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...
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48 CFR 970.4402-4 - Nuclear material transfers.
Code of Federal Regulations, 2011 CFR
2011-10-01
... 48 Federal Acquisition Regulations System 5 2011-10-01 2011-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...
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48 CFR 970.4402-4 - Nuclear material transfers.
Code of Federal Regulations, 2013 CFR
2013-10-01
... 48 Federal Acquisition Regulations System 5 2013-10-01 2013-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...
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48 CFR 970.4402-4 - Nuclear material transfers.
Code of Federal Regulations, 2010 CFR
2010-10-01
... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...
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48 CFR 970.4402-4 - Nuclear material transfers.
Code of Federal Regulations, 2012 CFR
2012-10-01
... 48 Federal Acquisition Regulations System 5 2012-10-01 2012-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...
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Design reuse experience of space and hazardous operations robots
NASA Technical Reports Server (NTRS)
Oneil, P. Graham
1994-01-01
A comparison of design drivers for space and hazardous nuclear waste operating robots details similarities and differences in operations, performance and environmental parameters for these critical environments. The similarities are exploited to provide low risk system components based on reuse principles and design knowledge. Risk reduction techniques are used for bridging areas of significant differences. As an example, risk reduction of a new sensor design for nuclear environment operations is employed to provide upgradeable replacement units in a reusable architecture for significantly higher levels of radiation.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
D. Kokkinos
2005-04-28
The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophymore » on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory.« less
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Radiological survey of Ingalls Shipbuilding Division, Pascagoula, Mississippi, and environs
DOE Office of Scientific and Technical Information (OSTI.GOV)
Fowler, T.W.; Windham, S.T.; Callis, R.S.
1983-09-01
This report presents results of the survey conducted by EERF personnel to assess environmental radioactivity remaining from operations of nuclear-powered vessels at Ingalls Shipyard, Pascagoula, Mississippi. Since Ingalls Shipyard will no longer build or service nuclear powered ships and has completed the decommissioning of the nuclear support facilities, an additional purpose of the survey was to determine if there is any remaining radioactivity from previous operations which could contribute to significant population exposure.
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Savannah River Site nuclear materials management plan FY 2017-2031
DOE Office of Scientific and Technical Information (OSTI.GOV)
Magoulas, V.
The purpose of the Nuclear Materials Management Plan (herein referred to as “this Plan”) is to integrate and document the activities required to disposition the legacy and/or surplus Enriched Uranium (EU) and Plutonium (Pu) and other nuclear materials already stored or anticipated to be received by facilities at the Department of Energy (DOE) Savannah River Site (SRS) as well as the activities to support the DOE Tritium mission. It establishes a planning basis for EU and Pu processing operations in Environmental Management Operations (EMO) facilities through the end of their program missions and for the tritium through the National Nuclearmore » Security Administration (NNSA) Defense Programs (DP) facilities. Its development is a joint effort among the Department of Energy - Savannah River (DOE-SR), DOE – Environmental Management (EM), NNSA Office of Material Management and Minimization (M3), NNSA Savannah River Field Office (SRFO), and the Management and Operations (M&O) contractor, Savannah River Nuclear Solutions, LLC (SRNS). Life-cycle program planning for Nuclear Materials Stabilization and Disposition and the Tritium Enterprise may use this Plan as a basis for the development of the nuclear materials disposition scope and schedule. This Plan assumes full funding to accomplish the required project and operations activities. It is recognized that some aspects of this Plan are pre decisional with regard to National Environmental Policy Act (NEPA); in such cases new NEPA actions will be required.« less
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Role of Nuclear Pools of Aminoacyl-tRNA Synthetases in tRNA Nuclear Export
Azad, Abul K.; Stanford, David R.; Sarkar, Srimonti; Hopper, Anita K.
2001-01-01
Reports of nuclear tRNA aminoacylation and its role in tRNA nuclear export (Lund and Dahlberg, 1998; Sarkar et al., 1999; Grosshans et al., 2000a) have led to the prediction that there should be nuclear pools of aminoacyl-tRNA synthetases. We report that in budding yeast there are nuclear pools of tyrosyl-tRNA synthetase, Tys1p. By sequence alignments we predicted a Tys1p nuclear localization sequence and showed it to be sufficient for nuclear location of a passenger protein. Mutations of this nuclear localization sequence in endogenous Tys1p reduce nuclear Tys1p pools, indicating that the motif is also important for nucleus location. The mutations do not significantly affect catalytic activity, but they do cause defects in export of tRNAs to the cytosol. Despite export defects, the cells are viable, indicating that nuclear tRNA aminoacylation is not required for all tRNA nuclear export paths. Because the tRNA nuclear exportin, Los1p, is also unessential, we tested whether tRNA aminoacylation and Los1p operate in alternative tRNA nuclear export paths. No genetic interactions between aminoacyl-tRNA synthetases and Los1p were detected, indicating that tRNA nuclear aminoacylation and Los1p operate in the same export pathway or there are more than two pathways for tRNA nuclear export. PMID:11359929
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Role of nuclear pools of aminoacyl-tRNA synthetases in tRNA nuclear export.
Azad, A K; Stanford, D R; Sarkar, S; Hopper, A K
2001-05-01
Reports of nuclear tRNA aminoacylation and its role in tRNA nuclear export (Lund and Dahlberg, 1998; Sarkar et al., 1999; Grosshans et al., 20001) have led to the prediction that there should be nuclear pools of aminoacyl-tRNA synthetases. We report that in budding yeast there are nuclear pools of tyrosyl-tRNA synthetase, Tys1p. By sequence alignments we predicted a Tys1p nuclear localization sequence and showed it to be sufficient for nuclear location of a passenger protein. Mutations of this nuclear localization sequence in endogenous Tys1p reduce nuclear Tys1p pools, indicating that the motif is also important for nucleus location. The mutations do not significantly affect catalytic activity, but they do cause defects in export of tRNAs to the cytosol. Despite export defects, the cells are viable, indicating that nuclear tRNA aminoacylation is not required for all tRNA nuclear export paths. Because the tRNA nuclear exportin, Los1p, is also unessential, we tested whether tRNA aminoacylation and Los1p operate in alternative tRNA nuclear export paths. No genetic interactions between aminoacyl-tRNA synthetases and Los1p were detected, indicating that tRNA nuclear aminoacylation and Los1p operate in the same export pathway or there are more than two pathways for tRNA nuclear export.
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Shutdown Dose Rate Analysis for the long-pulse D-D Operation Phase in KSTAR
NASA Astrophysics Data System (ADS)
Park, Jin Hun; Han, Jung-Hoon; Kim, D. H.; Joo, K. S.; Hwang, Y. S.
2017-09-01
KSTAR is a medium size fully superconducting tokamak. The deuterium-deuterium (D-D) reaction in the KSTAR tokamak generates neutrons with a peak yield of 3.5x1016 per second through a pulse operation of 100 seconds. The effect of neutron generation from full D-D high power KSTAR operation mode to the machine, such as activation, shutdown dose rate, and nuclear heating, are estimated for an assurance of safety during operation, maintenance, and machine upgrade. The nuclear heating of the in-vessel components, and neutron activation of the surrounding materials have been investigated. The dose rates during operation and after shutdown of KSTAR have been calculated by a 3D CAD model of KSTAR with the Monte Carlo code MCNP5 (neutron flux and decay photon), the inventory code FISPACT (activation and decay photon) and the FENDL 2.1 nuclear data library.
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A program for preserving and advancing nuclear power in the USA
DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
1988-05-01
In the USA, utilities are very unlikely to begin ordering any new nuclear plants for use before the year 2000. Too many obstacles currently exist. On the other hand, long-term influences ultimately will force construction of more nuclear units. The problem is whether to do nothing now, and wait until economic forces dictate action, or begin meaningful preparations for the future. Approximately 100 nuclear plants currently are operating in the USA and another dozen will start up within the next few years. Completion of those plants will mark the end of new startups for more than a decade to come.more » Many nuclear facilities have already operated for 10 to 20 years, and in some cases longer. While the average operating lifetime of nuclear stations has yet to be determined, 30 to 50 years is usually assumed. Therefore, as plants age, decommissioning will be necessary and the number of operating units will steadily decline. Nuclear energy production will peak (after new startups) at approximately 20 percent of total national electricity production and, as decommissioning accelerates, will decline towards zero during the first few decades of the next century. All types of power plants age and must eventually be replaced. Furthermore, even taking into account modest growth and ever improving conservation, increasing demand will require the building of several hundred new electrical generating facilities during the next several decades. What types of generating plants will be built is not clear. Will coal satisfy all our needs? Most unlikely. Oil? Out of the question. Natural gas? A share. Hydro? Few new dams will be built. Passive energies, such as solar? A minor fraction. Do without nuclear power? Most unlikely.« less
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Radionuclide Basics: Plutonium
Plutonium (chemical symbol Pu) is a radioactive metal. Plutonium is considered a man-made element. Plutonium-239 is used to make nuclear weapons. Pu-239 and Pu-240 are byproducts of nuclear reactor operations and nuclear bomb explosions.
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-06
...- 2010-0373] Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos... and DPR-25 for Dresden 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...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-07-08
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-244; Docket No. 72-67] R.E. Ginna Nuclear Power Plant, LLC, R.E. Ginna Nuclear Power Plant, R.E. Ginna Independent Spent Fuel Storage Installation; Notice of... Facility Operating License No. DPR-18, for the R.E. Ginna Nuclear Power Plant (Ginna), currently held by R...
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Mahe, Charly; Chabal, Caroline
2013-07-01
The CEA has developed many compact characterization tools to follow sensitive operations in a nuclear environment. Usually, these devices are made to carry out radiological inventories, to prepare nuclear interventions or to supervise some special operations. These in situ measurement techniques mainly take place at different stages of clean-up operations and decommissioning projects, but they are also in use to supervise sensitive operations when the nuclear plant is still operating. In addition to this, such tools are often associated with robots to access very highly radioactive areas, and thus can be used in accident situations. Last but not least, themore » radiological data collected can be entered in 3D calculation codes used to simulate the doses absorbed by workers in real time during operations in a nuclear environment. Faced with these ever-greater needs, nuclear measurement instrumentation always has to involve on-going improvement processes. Firstly, this paper will describe the latest developments and results obtained in both gamma and alpha imaging techniques. The gamma camera has been used by the CEA since the 1990's and several changes have made this device more sensitive, more compact and more competitive for nuclear plant operations. It is used to quickly identify hot spots, locating irradiating sources from 50 keV to 1500 keV. Several examples from a wide field of applications will be presented, together with the very latest developments. The alpha camera is a new camera used to see invisible alpha contamination on several kinds of surfaces. The latest results obtained allow real time supervision of a glove box cleaning operation (for {sup 241}Am contamination). The detection principle as well as the main trials and results obtained will be presented. Secondly, this paper will focus on in situ gamma spectrometry methods developed by the CEA with compact gamma spectrometry probes (CdZnTe, LaBr{sub 3}, NaI, etc.). The radiological data collected is used to quantify the activity of hot spots and can also then be entered in 3D models of nuclear plants to simulate intervention scenarios. Recent developments and results will be presented regarding this. Finally, thanks to a large amount of feedback, the interest of using complementary measurements will be discussed. In fact, the recent use of 3D simulation codes requires very accurate knowledge of nuclear plant radiological data. The use of coupled devices such as imaging devices, (gamma and alpha cameras), gamma spectrometry, dose rate mapping, collimated / un-collimated measurements and many other physical values gives an approach to the radiological knowledge of a process or plant with the lowest possible uncertainty. In line with this, the paper will conclude with the future developments and trials that could be assessed in that field of application. (authors)« less
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-07
...; NRC-2013-0245] In the Matter of Exelon Generation Company, LLC; Dresden Nuclear Power Station... licenses authorize the operation of the Dresden Nuclear Power Station (Dresden Station) in accordance with... actions described below will be taken at Dresden Nuclear Power Station and other nuclear plants in Exelon...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-02-20
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-295 and 50-304; NRC-2013-0034] Zion Nuclear Power Station, Units 1 and 2; ZionSolutions, LLC; Consideration of Indirect Transfer AGENCY: Nuclear Regulatory... the indirect transfer of Facility Operating License Nos. DPR-39 and DPR-48 for Zion Nuclear Power...
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Code of Federal Regulations, 2012 CFR
2012-01-01
..., systems and components for nuclear power reactors. 50.69 Section 50.69 Energy NUCLEAR REGULATORY..., systems and components for nuclear power reactors. (a) Definitions. Risk-Informed Safety Class (RISC)-1... holder of a license to operate a light water reactor (LWR) nuclear power plant under this part; a holder...
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Code of Federal Regulations, 2013 CFR
2013-01-01
..., systems and components for nuclear power reactors. 50.69 Section 50.69 Energy NUCLEAR REGULATORY..., systems and components for nuclear power reactors. (a) Definitions. Risk-Informed Safety Class (RISC)-1... holder of a license to operate a light water reactor (LWR) nuclear power plant under this part; a holder...
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Code of Federal Regulations, 2014 CFR
2014-01-01
..., systems and components for nuclear power reactors. 50.69 Section 50.69 Energy NUCLEAR REGULATORY..., systems and components for nuclear power reactors. (a) Definitions. Risk-Informed Safety Class (RISC)-1... holder of a license to operate a light water reactor (LWR) nuclear power plant under this part; a holder...
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Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 2 2014-01-01 2014-01-01 false Illustrative List of Nuclear Reactor Equipment Under NRC... List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note: A nuclear reactor... core of a nuclear reactor and capable of withstanding the operating pressure of the primary coolant. (2...
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Revitalizing Nuclear Operations in the Joint Environment
2014-02-01
height of the Cold War, US schol - ars and joint operational planners were working simultaneously on weapons development and operational art to employ...leadership’s large-target- category withholds thought necessary to maintain stability in a strategic crisis. The inclusion of nuclear effects and...escalation. The inclusion of these points in tomorrow’s doctrine as well as an intellec- tual discussion on the topic will inform Joint Staff planners
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Method of controlling crystallite size in nuclear-reactor fuels
Lloyd, Milton H.; Collins, Jack L.; Shell, Sam E.
1985-01-01
Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.
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77 FR 20853 - Entergy Nuclear Operations, Inc.; Establishment of Atomic Safety and Licensing Board
Federal Register 2010, 2011, 2012, 2013, 2014
2012-04-06
... Operations, Inc.; Establishment of Atomic Safety and Licensing Board Pursuant to delegation by the Commission... Atomic Safety and Licensing Board (Board) is being established to preside over the following proceeding... administrative judges: Ann Marshall Young, Chair, Atomic Safety and Licensing Board Panel, U.S. Nuclear...
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75 FR 53985 - Southern Nuclear Operating Company Establishment of Atomic Safety And Licensing Board
Federal Register 2010, 2011, 2012, 2013, 2014
2010-09-02
...] Southern Nuclear Operating Company Establishment of Atomic Safety And Licensing Board Pursuant to..., notice is hereby given that an Atomic Safety and Licensing Board (Board) is being established to preside...). The Board is comprised of the following administrative judges: G. Paul Bollwerk, III, Chairman, Atomic...
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78 FR 73898 - Operator Licensing Examination Standards for Power Reactors
Federal Register 2010, 2011, 2012, 2013, 2014
2013-12-09
... Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Draft NUREG; request for comment. SUMMARY: The U.S..., Revision 10, ``Operator Licensing Examination Standards for Power Reactors.'' DATES: Submit comments [email protected] . Both of the Office of New Reactors; or Timothy Kolb, Office of Nuclear Reactor Regulation, U...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-11-21
... expressed his belief that Entergy deliberately mismanaged its decommissioning trust funds and knowingly provided false financial documentation supporting filings before the Commission and that the NRC staff was... that amended the original petition, the Petitioner expressed his belief that, because the NRC's...
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10 CFR 51.53 - Postconstruction environmental reports.
Code of Federal Regulations, 2014 CFR
2014-01-01
... renewal of a license to operate a nuclear power plant under part 54 of this chapter shall submit with its... for a nuclear power reactor shall submit this report only in connection with the first licensing action authorizing full-power operation. In this report, the applicant shall discuss the same matters...
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Method of controlling crystallite size in nuclear-reactor fuels
Lloyd, M.H.; Collins, J.L.; Shell, S.E.
Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.
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75 FR 15746 - Entergy Operations, Inc., Waterford Steam Electric Station, Unit 3; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-30
... operating nuclear power plants, but noted that the Commission's regulations provide mechanisms for..., letter from R. W. Borchardt, NRC, to M. S. Fertel, Nuclear Energy Institute). The licensee's request for..., the Commission) now or hereafter in effect. The facility consists of one pressurized-water reactor...
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Human Error: The Stakes Are Raised.
ERIC Educational Resources Information Center
Greenberg, Joel
1980-01-01
Mistakes related to the operation of nuclear power plants and other technologically complex systems are discussed. Recommendations are given for decreasing the chance of human error in the operation of nuclear plants. The causes of the Three Mile Island incident are presented in terms of the human error element. (SA)
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-23
... NUCLEAR REGULATORY COMMISSION [NRC-2010-0110; 50-382] Entergy Operations, Inc.; Waterford Steam Electric Station, Unit 3 Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear... the Waterford Steam Electric Station, Unit 3 (Waterford 3), located in St. Charles Parish, Louisiana...
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Nuclear Safety Information Center, Its Products and Services
ERIC Educational Resources Information Center
Buchanan, J. R.
1970-01-01
The Nuclear Safety Information Center (NSIC) serves as a focal point for the collection, analysis and dissemination of information related to safety problems encountered in the design, analysis, and operation of nuclear facilities. (Author/AB)
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Experience with ALARA and ALARA procedures in a nuclear power plant
DOE Office of Scientific and Technical Information (OSTI.GOV)
Abrahamse, J.C.
1995-03-01
The nuclear power plant Borssele is a Siemens two-loop Pressurized Water Reactor having a capacity of 480 MWe and in operation since 1973. The nuclear power plant Borssle is located in the southwest of the Netherlands, near the Westerschelde River. In the first nine years of operation the radiation level in the primary system increased, reaching a maximum in 1983. The most important reason for this high radiation level was the cobalt content of the grid assemblies of the fuel elements. After resolving this problem, the radiation level decreased to a level comparable with that of other nuclear power plants.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Krebs, H., E-mail: hermann.krebs@rub.de; Epelbaum, E., E-mail: evgeny.epelbaum@rub.de; Kavli Institute for Theoretical Physics, University of California, Santa Barbara, CA 93016
We present the complete derivation of the nuclear axial charge and current operators as well as the pseudoscalar operators to fourth order in the chiral expansion relative to the dominant one-body contribution using the method of unitary transformation. We demonstrate that the unitary ambiguity in the resulting operators can be eliminated by the requirement of renormalizability and by matching of the pion-pole contributions to the nuclear forces. We give expressions for the renormalized single-, two- and three-nucleon contributions to the charge and current operators and pseudoscalar operators including the relevant relativistic corrections. We also verify explicitly the validity of themore » continuity equation.« less
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-04-29
... Supplemental Environmental Impact Statement for the Nuclear Facility Portion of the Chemistry and Metallurgy... Draft Supplemental Environmental Impact Statement for the Nuclear Facility Portion of the Chemistry and... alternatives for constructing and operating the nuclear facility (NF) portion of the Chemistry and Metallurgy...
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NUCLEAR REACTOR CONTROL SYSTEM
Epler, E.P.; Hanauer, S.H.; Oakes, L.C.
1959-11-01
A control system is described for a nuclear reactor using enriched uranium fuel of the type of the swimming pool and other heterogeneous nuclear reactors. Circuits are included for automatically removing and inserting the control rods during the course of normal operation. Appropriate safety circuits close down the nuclear reactor in the event of emergency.
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10 CFR 50.101 - Retaking possession of special nuclear material.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 1 2013-01-01 2013-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...
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10 CFR 50.101 - Retaking possession of special nuclear material.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 1 2011-01-01 2011-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...
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10 CFR 50.101 - Retaking possession of special nuclear material.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 1 2014-01-01 2014-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...
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10 CFR 50.101 - Retaking possession of special nuclear material.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 1 2010-01-01 2010-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...
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10 CFR 50.101 - Retaking possession of special nuclear material.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 1 2012-01-01 2012-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-09
... nuclear power plants, but noted that the Commission's regulations provide mechanisms for individual... from R. W. Borchardt, NRC, to M. S. Fertel, Nuclear Energy Institute). The licensee's request for an... Regulatory Commission (NRC, the Commission) now or hereafter in effect. The facility consists of two...
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Information Services at the Nuclear Safety Analysis Center.
ERIC Educational Resources Information Center
Simard, Ronald
This paper describes the operations of the Nuclear Safety Analysis Center. Established soon after an accident at the Three Mile Island nuclear power plant near Harrisburg, Pennsylvania, its efforts were initially directed towards a detailed analysis of the accident. Continuing functions include: (1) the analysis of generic nuclear safety issues,…
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Code of Federal Regulations, 2014 CFR
2014-01-01
... authorization means the authorization provided by the Director of New Reactors or the Director of Nuclear... identical nuclear reactors (modules) and each module is a separate nuclear reactor capable of being operated... nuclear power reactor of the type described in 10 CFR 50.22. The approval may be for either the final...
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Code of Federal Regulations, 2011 CFR
2011-01-01
... authorization means the authorization provided by the Director of New Reactors or the Director of Nuclear... identical nuclear reactors (modules) and each module is a separate nuclear reactor capable of being operated... nuclear power reactor of the type described in 10 CFR 50.22. The approval may be for either the final...
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Code of Federal Regulations, 2013 CFR
2013-01-01
... authorization means the authorization provided by the Director of New Reactors or the Director of Nuclear... identical nuclear reactors (modules) and each module is a separate nuclear reactor capable of being operated... nuclear power reactor of the type described in 10 CFR 50.22. The approval may be for either the final...
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Code of Federal Regulations, 2012 CFR
2012-01-01
... authorization means the authorization provided by the Director of New Reactors or the Director of Nuclear... identical nuclear reactors (modules) and each module is a separate nuclear reactor capable of being operated... nuclear power reactor of the type described in 10 CFR 50.22. The approval may be for either the final...
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DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
The New York Power Authority (NYPA) and Entergy Corp. of New Orleans, La., announced recently the signing of a memorandum of understanding as a step toward a contract for Entergy to provide management services to NYPA`s two nuclear power plants. The agreement is the first of its kind. NYPA is the nation`s largest state-owned electric utility and supplier of one-quarter of New York`s electricity. Its nuclear plants are Indian Point 3 (IP3) in Buchanan, Westchester County, and James A. FitzPatrick in Scriba, Oswego County. Entergy is a utility holding company and its subsidiary, Entergy Operations Inc., is widely recognized asmore » one of the leading nuclear operators in the United States. {open_quotes}NYPA`s nuclear plants are assets that belong to the people of New York,{close_quotes} said C.D. {open_quotes}Rapp{close_quotes} Rappleyea, NYPA`s chairman and CEO. {open_quotes}Our alliance with Entergy can provide the people of this state with added assurance that these plants will operate with the highest level of safety and efficiency.{close_quotes} FitzPatrick, an 800 MW boiling water reactor, has operated since 1975 and IP3, a 980 MW pressurized water reactor, since 1976. Although both are currently running well, they have had problems in recent years, and IP3 is on the US Nuclear Regulatory Commission`s (NRC) list of plants requiring increased regulatory attention. Entergy operated both types of reactors, has three single-unit sites like NYPA`s and is experienced in operating plants for different utility owners.« less
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The American nuclear construction craftsmen: Will we be ready to build again
DOE Office of Scientific and Technical Information (OSTI.GOV)
Bravo, R.
1990-01-01
The present state of nuclear plant maintenance and operations support reflects sexual, ethnic, and radical integration; continued educational advances; some computer literacy; mixed trades in maintenance; detailed training for maintenance and operations work in the operating plant; plant safety awareness and respect; need for top-quality, take the time to do it right mentality; and planning. With no new nuclear construction, what will be the specific talents, focus, and contributions that the craftsmen can be expected to bring to the project To be prepared to successfully manage the next generation of nuclear plant construction, the industry must be acutely aware ofmore » the needs of the labor pool. To be aware of the needs requires an intimate knowledge of the present state of the craft talent, the changed expectations of their contributions, and the effects of new technologies, materials, methods, and individuals that will be used to design and build.« less
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Khoma, Mykhaylo; Jaquet, Ralph
2017-09-21
The kinetic energy operator for triatomic molecules with coordinate or distance-dependent nuclear masses has been derived. By combination of the chain rule method and the analysis of infinitesimal variations of molecular coordinates, a simple and general technique for the construction of the kinetic energy operator has been proposed. The asymptotic properties of the Hamiltonian have been investigated with respect to the ratio of the electron and proton mass. We have demonstrated that an ad hoc introduction of distance (and direction) dependent nuclear masses in Cartesian coordinates preserves the total rotational invariance of the problem. With the help of Wigner rotation functions, an effective Hamiltonian for nuclear motion can be derived. In the derivation, we have focused on the effective trinuclear Hamiltonian. All necessary matrix elements are given in closed analytical form. Preliminary results for the influence of non-adiabaticity on vibrational band origins are presented for H 3 + .
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Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 2 2012-01-01 2012-01-01 false Illustrative List of Nuclear Reactor Equipment Under NRC... List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note—A nuclear reactor basically... nuclear reactor and capable of withstanding the operating pressure of the primary coolant. (2) On-line (e...
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Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 2 2013-01-01 2013-01-01 false Illustrative List of Nuclear Reactor Equipment Under NRC... List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note—A nuclear reactor basically... nuclear reactor and capable of withstanding the operating pressure of the primary coolant. (2) On-line (e...
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Bimodal Nuclear Thermal Rocket Analysis Developments
NASA Technical Reports Server (NTRS)
Belair, Michael; Lavelle, Thomas; Saimento, Charles; Juhasz, Albert; Stewart, Mark
2014-01-01
Nuclear thermal propulsion has long been considered an enabling technology for human missions to Mars and beyond. One concept of operations for these missions utilizes the nuclear reactor to generate electrical power during coast phases, known as bimodal operation. This presentation focuses on the systems modeling and analysis efforts for a NERVA derived concept. The NERVA bimodal operation derives the thermal energy from the core tie tube elements. Recent analysis has shown potential temperature distributions in the tie tube elements that may limit the thermodynamic efficiency of the closed Brayton cycle used to generate electricity with the current design. The results of this analysis are discussed as well as the potential implications to a bimodal NERVA type reactor.
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Upgrading the fuel-handling machine of the Novovoronezh nuclear power plant unit no. 5
NASA Astrophysics Data System (ADS)
Terekhov, D. V.; Dunaev, V. I.
2014-02-01
The calculation of safety parameters was carried out in the process of upgrading the fuel-handling machine (FHM) of the Novovoronezh nuclear power plant (NPP) unit no. 5 based on the results of quantitative safety analysis of nuclear fuel transfer operations using a dynamic logical-and-probabilistic model of the processing procedure. Specific engineering and design concepts that made it possible to reduce the probability of damaging the fuel assemblies (FAs) when performing various technological operations by an order of magnitude and introduce more flexible algorithms into the modernized FHM control system were developed. The results of pilot operation during two refueling campaigns prove that the total reactor shutdown time is lowered.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Kenneth Thomas
2012-02-01
Life extension beyond 60 years for the U.S operating nuclear fleet requires that instrumentation and control (I&C) systems be upgraded to address aging and reliability concerns. It is impractical for the legacy systems based on 1970's vintage technology operate over this extended time period. Indeed, utilities have successfully engaged in such replacements when dictated by these operational concerns. However, the replacements have been approached in a like-for-like manner, meaning that they do not take advantage of the inherent capabilities of digital technology to improve business functions. And so, the improvement in I&C system performance has not translated to bottom-line performancemore » improvement for the fleet. Therefore, wide-scale modernization of the legacy I&C systems could prove to be cost-prohibitive unless the technology is implemented in a manner to enable significant business innovation as a means of off-setting the cost of upgrades. A Future Vision of a transformed nuclear plant operating model based on an integrated digital environment has been developed as part of the Advanced Instrumentation, Information, and Control (II&C) research pathway, under the Light Water Reactor (LWR) Sustainability Program. This is a research and development program sponsored by the U.S. Department of Energy (DOE), performed in close collaboration with the nuclear utility industry, to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. DOE's program focus is on longer-term and higher-risk/reward research that contributes to the national policy objectives of energy security and environmental security . The Advanced II&C research pathway is being conducted by the Idaho National Laboratory (INL). The Future Vision is based on a digital architecture that encompasses all aspects of plant operations and support, integrating plant systems, plant work processes, and plant workers in a seamless digital environment to enhance nuclear safety, increase productivity, and improve overall plant performance. The long-term goal is to transform the operating model of the nuclear power plants (NPP)s from one that is highly reliant on a large staff performing mostly manual activities to an operating model based on highly integrated technology with a smaller staff. This digital transformation is critical to addressing an array of issues facing the plants, including aging of legacy analog systems, potential shortage of technical workers, ever-increasing expectations for nuclear safety improvement, and relentless pressure to reduce cost. The Future Vision is based on research is being conducted in the following major areas of plant function: (1) Highly integrated control rooms; (2) Highly automated plant; (3) Integrated operations; (4) Human performance improvement for field workers; and (5) Outage safety and efficiency. Pilot projects will be conducted in each of these areas as the means for industry to collectively integrate these new technologies into nuclear plant work activities. The pilot projects introduce new digital technologies into the nuclear plant operating environment at host operating plants to demonstrate and validate them for production usage. In turn, the pilot project technologies serve as the stepping stones to the eventual seamless digital environment as described in the Future Vision.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Kenneth Thomas; Bruce Hallbert
2013-02-01
Life extension beyond 60 years for the U.S operating nuclear fleet requires that instrumentation and control (I&C) systems be upgraded to address aging and reliability concerns. It is impractical for the legacy systems based on 1970’s vintage technology operate over this extended time period. Indeed, utilities have successfully engaged in such replacements when dictated by these operational concerns. However, the replacements have been approached in a like-for-like manner, meaning that they do not take advantage of the inherent capabilities of digital technology to improve business functions. And so, the improvement in I&C system performance has not translated to bottom-line performancemore » improvement for the fleet. Therefore, wide-scale modernization of the legacy I&C systems could prove to be cost-prohibitive unless the technology is implemented in a manner to enable significant business innovation as a means of off-setting the cost of upgrades. A Future Vision of a transformed nuclear plant operating model based on an integrated digital environment has been developed as part of the Advanced Instrumentation, Information, and Control (II&C) research pathway, under the Light Water Reactor (LWR) Sustainability Program. This is a research and development program sponsored by the U.S. Department of Energy (DOE), performed in close collaboration with the nuclear utility industry, to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. DOE’s program focus is on longer-term and higher-risk/reward research that contributes to the national policy objectives of energy security and environmental security . The Advanced II&C research pathway is being conducted by the Idaho National Laboratory (INL). The Future Vision is based on a digital architecture that encompasses all aspects of plant operations and support, integrating plant systems, plant work processes, and plant workers in a seamless digital environment to enhance nuclear safety, increase productivity, and improve overall plant performance. The long-term goal is to transform the operating model of the nuclear power plants (NPP)s from one that is highly reliant on a large staff performing mostly manual activities to an operating model based on highly integrated technology with a smaller staff. This digital transformation is critical to addressing an array of issues facing the plants, including aging of legacy analog systems, potential shortage of technical workers, ever-increasing expectations for nuclear safety improvement, and relentless pressure to reduce cost. The Future Vision is based on research is being conducted in the following major areas of plant function: 1. Highly integrated control rooms 2. Highly automated plant 3. Integrated operations 4. Human performance improvement for field workers 5. Outage safety and efficiency. Pilot projects will be conducted in each of these areas as the means for industry to collectively integrate these new technologies into nuclear plant work activities. The pilot projects introduce new digital technologies into the nuclear plant operating environment at host operating plants to demonstrate and validate them for production usage. In turn, the pilot project technologies serve as the stepping stones to the eventual seamless digital environment as described in the Future Vision.« less
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Improved pulse shape discriminator for fast neutron-gamma ray detection system
NASA Technical Reports Server (NTRS)
Lockwood, J. A.; St. Onge, R.
1969-01-01
Discriminator in nuclear particle detection system distinguishes nuclear particle type and energy among many different nuclear particles. Discriminator incorporates passive, linear circuit elements so that it will operate over a wide dynamic range.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Cui, Yonggang
In implementation of nuclear safeguards, many different techniques are being used to monitor operation of nuclear facilities and safeguard nuclear materials, ranging from radiation detectors, flow monitors, video surveillance, satellite imagers, digital seals to open source search and reports of onsite inspections/verifications. Each technique measures one or more unique properties related to nuclear materials or operation processes. Because these data sets have no or loose correlations, it could be beneficial to analyze the data sets together to improve the effectiveness and efficiency of safeguards processes. Advanced visualization techniques and machine-learning based multi-modality analysis could be effective tools in such integratedmore » analysis. In this project, we will conduct a survey of existing visualization and analysis techniques for multi-source data and assess their potential values in nuclear safeguards.« less
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RUSSIAN-ORIGIN HIGHLY ENRICHED URANIUM SPENT NUCLEAR FUEL SHIPMENT FROM BULGARIA
DOE Office of Scientific and Technical Information (OSTI.GOV)
Kelly Cummins; Igor Bolshinsky; Ken Allen
2009-07-01
In July 2008, the Global Threat Reduction Initiative and the IRT 2000 research reactor in Sofia, Bulgaria, operated by the Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped 6.4 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel (SNF) to the Russian Federation. The shipment, which resulted in the removal of all HEU from Bulgaria, was conducted by truck, barge, and rail modes of transport across two transit countries before reaching the final destination at the Production Association Mayak facility in Chelyabinsk, Russia. This paper describes the work, equipment, organizations, and approvals that were required tomore » complete the spent fuel shipment and provides lessons learned that might assist other research reactor operators with their own spent nuclear fuel shipments.« less
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Nuclear power technology requirements for NASA exploration missions
NASA Technical Reports Server (NTRS)
Bloomfield, Harvey S.
1990-01-01
It is pointed out that future exploration of the moon and Mars will mandate developments in many areas of technology. In particular, major advances will be required in planet surface power systems. Critical nuclear technology challenges that can enable strategic self-sufficiency, acceptable operational costs, and cost-effective space transportation goals for NASA exploration missions have been identified. Critical technologies for surface power systems include stationary and mobile nuclear reactor and radioisotope heat sources coupled to static and dynamic power conversion devices. These technologies can provide dramatic reductions in mass, leading to operational and transportation cost savings. Critical technologies for space transportation systems include nuclear thermal rocket and nuclear electric propulsion options, which present compelling concepts for significantly reducing mass, cost, or travel time required for Earth-Mars transport.
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NASA Astrophysics Data System (ADS)
Telichenko, Valeriy; Malykha, Galina; Dorogan, Igor
2017-10-01
The article is devoted to the organization of construction of nuclear medicine facilities in Russia. The article describes the main methods of nuclear medical diagnostics, as well as the peculiarities of nuclear medicine facilities that determine the need for application of specific methods for organizing and managing the construction, methods of requirements management in the organization of construction of nuclear medicine facilities. Sustainable development of the transport of radioactive isotopes from the place of production to places of consumption is very important for the safety of the population. The requirements management system is an important and necessary component in organizing the construction of complex facilities, such as nuclear medicine facilities. The author developed and proposed a requirements management system for the design, construction and operation of a nuclear medicine facility, which provides for a cyclic sequence of actions. This system allows reducing the consumption of resources including material and energy during construction and operation of complex objects.
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48 CFR 970.2703-2 - Patent rights clause provisions for management and operating contractors.
Code of Federal Regulations, 2010 CFR
2010-10-01
...-exempted areas of technology or in operation of DOE facilities primarily dedicated to naval nuclear... for-profit, large business firm and the contract does not have a technology transfer mission or if... dedicated to naval nuclear propulsion or weapons related programs. That clause provides for DOE's statutory...
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48 CFR 970.2703-2 - Patent rights clause provisions for management and operating contractors.
Code of Federal Regulations, 2011 CFR
2011-10-01
...-exempted areas of technology or in operation of DOE facilities primarily dedicated to naval nuclear... for-profit, large business firm and the contract does not have a technology transfer mission or if... dedicated to naval nuclear propulsion or weapons related programs. That clause provides for DOE's statutory...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-10-25
... NRC's Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the... Docketing of the Application, Notice of Opportunity for Hearing for Facility Operating License No. NPF-003 for an Additional 20-Year Period; Firstenergy Nuclear Operating Company, Davis-Besse Nuclear Power...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-01-08
... CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for these.... The operational and management controls, as described in Nuclear Energy Institute (NEI) 08-09... in Nuclear Energy Institute (NEI) 08-09, Revision 6, would be implemented concurrent with the full...
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NERVA-Derived Nuclear Thermal Propulsion Dual Mode Operation
NASA Astrophysics Data System (ADS)
Zweig, Herbert R.; Hundal, Rolv
1994-07-01
Generation of electrical power using the nuclear heat source of a NERVA-derived nuclear thermal rocket engine is presented. A 111,200 N thrust engine defined in a study for NASA-LeRC in FY92 is the reference engine for a three-engine vehicle for which a 50 kWe capacity is required. Processes are described for energy extraction from the reactor and for converting the energy to electricity. The tie tubes which support the reactor fuel elements are the source of thermal energy. The study focuses on process systems using Stirling cycle energy conversion operating at 980 K and an alternate potassium-Rankine system operating at 1,140 K. Considerations are given of the effect of the power production on turbopump operation, ZrH moderator dissociation, creep strain in the tie tubes, hydrogen permeation through the containment materials, requirements for a backup battery system, and the effects of potential design changes on reactor size and criticality. Nuclear considerations include changing tie tube materials to TZM, changing the moderator to low vapor-pressure yttrium hydride, and changing the fuel form from graphite matrix to a carbon-carbide composite.
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Spent Nuclear Fuel Disposition
DOE Office of Scientific and Technical Information (OSTI.GOV)
Wagner, John C.
One interdisciplinary field devoted to achieving the end-state of used nuclear fuel (UNF) through reuse and/or permanent disposal. The reuse option aims to make use of the remaining energy content in UNF and reduce the amount of long-lived radioactive materials that require permanent disposal. The planned approach in the U.S., as well as in many other countries worldwide, is direct permanent disposal in a deep geologic repository. Used nuclear fuel is fuel that has been irradiated in a nuclear reactor to the point where it is no longer capable of sustaining operational objectives. The vast majority (by mass) of UNFmore » is from electricity generation in commercial nuclear power reactors. Furthermore, the other main source of UNF in the U.S. is the Department of Energy’s (DOE) and other federal agencies’ operation of reactors in support of federal government missions, such as materials production, nuclear propulsion, research, testing, and training. Upon discharge from a reactor, UNF emits considerable heat from radioactive decay. Some period of active on-site cooling (e.g., 2 or more years) is typically required to facilitate efficient packaging and transportation to a disposition facility. Hence, the field of UNF disposition broadly includes storage, transportation and ultimate disposition. See also: Nuclear Fission (content/nuclear-fission/458400), Nuclear Fuels (/content/nuclear-fuels/458600), Nuclear Fuel Cycle (/content/nuclear-fuel-cycle/458500), Nuclear Fuels Reprocessing (/content/nuclear-fuels-reprocessing/458700), Nuclear Power (/content/nuclear-power/459600), Nuclear Reactor (/content/nuclear-reactor/460100), Radiation (/content/radiation/566300), and Radioactive Waste Management (/content/radioactive-waste-management/568900).« less
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Spent Nuclear Fuel Disposition
Wagner, John C.
2016-05-22
One interdisciplinary field devoted to achieving the end-state of used nuclear fuel (UNF) through reuse and/or permanent disposal. The reuse option aims to make use of the remaining energy content in UNF and reduce the amount of long-lived radioactive materials that require permanent disposal. The planned approach in the U.S., as well as in many other countries worldwide, is direct permanent disposal in a deep geologic repository. Used nuclear fuel is fuel that has been irradiated in a nuclear reactor to the point where it is no longer capable of sustaining operational objectives. The vast majority (by mass) of UNFmore » is from electricity generation in commercial nuclear power reactors. Furthermore, the other main source of UNF in the U.S. is the Department of Energy’s (DOE) and other federal agencies’ operation of reactors in support of federal government missions, such as materials production, nuclear propulsion, research, testing, and training. Upon discharge from a reactor, UNF emits considerable heat from radioactive decay. Some period of active on-site cooling (e.g., 2 or more years) is typically required to facilitate efficient packaging and transportation to a disposition facility. Hence, the field of UNF disposition broadly includes storage, transportation and ultimate disposition. See also: Nuclear Fission (content/nuclear-fission/458400), Nuclear Fuels (/content/nuclear-fuels/458600), Nuclear Fuel Cycle (/content/nuclear-fuel-cycle/458500), Nuclear Fuels Reprocessing (/content/nuclear-fuels-reprocessing/458700), Nuclear Power (/content/nuclear-power/459600), Nuclear Reactor (/content/nuclear-reactor/460100), Radiation (/content/radiation/566300), and Radioactive Waste Management (/content/radioactive-waste-management/568900).« less
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Occupational Employment in Nuclear-Related Activities, 1981.
ERIC Educational Resources Information Center
Baker, Joe G.; Olsen, Kathryn
Employment in nuclear- and nuclear energy-related activities in 1981 was examined and compared to that in previous years. Survey instruments were returned by 784 establishments. Total 1981 nuclear-related employment was estimated to be 249,500--a growth of 22,600 (10%) workers over the 1977 total. Government-owned, contractor-operated (GOCO)…
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Human Factors Research and Nuclear Safety.
ERIC Educational Resources Information Center
Moray, Neville P., Ed.; Huey, Beverly M., Ed.
The Panel on Human Factors Research Needs in Nuclear Regulatory Research was formed by the National Research Council in response to a request from the Nuclear Regulatory Commission (NRC). The NRC asked the research council to conduct an 18-month study of human factors research needs for the safe operation of nuclear power plants. This report…
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10 CFR 140.91 - Appendix A-Form of nuclear energy liability policy for facilities.
Code of Federal Regulations, 2010 CFR
2010-01-01
... designed or used for (a) separating the isotopes of uranium or plutonium, (b) processing or utilizing spent... processing, fabricating or alloying of special nuclear material if at any time the total amount of such... operations conducted thereat; Nuclear reactor means any apparatus designed or used to sustain nuclear fission...
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10 CFR 140.91 - Appendix A-Form of nuclear energy liability policy for facilities.
Code of Federal Regulations, 2013 CFR
2013-01-01
... designed or used for (a) separating the isotopes of uranium or plutonium, (b) processing or utilizing spent... processing, fabricating or alloying of special nuclear material if at any time the total amount of such... operations conducted thereat; Nuclear reactor means any apparatus designed or used to sustain nuclear fission...
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10 CFR 140.91 - Appendix A-Form of nuclear energy liability policy for facilities.
Code of Federal Regulations, 2014 CFR
2014-01-01
... designed or used for (a) separating the isotopes of uranium or plutonium, (b) processing or utilizing spent... processing, fabricating or alloying of special nuclear material if at any time the total amount of such... operations conducted thereat; Nuclear reactor means any apparatus designed or used to sustain nuclear fission...
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10 CFR 140.91 - Appendix A-Form of nuclear energy liability policy for facilities.
Code of Federal Regulations, 2012 CFR
2012-01-01
... designed or used for (a) separating the isotopes of uranium or plutonium, (b) processing or utilizing spent... processing, fabricating or alloying of special nuclear material if at any time the total amount of such... operations conducted thereat; Nuclear reactor means any apparatus designed or used to sustain nuclear fission...
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10 CFR 140.91 - Appendix A-Form of nuclear energy liability policy for facilities.
Code of Federal Regulations, 2011 CFR
2011-01-01
... designed or used for (a) separating the isotopes of uranium or plutonium, (b) processing or utilizing spent... processing, fabricating or alloying of special nuclear material if at any time the total amount of such... operations conducted thereat; Nuclear reactor means any apparatus designed or used to sustain nuclear fission...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-11
... Power Plant Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory... Code of Federal Regulations (10 CFR), Appendix R, ``Fire Protection Program for Nuclear Power...), for the operation of the James A. FitzPatrick Nuclear Power Plant (JAFNPP) located in Oswego County...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-06-18
... Atomic Electric Company, Yankee Nuclear Power Station, Confirmatory Order Modifying License (Effective... of 10 CFR part 72, Subpart K at the Yankee Nuclear Power Station. The facility is located at the... Facility Operating License for Yankee Nuclear Power Station must be modified to include provisions with...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-01-07
... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-528, 50-529, 50-530; NRC-2009-0012] Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of the Final Supplement 43... of operation for the Palo Verde Nuclear Generating Station (PVNGS). Possible alternatives to the...
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Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 2 2013-01-01 2013-01-01 false Scope. 140.2 Section 140.2 Energy NUCLEAR REGULATORY... there has been an extraordinary nuclear occurrence. The form of nuclear energy liability policy for... license issued under 10 CFR parts 50, 52, or 54 to operate a nuclear reactor, and (2) With respect to an...
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Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 2 2014-01-01 2014-01-01 false Scope. 140.2 Section 140.2 Energy NUCLEAR REGULATORY... there has been an extraordinary nuclear occurrence. The form of nuclear energy liability policy for... license issued under 10 CFR parts 50, 52, or 54 to operate a nuclear reactor, and (2) With respect to an...
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Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 2 2012-01-01 2012-01-01 false Scope. 140.2 Section 140.2 Energy NUCLEAR REGULATORY... there has been an extraordinary nuclear occurrence. The form of nuclear energy liability policy for... license issued under 10 CFR parts 50, 52, or 54 to operate a nuclear reactor, and (2) With respect to an...
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Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 2 2010-01-01 2010-01-01 false Scope. 140.2 Section 140.2 Energy NUCLEAR REGULATORY... there has been an extraordinary nuclear occurrence. The form of nuclear energy liability policy for... license issued under 10 CFR parts 50, 52, or 54 to operate a nuclear reactor, and (2) With respect to an...
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Citizen Education on Nuclear Technology (CENT). Teacher's Guide.
ERIC Educational Resources Information Center
Intermountain Science Experience Center, ID Falls, ID.
Using an interdisciplinary approach, this curriculum focuses on understanding: (1) the fundamental principles of operating a nuclear power plant; (2) the place of nuclear energy in the overall energy supply/demand situation; (3) risk-benefit balance of the major energy sources; and (4) the role of political action in developing nuclear energy…
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Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 2 2011-01-01 2011-01-01 false Scope. 140.2 Section 140.2 Energy NUCLEAR REGULATORY... there has been an extraordinary nuclear occurrence. The form of nuclear energy liability policy for... license issued under 10 CFR parts 50, 52, or 54 to operate a nuclear reactor, and (2) With respect to an...
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75 FR 42469 - Firstenergy Nuclear Operating Company; Request for Licensing Action
Federal Register 2010, 2011, 2012, 2013, 2014
2010-07-21
... nuclear plant in Ohio, preventing the reactor from restarting until such time that the NRC determines... Commission's regulations. The request has been referred to the Director of the Office of Nuclear Reactor... of Nuclear Reactor Regulation. [FR Doc. 2010-17834 Filed 7-20-10; 8:45 am] BILLING CODE 7590-01-P ...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-06-28
...; Three Mile Island Nuclear Station, Unit 1; Environmental Assessment and Finding of No Significant Impact... Company, LLC (the licensee), for operation of Three Mile Island Nuclear Station, Unit 1 (TMI-1), located... Three Mile Island Nuclear Station, Units 1 and 2, NUREG-0552, dated December 1972, and Generic...
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Optimally moderated nuclear fission reactor and fuel source therefor
Ougouag, Abderrafi M [Idaho Falls, ID; Terry, William K [Shelley, ID; Gougar, Hans D [Idaho Falls, ID
2008-07-22
An improved nuclear fission reactor of the continuous fueling type involves determining an asymptotic equilibrium state for the nuclear fission reactor and providing the reactor with a moderator-to-fuel ratio that is optimally moderated for the asymptotic equilibrium state of the nuclear fission reactor; the fuel-to-moderator ratio allowing the nuclear fission reactor to be substantially continuously operated in an optimally moderated state.
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2010-05-27
small modular reactors and extend the lives and improve the operation of existing commercial nuclear power plants. 40 Interdisciplinary MIT Study, The Future of Nuclear Power, Massachusetts Institute of Technology, 2003, p. 79. 41 Gronlund, Lisbeth, David Lochbaum, and Edwin Lyman, Nuclear Power in a Warming World, Union of Concerned Scientists, December 2007. 42 Travis Madsen, Tony Dutzik, and Bernadette Del Chiaro, et al., Generating Failure: How Building Nuclear Power Plants
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Michel-Sendis, F.; Gauld, I.; Martinez, J. S.; ...
2017-08-02
SFCOMPO-2.0 is the new release of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) database of experimental assay measurements. These measurements are isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel (SNF) samples. We supplement the measurements with design information for the fuel assembly and fuel rod from which each sample was taken, as well as with relevant information on operating conditions and characteristics of the host reactors. These data are necessary for modeling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECDmore » NEA under the guidance of the Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF), which is part of the NEA Working Party on Nuclear Criticality Safety (WPNCS). Significant efforts aimed at establishing a thorough, reliable, publicly available resource for code validation and safety applications have led to the capture and standardization of experimental data from 750 SNF samples from more than 40 reactors. These efforts have resulted in the creation of the SFCOMPO-2.0 database, which is publicly available from the NEA Data Bank. Our paper describes the new database, and applications of SFCOMPO-2.0 for computer code validation, integral nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Michel-Sendis, F.; Gauld, I.; Martinez, J. S.
SFCOMPO-2.0 is the new release of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) database of experimental assay measurements. These measurements are isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel (SNF) samples. We supplement the measurements with design information for the fuel assembly and fuel rod from which each sample was taken, as well as with relevant information on operating conditions and characteristics of the host reactors. These data are necessary for modeling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECDmore » NEA under the guidance of the Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF), which is part of the NEA Working Party on Nuclear Criticality Safety (WPNCS). Significant efforts aimed at establishing a thorough, reliable, publicly available resource for code validation and safety applications have led to the capture and standardization of experimental data from 750 SNF samples from more than 40 reactors. These efforts have resulted in the creation of the SFCOMPO-2.0 database, which is publicly available from the NEA Data Bank. Our paper describes the new database, and applications of SFCOMPO-2.0 for computer code validation, integral nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.« less
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Cyber security evaluation of II&C technologies
DOE Office of Scientific and Technical Information (OSTI.GOV)
Thomas, Ken
The Light Water Reactor Sustainability (LWRS) Program is a research and development program sponsored by the Department of Energy, which is conducted in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. Within the LWRS Program, the Advanced Instrumentation, Information, and Control (II&C) Systems Technologies Pathway conducts targeted research and development (R&D) tomore » address aging and reliability concerns with the legacy instrumentation and control and related information systems of the U.S. operating light water reactor (LWR) fleet. The II&C Pathway is conducted by Idaho National Laboratory (INL). Cyber security is a common concern among nuclear utilities and other nuclear industry stakeholders regarding the digital technologies that are being developed under this program. This concern extends to the point of calling into question whether these types of technologies could ever be deployed in nuclear plants given the possibility that the information in them can be compromised and the technologies themselves can potentially be exploited to serve as attack vectors for adversaries. To this end, a cyber security evaluation has been conducted of these technologies to determine whether they constitute a threat beyond what the nuclear plants already manage within their regulatory-required cyber security programs. Specifically, the evaluation is based on NEI 08-09, which is the industry’s template for cyber security programs and evaluations, accepted by the Nuclear Regulatory Commission (NRC) as responsive to the requirements of the nuclear power plant cyber security regulation found in 10 CFR 73.54. The evaluation was conducted by a cyber security team with expertise in nuclear utility cyber security programs and experience in conducting these evaluations. The evaluation has determined that, for the most part, cyber security will not be a limiting factor in the application of these technologies to nuclear power plant applications.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
This standard presents program criteria and implementation guidance for an operational configuration management program for DOE nuclear and non-nuclear facilities. This Part 2 includes chapters on implementation guidance for operational configuration management, implementation guidance for design reconstitution, and implementation guidance for material condition and aging management. Appendices are included on design control, examples of design information, conduct of walkdowns, and content of design information summaries.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Liu, Ning; Rutherford, Phil; Dassler, David
2012-09-01
This Annual Site Environmental Report (ASER) for 2011 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, operation and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988,more » and all subsequent radiological work has been directed toward environmental restoration and decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2011 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Liu, Ning; Rutherford, Phil; Dassler, David
2013-09-01
This Annual Site Environmental Report (ASER) for 2012 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, operation and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988,more » and all subsequent radiological work has been directed toward environmental restoration and decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2012 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less
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Intelligent Modeling for Nuclear Power Plant Accident Management
DOE Office of Scientific and Technical Information (OSTI.GOV)
Darling, Michael Christropher; Luger, George F.; Jones, Thomas B.
This study explores the viability of using counterfactual reasoning for impact analyses when understanding and responding to “beyond-design-basis” nuclear power plant accidents. Currently, when a severe nuclear power plant accident occurs, plant operators rely on Severe Accident Management Guidelines. However, the current guidelines are limited in scope and depth: for certain types of accidents, plant operators would have to work to mitigate the damage with limited experience and guidance for the particular situation. We aim to fill the need for comprehensive accident support by using a dynamic Bayesian network to aid in the diagnosis of a nuclear reactor’s state andmore » to analyze the impact of possible response measures.« less
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Decontamination, decommissioning, and vendor advertorial issue, 2008
DOE Office of Scientific and Technical Information (OSTI.GOV)
Agnihotri, Newal
The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the bestmore » TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company.« less
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Intelligent Modeling for Nuclear Power Plant Accident Management
Darling, Michael Christropher; Luger, George F.; Jones, Thomas B.; ...
2018-03-29
This study explores the viability of using counterfactual reasoning for impact analyses when understanding and responding to “beyond-design-basis” nuclear power plant accidents. Currently, when a severe nuclear power plant accident occurs, plant operators rely on Severe Accident Management Guidelines. However, the current guidelines are limited in scope and depth: for certain types of accidents, plant operators would have to work to mitigate the damage with limited experience and guidance for the particular situation. We aim to fill the need for comprehensive accident support by using a dynamic Bayesian network to aid in the diagnosis of a nuclear reactor’s state andmore » to analyze the impact of possible response measures.« less
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A simulator-based nuclear reactor emergency response training exercise.
Waller, Edward; Bereznai, George; Shaw, John; Chaput, Joseph; Lafortune, Jean-Francois
Training offsite emergency response personnel basic awareness of onsite control room operations during nuclear power plant emergency conditions was the primary objective of a week-long workshop conducted on a CANDU® virtual nuclear reactor simulator available at the University of Ontario Institute of Technology, Oshawa, Canada. The workshop was designed to examine both normal and abnormal reactor operating conditions, and to observe the conditions in the control room that may have impact on the subsequent offsite emergency response. The workshop was attended by participants from a number of countries encompassing diverse job functions related to nuclear emergency response. Objectives of the workshop were to provide opportunities for participants to act in the roles of control room personnel under different reactor operating scenarios, providing a unique experience for participants to interact with the simulator in real-time, and providing increased awareness of control room operations during accident conditions. The ability to "pause" the simulator during exercises allowed the instructors to evaluate and critique the performance of participants, and to provide context with respect to potential offsite emergency actions. Feedback from the participants highlighted (i) advantages of observing and participating "hands-on" with operational exercises, (ii) their general unfamiliarity with control room operational procedures and arrangements prior to the workshop, (iii) awareness of the vast quantity of detailed control room procedures for both normal and transient conditions, and (iv) appreciation of the increased workload for the operators in the control room during a transient from normal operations. Based upon participant feedback, it was determined that the objectives of the training had been met, and that future workshops should be conducted.
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Human resource development for nuclear generation - from the perspective of a utility company
NASA Astrophysics Data System (ADS)
Kahar, Wan Shakirah Wan Abdul; Mostafa, Nor Azlan; Salim, Mohd Faiz
2017-01-01
Malaysia is currently in the planning phase of its nuclear power program, with the first unit targeted to be operational in 2030. Training of nuclear power plant (NPP) staffs are usually long and rigorous due to the complexity and safety aspects of nuclear power. As the sole electricity utility in the country, it is therefore essential that Tenaga Nasional Berhad (TNB) prepares early in developing its human resource and nuclear expertise as a potential NPP owner-operator. A utility also has to be prudent in managing its work force efficiently and effectively, while ensuring that adequate preparations are being made to acquire the necessary nuclear knowledge with sufficient training lead time. There are several approaches to training that can be taken by a utility company with no experience in nuclear power. These include conducting feasibility studies and benchmarking exercises, preparing long term human resource development, increasing the exposure on nuclear power technology to both the top management and general staff, and employing the assistance of relevant agencies locally and abroad. This paper discusses the activities done and steps taken by TNB in its human resource development for Malaysia's nuclear power program.
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Social Institutions and Nuclear Energy
ERIC Educational Resources Information Center
Weinberg, Alvin M.
1972-01-01
Nuclear technologists can offer an all but infinite source of relatively cheap and clean energy" but society must decide whether the price of eternal vigilance needed to ensure proper and safe operation of its nuclear energy system" is worth the benefits. (Author/AL)
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OECD/NEA study on the economics of the long-term operation of nuclear power plants
DOE Office of Scientific and Technical Information (OSTI.GOV)
Lokhov, A.; Cameron, R.
2012-07-01
The OECD Nuclear Energy Agency (NEA) established the Ad hoc expert group on the Economics of Long-term Operation (LTO) of Nuclear Power Plants. The primary aim of this group is to collect and analyse technical and economic data on the upgrade and lifetime extension experience in OECD countries, and to assess the likely applications for future extensions. This paper describes the key elements of the methodology of economic assessment of LTO and initial findings for selected NEA member countries. (authors)
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Taslitt, N.
1985-09-01
The objectives of this project were to (1) determine whether the radiation from a nuclear weapon can disable various arming and fuzing components by causing permanent damage; (2) determine whether transient nuclear radiation can induce an operating fuze to malfunction; and (3) compare nuclear weapon radiation effects with those produced by various radiation simulators. Data obtained revealed that none of the inertial components were detrimentally affected. The electronic components were severely degraded but would have satisfactorily accomplished their tactical functions. No electromagnetic effects were detected.
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Navarro, R.; Sembera, E.D.; Jungblut, W.L.
1977-01-01
The United States Geological Survey (USGS), Branch of Earthquake Hazards (BEH), Las Vegas, Nevada has provided ERDA, Nevada Operations Office, with seismic monitoring support to the underground nuclear weapons test program conducted at the Nevada Test Site (NTS) since September 1961. Activities from September 15, 1961 to September 13, 1963 are summarized in the report, "Seismic Dats Summary Nuclear Detonation Program, 1961 thru 1963", (Mickey and Shugart 1964) which lists seismic records obtained from all announced underground nuclear tests conducted during that period.
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1987-11-30
1975 to study weapons effects . All six were tunnel-type nuclear tests. The following table summarizes data on these events: OPERATION TOGGLE ARBOR...194 nuclear device tests conducted, 161 were for weapons related or effects purposes, and 33 were safety ex- periments. An additional 22 nuclear...on 25 April 1962 until the last atmospheric test on 4 November 1962, 40 weapons development and weapons effects tests were conducted as part of
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NASA Astrophysics Data System (ADS)
Warren, John L.; Vadnais, Kenneth G.
1997-01-01
Recent advances in miniature photomultiplier tubes and low power electronics have made possible a new generation of small gamma-ray radiation detectors specifically designed for use by government and law enforcement agencies for the detection and interdiction of concealed nuclear materials. This paper describes an inexpensive pager sized radiation detector that can be worn on the belt or carried in a pocket for hands free operation, and which can quietly alert the operator to the presence of nuclear material. The sensitivity performance of the detector technology and the application of the instrument to law enforcement and nuclear smuggling are discussed.
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-07-30
... Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to the Primary Sampling System.... The amendment requests to modify the Primary Sampling System (PSS) design, including changes to Tier 1....13-1 ``Primary Sampling System,'' and Subsection 2.3.13, ``Primary Sampling System'' of the Updated...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-07-30
... Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to the Primary Sampling System.... The amendment requests to modify the Primary Sampling System (PSS) design, including changes to Tier 1....13-1 ``Primary Sampling System,'' and Subsection 2.3.13, ``Primary Sampling System'' of the Updated...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-08-16
... Nuclear Operations Group, Inc.; Establishment of Atomic Safety and Licensing Board Pursuant to delegation... 2.106, 2.300, 2.313(a), and 2.318, notice is hereby given that an Atomic Safety and Licensing Board..., 2010. The Board is comprised of the following administrative judges: Alan S. Rosenthal, Chair, Atomic...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-10-18
... NUCLEAR REGULATORY COMMISSION [NRC-2011-0241] Biweekly Notice; Applications and Amendments to Facility Operating Licenses; Involving No Significant Hazards Considerations Background Pursuant to section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission or NRC) is publishing...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-04-17
... NUCLEAR REGULATORY COMMISSION [NRC-2012-0090] Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations Background Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission or...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-07-23
... NUCLEAR REGULATORY COMMISSION [NRC-2013-0158] Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations Background Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission or...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-09-06
... NUCLEAR REGULATORY COMMISSION [NRC-2011-0205] Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations Background Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission or NRC) is publishing thi...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-02-22
... NUCLEAR REGULATORY COMMISSION [NRC-2011-0040] Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations I. Background Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission or NRC) is publishing...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-01-25
... NUCLEAR REGULATORY COMMISSION [NRC-2011-0019] Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations I. Background Pursuant to section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission or NRC) is publishing...
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NASA Astrophysics Data System (ADS)
Shchelik, S. V.; Pavlov, A. S.
2013-07-01
Results of work on restoring the service properties of filtering material used in the high-temperature reactor coolant purification system of a VVER-1000 reactor are presented. A quantitative assessment is given to the effect from subjecting a high-temperature sorbent to backwashing operations carried out with the use of regular capacities available in the design process circuit in the first years of operation of Unit 3 at the Kalinin nuclear power plant. Approaches to optimizing this process are suggested. A conceptual idea about comprehensively solving the problem of achieving more efficient and safe operation of the high-temperature active water treatment system (AWT-1) on a nuclear power industry-wide scale is outlined.
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Report on {open_quotes}audit of internal controls over special nuclear materials{close_quotes}
DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
1996-04-01
The Department of Energy (Department) is responsible for safeguarding a significant amount of plutonium, uranium-233 and enriched uranium - collectively referred to as special nuclear materials - stored in the United States. The Department`s office of Nonproliferation and National Security has overall management cognizance for developing policies for safeguarding these materials, while other Headquarters program offices have {open_quotes}landlord{close_quotes} responsibilities for the sites where the materials are stored, and the Department`s operations and field offices provide onsite management of contractor operations. The Department`s management and operating contractors, under the direction of the Department, safeguard and account for the special nuclear materialmore » stored at Department sites.« less
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Spent sealed radium sources conditioning in Latin America
DOE Office of Scientific and Technical Information (OSTI.GOV)
Mourao, R.P.
1999-06-01
The management of spent sealed sources is considered by the International Atomic Energy Agency (IAEA) one of the greatest challenges faced by nuclear authorities today, especially in developing countries. One of the Agency`s initiatives to tackle this problem is the Spent Radium Sources Conditioning Project, a worldwide project relying on the regional co-operation between countries. A team from the Brazilian nuclear research institute Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) was chosen as the expert team to carry out the operations in Latin America; since December 1996 radium sources have been safely conditioned in Uruguay, Nicaragua, Guatemala, Ecuador and Paraguay.more » A Quality Assurance Program was established, encompassing the qualification of the capsule welding process, written operational procedures referring to all major steps of the operation, calibration of monitors and information retrievability. A 200L carbon steel drum-based packaging concept was used to condition the sources, its cavity being designed to receive the lead shield device containing stainless steel capsules with the radium sources. As a result of these operations, a total amount of 2,897 mg of needles, tubes, medical applicators, standard sources for calibration, lightning rods, secondary wastes and contaminated objects were stored in proper conditions and are now under control of the nuclear authorities of the visited countries.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Liu, Ning; Rutherford, Phil; Amar, Ravnesh
2009-09-01
This Annual Site Environmental Report (ASER) for 2008 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988; allmore » subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. In May 2007, the D&D operations in Area IV were suspended by the DOE. The environmental monitoring programs were continued throughout the year. Results of the radiological monitoring program for the calendar year 2008 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less
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Current Status of Continued Operation for Kori unit 1 beyond Design Life
DOE Office of Scientific and Technical Information (OSTI.GOV)
Tai-hyun Kim; Pan-sool Kim; Yeon-sang Yu
2006-07-01
Since the commercial operation of Kori Nuclear Power Plant unit 1 in April 1978, Korea has achieved rapid growth in its nuclear industry, and now has 20 operating nuclear power plants. As the design life of Kori unit 1 comes to an end, Korea Hydro and Nuclear Power Co., Ltd.(KHNP) is preparing for the continued operation of the plant for the first time in Korea. The feasibility of continued operation beyond design life has been already proven in many countries. Developed countries, such as the USA, England, Japan and so on, are also proceeding with the continued operation of NPPsmore » whose design life or license is due to expire, as long as the adequate safety and aging management review meet the acceptance criteria. Continued operation is absolutely needed for countries lacking in natural resources, such as Korea, in view of the efficient utilization of energy resources and reduction of greenhouse gases (CO{sub 2}) emission. For the continued operation beyond design life (30 yrs) of Kori unit 1, KHNP has performed Lifetime Management (PLiM) study, Periodic Safety Review (PSR), Probabilistic Safety Assessment (PSA) and Environmental Qualification (EQ), etc. and replaced main equipment, such as Steam Generators, Low Pressure Turbine Rotor, RCP Internals, Main Transformer, Main Generator, and so on. In September 2005, The Regulation of Atomic Energy Act in Korea was revised and published referring to License Renewal Rule of the USA. According to the revised regulations, KHNP is performing Life Assessment for Main Systems, Structures and Components (SSCs) and Radiological Impacts on the Environment with PSR for continued operation. (authors)« less
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Fault Diagnosis with Multi-State Alarms in a Nuclear Power Control Simulation
DOE Office of Scientific and Technical Information (OSTI.GOV)
Stuart A. Ragsdale; Roger Lew; Ronald L. Boring
2014-09-01
This research addresses how alarm systems can increase operator performance within nuclear power plant operations. The experiment examined the effects of two types of alarm systems (two-state and three-state alarms) on alarm compliance and diagnosis for two types of faults differing in complexity. We hypothesized the use of three-state alarms would improve performance in alarm recognition and fault diagnoses over that of two-state alarms. Sensitivity and criterion based on the Signal Detection Theory were used to measure performance. We further hypothesized that operator trust would be highest when using three-state alarms. The findings from this research showed participants performed bettermore » and had more trust in three-state alarms compared to two-state alarms. Furthermore, these findings have significant theoretical implications and practical applications as they apply to improving the efficiency and effectiveness of nuclear power plant operations.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Faybishenko, Boris; Birkholzer, Jens; Sassani, David
The overall objective of the Fifth Worldwide Review (WWR-5) is to document the current state-of-the-art of major developments in a number of nations throughout the World pursuing geological disposal programs, and to summarize challenging problems and experience that have been obtained in siting, preparing and reviewing cases for the operational and long-term safety of proposed and operating nuclear waste repositories. The scope of the Review is to address current specific technical issues and challenges in safety case development along with the interplay of technical feasibility, siting, engineering design issues, and operational and post-closure safety. In particular, the chapters included inmore » the report present the following types of information: the current status of the deep geological repository programs for high level nuclear waste and low- and intermediate level nuclear waste in each country, concepts of siting and radioactive waste and spent nuclear fuel management in different countries (with the emphasis of nuclear waste disposal under different climatic conditions and different geological formations), progress in repository site selection and site characterization, technology development, buffer/backfill materials studies and testing, support activities, programs, and projects, international cooperation, and future plans, as well as regulatory issues and transboundary problems.« less
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The Fundamentals and Status of Nuclear Power
NASA Astrophysics Data System (ADS)
Matzie, Regis A.
2011-11-01
Nuclear power has enormous potential to provide clean, safe base-load electricity to the world's growing population. Harnessing this potential in an economic and responsible manner is not without challenges. Safety remains the principal tenet of our operating fleet, which currently provides ˜20% of U.S. electricity generated. The performance of this fleet from economic and safety standpoints has improved dramatically over the past several decades. This nuclear generation also represents greater than 70% of the emission free electricity with hydroelectric power providing the majority of the remainder. There have been many lessons learned from the more than 50 years of experience with nuclear power and these have been factored into the new designs now being constructed worldwide. These new designs, which have enhanced safety compared to the operating fleet, have been simplified by employing passive safety systems and modular construction. There are applications for licenses of more than 20 new reactors under review by the U.S. Nuclear Regulatory Commission; the first of these licenses will be completed in early 2012, and the first new U.S. reactor will start operating in 2016. Yet there are still more improvements that can be made and these are being pursued to achieve an even greater deployment of nuclear power technology.
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The Nuclear Renaissance in the U.S.
Buongiorno, Jacopo
2018-04-23
Nuclear power currently provides 20% of the electricity generation in the U.S. and about 16% worldwide. As a carbon-free energy source, nuclear is receiving a lot of attention by industry, lawmakers and environmental groups, as they attempt to resolve the issue of man-made climate change. For the first time in 30 years several U.S. electric utilities have applied for construction and operation licenses of new nuclear power plants. This talk will review the safety, operational and economic record of the existing U.S. commercial reactor fleet, will provide an overview of the reactor designs considered for the new wave of plant construction, and will discuss several research projects being conducted at the Massachusetts Institute of Technology to support the expansion of nuclear power in the U.S. and overseas.
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Manzo, Vincent A.; Miles, Aaron R.
2016-10-31
In October 2015, Secretary of Defense Carter called for NATO to better integrate conventional and nuclear deterrence. Four months later, Assistant Secretary of Defense Robert Scher stated in Senate testimony that the DoD is "working to ensure an appropriate level of integration between nuclear and conventional planning and operations."
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-12-31
...., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown Decommissioning Activities Report AGENCY...) Accession No. ML13340A009), for the Crystal River Unit 3 Nuclear Generating Plant (CR-3). The PSDAR provides.... until 9 p.m., EST, at the Crystal River Nuclear Plant Training Center/Emergency Operations Facility...
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Federal Register 2010, 2011, 2012, 2013, 2014
2013-03-14
... NUCLEAR REGULATORY COMMISSION [Docket No. 50-302; NRC-2011-0301] Crystal River Unit 3 Nuclear... the Crystal River Unit 3 Nuclear Generating Plant (CR-3), located in Florida, Citrus County. The... notice (if that document is available in ADAMS) is provided the first time that a document is referenced...
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75 FR 13327 - Tennessee Valley Authority; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Exemption
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-19
... the rule's compliance date for all operating nuclear power plants, but noted that the Commission's... compliance date (Reference: June 4, 2009, letter from R. W. Borchardt, NRC, to M. S. Fertel, Nuclear Energy... the U.S. Nuclear Regulatory Commission (NRC, the Commission) now or hereafter in effect. The facility...
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10 CFR 140.94 - Appendix D-Form of indemnity agreement with Federal agencies.
Code of Federal Regulations, 2011 CFR
2011-01-01
... (hereinafter referred to as the Act). Article I As used in this agreement, 1. Nuclear reactor, byproduct... irradiated or to be irradiated by, the nuclear reactor or reactors subject to the license or licenses... construction of a nuclear reactor with respect to which no operating license has been issued by the Nuclear...
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JPRS Report, Nuclear Developments
1988-06-03
arranged according to degree of severity, and action plans will be developed for necessary measures appropriate to each level. Nuclear Disaster Chief...For the purpose of shielding the country as much as possible from the damages of nuclear accidents, first, a " Nuclear Disaster Headquarters" will be...formed within TAEC to oversee operations called for by the " Nuclear Disaster Guidelines," and coordination of the activities designed to meet an
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The alternative strategies of the development of the nuclear power industry in the 21st century
NASA Astrophysics Data System (ADS)
Goverdovskii, A. A.; Kalyakin, S. G.; Rachkov, V. I.
2014-05-01
This paper emphasizes the urgency of scientific-and-technical and sociopolitical problems of the modern nuclear power industry without solving of which the transition from local nuclear power systems now in operation to a large-scale nuclear power industry would be impossible. The existing concepts of the longterm strategy of the development of the nuclear power industry have been analyzed. On the basis of the scenarios having been developed it was shown that the most promising alternative is the orientation towards the closed nuclear fuel cycle with fast neutron reactors (hereinafter referred to as fast reactors) that would meet the requirements on the acceptable safety. It was concluded that the main provisions of "The Strategy of the Development of the Nuclear Power Industry of Russia for the First Half of the 21st Century" approved by the Government of the Russian Federation in the year 2000 remain the same at present as well, although they require to be elaborated with due regard for new realities in the market for fossil fuels, the state of both the Russian and the world economy, as well as tightening of requirements related to safe operation of nuclear power stations (NPSs) (for example, after the severe accident at the Fukushima nuclear power station, Japan) and nonproliferation of nuclear weapons.
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ERIC Educational Resources Information Center
KOVNER, EDGAR A.
PROBLEMS CONFRONTED BY PLANNERS OF NUCLEAR PROGRAMS AT THE TECHNICIAN LEVEL INCLUDE (1) LACK OF PRECEDENT IN CURRICULUM, COURSE OUTLINES, AND GRADUATE PLACEMENT, (2) DIFFICULTY IN DETERMINING COSTS OF LABORATORY CONSTRUCTION, EQUIPMENT, AND OPERATION, AND (3) REQUIREMENT OF ATOMIC ENERGY COMMISSION LICENSES IN NUCLEAR OCCUPATIONS. A 92-SEMESTER…
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Code of Federal Regulations, 2014 CFR
2014-07-01
... electrical power for public use by any fuel cycle through utilization of nuclear energy. (b) Uranium fuel... directly support the production of electrical power for public use utilizing nuclear energy, but excludes... ENVIRONMENTAL RADIATION PROTECTION STANDARDS FOR NUCLEAR POWER OPERATIONS General Provisions § 190.02...
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Code of Federal Regulations, 2010 CFR
2010-07-01
... electrical power for public use by any fuel cycle through utilization of nuclear energy. (b) Uranium fuel... directly support the production of electrical power for public use utilizing nuclear energy, but excludes... ENVIRONMENTAL RADIATION PROTECTION STANDARDS FOR NUCLEAR POWER OPERATIONS General Provisions § 190.02...
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78 FR 23684 - Personnel Access Authorization Requirements for Nuclear Power Plants
Federal Register 2010, 2011, 2012, 2013, 2014
2013-04-22
... Nuclear Energy Institute (NEI or the petitioner) on January 25, 2013. The petition was docketed by the NRC... affecting the nuclear energy industry, including the regulatory aspects of generic operational and technical... 22, 2013 / Proposed Rules#0;#0; [[Page 23684
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Licensed operating reactors: Status summary report, data as of December 31, 1995. Volume 20
DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
1996-06-01
The US Nuclear Regulatory Commission`s monthly summary of licensed nuclear power reactor data is based primarily on the operating data report submitted by licensees for each unit. This report is divided into two sections: the first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 availability factors, capacity factors, and forced outage rates are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensees and notes to the use of weighted averages and starting dates other than commercial operation are provided.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Sitdikov,I.; Zenkov, A.; Tsibulnikov, Y.
The Material Protection, Control and Accounting (MPC&A) Program has been working since 1994 with nuclear sites in Russia to upgrade the physical protection (PP) and material control and accounting (MC&A) functions at facilities containing weapons usable nuclear material. In early 2001, the MPC&A program initiated the MPC&A Operations Monitoring (MOM) Project to monitor facilities where MPC&A upgrades have been installed to provide increased confidence that personnel are present and vigilant, provide confidence that security procedures are being properly performed and provide additional assurance that nuclear materials have not been stolen. The MOM project began as a pilot project at themore » Moscow State Engineering Physics Institute (MEPhI) and a MOM system was successfully installed in October 2001. Following the success of the MEPhI pilot project, the MPC&A Program expanded the installation of MOM systems to several other Russian facilities, including the Nuclear Physics Institute (NPI) in Tomsk. The MOM system was made operational at NPI in October 2004. This paper is focused on the experience gained from operation of this system and the objectives of the MOM system. The paper also describes how the MOM system is used at NPI and, in particular, how the data is analyzed. Finally, potential expansion of the MOM system at NPI is described.« less
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NASA Astrophysics Data System (ADS)
Stacey, W. M.
2009-09-01
The possibility that a tokamak D-T fusion neutron source, based on ITER physics and technology, could be used to drive sub-critical, fast-spectrum nuclear reactors fueled with the transuranics (TRU) in spent nuclear fuel discharged from conventional nuclear reactors has been investigated at Georgia Tech in a series of studies which are summarized in this paper. It is found that sub-critical operation of such fast transmutation reactors is advantageous in allowing longer fuel residence time, hence greater TRU burnup between fuel reprocessing stages, and in allowing higher TRU loading without compromising safety, relative to what could be achieved in a similar critical transmutation reactor. The required plasma and fusion technology operating parameter range of the fusion neutron source is generally within the anticipated operational range of ITER. The implications of these results for fusion development policy, if they hold up under more extensive and detailed analysis, is that a D-T fusion tokamak neutron source for a sub-critical transmutation reactor, built on the basis of the ITER operating experience, could possibly be a logical next step after ITER on the path to fusion electrical power reactors. At the same time, such an application would allow fusion to contribute to meeting the nation's energy needs at an earlier stage by helping to close the fission reactor nuclear fuel cycle.
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Weakly interacting massive particle-nucleus elastic scattering response
NASA Astrophysics Data System (ADS)
Anand, Nikhil; Fitzpatrick, A. Liam; Haxton, W. C.
2014-06-01
Background: A model-independent formulation of weakly interacting massive particle (WIMP)-nucleon scattering was recently developed in Galilean-invariant effective field theory. Purpose: Here we complete the embedding of this effective interaction in the nucleus, constructing the most general elastic nuclear cross section as a factorized product of WIMP and nuclear response functions. This form explicitly defines what can and cannot be learned about the low-energy constants of the effective theory—and consequently about candidate ultraviolet theories of dark matter—from elastic scattering experiments. Results: We identify those interactions that cannot be reliably treated in a spin-independent/spin-dependent (SI/SD) formulation: For derivative- or velocity-dependent couplings, the SI/SD formulation generally mischaracterizes the relevant nuclear operator and its multipolarity (e.g., scalar or vector) and greatly underestimates experimental sensitivities. This can lead to apparent conflicts between experiments when, in fact, none may exist. The new nuclear responses appearing in the factorized cross section are related to familiar electroweak nuclear operators such as angular momentum l⃗(i) and the spin-orbit coupling σ⃗(i).l⃗(i). Conclusions: To unambiguously interpret experiments and to extract all of the available information on the particle physics of dark matter, experimentalists will need to (1) do a sufficient number of experiments with nuclear targets having the requisite sensitivities to the various operators and (2) analyze the results in a formalism that does not arbitrarily limit the candidate operators. In an appendix we describe a code that is available to help interested readers implement such an analysis.
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NASA Astrophysics Data System (ADS)
Schmitt, Kara Anne
This research aims to prove that strict adherence to procedures and rigid compliance to process in the US Nuclear Industry may not prevent incidents or increase safety. According to the Institute of Nuclear Power Operations, the nuclear power industry has seen a recent rise in events, and this research claims that a contributing factor to this rise is organizational, cultural, and based on peoples overreliance on procedures and policy. Understanding the proper balance of function allocation, automation and human decision-making is imperative to creating a nuclear power plant that is safe, efficient, and reliable. This research claims that new generations of operators are less engaged and thinking because they have been instructed to follow procedures to a fault. According to operators, they were once to know the plant and its interrelations, but organizationally more importance is now put on following procedure and policy. Literature reviews were performed, experts were questioned, and a model for context analysis was developed. The Context Analysis Method for Identifying Design Solutions (CAMIDS) Model was created, verified and validated through both peer review and application in real world scenarios in active nuclear power plant simulators. These experiments supported the claim that strict adherence and rigid compliance to procedures may not increase safety by studying the industry's propensity for following incorrect procedures, and when it directly affects the outcome of safety or security of the plant. The findings of this research indicate that the younger generations of operators rely highly on procedures, and the organizational pressures of required compliance to procedures may lead to incidents within the plant because operators feel pressured into following the rules and policy above performing the correct actions in a timely manner. The findings support computer based procedures, efficient alarm systems, and skill of the craft matrices. The solution to the problems facing the industry include in-depth, multiple fault failure training which tests the operator's knowledge of the situation. This builds operator collaboration, competence and confidence to know what to do, and when to do it in response to an emergency situation. Strict adherence to procedures and rigid compliance to process may not prevent incidents or increase safety; building operators' fundamental skills of collaboration, competence and confidence will.
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78 FR 70934 - Trespassing on DOE Property: Kansas City Plant Facilities
Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-27
..., National Nuclear Security Administration, Kirtland Operations operating area. The facilities are described...). Addition of the Kirtland Operations operating area property does not terminate the prior Kansas City Plant...
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NASA Astrophysics Data System (ADS)
Ripani, M.
2015-08-01
The main features of nuclear fission as physical phenomenon will be revisited, emphasizing its peculiarities with respect to other nuclear reactions. Some basic concepts underlying the operation of nuclear reactors and the main types of reactors will be illustrated, including fast reactors, showing the most important differences among them. The nuclear cycle and radioactive-nuclear-waste production will be also discussed, along with the perspectives offered by next generation nuclear assemblies being proposed. The current situation of nuclear power in the world, its role in reducing carbon emission and the available resources will be briefly illustrated.
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NASA Technical Reports Server (NTRS)
Hrbud, Ivana; VanDyke, Melissa; Houts, Mike; Goodfellow, Keith; Schafer, Charles (Technical Monitor)
2001-01-01
The Safe Affordable Fission Engine (SAFE) test series addresses Phase 1 Space Fission Systems issues in particular non-nuclear testing and system integration issues leading to the testing and non-nuclear demonstration of a 400-kW fully integrated flight unit. The first part of the SAFE 30 test series demonstrated operation of the simulated nuclear core and heat pipe system. Experimental data acquired in a number of different test scenarios will validate existing computational models, demonstrated system flexibility (fast start-ups, multiple start-ups/shut downs), simulate predictable failure modes and operating environments. The objective of the second part is to demonstrate an integrated propulsion system consisting of a core, conversion system and a thruster where the system converts thermal heat into jet power. This end-to-end system demonstration sets a precedent for ground testing of nuclear electric propulsion systems. The paper describes the SAFE 30 end-to-end system demonstration and its subsystems.
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High-pressure plastic scintillation detector for measuring radiogenic gases in flow systems
NASA Astrophysics Data System (ADS)
Schell, W. R.; Vives-Batlle, J.; Yoon, S. R.; Tobin, M. J.
1999-02-01
Radioactive gases are emitted into the atmosphere from nuclear electric power and nuclear fuel reprocessing plants, from hospitals discarding xenon used in diagnostic medicine, as well as from nuclear weapons tests. A high-pressure plastic scintillation detector was constructed to measure atmospheric levels of such radioactive gases by detecting the beta and internal conversion (IC) electron decays. Operational tests and calibrations were made that permit integration of the flow detectors into a portable Gas Analysis, Separation and Purification system (GASP). The equipment developed can be used for measuring fission gases released from nuclear reactor sources and/or as part of monitoring equipment for enforcing the Comprehensive Test Ban Treaty. The detector is being used routinely for in-line gas separation efficiency measurements, at the elevated operational pressures used for the high-pressure swing analysis system (2070 kPa) and at flow rates of 5-15 l/min [1, 2]. This paper presents the design features, operational methods, calibration, and detector applications.
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10 CFR 55.45 - Operating tests.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 2 2011-01-01 2011-01-01 false Operating tests. 55.45 Section 55.45 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) OPERATORS' LICENSES Written Examinations and Operating Tests § 55.45 Operating tests. (a) Content. The operating tests administered to applicants for operator and senior...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-06-03
... seismic analyses of the Nuclear Island (NI). Reclassifying backfill over the slopes of the excavation does... to define the VEGP GMRS and FIRS or the VEGP SASSI SSI seismic analyses of the Nuclear Island (NI...
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Code of Federal Regulations, 2011 CFR
2011-07-01
... § 192.32 Standards. (a) Standards for application during processing operations and prior to the end of... nonoperational and subject to a license by the Nuclear Regulatory Commission or an Agreement State shall limit... the Nuclear Regulatory Commission or Agreement State into individual site licenses. (ii) The Nuclear...
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10 CFR 810.7 - Generally authorized activities.
Code of Federal Regulations, 2011 CFR
2011-01-01
... determined that the following activities are generally authorized, provided no sensitive nuclear technology... continuing programs, to enhance the operational safety of an existing civilian nuclear power plant in a... off-site population posed by a civilian nuclear power plant in such a country; provided the Department...
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Code of Federal Regulations, 2010 CFR
2010-07-01
... § 192.32 Standards. (a) Standards for application during processing operations and prior to the end of... nonoperational and subject to a license by the Nuclear Regulatory Commission or an Agreement State shall limit... the Nuclear Regulatory Commission or Agreement State into individual site licenses. (ii) The Nuclear...
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10 CFR 810.7 - Generally authorized activities.
Code of Federal Regulations, 2010 CFR
2010-01-01
... determined that the following activities are generally authorized, provided no sensitive nuclear technology... continuing programs, to enhance the operational safety of an existing civilian nuclear power plant in a... off-site population posed by a civilian nuclear power plant in such a country; provided the Department...
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75 FR 9444 - Agency Information Collection Activities: Proposed Collection; Comment Request
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-02
... applications for licenses and amendments thereto to construct and operate nuclear power plants, preliminary or... NUCLEAR REGULATORY COMMISSION [Docket No. NRC-2010-0063] Agency Information Collection Activities: Proposed Collection; Comment Request AGENCY: U.S. Nuclear Regulatory Commission (NRC). ACTION: Notice of...
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10 CFR 55.59 - Requalification.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 2 2014-01-01 2014-01-01 false Requalification. 55.59 Section 55.59 Energy NUCLEAR... reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable and... outside containment). (AA) A nuclear instrumentation failure. (ii) Each licensed operator and senior...
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Major safety provisions in nuclear-powered ships
DOE Office of Scientific and Technical Information (OSTI.GOV)
Khlopkin, N.S.; Belyaev, V.M.; Dubrovin, A.M.
1984-12-01
Considerable experience has been accumulated in the Soviet Union on the design, construction and operation of nuclear-powered civilian ships: the icebreakers Lenin, Leonid Brezhnev and Sibir. The nuclear steam plants (NSP) used on these as the main energy source have been found to be highly reliable and safe, and it is desirable to use them in the future not only in icebreakers but also in transport ships for use in ice fields. The Soviet program for building and developing nuclear-powered ships has involved careful attention to safety in ships containing NSP. The experience with the design and operation of nuclearmore » icebreakers in recent years has led to the revision of safety standards for the nuclear ships and correspondingly ship NSP and international guidelines have been developed. If one meets the requirements as set forth in these documents, one has a safe basis for future Soviet nuclear-powered ships. The primary safety provisions for NSP are presented in this paper.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Haas, P M; Selby, D L; Hanley, M J
1983-09-01
This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of those variables is recommended. A high-level model of the Systems Approach to Training for use in the nuclear industry, which could serve as a model for NRC evaluation of industrymore » programs, is presented. The model is consistent with current publically stated NRC policy, with the approach being followed by the Institute for Nuclear Power Operations, and with current training technology. Checklists to be used by NRC evaluators to assess training programs for NPP control-room personnel are proposed which are based on this model.« less
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The United States Army Medical Department Journal. October-December 2007
2007-12-01
weapons assembly/disassembly and functions check; individual chemical, biological , radiological, nuclear and high-explosive defense; and the operation of...the 40 Army Warrior Tasks and 11 Battle Drills, to include advanced land navigation training; weapons familiarization and qualification; convoy...operations; chemical, biological , radiological, nuclear and high- explosive defense; and squad and platoon-patrol exercises in both woodland and urban
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Congressional Presentation for Foreign Operations, Fiscal Year 1999.
1998-01-01
chemical and biological weapons technology in Africa. However, there remains much to be done: - • Terrorism: The economic and political weakness of many...OPERATIONAL GOAL: Counter the proliferation of missile technology and nuclear, chemical, and biological Weapons . Levels of cooperation with our...34 terrorism; chemical, biological , nuclear, or radiological weapons . 6. Enhance CT cooperation through the establishment of legal instruments like mutual
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Code of Federal Regulations, 2010 CFR
2010-01-01
... State Materials and Environmental Management Programs, or Director, Office of Nuclear Material Safety... Reorganization Act, and this chapter, he will issue a license. If the license is for a facility, or for receipt... operations area under parts 60 or 63 of this chapter, or if it is to receive and possess high-level...
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The Chinese Navy: Expanding Capabilities, Evolving Roles
2011-01-01
AIRCRAFT 149 possible that the greater resources required to produce nuclear -powered boats might result in a reduction in the overall submarine...rines (two of which are nuclear powered), and other force enhancements such as three types of capable maritime interdiction aircraft, fast missile... disaster -relief operations, amphibious operations on disputed maritime territories, escorting merchant shipping, or (in the case of submarines and
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-07-28
... alternative, and the no-action alternative. The factors considered in the record of decision can be found in...-Year Period; Record of Decision Notice is hereby given that the U.S. Nuclear Regulatory Commission (the.... The notice also serves as the record of decision for the Renewal of Facility Operating License No. NPF...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-01
... Company, Mail Code A221, 220 Operation Way, Cayce, South Carolina 29033-3701. Tel: (803) 217-9162. i. FERC... withdrawal from, and discharge to, the Project's Monticello and Parr reservoirs to serve the construction and operation needs of two new nuclear generating plants at the V.C. Summer Nuclear Station. To facilitate this...
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2007-05-10
objective is achieved through consequence management and fixed-site decontamination operations. The effectiveness of CBRN consequence management...decontamination operations. The effectiveness of CBRN consequence management and fixed-site decontamination executed in the Joint Security Area can be...when faced with Chemical, Biological, Radiological, or Nuclear (CBRN) contaminated ports of debarkation. The effectiveness of CBRN consequence
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1982-04-30
Nuclear Test Operations South Atlantic ARGUS Christofilos Theory FLORAL ARGUS Effect JASON Van Allen Belts Nuclear Test Personnel Review (MTPR) MIDAS ...precluded radiological exposure. Project 7.3 -- Surface Measurements (Project MIDAS ) Agencies: This project, code-named MIDAS for security reasons, was...weapon casings, but these personnel were badged and equipped with ten self-reading pocket dosimeters as well as alpha-detection equipment provided by the
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VVER Reactor Safety in Eastern Europe and Former Soviet Union
NASA Astrophysics Data System (ADS)
Papadopoulou, Demetra
2012-02-01
VVER Soviet-designed reactors that operate in Eastern Europe and former Soviet republics have heightened international concern for years due to major safety deficiencies. The governments of countries with VVER reactors have invested millions of dollars toward improving the safety of their nuclear power plants. Most of these reactors will continue to operate for the foreseeable future since they provide urgently-needed electrical power. Given this situation, this paper assesses the radiological consequences of a major nuclear accident in Eastern Europe. The paper also chronicles the efforts launched by the international nuclear community to improve the safety of the reactors and notes the progress made so far through extensive collaborative efforts in Armenia, Bulgaria, the Czech Republic, Hungary, Kazakhstan, Lithuania, Russia, Slovakia, and Ukraine to reduce the risks of nuclear accidents. Western scientific and technical staff collaborated with these countries to improve the safety of their reactor operations by strengthening the ability of the regulator to perform its oversight function, installing safety equipment and technologies, investing time in safety training, and working diligently to establish an enduring safety culture. Still, continued safety improvement efforts are necessary to ensure safe operating practices and achieve timely phase-out of older plants.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Liu, Ning; Rutherford, Phil; Lee, Majelle
2005-09-01
This Annual Site Environmental Report (ASER) for 2004 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). In the past, the Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder components. All nuclear work was terminated inmore » 1988; all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Closure of the liquid metal test facilities began in 1996. Results of the radiological monitoring program for the calendar year 2004 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Liu, Ning; Rutherford, Phil
2007-09-01
This Annual Site Environmental Report (ASER) for 2006 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). In the past, the Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder components. All nuclear work was terminated inmore » 1988; all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Closure of the liquid metal test facilities began in 1996. Results of the radiological monitoring program for the calendar year 2006 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Harrison, Thomas J.; Howard, Richard H.; Rader, Jordan D.
This document is a notional technology implementation plan (TIP) for the development, testing, and qualification of a prototypic fuel element to support design and construction of a nuclear thermal propulsion (NTP) engine, specifically its pre-flight ground test. This TIP outlines a generic methodology for the progression from non-nuclear out-of-pile (OOP) testing through nuclear in-pile (IP) testing, at operational temperatures, flows, and specific powers, of an NTP fuel element in an existing test reactor. Subsequent post-irradiation examination (PIE) will occur in existing radiological facilities. Further, the methodology is intended to be nonspecific with respect to fuel types and irradiation or examinationmore » facilities. The goals of OOP and IP testing are to provide confidence in the operational performance of fuel system concepts and provide data to program leadership for system optimization and fuel down-selection. The test methodology, parameters, collected data, and analytical results from OOP, IP, and PIE will be documented for reference by the NTP operator and the appropriate regulatory and oversight authorities. Final full-scale integrated testing would be performed separately by the reactor operator as part of the preflight ground test.« less
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Economic Analysis of National Nuclear Security Administration (NNSA) Modernization Alternatives
2007-11-01
without nuclear testing; works to reduce global danger from weapons of mass destruction; provides the U.S. Navy with safe and effective nuclear...SFE) covers the acquisition of glove boxes, long-lead facility, and actinide chemistry/materials characterization (AC/MC) equipment whose uniqueness...Hazard Category II AC/MC and actinide Research and Development operations, special nuclear 5 Babcock
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Nuclear Power Plant Module, NPP-1: Nuclear Power Cost Analysis.
ERIC Educational Resources Information Center
Whitelaw, Robert L.
The purpose of the Nuclear Power Plant Modules, NPP-1, is to determine the total cost of electricity from a nuclear power plant in terms of all the components contributing to cost. The plan of analysis is in five parts: (1) general formulation of the cost equation; (2) capital cost and fixed charges thereon; (3) operational cost for labor,…
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The Organization and Management of the Nuclear Weapons Program.
1997-03-01
over operations include the Defense Nuclear Facilities Safety Board, the Environmental Protection Agency, the Occupational Safety and Health...Safety, and Health. Still more guidance is received from the Defense Nuclear Facilities Safety Board and other external bodies such as the...state regulatory agencies, and the Defense Nuclear Facilities Safety Board. This chapter briefly reviews the most recent decade of this history, describes
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Confinement of Radioactive Materials at Defense Nuclear Facilities
2004-10-01
The design of defense nuclear facilities includes systems whose reliable operation is vital to the protection of the public, workers, and the...final safety-class barrier to the release of hazardous materials with potentially serious public consequences. The Defense Nuclear Facilities Safety...the public at certain defense nuclear facilities . This change has resulted in downgrading of the functional safety classification of confinement
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ERIC Educational Resources Information Center
McCamey, Randy B.
2003-01-01
The need for workers in the U.S. nuclear power industry to continually update their knowledge, skills, and abilities is critical to the safe and reliable operation of the country's nuclear power facilities. To improve their skills, knowledge, and abilities, many professionals in the nuclear power industry participate in continuing professional…
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Code of Federal Regulations, 2010 CFR
2010-01-01
... could occur in a nuclear power plant. These sessions shall provide brigade members with experience in... A. Fire protection program. A fire protection program shall be established at each nuclear power... fires that could occur in the plant and in using the types of equipment available in the nuclear power...
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Applications in Nuclear Energy Security
NASA Astrophysics Data System (ADS)
Sheffield, Richard
2009-05-01
A key roadblock to development of additional nuclear power capacity is a concern over management of nuclear waste. Nuclear waste is predominantly comprised of used fuel discharged from operating nuclear reactors. The roughly 100 operating US reactors currently produce about 20% of the US electricity and will create about 87,000 tons of such discharged or ``spent'' fuel over the course of their lifetimes. The long-term radioactivity of the spent fuel drives the need for deep geologic storage that remains stable for millions of years. Nearly all issues related to risks to future generations arising from long-term disposal of such spent nuclear fuel is attributable to approximately the 1% made up primarily of minor actinides. If we can reduce or eliminate this 1% of the spent fuel, then within a few hundred years the toxic nature of the spent fuel drops below that of the natural uranium ore that was originally mined for nuclear fuel. The minor actinides can be efficiently eliminated through nuclear transmutation using as a driver fast-neutrons produced by a spallation process initiated with a high-energy proton beam. This presentation will cover the system design considerations and issues of an accelerator driven transmutation system.
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NASA Astrophysics Data System (ADS)
Budnitz, Robert J.
2015-03-01
The 101 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of "significant events" since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs for large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and several companies are vigorously working on designs for smaller, modular reactors. Although the Fukushima reactor accident in March 2011 in Japan has been an almost unmitigated disaster for the local population due to their being displaced from their homes and workplaces and also due to the land contamination, its "lessons learned" have been important for the broader nuclear industry, and will surely result in safer nuclear plants worldwide - indeed, have already done so, with more safety improvements to come.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Budnitz, Robert J.
The 101 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of 'significant events' since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs formore » large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and several companies are vigorously working on designs for smaller, modular reactors. Although the Fukushima reactor accident in March 2011 in Japan has been an almost unmitigated disaster for the local population due to their being displaced from their homes and workplaces and also due to the land contamination, its 'lessons learned' have been important for the broader nuclear industry, and will surely result in safer nuclear plants worldwide - indeed, have already done so, with more safety improvements to come.« less
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NASA Astrophysics Data System (ADS)
Haxton, Wick; Lunardini, Cecilia
2008-09-01
Semi-leptonic electroweak interactions in nuclei—such as β decay, μ capture, charged- and neutral-current neutrino reactions, and electron scattering—are described by a set of multipole operators carrying definite parity and angular momentum, obtained by projection from the underlying nuclear charge and three-current operators. If these nuclear operators are approximated by their one-body forms and expanded in the nucleon velocity through order |p→|/M, where p→ and M are the nucleon momentum and mass, a set of seven multipole operators is obtained. Nuclear structure calculations are often performed in a basis of Slater determinants formed from harmonic oscillator orbitals, a choice that allows translational invariance to be preserved. Harmonic-oscillator single-particle matrix elements of the multipole operators can be evaluated analytically and expressed in terms of finite polynomials in q, where q is the magnitude of the three-momentum transfer. While results for such matrix elements are available in tabular form, with certain restriction on quantum numbers, the task of determining the analytic form of a response function can still be quite tedious, requiring the folding of the tabulated matrix elements with the nuclear density matrix, and subsequent algebra to evaluate products of operators. Here we provide a Mathematica script for generating these matrix elements, which will allow users to carry out all such calculations by symbolic manipulation. This will eliminate the errors that may accompany hand calculations and speed the calculation of electroweak nuclear cross sections and rates. We illustrate the use of the new script by calculating the cross sections for charged- and neutral-current neutrino scattering in 12C. Program summaryProgram title: SevenOperators Catalogue identifier: AEAY_v1_0 Program summary URL:http://cpc.cs.qub.ac.uk/summaries/AEAY_v1_0.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 2227 No. of bytes in distributed program, including test data, etc.: 19 382 Distribution format: tar.gz Programming language: Mathematica Computer: Any computer running Mathematica; tested on Mac OS X PowerPC (32-bit) running Mathematica 6.0.0 Operating system: Any running Mathematica RAM: Memory requirements determined by Mathematica; 512 MB or greater RAM and hard drive space of at least 3.0 GB recommended Classification: 17.16, 17.19 Nature of problem: Algebraic evaluation of harmonic oscillator nuclear matrix elements for the one-body multipole operators governing semi-leptonic weak interactions, such as charged- or neutral-current neutrino scattering off nuclei. Solution method: Mathematica evaluation of associated angular momentum algebra and spherical Bessel function radial integrals. Running time: Depends on the complexity of the one-body density matrix employed, but times of a few seconds are typical.
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Situation awareness and trust in computer-based procedures in nuclear power plant operations
DOE Office of Scientific and Technical Information (OSTI.GOV)
Throneburg, E. B.; Jones, J. M.
2006-07-01
Situation awareness and trust are two issues that need to be addressed in the design of computer-based procedures for nuclear power plants. Situation awareness, in relation to computer-based procedures, concerns the operators' knowledge of the plant's state while following the procedures. Trust concerns the amount of faith that the operators put into the automated procedures, which can affect situation awareness. This paper first discusses the advantages and disadvantages of computer-based procedures. It then discusses the known aspects of situation awareness and trust as applied to computer-based procedures in nuclear power plants. An outline of a proposed experiment is then presentedmore » that includes methods of measuring situation awareness and trust so that these aspects can be analyzed for further study. (authors)« less
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NASA Astrophysics Data System (ADS)
Budnitz, Robert J.
2011-11-01
The 104 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of "significant events" since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs for large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and some designers are taking a second look at the economies of smaller, modular reactors.
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PWR design for low doses in the United Kingdom: The present and the future
DOE Office of Scientific and Technical Information (OSTI.GOV)
Zodiates, A.M.; Willcock, A.
1995-03-01
The Pressurizer Water Reactor (PWR) design chosen for adoption by Nuclear Electric plc was based on the Westinghouse Standard Nuclear Unit Power Plant System (SNUPPS). This design was developed to meet the United Kingdom (UK) requirements and those improvements are embodied in the Sizewell B plant. Nuclear Electric plc is now looking to the design of the future PWRs to be built in the UK. These PWRs will be based as replicas of the Sizewell B design, but attention will be given to reducing operator doses further. This paper details the approach in operator protection improvements incorporated at Sizewall B,more » presents the estimated annual collective dose, and identifies the approach being adopted to reduce further operator doses in future plants.« less
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Kwech, Horst
1989-04-18
A robotic arm positionable within a nuclear vessel by access through a small diameter opening and having a mounting tube supported within the vessel and mounting a plurality of arm sections for movement lengthwise of the mounting tube as well as for movement out of a window provided in the wall of the mounting tube. An end effector, such as a grinding head or welding element, at an operating end of the robotic arm, can be located and operated within the nuclear vessel through movement derived from six different axes of motion provided by mounting and drive connections between arm sections of the robotic arm. The movements are achieved by operation of remotely-controllable servo motors, all of which are mounted at a control end of the robotic arm to be outside the nuclear vessel.
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Remec, Igor; Rosseel, Thomas M; Field, Kevin G
Life extensions of nuclear power plants to 60 and potentially 80 years of operation have renewed interest in long-term material degradation. One material being considered is concrete, with a particular focus on radiation-induced effects. Based on the projected neutron fluence values (E > 0.1 MeV) in the concrete biological shields of the US pressurized water reactor fleet and the available data on radiation effects on concrete, some decrease in mechanical properties of concrete cannot be ruled out during extended operation beyond 60 years. An expansion of the irradiated concrete database and a reliable determination of relevant neutron fluence energy cutoffmore » value are necessary to ensure reliable risk assessment for extended operation of nuclear power plants.« less
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Analysis of Operation TEAPOT nuclear test BEE radiological and meteorological data
DOE Office of Scientific and Technical Information (OSTI.GOV)
Quinn, V.E.
This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the BEE nuclear test of Operation TEAPOT. Inconsistencies in the radiological data and their resolution are discussed. The methods of normalizing the radiological data to a standard time and estimating fallout-arrival times are presented. The meteorological situations on event day and the following day are described. A comparison of the WSNSO fallout analysis with an analysis performed in the 1950's is presented. The radiological data used to derive the WSNSO fallout pattern are tabulated in an appendix.
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Northwest passage: Trade route for large air cushion vehicles
NASA Technical Reports Server (NTRS)
Anderson, J. L.
1973-01-01
A conceptual vehicle and powerplant (10,000-ton) nuclear-powered air-cushion vehicle (ACV) that could open the Northwest Passage and other Arctic passages to commercial traffic is identified. The report contains a description of the conceptual vehicle, including the powerplant and operations, an assessment of technical feasibility, estimates of capital and operating costs, and identification of eligible cargo and markets. A comparison of the nuclear ACV freighter with nuclear container ships shows that for containerized or roll-on/roll-off cargo the ACV would provide greatly reduced transit time between North Atlantic and North Pacific ports at a competitive cost.
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76 FR 59175 - Sunshine Act Meeting
Federal Register 2010, 2011, 2012, 2013, 2014
2011-09-23
...) (Tentative) a. Southern Nuclear Operating Co. (Vogtle Electric Generating Plant, Units 3 and 4)--Appeal of LBP-10-21 (Tentative) b. Luminant Generation Company LLC (Comanche Peak Nuclear Power Plant, Units 3...) c. Progress Energy Florida, Inc. (Levy County Nuclear Power Plant, Units 1 and 2), Staff Petition...
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10 CFR 52.167 - Issuance of manufacturing license.
Code of Federal Regulations, 2010 CFR
2010-01-01
... proposed reactor(s) can be incorporated into a nuclear power plant and operated at sites having... design and manufacture the proposed nuclear power reactor(s); (5) The proposed inspections, tests... the construction of a nuclear power facility using the manufactured reactor(s). (2) A holder of a...
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10 CFR 51.95 - Postconstruction environmental impact statements.
Code of Federal Regulations, 2011 CFR
2011-01-01
... the storage of spent fuel for the nuclear power plant within the scope of the generic determination in... a license to store spent fuel at a nuclear power reactor after expiration of the operating or... Section 51.95 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR...
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10 CFR 51.95 - Postconstruction environmental impact statements.
Code of Federal Regulations, 2012 CFR
2012-01-01
... the storage of spent fuel for the nuclear power plant within the scope of the generic determination in... a license to store spent fuel at a nuclear power reactor after expiration of the operating or... Section 51.95 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR...
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Defense Threat Reduction Agency > Home > Operating Status
FOIA Electronic Reading Room Privacy Impact Assessment DTRA No Fear Act Reporting Nuclear Test Personnel Review NTPR Fact Sheets NTPR Radiation Dose Assessment Documents US Atmospheric Nuclear Test History Documents US Underground Nuclear Test History Reports NTPR Radiation Exposure Reports Enewetak
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10 CFR 50.57 - Issuance of operating license. 1
Code of Federal Regulations, 2011 CFR
2011-01-01
... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...
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10 CFR 50.57 - Issuance of operating license. 1
Code of Federal Regulations, 2014 CFR
2014-01-01
... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...
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10 CFR 50.57 - Issuance of operating license. 1
Code of Federal Regulations, 2013 CFR
2013-01-01
... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...
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10 CFR 50.57 - Issuance of operating license. 1
Code of Federal Regulations, 2012 CFR
2012-01-01
... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...
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10 CFR 50.57 - Issuance of operating license. 1
Code of Federal Regulations, 2010 CFR
2010-01-01
... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...
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A dynamical systems model for nuclear power plant risk
NASA Astrophysics Data System (ADS)
Hess, Stephen Michael
The recent transition to an open access generation marketplace has forced nuclear plant operators to become much more cost conscious and focused on plant performance. Coincidentally, the regulatory perspective also is in a state of transition from a command and control framework to one that is risk-informed and performance-based. Due to these structural changes in the economics and regulatory system associated with commercial nuclear power plant operation, there is an increased need for plant management to explicitly manage nuclear safety risk. Application of probabilistic risk assessment techniques to model plant hardware has provided a significant contribution to understanding the potential initiating events and equipment failures that can lead to core damage accidents. Application of the lessons learned from these analyses has supported improved plant operation and safety over the previous decade. However, this analytical approach has not been nearly as successful in addressing the impact of plant processes and management effectiveness on the risks of plant operation. Thus, the research described in this dissertation presents a different approach to address this issue. Here we propose a dynamical model that describes the interaction of important plant processes among themselves and their overall impact on nuclear safety risk. We first provide a review of the techniques that are applied in a conventional probabilistic risk assessment of commercially operating nuclear power plants and summarize the typical results obtained. The limitations of the conventional approach and the status of research previously performed to address these limitations also are presented. Next, we present the case for the application of an alternative approach using dynamical systems theory. This includes a discussion of previous applications of dynamical models to study other important socio-economic issues. Next, we review the analytical techniques that are applicable to analysis of these models. Details of the development of the mathematical risk model are presented. This includes discussion of the processes included in the model and the identification of significant interprocess interactions. This is followed by analysis of the model that demonstrates that its dynamical evolution displays characteristics that have been observed at commercially operating plants. The model is analyzed using the previously described techniques from dynamical systems theory. From this analysis, several significant insights are obtained with respect to the effective control of nuclear safety risk. Finally, we present conclusions and recommendations for further research.
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Financing Strategies For A Nuclear Fuel Cycle Facility
DOE Office of Scientific and Technical Information (OSTI.GOV)
David Shropshire; Sharon Chandler
2006-07-01
To help meet the nation’s energy needs, recycling of partially used nuclear fuel is required to close the nuclear fuel cycle, but implementing this step will require considerable investment. This report evaluates financing scenarios for integrating recycling facilities into the nuclear fuel cycle. A range of options from fully government owned to fully private owned were evaluated using DPL (Decision Programming Language 6.0), which can systematically optimize outcomes based on user-defined criteria (e.g., lowest lifecycle cost, lowest unit cost). This evaluation concludes that the lowest unit costs and lifetime costs are found for a fully government-owned financing strategy, due tomore » government forgiveness of debt as sunk costs. However, this does not mean that the facilities should necessarily be constructed and operated by the government. The costs for hybrid combinations of public and private (commercial) financed options can compete under some circumstances with the costs of the government option. This analysis shows that commercial operations have potential to be economical, but there is presently no incentive for private industry involvement. The Nuclear Waste Policy Act (NWPA) currently establishes government ownership of partially used commercial nuclear fuel. In addition, the recently announced Global Nuclear Energy Partnership (GNEP) suggests fuels from several countries will be recycled in the United States as part of an international governmental agreement; this also assumes government ownership. Overwhelmingly, uncertainty in annual facility capacity led to the greatest variations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; and the annual operating costs, forgiveness of debt, and overnight costs dominate the costs computed for the government case. The uncertainty in operations, leading to lower than optimal processing rates (or annual plant throughput), is the most detrimental issue to achieving low unit costs. Conversely, lowering debt interest rates and the required return on investments can reduce costs for private industry.« less
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Operation CASTLE. Report of the Manager Santa Fe Operations. Extracted Version.
Nuclear explosion testing, *Test facilities, *Management planning and control, Pacific Ocean, Eniwetok Atoll, Bikini Atoll, Marshall Islands , Organizations, Construction, Operation, Management, Logistics support, Costs
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Liu, Ning; Rutherford, Phil; Amar, Ravnesh
2010-09-01
This Annual Site Environmental Report (ASER) for 2009 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, andmore » all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2009 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less
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DOE Office of Scientific and Technical Information (OSTI.GOV)
Liu, Ning; Rutherford, Phil; Amar, Ravnesh
2011-09-01
This Annual Site Environmental Report (ASER) for 2010 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, andmore » all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2010 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less
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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.
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Nuclear energy and radioactive waste disposal in the age of recycling
DOE Office of Scientific and Technical Information (OSTI.GOV)
Conca, James L.; Apted, Michael
2007-07-01
The magnitude of humanity's energy needs requires that we embrace a multitude of various energy sources and applications. For a variety of reasons, nuclear energy must be a major portion of the distribution, at least one third. The often-cited strategic hurdle to this approach is nuclear waste disposal. Present strategies concerning disposal of nuclear waste need to be changed if the world is to achieve both a sustainable energy distribution by 2040 and solve the largest environmental issue of the 21. century - global warming. It is hoped that ambitious proposals to replace fossil fuel power generation by alternatives willmore » drop the percentage of fossil fuel use substantially, but the absolute amount of fossil fuel produced electricity must be kept at or below its present 10 trillion kW-hrs/year. Unfortunately, the rapid growth in consumption to over 30 trillion kW-hrs/year by 2040, means that 20 trillion kW-hrs/yr of non-fossil fuel generated power has to come from other sources. If half of that comes from alternative non-nuclear, non-hydroelectric sources (an increase of 3000%), then nuclear still needs to increase by a factor of four worldwide to compensate. Many of the reasons nuclear energy did not expand after 1970 in North America (proliferation, capital costs, operational risks, waste disposal, and public fear) are no longer a problem. The WIPP site in New Mexico, an example of a solution to the nuclear waste disposal issue, and also to public fear, is an operating deep geologic nuclear waste repository in the massive bedded salt of the Salado Formation. WIPP has been operating for eight years, and as of this writing, has disposed of over 50,000 m{sup 3} of transuranic waste (>100 nCi/g but <23 Curie/liter) including high activity waste. The Salado Formation is an ideal host for any type of nuclear waste, especially waste from recycled spent fuel. (authors)« less
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Improving online risk assessment with equipment prognostics and health monitoring
DOE Office of Scientific and Technical Information (OSTI.GOV)
Coble, Jamie B.; Liu, Xiaotong; Briere, Chris
The current approach to evaluating the risk of nuclear power plant (NPP) operation relies on static probabilities of component failure, which are based on industry experience with the existing fleet of nominally similar light water reactors (LWRs). As the nuclear industry looks to advanced reactor designs that feature non-light water coolants (e.g., liquid metal, high temperature gas, molten salt), this operating history is not available. Many advanced reactor designs use advanced components, such as electromagnetic pumps, that have not been used in the US commercial nuclear fleet. Given the lack of rich operating experience, we cannot accurately estimate the evolvingmore » probability of failure for basic components to populate the fault trees and event trees that typically comprise probabilistic risk assessment (PRA) models. Online equipment prognostics and health management (PHM) technologies can bridge this gap to estimate the failure probabilities for components under operation. The enhanced risk monitor (ERM) incorporates equipment condition assessment into the existing PRA and risk monitor framework to provide accurate and timely estimates of operational risk.« less
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Code of Federal Regulations, 2010 CFR
2010-01-01
... environmental impacts of renewing the operating license for a nuclear power plant as required by section 102(2... cooling ponds and is not expected to be a problem during the license renewal term. Aquatic Ecology (for... depression beyond the site boundary. Impacts of large ground-water withdrawal for cooling tower makeup at...
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Operations Optimization of Nuclear Hybrid Energy Systems
Chen, Jun; Garcia, Humberto E.; Kim, Jong Suk; ...
2016-08-01
We proposed a plan for nuclear hybrid energy systems (NHES) as an effective element to incorporate high penetration of clean energy. Our paper focuses on the operations optimization of two specific NHES configurations to address the variability raised from various markets and renewable generation. Both analytical and numerical approaches are used to obtain the optimization solutions. Furthermore, key economic figures of merit are evaluated under optimized and constant operations to demonstrate the benefit of the optimization, which also suggests the economic viability of considered NHES under proposed operations optimizer. Furthermore, sensitivity analysis on commodity price is conducted for better understandingmore » of considered NHES.« less
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Operations Optimization of Nuclear Hybrid Energy Systems
DOE Office of Scientific and Technical Information (OSTI.GOV)
Chen, Jun; Garcia, Humberto E.; Kim, Jong Suk
We proposed a plan for nuclear hybrid energy systems (NHES) as an effective element to incorporate high penetration of clean energy. Our paper focuses on the operations optimization of two specific NHES configurations to address the variability raised from various markets and renewable generation. Both analytical and numerical approaches are used to obtain the optimization solutions. Furthermore, key economic figures of merit are evaluated under optimized and constant operations to demonstrate the benefit of the optimization, which also suggests the economic viability of considered NHES under proposed operations optimizer. Furthermore, sensitivity analysis on commodity price is conducted for better understandingmore » of considered NHES.« less
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NIF Operations Management Plan, August 2011
DOE Office of Scientific and Technical Information (OSTI.GOV)
Van Wonterghem, Bruno M.
Lawrence Livermore National Laboratory’s (LLNL) National Ignition Facility (NIF) is a key component of the National Nuclear Security Administration’s (NNSA) Stockpile Stewardship Program, whose purpose is to maintain the safety, reliability, and effectiveness of our nation’s nuclear stockpile without underground nuclear testing. The NIF is crucial to the Stockpile Stewardship Program because it is the only facility that can create the conditions of extreme temperature and pressure—conditions that exist only in stars or in exploding nuclear weapons—that are relevant to understanding how our modern nuclear weapons operate. As such, the NIF’s primary mission is to attain fusion ignition in themore » laboratory. Fusion ignition not only supports Stockpile Stewardship needs, but also provides the basis for future decisions about fusion’s potential as a long-term energy source. Additionally, NIF provides scientists with access to high-energy-density regimes that can yield new insight and understanding in the areas of astrophysics, hydrodynamics, material properties, plasma physics, and radiative properties. The use of the NIF to support the Stockpile Stewardship Program and the advancement of basic high-energy-density science understanding is planned and managed through program-level execution plans and NIF directorate-level management teams. An example of a plan is the National Ignition Campaign Execution Plan. The NIF Operations Management Plan provides an overview of the NIF Operations organization and describes how the NIF is supported by the LLNL infrastructure and how it is safely and responsibly managed and operated. Detailed information on NIF management of the organization is found in a series of supporting plans, policies, and procedures. A list of related acronyms can be found in Appendix A of this document. The purpose of this document is to provide a roadmap of how the NIF Operations organization functions. It provides a guide to understanding the requirements, document flow down, organizational vision and mission, performance metrics, and interrelationship of the NIF Operations organization with other directorate and laboratory organizations. This document also provides a listing of roles and responsibilities, core processes, procedures, authority matrices, change control boards, and other information necessary for successfully functioning in the NIF Operations organization. This document, the NIF Shot Operations Plan, and the NIF Maintenance Plan together represent the primary documents satisfying our Conduct of Operations compliance requirement.« less
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Testing in Support of Space Fission System Development and Qualification
NASA Technical Reports Server (NTRS)
Houts, Mike; Bragg-Sitton, Shannon; Garber, Anne; Godfrey, Tom; Martin, Jim; Pearson, Boise; Webster, Kenny
2007-01-01
Extensive data would be required for the qualification of a fission surface power (FSP) system. The strategy for qualifying a FSP system could have a significant programmatic impact. This paper explores potential options that could be used for qualifying FSP systems, including cost-effective means for obtaining required data. three methods for obtaining qualification data are analysis, non-nuclear testing, and nuclear testing. It has been over 40 years since the US qualified a space reactor for launch. During that time, advances have been made related to all three methods. Perhaps the greatest advancement has occurred in the area of computational tools for design and analysis. Tools that have been developed, coupled with modem computers, would have a significant impact on a FSP qualification. This would be especially true for systems with materials and fuels operating well within temperature, irradiation damage, and burnup limits. The ability to perform highly realistic non-nuclear testing has also advanced throughout the past four decades. Instrumented thermal simulators were developed during the 1970s and 1980s to assist in the development, operation, and assessment of terrestrial fission systems. Instrumented thermal simulators optimized for assisting in the development, operation, and assessment of modem FSP systems have been under development (and utilized) since 1998. These thermal simulators enable heat from fission to be closely mimicked (axial power profile, radial power profile, temperature, heat flux, etc.} and extensive data to be taken from the core region. Both steady-state and transient operation can be tested. For transient testing, reactivity feedback is calculated (or measured in cold/warm criticals) based on reactor temperature and/or dimensional changes. Pin power during a transient is then calculated based on the reactivity feedback that would occur given measured values of temperature and/or dimensional change. In this way nonnuclear testing can be used to provide very realistic information related to nuclear operation. Non-nuclear testing can be used at all levels, including component, subsystem, and integrated system testing. Realistic non-nuclear testing is most useful for systems operating within known temperature, irradiation damage, and burnup capabilities.
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78 FR 57904 - Request for a License To Export; Reactor Components
Federal Register 2010, 2011, 2012, 2013, 2014
2013-09-20
... NUCLEAR REGULATORY COMMISSION Request for a License To Export; Reactor Components Pursuant to 10..., systems, related reactors. operation of AP- XR177, 11006121. equipment, and 1000 (design) spare parts. nuclear reactors. Dated this 16th day of September 2013 in Rockville, Maryland. For The Nuclear Regulatory...
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Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-18
... understand VY's design, layout, and construction. This failure to comprehend and understand the layout... Facilities,'' and General Design Criteria 60, ``Control of Releases of Radioactive Materials to the Environment,'' and 64, ``Monitoring Radioactivity Releases,'' of Appendix A, ``General Design Criteria for...
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76 FR 59748 - Sunshine Act Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2011-09-27
.... Southern Nuclear Operating Co. (Vogtle Electric Generating Plant, Units 3 and 4)--Appeal of LBP-10-21 (Tentative). b. Luminant Generation Company LLC (Comanche Peak Nuclear Power Plant, Units 3 and 4... Florida, Inc. (Levy County Nuclear Power Plant, Units 1 and 2), Staff Petition for Review of LBP-10-20...
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Federal Register 2010, 2011, 2012, 2013, 2014
2010-10-01
... Supplemental Environmental Impact Statement for the Nuclear Facility Portion of the Chemistry and Metallurgy... construction and operation of the nuclear facility portion of the Chemistry and Metallurgy Research Building... Chemistry and Metallurgy Research Building Replacement Project at Los Alamos National Laboratory, Los Alamos...
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Soldiers’ Psychological Responses to Tactical Nuclear Warfare
1992-02-01
530. Greene , T.L. (1987). Description of a nuclear battlefield. In R.H. Young & B.H. Drum (Edo.), Proceedings of the Defense Nuclear Agency Symposium...ATTN: DEPT OF BEHAVOR SCI & LEADERSHIP ATTN: PMS/PMA-423 ATTN: DEPT OF PHYSICS COL J G CAMPBELL ATTN: SCIENCE RESEARCH LAB OPERATIONAL TEST & EVALUATION
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DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
A South Korean consortium won the contract to build and operate four nuclear power plants in Abu Dhabi valued at $20.4 billion. The deal was significant since it is the first major nuclear contract of its kind awarded in the rapidly growing Persian Gulf region, and signals the rise of Korea as an exporter of nuclear know-how.
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78 FR 70588 - STP Nuclear Operating Company; South Texas Project
Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-26
... efficiency; (8) wind power; (9) solar power; (10) hydroelectric power; (11) ocean wave and current energy... generic environmental impact statement for license renewal of nuclear plants; issuance. SUMMARY: Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) has published the final, plant-specific...
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78 FR 9745 - Kewaunee Power Station; Application for Amendment to Facility Operating License
Federal Register 2010, 2011, 2012, 2013, 2014
2013-02-11
... FURTHER INFORMATION CONTACT: Karl Feintuch, Project Manager, Office of Nuclear Reactor Regulation, U.S... Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2013-03037 Filed 2-8-13; 8:45 am] BILLING CODE... NUCLEAR REGULATORY COMMISSION [Docket No. 50-305; NRC-2013-0028] Kewaunee Power Station...
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10 CFR 50.30 - Filing of application; oath or affirmation.
Code of Federal Regulations, 2012 CFR
2012-01-01
... Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and... Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation, or the Director..., operating license, early site permit, combined license, or manufacturing license for a nuclear power reactor...
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Federal Register 2010, 2011, 2012, 2013, 2014
2012-12-20
... upgraded licenses or license renewals to operate the controls at a nuclear reactor facility. This... NUCLEAR REGULATORY COMMISSION [Docket No. NRC-2012-0184] Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB) Review; Comment Request AGENCY: Nuclear Regulatory...
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10 CFR 50.30 - Filing of application; oath or affirmation.
Code of Federal Regulations, 2011 CFR
2011-01-01
... Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and... Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation, or the Director..., operating license, early site permit, combined license, or manufacturing license for a nuclear power reactor...
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10 CFR 50.30 - Filing of application; oath or affirmation.
Code of Federal Regulations, 2014 CFR
2014-01-01
... Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and... Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation, or the Director..., operating license, early site permit, combined license, or manufacturing license for a nuclear power reactor...
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10 CFR 50.30 - Filing of application; oath or affirmation.
Code of Federal Regulations, 2013 CFR
2013-01-01
... Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and... Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation, or the Director..., operating license, early site permit, combined license, or manufacturing license for a nuclear power reactor...
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Code of Federal Regulations, 2013 CFR
2013-01-01
... in Light-Water-Cooled Nuclear Power Reactor Effluents I Appendix I to Part 50 Energy NUCLEAR... Criterion “As Low as is Reasonably Achievable” for Radioactive Material in Light-Water-Cooled Nuclear Power... light-water-cooled nuclear power reactors licensed under 10 CFR part 50 or part 52 of this chapter. The...
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Code of Federal Regulations, 2012 CFR
2012-01-01
... in Light-Water-Cooled Nuclear Power Reactor Effluents I Appendix I to Part 50 Energy NUCLEAR... Criterion “As Low as is Reasonably Achievable” for Radioactive Material in Light-Water-Cooled Nuclear Power... light-water-cooled nuclear power reactors licensed under 10 CFR part 50 or part 52 of this chapter. The...
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Code of Federal Regulations, 2014 CFR
2014-01-01
... in Light-Water-Cooled Nuclear Power Reactor Effluents I Appendix I to Part 50 Energy NUCLEAR... Criterion “As Low as is Reasonably Achievable” for Radioactive Material in Light-Water-Cooled Nuclear Power... light-water-cooled nuclear power reactors licensed under 10 CFR part 50 or part 52 of this chapter. The...
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Solving nuts-and-bolts nuclear problems
DOE Office of Scientific and Technical Information (OSTI.GOV)
Olmstead, A.; Schoen, J.
1979-05-01
The Operations and Maintenance Information Service (MIS), created and operated by NUS Corp., was designed to improve plant availability through the exchange of practical information between nuclear plants and a return to an emphasis on the problem-solving process. MIS meetings cover a range of plant problems and have been unique in bringing the rapid feedback of information pertinent to the day-to-day working operation of a total plant. Much of the response is by telephone contact, although the monthly newsletter, semi-annual meetings, and scheduled plant visits are also helpful.
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Mobile robotics application in the nuclear industry
DOE Office of Scientific and Technical Information (OSTI.GOV)
Jones, S.L.; White, J.R.
1995-03-01
Mobile robots have been developed to perform hazardous operations in place of human workers. Applications include nuclear plant inspection/maintenance, decontamination and decommissioning police/military explosive ordinance disposal (EOD), hostage/terrorist negotiations and fire fighting. Nuclear facilities have proven that robotic applications can be cost-effective solutions to reducing personnel exposure and plant downtime. The first applications of mobile robots in the nuclear industry began in the early 1980`s, with the first vehicles being one of a kind machines or adaptations of commercial EOD robots. These activities included efforts by numerous commercial companies, the U.S. Nuclear Regulatory Commission, EPRI, and several national laboratories. Somemore » of these efforts were driven by the recovery and cleanup activities at TMI which demonstrated the potential and need for a remote means of performing surveillance and maintenance tasks in nuclear plants. The use of these machines is now becoming commonplace in nuclear facilities throughout the world. The hardware maturity and the confidence of the users has progressed to the point where the applications of mobile robots is not longer considered a novelty. These machines are being used in applications where the result is to help achieve more aggressive goals for personnel radiation exposure and plant availability, perform tasks more efficiently, and allow plant operators to retrieve information from areas previously considered inaccessible. Typical examples include surveillance in high radiation areas (during operation and outage activities), radiation surveys, waste handling, and decontamination evolutions. This paper will discuss this evolution including specific applications experiences, examples of currently available technology, and the benefits derived from the use of mobile robotic vehicles in commercial nuclear power facilities.« less