Sample records for definition document reactor

  1. Safety approach to the selection of design criteria for the CRBRP reactor refueling system

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Meisl, C J; Berg, G E; Sharkey, N F

    1979-01-01

    The selection of safety design criteria for Liquid Metal Fast Breeder Reactor (LMFBR) refueling systems required the extrapolation of regulations and guidelines intended for Light Water Reactor refueling systems and was encumbered by the lack of benefit from a commercially licensed predecessor other than Fermi. The overall approach and underlying logic are described for developing safety design criteria for the reactor refueling system (RRS) of the Clinch River Breeder Reactor Plant (CRBRP). The complete selection process used to establish the criteria is presented, from the definition of safety functions to the finalization of safety design criteria in the appropriate documents.more » The process steps are illustrated by examples.« less

  2. 10 CFR 50.2 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... to bring and maintain the plant in safe shutdown (non-design basis accident). Applicant means a... Document Control Desk. Nuclear reactor means an apparatus, other than an atomic weapon, designed or used to... from the Restricted Data category pursuant to section 142 of the Act. Safe shutdown (non-design basis...

  3. 10 CFR 50.2 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... to bring and maintain the plant in safe shutdown (non-design basis accident). Applicant means a... Document Control Desk. Nuclear reactor means an apparatus, other than an atomic weapon, designed or used to... from the Restricted Data category pursuant to section 142 of the Act. Safe shutdown (non-design basis...

  4. 10 CFR 50.2 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... to bring and maintain the plant in safe shutdown (non-design basis accident). Applicant means a... Document Control Desk. Nuclear reactor means an apparatus, other than an atomic weapon, designed or used to... from the Restricted Data category pursuant to section 142 of the Act. Safe shutdown (non-design basis...

  5. 10 CFR 50.2 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... to bring and maintain the plant in safe shutdown (non-design basis accident). Applicant means a... Document Control Desk. Nuclear reactor means an apparatus, other than an atomic weapon, designed or used to... from the Restricted Data category pursuant to section 142 of the Act. Safe shutdown (non-design basis...

  6. Next Generation Nuclear Plant Defense-in-Depth Approach

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Edward G. Wallace; Karl N. Fleming; Edward M. Burns

    2009-12-01

    The purpose of this paper is to (1) document the definition of defense-in-depth and the pproach that will be used to assure that its principles are satisfied for the NGNP project and (2) identify the specific questions proposed for preapplication discussions with the NRC. Defense-in-depth is a safety philosophy in which multiple lines of defense and conservative design and evaluation methods are applied to assure the safety of the public. The philosophy is also intended to deliver a design that is tolerant to uncertainties in knowledge of plant behavior, component reliability or operator performance that might compromise safety. This papermore » includes a review of the regulatory foundation for defense-in-depth, a definition of defense-in-depth that is appropriate for advanced reactor designs based on High Temperature Gas-cooled Reactor (HTGR) technology, and an explanation of how this safety philosophy is achieved in the NGNP.« less

  7. 10 CFR 100.3 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... COMMISSION (CONTINUED) REACTOR SITE CRITERIA § 100.3 Definitions. As used in this part: Combined license... power facilities. Exclusion area means that area surrounding the reactor, in which the reactor licensee.... Activities unrelated to operation of the reactor may be permitted in an exclusion area under appropriate...

  8. 10 CFR 100.3 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... COMMISSION (CONTINUED) REACTOR SITE CRITERIA § 100.3 Definitions. As used in this part: Combined license... power facilities. Exclusion area means that area surrounding the reactor, in which the reactor licensee.... Activities unrelated to operation of the reactor may be permitted in an exclusion area under appropriate...

  9. Reactor operation environmental information document

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Haselow, J.S.; Price, V.; Stephenson, D.E.

    1989-12-01

    The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimalmore » impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.« less

  10. 10 CFR 2.1105 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Hearing Procedures for Expansion of Spent Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors § 2.1105 Definitions. As used in this part: (a) Civilian nuclear power reactor means a civilian... reactor following irradiation, the constituent elements of which have not been separated by reprocessing. ...

  11. 40 CFR 60.701 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Synthetic Organic Chemical Manufacturing Industry (SOCMI) Reactor Processes § 60.701 Definitions. As used in... means any noncontinuous reactor process that is not characterized by steady-state conditions and in.... Reactor processes are unit operations in which one or more chemicals, or reactants other than air, are...

  12. 10 CFR 2.1105 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors § 2.1105 Definitions. As used in this part: (a) Civilian nuclear power reactor means a civilian nuclear power plant required to be licensed... nuclear fuel means fuel that has been withdrawn from a nuclear reactor following irradiation, the...

  13. 10 CFR 2.1105 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors § 2.1105 Definitions. As used in this part: (a) Civilian nuclear power reactor means a civilian nuclear power plant required to be licensed... nuclear fuel means fuel that has been withdrawn from a nuclear reactor following irradiation, the...

  14. 10 CFR 2.1105 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Hearing Procedures for Expansion of Spent Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors § 2.1105 Definitions. As used in this part: (a) Civilian nuclear power reactor means a civilian... 10 Energy 1 2011-01-01 2011-01-01 false Definitions. 2.1105 Section 2.1105 Energy NUCLEAR...

  15. 10 CFR 2.1105 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Hearing Procedures for Expansion of Spent Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors § 2.1105 Definitions. As used in this part: (a) Civilian nuclear power reactor means a civilian... 10 Energy 1 2012-01-01 2012-01-01 false Definitions. 2.1105 Section 2.1105 Energy NUCLEAR...

  16. Defining the "proven technology" technical criterion in the reactor technology assessment for Malaysia's nuclear power program

    NASA Astrophysics Data System (ADS)

    Anuar, Nuraslinda; Kahar, Wan Shakirah Wan Abdul; Manan, Jamal Abdul Nasir Abd

    2015-04-01

    Developing countries that are considering the deployment of nuclear power plants (NPPs) in the near future need to perform reactor technology assessment (RTA) in order to select the most suitable reactor design. The International Atomic Energy Agency (IAEA) reported in the Common User Considerations (CUC) document that "proven technology" is one of the most important technical criteria for newcomer countries in performing the RTA. The qualitative description of five desired features for "proven technology" is relatively broad and only provides a general guideline to its characterization. This paper proposes a methodology to define the "proven technology" term according to a specific country's requirements using a three-stage evaluation process. The first evaluation stage screens the available technologies in the market against a predefined minimum Technology Readiness Level (TRL) derived as a condition based on national needs and policy objectives. The result is a list of technology options, which are then assessed in the second evaluation stage against quantitative definitions of CUC desired features for proven technology. The potential technology candidates produced from this evaluation is further narrowed down to obtain a list of proven technology candidates by assessing them against selected risk criteria and the established maximum allowable total score using a scoring matrix. The outcome of this methodology is the proven technology candidates selected using an accurate definition of "proven technology" that fulfills the policy objectives, national needs and risk, and country-specific CUC desired features of the country that performs this assessment. A simplified assessment for Malaysia is carried out to demonstrate and suggest the use of the proposed methodology. In this exercise, ABWR, AP1000, APR1400 and EPR designs assumed the top-ranks of proven technology candidates according to Malaysia's definition of "proven technology".

  17. A document review to characterize Atomic International SNAP fuels shipped to INEL 1966--1973

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wahnschaffe, S.D.; Lords, R.E.; Kneff, D.W.

    1995-09-01

    This report provides the results of a document search and review study to obtain information on the spent fuels for the following six Nuclear Auxiliary Power (SNAP) reactor cores now stored at the Idaho National Engineering Laboratory (INEL): SNAP-2 Experimental Reactor, SNAP-2 Development Reactor, SNAP-10A Ground Test Reactor, SNAP-8 Experimental Reactor, SNAP-8 Development Reactor, and Shield Test Reactor. The report also covers documentation on SNAP fuel materials from four in-pile materials tests: NAA-82-1, NAA-115-2, NAA-117-1, and NAA-121. Pieces of these fuel materials are also stored at INEL as part of the SNAP fuel shipments.

  18. 77 FR 37074 - License Amendment Request From the Alan J. Blotcky Reactor Facility

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-20

    ... the Alan J. Blotcky Reactor Facility AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... section of this document. FOR FURTHER INFORMATION CONTACT: Theodore Smith, Project Manager, Reactor... provided the first time that a document is referenced. The Alan J. Blotcky Reactor Facility Decommissioning...

  19. Minutes of the third annual meeting of the Panel on Reference Nuclear Data. [BNL, October 5, 1978

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Burrows, T.W.; Stewart, L.; Coyne, J.J.

    1979-05-01

    The major activities of the meeting were as follows: welcome; organization, approval of minutes of the second meeting, and approval of agenda; review of nuclear data compilation and evaluation efforts (national and international efforts, master data files, publications); summary of 1977 panel meeting; definition of reference nuclear data; discussion of specific data needs and possible data center contributions (reactor physics, medicine and biology, controlled thermonuclear reactors and astrophysics); establishment of current interest and future direction of the panel; adjournment. Recommendations and action items are listed. Tables on nuclear data needs in applied physics, medicine and biology, and controlled thermonuclear reactorsmore » and astrophysics are presented. Appendixes include membership lists of various committees, summaries of publication activities, survey results, correspondence, and portions of the documents Proceedings of the Magnetic Fusion Energy Blanket and Shield Workshop and National Needs for Critically Evaluated Physical and Chemical Data. (RWR)« less

  20. 40 CFR 60.611 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... From the Synthetic Organic Chemical Manufacturing Industry (SOCMI) Air Oxidation Unit Processes § 60... given them. Air Oxidation Reactor means any device or process vessel in which one or more organic... compounds. Ammoxidation and oxychlorination reactions are included in this definition. Air Oxidation Reactor...

  1. 40 CFR 60.611 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... From the Synthetic Organic Chemical Manufacturing Industry (SOCMI) Air Oxidation Unit Processes § 60... given them. Air Oxidation Reactor means any device or process vessel in which one or more organic... compounds. Ammoxidation and oxychlorination reactions are included in this definition. Air Oxidation Reactor...

  2. 40 CFR 60.611 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... From the Synthetic Organic Chemical Manufacturing Industry (SOCMI) Air Oxidation Unit Processes § 60... given them. Air Oxidation Reactor means any device or process vessel in which one or more organic... compounds. Ammoxidation and oxychlorination reactions are included in this definition. Air Oxidation Reactor...

  3. 40 CFR 60.611 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... From the Synthetic Organic Chemical Manufacturing Industry (SOCMI) Air Oxidation Unit Processes § 60... given them. Air Oxidation Reactor means any device or process vessel in which one or more organic... compounds. Ammoxidation and oxychlorination reactions are included in this definition. Air Oxidation Reactor...

  4. Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Culbert, W.H.

    1985-10-01

    This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliancemore » with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit.« less

  5. Space Nuclear Power Plant Pre-Conceptual Design Report, For Information

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    B. Levine

    2006-01-27

    This letter transmits, for information, the Project Prometheus Space Nuclear Power Plant (SNPP) Pre-Conceptual Design Report completed by the Naval Reactors Prime Contractor Team (NRPCT). This report documents the work pertaining to the Reactor Module, which includes integration of the space nuclear reactor with the reactor radiation shield, energy conversion, and instrumentation and control segments. This document also describes integration of the Reactor Module with the Heat Rejection segment, the Power Conditioning and Distribution subsystem (which comprise the SNPP), and the remainder of the Prometheus spaceship.

  6. 10 CFR 52.1 - Definitions.

    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...

  7. 10 CFR 52.1 - Definitions.

    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...

  8. 10 CFR 52.1 - Definitions.

    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...

  9. 10 CFR 52.1 - Definitions.

    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...

  10. Guideline for Performing Systematic Approach to Evaluate and Qualify Legacy Documents that Support Advanced Reactor Technology Activity

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Honma, George

    The establishment of a systematic process for the evaluation of historic technology information for use in advanced reactor licensing is described. Efforts are underway to recover and preserve Experimental Breeder Reactor II and Fast Flux Test Facility historical data. These efforts have generally emphasized preserving information from data-acquisition systems and hard-copy reports and entering it into modern electronic formats suitable for data retrieval and examination. The guidance contained in this document has been developed to facilitate consistent and systematic evaluation processes relating to quality attributes of historic technical information (with focus on sodium-cooled fast reactor (SFR) technology) that will bemore » used to eventually support licensing of advanced reactor designs. The historical information may include, but is not limited to, design documents for SFRs, research-and-development (R&D) data and associated documents, test plans and associated protocols, operations and test data, international research data, technical reports, and information associated with past U.S. Nuclear Regulatory Commission (NRC) reviews of SFR designs. The evaluation process is prescribed in terms of SFR technology, but the process can be used to evaluate historical information for any type of advanced reactor technology. An appendix provides a discussion of typical issues that should be considered when evaluating and qualifying historical information for advanced reactor technology fuel and source terms, based on current light water reactor (LWR) requirements and recent experience gained from Next Generation Nuclear Plant (NGNP).« less

  11. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Anuar, Nuraslinda, E-mail: nuraslinda@uniten.edu.my; Kahar, Wan Shakirah Wan Abdul, E-mail: shakirah@tnb.com.my; Manan, Jamal Abdul Nasir Abd

    Developing countries that are considering the deployment of nuclear power plants (NPPs) in the near future need to perform reactor technology assessment (RTA) in order to select the most suitable reactor design. The International Atomic Energy Agency (IAEA) reported in the Common User Considerations (CUC) document that “proven technology” is one of the most important technical criteria for newcomer countries in performing the RTA. The qualitative description of five desired features for “proven technology” is relatively broad and only provides a general guideline to its characterization. This paper proposes a methodology to define the “proven technology” term according to amore » specific country’s requirements using a three-stage evaluation process. The first evaluation stage screens the available technologies in the market against a predefined minimum Technology Readiness Level (TRL) derived as a condition based on national needs and policy objectives. The result is a list of technology options, which are then assessed in the second evaluation stage against quantitative definitions of CUC desired features for proven technology. The potential technology candidates produced from this evaluation is further narrowed down to obtain a list of proven technology candidates by assessing them against selected risk criteria and the established maximum allowable total score using a scoring matrix. The outcome of this methodology is the proven technology candidates selected using an accurate definition of “proven technology” that fulfills the policy objectives, national needs and risk, and country-specific CUC desired features of the country that performs this assessment. A simplified assessment for Malaysia is carried out to demonstrate and suggest the use of the proposed methodology. In this exercise, ABWR, AP1000, APR1400 and EPR designs assumed the top-ranks of proven technology candidates according to Malaysia’s definition of “proven technology”.« less

  12. Advanced Nuclear Technology: Advanced Light Water Reactors Utility Requirements Document Small Modular Reactors Inclusion Summary

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Loflin, Leonard; McRimmon, Beth

    2014-12-18

    This report summarizes a project by EPRI to include requirements for small modular light water reactors (smLWR) into the EPRI Utility Requirements Document (URD) for Advanced Light Water Reactors. The project was jointly funded by EPRI and the U.S. Department of Energy (DOE). The report covers the scope and content of the URD, the process used to revise the URD to include smLWR requirements, a summary of the major changes to the URD to include smLWR, and how to use the URD as revised to achieve value on new plant projects.

  13. SP-100 Program: space reactor system and subsystem investigations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Harty, R.B.

    1983-09-30

    For a space reactor power system, a comprehensive safety program will be required to assure that no undue risk is present. This report summarizes the nuclear safety review/approval process that will be required for a space reactor system. The documentation requirements are presented along with a summary of the required contents of key documents. Finally, the aerospace safety program conducted for the SNAP-10A reactor system is summarized. The results of this program are presented to show the type of program that can be expected and to provide information that could be usable in future programs.

  14. SP-100 program: Space reactor system and subsystem investigations

    NASA Astrophysics Data System (ADS)

    Harty, R. B.

    1983-09-01

    For a space reactor power system, a comprehensive safety program will be required to assure that no undue risk is present. The nuclear safety review/approval process that is required for a space reactor system is summarized. The documentation requirements are presented along with a summary of the required contents of key documents. Finally, the aerospace safety program conducted for the SNAP-10A reactor system is summarized. The results of this program are presented to show the type of program that is expected and to provide information that could be usable in future programs.

  15. Environmental Information Document: L-reactor reactivation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mackey, H.E. Jr.

    1982-04-01

    Purpose of this Environmental Information Document is to provide background for assessing environmental impacts associated with the renovation, restartup, and operation of L Reactor at the Savannah River Plant (SRP). SRP is a major US Department of Energy installation for the production of nuclear materials for national defense. The purpose of the restart of L Reactor is to increase the production of nuclear weapons materials, such as plutonium and tritium, to meet projected needs in the nuclear weapons program.

  16. INL Experimental Program Roadmap for Thermal Hydraulic Code Validation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Glenn McCreery; Hugh McIlroy

    2007-09-01

    Advanced computer modeling and simulation tools and protocols will be heavily relied on for a wide variety of system studies, engineering design activities, and other aspects of the Next Generation Nuclear Power (NGNP) Very High Temperature Reactor (VHTR), the DOE Global Nuclear Energy Partnership (GNEP), and light-water reactors. The goal is for all modeling and simulation tools to be demonstrated accurate and reliable through a formal Verification and Validation (V&V) process, especially where such tools are to be used to establish safety margins and support regulatory compliance, or to design a system in a manner that reduces the role ofmore » expensive mockups and prototypes. Recent literature identifies specific experimental principles that must be followed in order to insure that experimental data meet the standards required for a “benchmark” database. Even for well conducted experiments, missing experimental details, such as geometrical definition, data reduction procedures, and manufacturing tolerances have led to poor Benchmark calculations. The INL has a long and deep history of research in thermal hydraulics, especially in the 1960s through 1980s when many programs such as LOFT and Semiscle were devoted to light-water reactor safety research, the EBRII fast reactor was in operation, and a strong geothermal energy program was established. The past can serve as a partial guide for reinvigorating thermal hydraulic research at the laboratory. However, new research programs need to fully incorporate modern experimental methods such as measurement techniques using the latest instrumentation, computerized data reduction, and scaling methodology. The path forward for establishing experimental research for code model validation will require benchmark experiments conducted in suitable facilities located at the INL. This document describes thermal hydraulic facility requirements and candidate buildings and presents examples of suitable validation experiments related to VHTRs, sodium-cooled fast reactors, and light-water reactors. These experiments range from relatively low-cost benchtop experiments for investigating individual phenomena to large electrically-heated integral facilities for investigating reactor accidents and transients.« less

  17. Review of the Tri-Agency Space Nuclear Reactor Power System Technology Program

    NASA Technical Reports Server (NTRS)

    Ambrus, J. H.; Wright, W. E.; Bunch, D. F.

    1984-01-01

    The Space Nuclear Reactor Power System Technology Program designated SP-100 was created in 1983 by NASA, the U.S. Department of Defense, and the Defense Advanced Research Projects Agency. Attention is presently given to the development history of SP-100 over the course of its first year, in which it has been engaged in program objectives' definition, the analysis of civil and military missions, nuclear power system functional requirements' definition, concept definition studies, the selection of primary concepts for technology feasibility validation, and the acquisition of initial experimental and analytical results.

  18. 77 FR 41670 - Definition of Terms

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-16

    ... cryptography'', 2. On page 642, add the term ``Explosives'', 3. On page 650, add the term ``Nuclear reactor... ``Commerce Control List''. * * * * * Nuclear reactor. (Cat 0 and 2) includes the items within or attached directly to the reactor vessel, the equipment which controls the level of power in the core, and the...

  19. Supervisory Control System Architecture for Advanced Small Modular Reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cetiner, Sacit M; Cole, Daniel L; Fugate, David L

    2013-08-01

    This technical report was generated as a product of the Supervisory Control for Multi-Modular SMR Plants project within the Instrumentation, Control and Human-Machine Interface technology area under the Advanced Small Modular Reactor (SMR) Research and Development Program of the U.S. Department of Energy. The report documents the definition of strategies, functional elements, and the structural architecture of a supervisory control system for multi-modular advanced SMR (AdvSMR) plants. This research activity advances the state-of-the art by incorporating decision making into the supervisory control system architectural layers through the introduction of a tiered-plant system approach. The report provides a brief history ofmore » hierarchical functional architectures and the current state-of-the-art, describes a reference AdvSMR to show the dependencies between systems, presents a hierarchical structure for supervisory control, indicates the importance of understanding trip setpoints, applies a new theoretic approach for comparing architectures, identifies cyber security controls that should be addressed early in system design, and describes ongoing work to develop system requirements and hardware/software configurations.« less

  20. 10 CFR 862.3 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... landing or for any other reason. (f) Manager of Operations. The manager of a DOE field office, the Manager of the Pittsburgh Naval Reactors Office, the Manager of the Schnectady Naval Reactors Office and, for...

  1. 10 CFR 862.3 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... landing or for any other reason. (f) Manager of Operations. The manager of a DOE field office, the Manager of the Pittsburgh Naval Reactors Office, the Manager of the Schnectady Naval Reactors Office and, for...

  2. 10 CFR 862.3 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... landing or for any other reason. (f) Manager of Operations. The manager of a DOE field office, the Manager of the Pittsburgh Naval Reactors Office, the Manager of the Schnectady Naval Reactors Office and, for...

  3. 10 CFR 862.3 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... landing or for any other reason. (f) Manager of Operations. The manager of a DOE field office, the Manager of the Pittsburgh Naval Reactors Office, the Manager of the Schnectady Naval Reactors Office and, for...

  4. 49 CFR 1177.1 - Definitions and classifications of documents.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 8 2011-10-01 2011-10-01 false Definitions and classifications of documents. 1177.1 Section 1177.1 Transportation Other Regulations Relating to Transportation (Continued) SURFACE... Definitions and classifications of documents. (a) A “primary document” is a mortgage (excluding those under...

  5. 78 FR 3470 - DTE Electric Company (Formerly the Detroit Edison Company), Notice of Availability of Final...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-16

    ...--specific Web page at http://www.nrc.gov/reactors/new-reactors/col/fermi.html . The Ellis Library and... possesses and are publicly-available, using any of the following methods: Federal Rulemaking Web site: Go to... Documents Access and Management System (ADAMS): You may access publicly-available documents online in the...

  6. Gary-Chicago-Milwaukee corridor : corridor transportation information center : system glossary

    DOT National Transportation Integrated Search

    1995-10-30

    The following definitions, abbreviations and acronyms are generated from the : System Definition Document (Document #9931.GCM), the Interface Control : Specification (Document #9932.GCM), and the Requirements Specification (Document : #9933.GCM). The...

  7. 75 FR 13610 - Office of New Reactors; Interim Staff Guidance on Implementation of a Seismic Margin Analysis for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-22

    ... Staff Guidance on Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic... Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment,'' (Agencywide Documents.../COL-ISG-020 ``Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic Risk...

  8. 10 CFR 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear...

    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...

  9. 10 CFR 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear...

    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...

  10. 10 CFR 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear...

    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...

  11. Documentation for MeshKit - Reactor Geometry (&mesh) Generator

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jain, Rajeev; Mahadevan, Vijay

    2015-09-30

    This report gives documentation for using MeshKit’s Reactor Geometry (and mesh) Generator (RGG) GUI and also briefly documents other algorithms and tools available in MeshKit. RGG is a program designed to aid in modeling and meshing of complex/large hexagonal and rectilinear reactor cores. RGG uses Argonne’s SIGMA interfaces, Qt and VTK to produce an intuitive user interface. By integrating a 3D view of the reactor with the meshing tools and combining them into one user interface, RGG streamlines the task of preparing a simulation mesh and enables real-time feedback that reduces accidental scripting mistakes that could waste hours of meshing.more » RGG interfaces with MeshKit tools to consolidate the meshing process, meaning that going from model to mesh is as easy as a button click. This report is designed to explain RGG v 2.0 interface and provide users with the knowledge and skills to pilot RGG successfully. Brief documentation of MeshKit source code, tools and other algorithms available are also presented for developers to extend and add new algorithms to MeshKit. RGG tools work in serial and parallel and have been used to model complex reactor core models consisting of conical pins, load pads, several thousands of axially varying material properties of instrumentation pins and other interstices meshes.« less

  12. Implementation Plan for Qualification of Sodium-Cooled Fast Reactor Technology Information

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moe, Wayne; Honma, George

    This document identifies and discusses implementation elements that can be used to facilitate consistent and systematic evaluation processes relating to quality attributes of technical information (with focus on SFR technology) that will be used to support licensing of advanced reactor designs. Information may include, but is not limited to, design documents for SFRs, research-and-development (R&D) data and associated documents, test plans and associated protocols, operations and test data, international research data, technical reports, and information associated with past U.S. Nuclear Regulatory Commission (NRC) reviews of SFR designs. The approach for determining acceptability of test data, analysis, and/or other technical informationmore » is based on guidance provided in INL/EXT-15-35805, “Guidance on Evaluating Historic Technology Information for Use in Advanced Reactor Licensing.” The implementation plan can be adopted into a working procedure at each of the national laboratories performing data qualification, or by applicants seeking future license application for advanced reactor technology.« less

  13. 40 CFR 60.701 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Synthetic Organic Chemical Manufacturing Industry (SOCMI) Reactor Processes § 60.701 Definitions. As used in... means by individual stream components, not carbon equivalents. Car-seal means a seal that is placed on a...

  14. Proceedings of the 1992 topical meeting on advances in reactor physics. Volume 2

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1992-04-01

    This document, Volume 2, presents proceedings of the 1992 Topical Meeting on Advances in Reactor Physics on March 8--11, 1992 at Charleston, SC. Session topics were as follows: Transport Theory; Fast Reactors; Plant Analyzers; Integral Experiments/Measurements & Analysis; Core Computational Systems; Reactor Physics; Monte Carlo; Safety Aspects of Heavy Water Reactors; and Space-Time Core Kinetics. The individual reports have been cataloged separately. (FI)

  15. Definition of a Robust Supervisory Control Scheme for Sodium-Cooled Fast Reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ponciroli, R.; Passerini, S.; Vilim, R. B.

    In this work, an innovative control approach for metal-fueled Sodium-cooled Fast Reactors is proposed. With respect to the classical approach adopted for base-load Nuclear Power Plants, an alternative control strategy for operating the reactor at different power levels by respecting the system physical constraints is presented. In order to achieve a higher operational flexibility along with ensuring that the implemented control loops do not influence the system inherent passive safety features, a dedicated supervisory control scheme for the dynamic definition of the corresponding set-points to be supplied to the PID controllers is designed. In particular, the traditional approach based onmore » the adoption of tabulated lookup tables for the set-point definition is found not to be robust enough when failures of the implemented SISO (Single Input Single Output) actuators occur. Therefore, a feedback algorithm based on the Reference Governor approach, which allows for the optimization of reference signals according to the system operating conditions, is proposed.« less

  16. Aging management program of the reactor building concrete at Point Lepreau Generating Station

    NASA Astrophysics Data System (ADS)

    Aldea, C.-M.; Shenton, B.; Demerchant, M. M.; Gendron, T.

    2011-04-01

    In order for New Brunswick Power Nuclear (NBPN) to control the risks of degradation of the concrete reactor building at the Point Lepreau Generating Station (PLGS) the development of an aging management plan (AMP) was initiated. The intention of this plan was to determine the requirements for specific structural components of concrete of the reactor building that require regular inspection and maintenance to ensure the safe and reliable operation of the plant. The document is currently in draft form and presents an integrated methodology for the application of an AMP for the concrete of the reactor building. The current AMP addresses the reactor building structure and various components, such as joint sealant and liners that are integral to the structure. It does not include internal components housed within the structure. This paper provides background information regarding the document developed and the strategy developed to manage potential degradation of the concrete of the reactor building, as well as specific programs and preventive and corrective maintenance activities initiated.

  17. 77 FR 55877 - Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-11

    ...-492- 3668; email: [email protected] . NRC's Agencywide Documents Access and Management System... Systems for Light-Water Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Systems for Boiling Water Reactor Power Plants.'' This regulatory guide is being revised to: (1) Expand...

  18. 10 CFR 73.4 - Communications.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ...: Document Control Desk, Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors...://www.nrc.gov/site-help/e-submittals.html; by e-mail to [email protected]; or by writing the Office...

  19. Handbook explaining the fundamentals of nuclear and atomic physics

    NASA Technical Reports Server (NTRS)

    Hanlen, D. F.; Morse, W. J.

    1969-01-01

    Indoctrination document presents nuclear, reactor, and atomic physics in an easy, straightforward manner. The entire subject of nuclear physics including atomic structure ionization, isotopes, radioactivity, and reactor dynamics is discussed.

  20. 75 FR 36126 - Office of New Reactors; Proposed Revision to Standard Review Plan Section 13.6.1, Revision 1 on...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-24

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0228] Office of New Reactors; Proposed Revision to Standard Review Plan Section 13.6.1, Revision 1 on Physical Security--Combined License and Operating...), Section 13.6.1 on ``Physical Security--Combined License and Operating Reactors,'' (Agencywide Documents...

  1. Appendix F. Developmental enforcement algorithm definition document : predictive braking enforcement algorithm definition document.

    DOT National Transportation Integrated Search

    2012-05-01

    The purpose of this document is to fully define and describe the logic flow and mathematical equations for a predictive braking enforcement algorithm intended for implementation in a Positive Train Control (PTC) system.

  2. 40 CFR 60.701 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Volatile Organic Compound Emissions From Synthetic Organic Chemical Manufacturing Industry (SOCMI) Reactor Processes § 60.701 Definitions. As used in.... Incinerator means an enclosed combustion device that is used for destroying organic compounds. If there is...

  3. 40 CFR 60.701 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Volatile Organic Compound Emissions From Synthetic Organic Chemical Manufacturing Industry (SOCMI) Reactor Processes § 60.701 Definitions. As used in.... Incinerator means an enclosed combustion device that is used for destroying organic compounds. If there is...

  4. 10 CFR 140.5 - Communications.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ...: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Federal and State Materials and Environmental Management Programs, or..., Rockville, Maryland; or, where practicable, by electronic submission, for example, via Electronic...

  5. 10 CFR 140.5 - Communications.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ...: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Federal and State Materials and Environmental Management Programs, or..., Rockville, Maryland; or, where practicable, by electronic submission, for example, via Electronic...

  6. Manned space flight nuclear system safety. Volume 3: Reactor system preliminary nuclear safety analysis. Part 1: Reference Design Document (RDD)

    NASA Technical Reports Server (NTRS)

    1972-01-01

    The Reference Design Document, of the Preliminary Safety Analysis Report (PSAR) - Reactor System provides the basic design and operations data used in the nuclear safety analysis of the Rector Power Module as applied to a Space Base program. A description of the power module systems, facilities, launch vehicle and mission operations, as defined in NASA Phase A Space Base studies is included. Each of two Zirconium Hydride Reactor Brayton power modules provides 50 kWe for the nominal 50 man Space Base. The INT-21 is the prime launch vehicle. Resupply to the 500 km orbit over the ten year mission is provided by the Space Shuttle. At the end of the power module lifetime (nominally five years), a reactor disposal system is deployed for boost into a 990 km high altitude (long decay time) earth orbit.

  7. 8 CFR 270.1 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Definitions. 270.1 Section 270.1 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS PENALTIES FOR DOCUMENT FRAUD § 270.1 Definitions. For the purpose of this part— Document means an instrument on which is recorded, by means of...

  8. Reactor operations informal monthly report, May 1, 1995--May 31, 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hauptman, H.M.; Petro, J.N.; Jacobi, O.

    1995-05-01

    This document is an informal progress report for the operational performance of the Brookhaven Medical Research Reactor, and the Brookhaven High Flux Beam Reactor, for the month of May, 1995. Both machines ran well during this period, with no reportable instrumentation problems, all scheduled maintenance performed, and only one reportable occurance, involving a particle on Vest Button, Personnel Radioactive Contamination.

  9. 40 CFR 63.1579 - What definitions apply to this subpart?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... regeneration of catalyst in situ in any one of several reactors (e.g., 4 or 5 separate reactors) that can be..., wet injection, or caustic injection control device that treats (in-situ) the catalytic reforming unit...) at specified intervals or at the owner's or operator's convenience for in situ catalyst regeneration...

  10. 40 CFR 63.1579 - What definitions apply to this subpart?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... regeneration of catalyst in situ in any one of several reactors (e.g., 4 or 5 separate reactors) that can be..., wet injection, or caustic injection control device that treats (in-situ) the catalytic reforming unit...) at specified intervals or at the owner's or operator's convenience for in situ catalyst regeneration...

  11. 40 CFR 63.1579 - What definitions apply to this subpart?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... regeneration of catalyst in situ in any one of several reactors (e.g., 4 or 5 separate reactors) that can be..., wet injection, or caustic injection control device that treats (in-situ) the catalytic reforming unit...) at specified intervals or at the owner's or operator's convenience for in situ catalyst regeneration...

  12. System Definition Document

    DOT National Transportation Integrated Search

    1996-06-12

    The Gary-Chicago-Milwaukee (GCM) Corridor Transportation Information Center : (C-TIC) System Definition Document describes the C-TIC concept and defines the : high level processes and dataflows. The Requirements Specification together : with the Inte...

  13. 8 CFR 1270.1 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Definitions. 1270.1 Section 1270.1 Aliens... PENALTIES FOR DOCUMENT FRAUD § 1270.1 Definitions. For the purpose of this part— Document means an instrument on which is recorded, by means of letters, figures, or marks, matters which may be used to fulfill...

  14. 8 CFR 1270.1 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 8 Aliens and Nationality 1 2014-01-01 2014-01-01 false Definitions. 1270.1 Section 1270.1 Aliens... PENALTIES FOR DOCUMENT FRAUD § 1270.1 Definitions. For the purpose of this part— Document means an instrument on which is recorded, by means of letters, figures, or marks, matters which may be used to fulfill...

  15. 8 CFR 1270.1 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 8 Aliens and Nationality 1 2011-01-01 2011-01-01 false Definitions. 1270.1 Section 1270.1 Aliens... PENALTIES FOR DOCUMENT FRAUD § 1270.1 Definitions. For the purpose of this part— Document means an instrument on which is recorded, by means of letters, figures, or marks, matters which may be used to fulfill...

  16. 8 CFR 1270.1 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 8 Aliens and Nationality 1 2012-01-01 2012-01-01 false Definitions. 1270.1 Section 1270.1 Aliens... PENALTIES FOR DOCUMENT FRAUD § 1270.1 Definitions. For the purpose of this part— Document means an instrument on which is recorded, by means of letters, figures, or marks, matters which may be used to fulfill...

  17. 15 CFR 280.2 - Definitions used in this subpart.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... PROGRAMS FASTENER QUALITY General § 280.2 Definitions used in this subpart. In addition to the definitions... the United States Patent and Trademark Office. Act. The Fastener Quality Act (15 U.S.C. 5401 et seq... ISO/IEC Guides or other documents, and redesignations of those Guides or documents. Under Secretary...

  18. 15 CFR 280.2 - Definitions used in this subpart.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... PROGRAMS FASTENER QUALITY General § 280.2 Definitions used in this subpart. In addition to the definitions... the United States Patent and Trademark Office. Act. The Fastener Quality Act (15 U.S.C. 5401 et seq... ISO/IEC Guides or other documents, and redesignations of those Guides or documents. Under Secretary...

  19. Manned space flight nuclear system safety. Volume 3: Reactor system preliminary nuclear safety analysis. Part 2: Accident Model Document (AMD)

    NASA Technical Reports Server (NTRS)

    1972-01-01

    The Accident Model Document is one of three documents of the Preliminary Safety Analysis Report (PSAR) - Reactor System as applied to a Space Base Program. Potential terrestrial nuclear hazards involving the zirconium hydride reactor-Brayton power module are identified for all phases of the Space Base program. The accidents/events that give rise to the hazards are defined and abort sequence trees are developed to determine the sequence of events leading to the hazard and the associated probabilities of occurence. Source terms are calculated to determine the magnitude of the hazards. The above data is used in the mission accident analysis to determine the most probable and significant accidents/events in each mission phase. The only significant hazards during the prelaunch and launch ascent phases of the mission are those which arise form criticality accidents. Fission product inventories during this time period were found to be very low due to very limited low power acceptance testing.

  20. 9 CFR 51.20 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Indemnity for Sheep, Goats, and Horses § 51.20 Definitions. Accredited veterinarian. A veterinarian approved... for the Administrator. Affected herd/flock. Any herd or flock in which any cattle, bison, breeding swine, sheep, or goat has been classified as a brucellosis reactor and which has not been released from...

  1. 9 CFR 51.20 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Indemnity for Sheep, Goats, and Horses § 51.20 Definitions. Accredited veterinarian. A veterinarian approved... for the Administrator. Affected herd/flock. Any herd or flock in which any cattle, bison, breeding swine, sheep, or goat has been classified as a brucellosis reactor and which has not been released from...

  2. Updating the definition and role of public health nursing to advance and guide the specialty.

    PubMed

    Bekemeier, Betty; Walker Linderman, Tessa; Kneipp, Shawn; Zahner, Susan J

    2015-01-01

    National changes in the context for public health services are influencing the nature of public health nursing practice. Despite this, the document that defines public health nursing as a specialty--The Definition and Role of Public Health Nursing--has remained in wide use since its publication in 1996 without a review or update. With support from the American Public Health Association (APHA) Public Health Nursing Section, a national Task Force, was formed in November 2012 to update the definition of public health nursing, using processes that reflected deliberative democratic principles. A yearlong process was employed that included a modified Delphi technique and various modes of engagement such as online discussion boards, questionnaires, and public comment to review. The resulting 2013 document consisted of a reaffirmation of the one-sentence 1996 definition, while updating supporting documentation to align with the current social, economic, political, and health care context. The 2013 document was strongly endorsed by vote of the APHA Public Health Nursing Section elected leadership. The 2013 definition and document affirm the relevance of a population-focused definition of public health nursing to complex systems addressed in current practice and articulate critical roles of public health nurses (PHN) in these settings. © 2014 Wiley Periodicals, Inc.

  3. 10 CFR 51.121 - Status of NEPA actions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... address inquiries to: (a) Utilization facilities: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate, U.S. Nuclear Regulatory Commission... NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND...

  4. 10 CFR 51.121 - Status of NEPA actions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... address inquiries to: (a) Utilization facilities: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate, U.S. Nuclear Regulatory Commission... NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND...

  5. 10 CFR 51.121 - Status of NEPA actions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... address inquiries to: (a) Utilization facilities: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate, U.S. Nuclear Regulatory Commission... NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND...

  6. Aluminum Carbothermic Technology

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bruno, Marshall J.

    2005-03-31

    This report documents the non-proprietary research and development conducted on the Aluminum Carbothermic Technology (ACT) project from contract inception on July 01, 2000 to termination on December 31, 2004. The objectives of the program were to demonstrate the technical and economic feasibility of a new carbothermic process for producing commercial grade aluminum, designated as the ''Advanced Reactor Process'' (ARP). The scope of the program ranged from fundamental research through small scale laboratory experiments (65 kW power input) to larger scale test modules at up to 1600 kW power input. The tasks included work on four components of the process, Stagesmore » 1 and 2 of the reactor, vapor recovery and metal alloy decarbonization; development of computer models; and economic analyses of capital and operating costs. Justification for developing a new, carbothermic route to aluminum production is defined by the potential benefits in reduced energy, lower costs and more favorable environmental characteristics than the conventional Hall-Heroult process presently used by the industry. The estimated metrics for these advantages include energy rates at approximately 10 kWh/kg Al (versus over 13 kWh/kg Al for Hall-Heroult), capital costs as low as $1250 per MTY (versus 4,000 per MTY for Hall-Heroult), operating cost reductions of over 10%, and up to 37% reduction in CO2 emissions for fossil-fuel power plants. Realization of these benefits would be critical to sustaining the US aluminum industries position as a global leader in primary aluminum production. One very attractive incentive for ARP is its perceived ability to cost effectively produce metal over a range of smelter sizes, not feasible for Hall-Heroult plants which must be large, 240,000 TPY or more, to be economical. Lower capacity stand alone carbothermic smelters could be utilized to supply molten metal at fabrication facilities similar to the mini-mill concept employed by the steel industry. Major accomplishments for the program include definition of the system thermo-chemistry, demonstration of reactor stage 1, development of reactor stage 2 critical components in a 500 kW module, experimental determination of the vapor recovery reactor fundamentals, detailed design and installation of an advanced stage 1/vapor recovery reactor, feasibility of efficient separation of Al-C metal alloy product, updated capital and operating cost estimates, and development of computer models for all steps of the Advanced Reactor Process.« less

  7. VET in Schools 2016: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2017

    2017-01-01

    This document covers the data terms used in the "VET in Schools 2016" summary publication. The primary purpose of this document is to assist users to understand the specific data terms. Terms that appear in the publication are listed in alphabetical order with the following information provided for each: (1) definition: a brief…

  8. SciReader enables reading of medical content with instantaneous definitions.

    PubMed

    Gradie, Patrick R; Litster, Megan; Thomas, Rinu; Vyas, Jay; Schiller, Martin R

    2011-01-25

    A major problem patients encounter when reading about health related issues is document interpretation, which limits reading comprehension and therefore negatively impacts health care. Currently, searching for medical definitions from an external source is time consuming, distracting, and negatively impacts reading comprehension and memory of the material. SciReader was built as a Java application with a Flex-based front-end client. The dictionary used by SciReader was built by consolidating data from several sources and generating new definitions with a standardized syntax. The application was evaluated by measuring the percentage of words defined in different documents. A survey was used to test the perceived effect of SciReader on reading time and comprehension. We present SciReader, a web-application that simplifies document interpretation by allowing users to instantaneously view medical, English, and scientific definitions as they read any document. This tool reveals the definitions of any selected word in a small frame at the top of the application. SciReader relies on a dictionary of ~750,000 unique Biomedical and English word definitions. Evaluation of the application shows that it maps ~98% of words in several different types of documents and that most users tested in a survey indicate that the application decreases reading time and increases comprehension. SciReader is a web application useful for reading medical and scientific documents. The program makes jargon-laden content more accessible to patients, educators, health care professionals, and the general public.

  9. 10 CFR 73.4 - Communications.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ...: Document Control Desk, Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or Director, Division of Security Policy... 10 Energy 2 2012-01-01 2012-01-01 false Communications. 73.4 Section 73.4 Energy NUCLEAR...

  10. VET in Schools 2009: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "VET in Schools 2009" report. The primary purpose of this document is to assist users of the report to understand the specific data terms used within it. Terms that appear in the report are listed in alphabetical order with the following information provided for each: (1) Definition: a…

  11. VET in Schools 2008: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "VET in Schools 2008" report. The primary purpose of this document is to assist users of the report to understand the specific data terms used within it. Terms that appear in the report are listed in alphabetical order with the following information provided for each: (1) Definition: a…

  12. VET in Schools, 2007: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2009

    2009-01-01

    This document covers the data terms used in the "VET in Schools, 2007" report. The primary purpose of this document is to help users of the report understand the specific data terms used in it. Terms that appear in the report are listed in alphabetical order with the following information provided for each: (1) Definition: a brief…

  13. VET in Schools, 2006: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2008

    2008-01-01

    This document covers the data terms used in the "VET in Schools, 2006" report. The primary purpose of this document is to help users understand the specific data terms used in the report. Terms that appear in the report are listed in alphabetical order with the following information provided for each: (1) Definition: a brief explanation…

  14. 78 FR 24441 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Evolutionary...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-25

    ... Reactor (U.S. EPR) will hold a meeting on May 8-9, 2013, Room T-2B1, 11545 Rockville Pike, Rockville... License Application (COLA) associated with the U.S. EPR Design Control Document (DCD). The Subcommittee...

  15. 76 FR 22935 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-25

    ... Power Reactor (U.S. EPR) will hold a meeting on May 11, 2011, Room T-2B1, 11545 Rockville Pike.... EPR Design Control Document (DCD). The Subcommittee will hear presentations by and hold discussions...

  16. 10 CFR 2.107 - Withdrawal of application.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... NUCLEAR REGULATORY COMMISSION AGENCY RULES OF PRACTICE AND PROCEDURE Procedure for Issuance, Amendment... authorize the removal of any document from the files of the Commission. (c) The Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Federal and State Materials and...

  17. 10 CFR 2.107 - Withdrawal of application.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... NUCLEAR REGULATORY COMMISSION AGENCY RULES OF PRACTICE AND PROCEDURE Procedure for Issuance, Amendment... authorize the removal of any document from the files of the Commission. (c) The Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Federal and State Materials and...

  18. Quality Assurance Program Plan for SFR Metallic Fuel Data Qualification

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Benoit, Timothy; Hlotke, John Daniel; Yacout, Abdellatif

    2017-07-05

    This document contains an evaluation of the applicability of the current Quality Assurance Standards from the American Society of Mechanical Engineers Standard NQA-1 (NQA-1) criteria and identifies and describes the quality assurance process(es) by which attributes of historical, analytical, and other data associated with sodium-cooled fast reactor [SFR] metallic fuel and/or related reactor fuel designs and constituency will be evaluated. This process is being instituted to facilitate validation of data to the extent that such data may be used to support future licensing efforts associated with advanced reactor designs. The initial data to be evaluated under this program were generatedmore » during the US Integral Fast Reactor program between 1984-1994, where the data includes, but is not limited to, research and development data and associated documents, test plans and associated protocols, operations and test data, technical reports, and information associated with past United States Nuclear Regulatory Commission reviews of SFR designs.« less

  19. Preliminary Tritium Management Design Activities at ORNL

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Harrison, Thomas J.; Felde, David K.; Logsdon, Randall J.

    2016-09-01

    Interest in salt-cooled and salt-fueled reactors has increased over the last decade (Forsberg et al. 2016). Several private companies and universities in the United States, as well as governments in other countries, are developing salt reactor designs and/or technology. Two primary issues for the development and deployment of many salt reactor concepts are (1) the prevention of tritium generation and (2) the management of tritium to prevent release to the environment. In 2016, the US Department of Energy (DOE) initiated a research project under the Advanced Reactor Technology Program to (1) experimentally assess the feasibility of proposed methods for tritiummore » mitigation and (2) to perform an engineering demonstration of the most promising methods. This document describes results from the first year’s efforts to define, design, and build an experimental apparatus to test potential methods for tritium management. These efforts are focused on producing a final design document as the basis for the apparatus and its scheduled completion consistent with available budget and approvals for facility use.« less

  20. 30 CFR 550.200 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... OPERATIONS IN THE OUTER CONTINENTAL SHELF Plans and Information General Information § 550.200 Definitions... of Safety and Environmental Enforcement. CID means Conservation Information Document. CZMA means Coastal Zone Management Act. DOCD means Development Operations Coordination Document. DPP means...

  1. 10 CFR 100.4 - Communications.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Communications. 100.4 Section 100.4 Energy NUCLEAR... under them should be sent by mail addressed to: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate, U.S. Nuclear Regulatory Commission...

  2. 9 CFR 86.5 - Documentation requirements for interstate movement of covered livestock.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ....g., an equine infectious anemia test chart, as agreed to by the shipping and receiving States or... documentation in accordance with part 88 of this chapter. Equine infectious anemia reactors moving interstate...

  3. Determine Operating Reactor to Use for the 2016 PCI Level 1 Milestone

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Clarno, Kevin T.

    2016-01-30

    The Consortium for Advanced Simulation of Light Water Reactors (LWRs) (CASL) Level 1 milestone to “Assess the analysis capability for core-wide [pressurized water reactor] PWR Pellet- Clad Interaction (PCI) screening and demonstrate detailed 3-D analysis on selected sub-region” (L1:CASL.P13.03) requires a particular type of nuclear power plant for the assessment. This report documents the operating reactor and cycles chosen for this assessment in completion of the physics integration (PHI) milestone to “Determine Operating Reactor to use for PCI L1 Milestone” (L3:PHI.CMD.P12.02). Watts Bar Unit 1 experienced (at least) one fuel rod failure in each of cycles 6 and 7, andmore » at least one was deemed to be duty related rather than being primarily related to a manufacturing defect or grid effects. This brief report documents that the data required to model cycles 1–12 of Watts Bar Unit 1 using VERA-CS contains sufficient data to model the PHI portion of the PCI challenge problem. A list of additional data needs is also provided that will be important for verification and validation of the BISON results.« less

  4. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The SPS Concept Development and Evaluation Program includes a comparative assessment. An early first step in the assessment process is the selection and characterization of alternative technologies. This document describes the cost and performance (i.e., technical and environmental) characteristics of six central station energy alternatives: (1) conventional coal-fired powerplant; (2) conventional light water reactor (LWR); (3) combined cycle powerplant with low-Btu gasifiers; (4) liquid metal fast breeder reactor (LMFBR); (5) photovoltaic system without storage; and (6) fusion reactor.

  5. The 5-kwe reactor thermoelectric system summary

    NASA Technical Reports Server (NTRS)

    Vanosdol, J. H. (Editor)

    1973-01-01

    Design of the 5-kwe reactor thermoelectric system was initiated in February 1972 and extended through the conceptual design phase into the preliminary design phase. Design effort was terminated in January, 1973. This report documents the system and component requirements, design approaches, and performance and design characteristics for the 5-kwe system. Included is summary information on the reactor, radiation shields, power conversion systems, thermoelectric pump, radiator/structure, liquid metal components, and the control system.

  6. Automated storage and retrieval of data obtained in the Interkosmos project

    NASA Technical Reports Server (NTRS)

    Ziolkovski, K.; Pakholski, V.

    1975-01-01

    The formation of a data bank and information retrieval system for scientific data is described. The stored data can be digital or documentation data. Data classification methods are discussed along with definition and compilation of the dictionary utilized, definition of the indexing scheme, and definition of the principles used in constructing a file for documents, data blocks, and tapes. Operating principles are also presented.

  7. Mars power system concept definition study. Volume 1: Study results

    NASA Technical Reports Server (NTRS)

    Littman, Franklin D.

    1994-01-01

    A preliminary top level study was completed to define power system concepts applicable to Mars surface applications. This effort included definition of power system requirements and selection of power systems with the potential for high commonality. These power systems included dynamic isotope, Proton Exchange Membrane (PEM) regenerative fuel cell, sodium sulfur battery, photovoltaic, and reactor concepts. Design influencing factors were identified. Characterization studies were then done for each concept to determine system performance, size/volume, and mass. Operations studies were done to determine emplacement/deployment maintenance/servicing, and startup/shutdown requirements. Technology development roadmaps were written for each candidate power system (included in Volume 2). Example power system architectures were defined and compared on a mass basis. The dynamic isotope power system and nuclear reactor power system architectures had significantly lower total masses than the photovoltaic system architectures. Integrated development and deployment time phasing plans were completed for an example DIPS and reactor architecture option to determine the development strategies required to meet the mission scenario requirements.

  8. Margin of Safety Definition and Examples Used in Safety Basis Documents and the USQ Process

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Beaulieu, R. A.

    The Nuclear Safety Management final rule, 10 CFR 830, provides an undefined term, margin of safety (MOS). Safe harbors listed in 10 CFR 830, Table 2, such as DOE-STD-3009 use but do not define the term. This lack of definition has created the need for the definition. This paper provides a definition of MOS and documents examples of MOS as applied in a U.S. Department of Energy (DOE) approved safety basis for an existing nuclear facility. If we understand what MOS looks like regarding Technical Safety Requirements (TSR) parameters, then it helps us compare against other parameters that do notmore » involve a MOS. This paper also documents parameters that are not MOS. These criteria could be used to determine if an MOS exists in safety basis documents. This paper helps DOE, including the National Nuclear Security Administration (NNSA) and its contractors responsible for the safety basis improve safety basis documents and the unreviewed safety question (USQ) process with respect to MOS.« less

  9. Glossary of CERCLA, RCRA and TSCA related terms and acronyms. Environmental Guidance

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1993-10-01

    This glossary contains CERCLA, RCRA and TSCA related terms that are most often encountered in the US Department of Energy (DOE) Environmental Restoration and Emergency Preparedness activities. Detailed definitions are included for key terms. The CERCLA definitions included in this glossary are taken from the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as amended and related federal rulemakings. The RCRA definitions included in this glossary are taken from the Resource Conservation and Recovery Act (RCRA) and related federal rulemakings. The TSCA definitions included in this glossary are taken from the Toxic Substances and Control Act (TSCA) and related federalmore » rulemakings. Definitions related to TSCA are limited to those sections in the statute and regulations concerning PCBs and asbestos.Other sources for definitions include additional federal rulemakings, assorted guidance documents prepared by the US Environmental Protection Agency (EPA), guidance and informational documents prepared by the US Department of Energy (DOE), and DOE Orders. The source of each term is noted beside the term. Terms presented in this document reflect revised and new definitions published before July 1, 1993.« less

  10. Supplemental Thermal-Hydraulic Transient Analyses of BR2 in Support of Conversion to LEU Fuel

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Licht, J.; Dionne, B.; Sikik, E.

    2016-01-01

    Belgian Reactor 2 (BR2) is a research and test reactor located in Mol, Belgium and is primarily used for radioisotope production and materials testing. The Materials Management and Minimization (M3) Reactor Conversion Program of the National Nuclear Security Administration (NNSA) is supporting the conversion of the BR2 reactor from Highly Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU) fuel. The RELAP5/Mod 3.3 code has been used to perform transient thermal-hydraulic safety analyses of the BR2 reactor to support reactor conversion. A RELAP5 model of BR2 has been validated against select transient BR2 reactor experiments performed in 1963 by showingmore » agreement with measured cladding temperatures. Following the validation, the RELAP5 model was then updated to represent the current use of the reactor; taking into account core configuration, neutronic parameters, trip settings, component changes, etc. Simulations of the 1963 experiments were repeated with this updated model to re-evaluate the boiling risks associated with the currently allowed maximum heat flux limit of 470 W/cm 2 and temporary heat flux limit of 600 W/cm 2. This document provides analysis of additional transient simulations that are required as part of a modern BR2 safety analysis report (SAR). The additional simulations included in this report are effect of pool temperature, reduced steady-state flow rate, in-pool loss of coolant accidents, and loss of external cooling. The simulations described in this document have been performed for both an HEU- and LEU-fueled core.« less

  11. 10 CFR 2.107 - Withdrawal of application.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... application does not authorize the removal of any document from the files of the Commission. (c) The Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and Safeguards, as appropriate, will cause to be published in the Federal Register a notice...

  12. 75 FR 67636 - Physical Protection of Shipments of Irradiated Reactor Fuel

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-03

    ...-2010-0340; Draft NUREG-0561, Revision 2] RIN 3150-AI64 Physical Protection of Shipments of Irradiated...- 0561, ``Physical Protection of Shipments of Irradiated Reactor Fuel.'' This document provides guidance to a licensee or applicant for implementation of proposed 10 CFR 73.37, ``Requirements for Physical...

  13. 78 FR 31821 - Physical Protection of Shipments of Irradiated Reactor Fuel

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-28

    ... NUCLEAR REGULATORY COMMISSION 10 CFR Part 73 [NRC-2010-0340; NRC-2009-0163] RIN 3150-AI64 Physical..., ``Physical Protection of Shipments of Irradiated Reactor Fuel.'' This revised document sets forth means... physical protection of spent nuclear fuel (SNF) during transportation by road, rail, and water; and for...

  14. 75 FR 62892 - Massachusetts Institute of Technology Research Reactor Environmental Assessment and Finding of No...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-13

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-020; NRC-2010-0313] Massachusetts Institute of Technology Research Reactor Environmental Assessment and Finding of No Significant Impact Correction In notice document 2010-24809 beginning on page 61220 in the issue of Monday, October 4, 2010, make the...

  15. Analysis of dosimetry from the H.B. Robinson unit 2 pressure vessel benchmark using RAPTOR-M3G and ALPAN

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fischer, G.A.

    2011-07-01

    Document available in abstract form only, full text of document follows: The dosimetry from the H. B. Robinson Unit 2 Pressure Vessel Benchmark is analyzed with a suite of Westinghouse-developed codes and data libraries. The radiation transport from the reactor core to the surveillance capsule and ex-vessel locations is performed by RAPTOR-M3G, a parallel deterministic radiation transport code that calculates high-resolution neutron flux information in three dimensions. The cross-section library used in this analysis is the ALPAN library, an Evaluated Nuclear Data File (ENDF)/B-VII.0-based library designed for reactor dosimetry and fluence analysis applications. Dosimetry is evaluated with the industry-standard SNLRMLmore » reactor dosimetry cross-section data library. (authors)« less

  16. VVER-440 and VVER-1000 reactor dosimetry benchmark - BUGLE-96 versus ALPAN VII.0

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Duo, J. I.

    2011-07-01

    Document available in abstract form only, full text of document follows: Analytical results of the vodo-vodyanoi energetichesky reactor-(VVER-) 440 and VVER-1000 reactor dosimetry benchmarks developed from engineering mockups at the Nuclear Research Inst. Rez LR-0 reactor are discussed. These benchmarks provide accurate determination of radiation field parameters in the vicinity and over the thickness of the reactor pressure vessel. Measurements are compared to calculated results with two sets of tools: TORT discrete ordinates code and BUGLE-96 cross-section library versus the newly Westinghouse-developed RAPTOR-M3G and ALPAN VII.0. The parallel code RAPTOR-M3G enables detailed neutron distributions in energy and space in reducedmore » computational time. ALPAN VII.0 cross-section library is based on ENDF/B-VII.0 and is designed for reactor dosimetry applications. It uses a unique broad group structure to enhance resolution in thermal-neutron-energy range compared to other analogous libraries. The comparison of fast neutron (E > 0.5 MeV) results shows good agreement (within 10%) between BUGLE-96 and ALPAN VII.O libraries. Furthermore, the results compare well with analogous results of participants of the REDOS program (2005). Finally, the analytical results for fast neutrons agree within 15% with the measurements, for most locations in all three mockups. In general, however, the analytical results underestimate the attenuation through the reactor pressure vessel thickness compared to the measurements. (authors)« less

  17. Definition and documentation of engineering processes

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    McDonald, G.W.

    1997-11-01

    This tutorial is an extract of a two-day workshop developed under the auspices of the Quality Engineering Department at Sandia National Laboratories. The presentation starts with basic definitions and addresses why processes should be defined and documented. It covers three primary topics: (1) process considerations and rationale, (2) approach to defining and documenting engineering processes, and (3) an IDEFO model of the process for defining engineering processes.

  18. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jaffke, Patrick John

    This acts as a short note on the effects of varying the value of the endpoints of the thermal, epithermal, and fast flux groups. As expected, varying these endpoints can alter the value of the cross-section for a given nuclide. This effect is quantified in this note for an important nuclide in reactor simulations, 238U. Uranium-238 is responsible for the production of Plutonium in most reactors, making it critical to understand all of the 238U capture modes leading to Plutonium. We explicitly quantify the reaction rates for 238U that are altered when we use a given research reactor fluxmore » and vary the endpoint definitions of said flux as well as the reactor position.« less

  19. BOLD VENTURE COMPUTATION SYSTEM for nuclear reactor core analysis, Version III

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vondy, D.R.; Fowler, T.B.; Cunningham, G.W. III.

    1981-06-01

    This report is a condensed documentation for VERSION III of the BOLD VENTURE COMPUTATION SYSTEM for nuclear reactor core analysis. An experienced analyst should be able to use this system routinely for solving problems by referring to this document. Individual reports must be referenced for details. This report covers basic input instructions and describes recent extensions to the modules as well as to the interface data file specifications. Some application considerations are discussed and an elaborate sample problem is used as an instruction aid. Instructions for creating the system on IBM computers are also given.

  20. 28 CFR 68.2 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... IMMIGRATION-RELATED EMPLOYMENT PRACTICES, AND DOCUMENT FRAUD § 68.2 Definitions. For purposes of this part: Adjudicatory proceeding means an administrative judicial-type proceeding, before the Office of the Chief... law by an Administrative Law Judge or the Chief Administrative Hearing Officer; Document fraud cases...

  1. 28 CFR 68.2 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... IMMIGRATION-RELATED EMPLOYMENT PRACTICES, AND DOCUMENT FRAUD § 68.2 Definitions. For purposes of this part: Adjudicatory proceeding means an administrative judicial-type proceeding, before the Office of the Chief... law by an Administrative Law Judge or the Chief Administrative Hearing Officer; Document fraud cases...

  2. Nuclear reactors built, being built, or planned, 1991

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Simpson, B.

    1992-07-01

    This document contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1991. The book is divided into three major sections: Section 1 consists of a reactor locator map and reactor tables; Section 2 includes nuclear reactors that are operating, being built, or planned; and Section 3 includes reactors that have been shut down permanently or dismantled. Sections 2 and 3 contain the following classification of reactors: Civilian, Production, Military, Export, and Critical Assembly. Export reactor refers to a reactor for which the principal nuclear contractor ismore » an American company -- working either independently or in cooperation with a foreign company (Part 4, in each section). Critical assembly refers to an assembly of fuel and assembly of fuel and moderator that requires an external source of neutrons to initiate and maintain fission. A critical assembly is used for experimental measurements (Part 5).« less

  3. N.S. SAVANNAH, DRAFT OF FINAL SAFEGUARDS REPORT TEST, START-UP AND TRIALS, NEW YORK SHIPBUILDING CORPORATION

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1960-04-01

    The N. S. Savannah program for testing, start-up, and initial operation of all reactor and propulsion components and systems is discussed. Definitions of test phases are given and various stages of the test program are outlined. A list of tests for the various reactor, propulsion, and other system components is included. (C.J.G.)

  4. Tailoring of EIA-649-1: Definition of Major (Class I) Engineering Change Proposal

    DTIC Science & Technology

    2015-05-15

    MISSILE SYSTEMS CENTER TAILORING TAILORING OF EIA -649-1: DEFINITION OF MAJOR (CLASS I) ENGINEERING CHANGE PROPOSAL APPROVED FOR...PUBLIC RELEASE; DISTRIBUTION IS UNLIMITED 1 Tailoring of EIA -649-1: Definition of Major (Class I) ECP. 1. Intent of this Tailoring Document...This tailoring document remedies a requirements gap in the industry consensus standard, EIA -649-1: 2015. Specifically, this tailoring provides a

  5. Space and Missile Systems Center Standard: Parts, Materials, and Processes Control Program for Space Vehicles

    DTIC Science & Technology

    2013-04-12

    statement of work. This document may be tailored by the acquisition activity for the specific application or program prior to contract award. 1.3...5 3. Definitions and Acronyms 3.1 Definitions The following definitions describe terms used throughout this document. Acquisition Activity The...acquisition activity is the Government, contractor, or subcontractor acquiring the equipment, system, subsystem, part, or material for which this

  6. What Is Real-World Data? A Review of Definitions Based on Literature and Stakeholder Interviews.

    PubMed

    Makady, Amr; de Boer, Anthonius; Hillege, Hans; Klungel, Olaf; Goettsch, Wim

    Despite increasing recognition of the value of real-world data (RWD), consensus on the definition of RWD is lacking. To review definitions publicly available for RWD to shed light on similarities and differences between them. A literature review and stakeholder interviews were used to compile data from eight groups of stakeholders. Data from documents and interviews were subjected to coding analysis. Definitions identified were classified into four categories: 1) data collected in a non-randomized controlled trial setting, 2) data collected in a non-interventional/non-controlled setting, 3) data collected in a non-experimental setting, and 4) others (i.e., data that do not fit into the other three categories). The frequency of definitions identified per category was recorded. Fifty-three documents and 20 interviews were assessed. Thirty-eight definitions were identified: 20 out of 38 definitions (53%) were category 1 definitions, 9 (24%) were category 2 definitions, 5 (13%) were category 3 definitions, and 4 (11%) were category 4 definitions. Differences were identified between, and within, definition categories. For example, opinions differed on the aspects of intervention with which non-interventional/non-controlled settings should abide. No definitions were provided in two interviews or identified in 33 documents. Most of the definitions defined RWD as data collected in a non-randomized controlled trial setting. A considerable number of definitions, however, diverged from this concept. Moreover, a significant number of authors and stakeholders did not have an official, institutional definition for RWD. Persisting variability in stakeholder definitions of RWD may lead to disparities among different stakeholders when discussing RWD use in decision making. Copyright © 2017 International Society for Pharmacoeconomics and Outcomes Research (ISPOR). Published by Elsevier Inc. All rights reserved.

  7. 10 CFR 100.3 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... input at the oscillators' supports. Safe Shutdown Earthquake Ground Motion is the vibratory ground... forces. Tectonic surface deformation is associated with earthquake processes. Testing reactor means a...

  8. 10 CFR 100.3 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... input at the oscillators' supports. Safe Shutdown Earthquake Ground Motion is the vibratory ground... forces. Tectonic surface deformation is associated with earthquake processes. Testing reactor means a...

  9. 7 CFR 1718.102 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... LOAN SECURITY DOCUMENTS FOR ELECTRIC BORROWERS Loan Contracts With Distribution Borrowers § 1718.102 Definitions. For the purposes of this subpart: Borrower means any organization that has an outstanding loan... defined in 7 CFR 1710.2. Loan documents means the mortgage (or other security instrument acceptable to RUS...

  10. XML and E-Journals: The State of Play.

    ERIC Educational Resources Information Center

    Wusteman, Judith

    2003-01-01

    Discusses the introduction of the use of XML (Extensible Markup Language) in publishing electronic journals. Topics include standards, including DTDs (Document Type Definition), or document type definitions; aggregator requirements; SGML (Standard Generalized Markup Language); benefits of XML for e-journals; XML metadata; the possibility of…

  11. 10 CFR 51.4 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... the land for public recreational purposes; (ii) Site exploration, including necessary borings to... building with space for installation of a training reactor). NRC means the Nuclear Regulatory Commission...

  12. 10 CFR 51.4 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... the land for public recreational purposes; (ii) Site exploration, including necessary borings to... building with space for installation of a training reactor). NRC means the Nuclear Regulatory Commission...

  13. Evaluation of nuclear facility decommissioning projects. Summary report: North Carolina State University Research and Training Reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Link, B.W.; Miller, R.L.

    1983-08-01

    This document summarizes information from the decommissioning of the NCSUR-3 (R-3), a 10 KWt university research and training reactor. The decommissioning data were placed in a computerized information retrieval/manipulation system which permits future utilization of this information in pre-decommissioning activities with other university reactors of similar design. The information is presented both in some detail in its computer output form and also as a manually assembled summarization which highlights the more significant aspects of the decommissioning project. Decommissioning data from a generic study, NUREG/CR 1756, Technology, Safety and Costs of Decommissioning Nuclear Research and Test Reactors, and the decommissioning ofmore » the Ames Laboratory Research Reactor (ALRR), a 5 MWt research reactor, is also included for comparison.« less

  14. 75 FR 76051 - Northern States Power Company-Minnesota, Prairie Island Nuclear Generating Plant, Units 1 and 2...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-07

    ..., 2010 (Agencywide Documents Access and Management System Accession Nos. ML093280883 and ML101480083... systems for light-water nuclear power reactors,'' and appendix K to 10 CFR part 50, ``ECCS Evaluation... core cooling system (ECCS) for reactors fueled with zircaloy or ZIRLO\\TM\\ cladding. In addition...

  15. 76 FR 5102 - Draft NUREG-0561, Revision 2; Physical Protection of Shipments of Irradiated Reactor Fuel...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-28

    ... 3150-AI64 [NRC-2010-0340] Draft NUREG-0561, Revision 2; Physical Protection of Shipments of Irradiated...-0561, ``Physical Protection of Shipments of Irradiated Reactor Fuel.'' This document provides guidance on implementing the provisions of proposed 10 CFR Part 73.37, ``Requirements for Physical Protection...

  16. 77 FR 61446 - Proposed Revision Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-09

    ... documents online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html . To begin the search... of digital instrumentation and control system PRAs, including common cause failures in PRAs and uncertainty analysis associated with new reactor digital systems, and (4) incorporation of additional...

  17. Cleanup Verification Package for the 118-H-6:2, 105-H Reactor Ancillary Support Areas, Below-Grade Structures, and Underlying Soils; the 118-H-6:3, 105-H Reactor Fuel Storage Basin and Underlying Soils; The 118-H-6:3 Fuel Storage Basin Deep Zone Side Slope Soils; the 100-H-9, 100-H-10, and 100-H-13 French Drains; the 100-H-11 and 100-H-12 Expansion Box French Drains; and the 100-H-14 and 100-H-31 Surface Contamination Zones

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    M. J. Appel

    2006-06-29

    This cleanup verification package documents completion of removal actions for the 105-H Reactor Ancillary Support Areas, Below-Grade Structures, and Underlying Soils (subsite 118-H-6:2); 105-H Reactor Fuel Storage Basin and Underlying Soils (118-H-6:3); and Fuel Storage Basin Deep Zone Side Slope Soils. This CVP also documents remedial actions for the following seven additional waste sties: French Drain C (100-H-9), French Drain D (100-H-10), Expansion Box French Drain E (100-H-11), Expansion Box French Drain F (100-H-12), French Drain G (100-H-13), Surface Contamination Zone H (100-H-14), and the Polychlorinated Biphenyl Surface Contamination Zone (100-H-31).

  18. Product Structure, the Heart of Product Definition

    NASA Technical Reports Server (NTRS)

    DeHoog, C., Jr.

    1999-01-01

    This paper describes the LMMSS Product Definition System (PDS) philosophy and approach were the use of each item parts document or software can be traced to a specific end item (EI) serial/tail number of the product. It explains why a part-oriented approach to data organization and configuration management is required. The definition of part-oriented is that all appropriate product definition data products will be collected. Referenced and managed by their linkage/relationship to parts/items, The paper will touch upon how LMMSS store/controls product definition information under each project's top product designator in a two tiered approach. One tier for each product end item and another tier which contain/controls listings of drawings, documents. Specifications and standards that are required for hardware item definition.

  19. Standard classification of software documentation

    NASA Technical Reports Server (NTRS)

    Tausworthe, R. C.

    1976-01-01

    General conceptual requirements for standard levels of documentation and for application of these requirements to intended usages. These standards encourage the policy to produce only those forms of documentation that are needed and adequate for the purpose. Documentation standards are defined with respect to detail and format quality. Classes A through D range, in order, from the most definitive down to the least definitive, and categories 1 through 4 range, in order, from high-quality typeset down to handwritten material. Criteria for each of the classes and categories, as well as suggested selection guidelines for each are given.

  20. 9 CFR 205.202 - “Effective financing statement” or EFS.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Uniform Commercial Code (or equivalent document under future successor State law), but can be an entirely separate document meeting the definition in (c)(4). Note that (c)(4) contains a comprehensive definition of... State allows electronic filing of financing statements without the signature of the debtor under...

  1. 9 CFR 205.202 - “Effective financing statement” or EFS.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Uniform Commercial Code (or equivalent document under future successor State law), but can be an entirely separate document meeting the definition in (c)(4). Note that (c)(4) contains a comprehensive definition of... State allows electronic filing of financing statements without the signature of the debtor under...

  2. sCO2 Brayton Cycle: Roadmap to sCO2 Power Cycles NE Commercial Applications.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mendez Cruz, Carmen Margarita; Rochau, Gary E.

    The mission of the Energy Conversion (EC) area of the Advanced Reactor Technology (ART) program is to commercialize the sCO2 Brayton cycle for Advance Reactors and for the Supercritical Transformational Electric Production (STEP) program. The near-term objective of the EC team efforts is to support the development of a commercially scalable Recompression Closed Brayton Cycle (RCBC) to be constructed for the first STEP demonstration system with the lowest risk possible. This document details the status of technology, policy and market considerations, documentation of gaps and needs, and outlines the steps necessary for the successful development and deployment of commercial sCO2more » Brayton Power Systems along the path to nuclear reactor applications. Document Control Version Creation Date Revisions Created By Release Date 1.0 2/29/2016 Preliminary Draft Mendez, C. 3/2/2016 2.0 7/29/2016 Preliminaty/Partial Report -- updated Focus Area structure, added commercial path forward Mendez, C. 8/10/16 3.0 5/1/2018 Updated Roadmap supports timeline changes and inclusion of grid qualification goals Mendez, C. 6/6/18« less

  3. Evaluation of nuclear-facility decommissioning projects. Summary report: Ames Laboratory Research Reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Link, B.W.; Miller, R.L.

    1983-07-01

    This document summarizes the available information concerning the decommissioning of the Ames Laboratory Research Reactor (ALRR), a five-megawatt heavy water moderated and cooled research reactor. The data were placed in a computerized information retrieval/manipulation system which permits its future utilization for purposes of comparative analysis. This information is presented both in detail in its computer output form and also as a manually assembled summarization which highlights the more important aspects of the decommissioning program. Some comparative information with reference to generic decommissioning data extracted from NUREG/CR 1756, Technology, Safety and Costs of Decommissioning Nuclear Research and Test Reactors, is included.

  4. Overview of the 2014 Edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    John D. Bess; J. Blair Briggs; Jim Gulliford

    2014-10-01

    The International Reactor Physics Experiment Evaluation Project (IRPhEP) is a widely recognized world class program. The work of the IRPhEP is documented in the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook). Integral data from the IRPhEP Handbook is used by reactor safety and design, nuclear data, criticality safety, and analytical methods development specialists, worldwide, to perform necessary validations of their calculational techniques. The IRPhEP Handbook is among the most frequently quoted reference in the nuclear industry and is expected to be a valuable resource for future decades.

  5. 76 FR 23630 - Office of New Reactors; Proposed Revision 2 to Standard Review Plan, Section 1.0 on Introduction...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-27

    ... Standard Review Plan, Section 1.0 on Introduction and Interfaces AGENCY: Nuclear Regulatory Commission (NRC... Revision 2 to Standard Review Plan (SRP), Section 1.0, ``Introduction and Interfaces'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110110573). The Office of New Reactors (NRO...

  6. 75 FR 8411 - Office of New Reactors: Interim Staff Guidance on Assessing the Consequences of an Accidental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-24

    ... the public will be better served by being able to review and comment on both documents at this time... Construction Inspection and Operational Programs, Office of New Reactors, U.S. Nuclear Regulatory Commission... conditions for such releases and define acceptable assumptions to describe exposure scenarios and pathways to...

  7. Cleanup Verification Package for the 118-F-7, 100-F Miscellaneous Hardware Storage Vault

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    M. J. Appel

    2006-11-02

    This cleanup verification package documents completion of remedial action for the 118-F-7, 100-F Miscellaneous Hardware Storage Vault. The site consisted of an inactive solid waste storage vault used for temporary storage of slightly contaminated reactor parts that could be recovered and reused for the 100-F Area reactor operations.

  8. Fabrication Technological Development of the Oxide Dispersion Strengthened Alloy MA957 for Fast Reactor Applications

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hamilton, Margaret L.; Gelles, David S.; Lobsinger, Ralph J.

    A significant amount of effort has been devoted to determining the properties and understanding the behavior of the alloy MA957 to define its potential usefulness as a cladding material in the fast breeder reactor program. The numerous characterization and fabrication studies that were conducted are documented in this report.

  9. Abbreviations and acronyms

    NASA Technical Reports Server (NTRS)

    1994-01-01

    This booklet provides a partial list of acronyms, abbreviations, and other short word forms, including their definitions, used in documents at the Goddard Space Flight Center (GSFC). This list does not preclude the use of other short forms of less general usage, as long as these short forms are identified the first time they appear in a document and are defined in a glossary in the document in which they are used. This document supplements information in the GSFC Scientific and Technical Information Handbook (GHB 2200.2/April 1989). It is not intended to contain all short word forms used in GSFC documents; however, it was compiled of actual short forms used in recent GSFC documents. The entries are listed first, alphabetically by the short form, and then again alphabetically by definition.

  10. ROMPS critical design review. Volume 2: Robot module design documentation

    NASA Technical Reports Server (NTRS)

    Dobbs, M. E.

    1992-01-01

    The robot module design documentation for the Remote Operated Materials Processing in Space (ROMPS) experiment is compiled. This volume presents the following information: robot module modifications; Easylab commands definitions and flowcharts; Easylab program definitions and flowcharts; robot module fault conditions and structure charts; and C-DOC flow structure and cross references.

  11. Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: simulations and experimental validations [ANIMMA--2015-IO-98

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jammes, C.; Filliatre, P.; De Izarra, G.

    The neutron flux monitoring system of the French GEN-IV sodium-cooled fast reactor will rely on high temperature fission chambers installed in the reactor vessel and capable of operating over a wide-range neutron flux. The definition of such a system is presented and the technological solutions are justified with the use of simulation and experimental results. (authors)

  12. Evaluation of ilmenite serpentine concrete and ordinary concrete as nuclear reactor shielding

    NASA Astrophysics Data System (ADS)

    Abulfaraj, Waleed H.; Kamal, Salah M.

    1994-07-01

    The present study involves adapting a formal decision methodology to the selection of alternative nuclear reactor concretes shielding. Multiattribute utility theory is selected to accommodate decision makers' preferences. Multiattribute utility theory (MAU) is here employed to evaluate two appropriate nuclear reactor shielding concretes in terms of effectiveness to determine the optimal choice in order to meet the radiation protection regulations. These concretes are Ordinary concrete (O.C.) and Ilmenite Serpentile concrete (I.S.C.). These are normal weight concrete and heavy heat resistive concrete, respectively. The effectiveness objective of the nuclear reactor shielding is defined and structured into definite attributes and subattributes to evaluate the best alternative. Factors affecting the decision are dose received by reactor's workers, the material properties as well as cost of concrete shield. A computer program is employed to assist in performing utility analysis. Based upon data, the result shows the superiority of Ordinary concrete over Ilmenite Serpentine concrete.

  13. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Goetsch, D.; Bieniussa, K.; Schulz, H.

    This paper is an abstract of the work performed in the frame of the development of the IPSN/GRS approach in view of the EPR conceptual safety features. EPR is a pressurized water reactor which will be based on the experience gained by utilities and designers in France and in Germany. The reactor coolant boundary of a PWR includes the reactor pressure vessel (RPV), those parts of the steam generators (SGs) which contain primary coolant, the pressurizer (PSR), the reactor coolant pumps (RCPs), the main coolant lines (MCLs) with their branches as well as the other connecting pipes and all branchingmore » pipes including the second isolation valves. The present work covering the integrity of the reactor coolant boundary is mainly restricted to the integrity of the main coolant lines (MCLs) and reflects the design requirements for the main components of the reactor coolant boundary. In the following the conceptual aspects, i.e. design, manufacture, construction and operation, will be assessed. A main aspect is the definition of break postulates regarding overall safety implications.« less

  14. 10 CFR 51.4 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... include: (A) Changes for temporary use of the land for public recreational purposes; (B) Site exploration... building with space for installation of a training reactor). (2) For materials licenses, taking any site...

  15. 10 CFR 51.4 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... include: (A) Changes for temporary use of the land for public recreational purposes; (B) Site exploration... building with space for installation of a training reactor). (2) For materials licenses, taking any site...

  16. 10 CFR 51.4 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... include: (A) Changes for temporary use of the land for public recreational purposes; (B) Site exploration... building with space for installation of a training reactor). (2) For materials licenses, taking any site...

  17. Integrated Information Support System (IISS). Volume 8. User Interface Subsystem. Part 39. Electronic Documentation System (EDS) User’s Manual

    DTIC Science & Technology

    1990-09-30

    conveying any rights or permission to manufacture, use, or market any patented invention that may in any way be related thereto. This technical report...Definition - Select .... 7-9 7-6 Character Class Definition - Other Options 7-10 7-7 Pattern/Action/State Defintion -Select 7-11 7-8 Pattern/Action/State...representation. Compound Document: A document which may contain mixed content i.e. text, graphics, etc. Conforming SGML Application: An SGML application that

  18. Milestone M3FT-15OR0203112. Build redesigned HFIR rabbit capsules and make ready for insertion for irradiation in HFIR

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Howard, Richard H; McDuffee, Joel Lee; Okuniewski, Maria A.

    2015-09-01

    This report details the fabrication and delivery of two Fuel Cycle Research and Development irradiation capsules (FCRP20 and FCRP03), with associated quality assurance documentation, to the High Flux Isotope Reactor. The capsules and documentation were delivered by September 30, 2015, thus meeting the deadline for milestone M3FT-15OR0203112. These irradiation experiments irradiate metal parallelepiped specimens that may consist of various compositions including uranium metal, steel, etc. This document contains a copy of the completed capsule fabrication request sheets, which detail all constituent components, pertinent drawings, etc., along with a detailed summary of the capsule assembly process performed by the Thermal Hydraulicsmore » and Irradiation Engineering Group (THIEG) in the Reactor and Nuclear Systems Division. A complete fabrication package record is maintained by THIEG and is available upon request.« less

  19. Cleanup Verification Package for the 118-F-1 Burial Ground

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    E. J. Farris and H. M. Sulloway

    2008-01-10

    This cleanup verification package documents completion of remedial action for the 118-F-1 Burial Ground on the Hanford Site. This burial ground is a combination of two locations formerly called Minor Construction Burial Ground No. 2 and Solid Waste Burial Ground No. 2. This waste site received radioactive equipment and other miscellaneous waste from 105-F Reactor operations, including dummy elements and irradiated process tubing; gun barrel tips, steel sleeves, and metal chips removed from the reactor; filter boxes containing reactor graphite chips; and miscellaneous construction solid waste.

  20. Evaluation of Nuclear Facility Decommissioning Projects program: a reference research reactor. Project summary report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Baumann, B.L.; Miller, R.L.

    1983-10-01

    This document presents, in summary form, generic conceptual information relevant to the decommissioning of a reference research reactor (RRR). All of the data presented were extracted from NUREG/CR-1756 and arranged in a form that will provide a basis for future comparison studies for the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program.

  1. 10 CFR 51.52 - Environmental effects of transportation of fuel and waste-Table S-4.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... thermal power level not exceeding 3,800 megawatts; (2) The reactor fuel is in the form of sintered uranium... Nuclear Power Plants,” WASH-1238, December 1972, and Supp. 1 NUREG-75/038 April 1975. Both documents are...-water-cooled nuclear power reactor, and submitted after February 4, 1975, shall contain a statement...

  2. 10 CFR 51.52 - Environmental effects of transportation of fuel and waste-Table S-4.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... thermal power level not exceeding 3,800 megawatts; (2) The reactor fuel is in the form of sintered uranium... Nuclear Power Plants,” WASH-1238, December 1972, and Supp. 1 NUREG-75/038 April 1975. Both documents are...-water-cooled nuclear power reactor, and submitted after February 4, 1975, shall contain a statement...

  3. 10 CFR 51.52 - Environmental effects of transportation of fuel and waste-Table S-4.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... thermal power level not exceeding 3,800 megawatts; (2) The reactor fuel is in the form of sintered uranium... Nuclear Power Plants,” WASH-1238, December 1972, and Supp. 1 NUREG-75/038 April 1975. Both documents are...-water-cooled nuclear power reactor, and submitted after February 4, 1975, shall contain a statement...

  4. 10 CFR 51.52 - Environmental effects of transportation of fuel and waste-Table S-4.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... thermal power level not exceeding 3,800 megawatts; (2) The reactor fuel is in the form of sintered uranium... Nuclear Power Plants,” WASH-1238, December 1972, and Supp. 1 NUREG-75/038 April 1975. Both documents are...-water-cooled nuclear power reactor, and submitted after February 4, 1975, shall contain a statement...

  5. 78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-28

    ... University of Illinois Advanced TRIGA Reactor, License No. R-115 The U.S. Nuclear Regulatory Commission (NRC) is noticing the termination of Facility Operating License No. R-115, for the University of Illinois... Operating License No. R-115 is terminated. The above referenced documents may be examined, and/or copied for...

  6. Cleanup Verification Package for the 118-C-1, 105-C Solid Waste Burial Ground

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    M. J. Appel and J. M. Capron

    2007-07-25

    This cleanup verification package documents completion of remedial action for the 118-C-1, 105-C Solid Waste Burial Ground. This waste site was the primary burial ground for general wastes from the operation of the 105-C Reactor and received process tubes, aluminum fuel spacers, control rods, reactor hardware, spent nuclear fuel and soft wastes.

  7. BLENDED CALCIUM ALUMINATE-CALCIUM SULFATE CEMENT-BASED GROUT FOR P-REACTOR VESSEL IN-SITU DECOMMISSIONING

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Langton, C.; Stefanko, D.

    2011-03-10

    The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout which has a pH greater than 12.4. In addition, blended calcium aluminate - calcium hemihydrate cement compositions can be formulated such that the primary cementitious phase is a stable crystalline material. A less alkaline material (pH {<=} 10.5) was desired to address a potential materials compatibilitymore » issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts [Wiersma, 2009a and b, Wiersma, 2010, and Serrato and Langton, 2010]. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere [Griffin, 2010, Stefanko, 2009 and Wiersma, 2009 and 2010, Bobbitt, 2010, respectively]. Radiolysis calculations are also provided in a separate document [Reyes-Jimenez, 2010].« less

  8. Analog to digital converter system for temperature monitoring -- B, C, D, DR, F, and H reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ballowe, J.W.

    1961-03-23

    This document discusses a proposal that certain presently installed reactor process water outlet temperature data logging equipment in subject reactors to be replaced with new functionally simplified equipment of a more adequate design. The primary purpose of the proposed installation is to replace existing equipment which is obsolete and in three reactors is worn out to the point where the equipment is out of service frequently for periods of time up to 8 hours or more. The new equipment will provide reliable process tube temperature information for use in the functions of reactor control and product accountability. Based upon anticipatedmore » incremental production gains resulting from use of the new equipment, the amortization period for the project is calculated at 2.7 years.« less

  9. NGNP Data Management and Analysis System Analysis and Web Delivery Capabilities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cynthia D. Gentillon

    2010-09-01

    Projects for the Very High Temperature Reactor Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the very high temperature reactor. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high-temperature and high-fluence environments. In addition, thermal-hydraulic experiments are conducted to validate codes used to assess reactor safety. The Very High Temperature Reactor Technology Development Office has established the NGNP Data Management and Analysis System (NDMAS) at the Idaho National Laboratory to ensure that very high temperature reactor data are (1) qualified for use, (2) stored in amore » readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the third NDMAS objective. It describes capabilities for displaying the data in meaningful ways and for data analysis to identify useful relationships among the measured quantities.« less

  10. Documentation of a Collaborative Transition Planning System: A Curriculum Planning Guide for Students with Mild Disabilities.

    ERIC Educational Resources Information Center

    Jackson, Jeanne

    This report describes and analyzes the transition process used at Savanna High School, Anaheim, California, and documents the unique contribution of the school's Independent Living Skills Transition Center. The report's seven sections focus on: (1) transition definitions and the need for a shared definition among agency personnel; (2) team…

  11. Transportation Shock and Vibration Literature Review

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Maheras, Steven J.; Lahti, Erik A.; Ross, Steven B.

    2013-06-06

    This report fulfills the M4 milestone M4FT-13OR08220112, "Report Documenting Experimental Activities." The purpose of this report is to document the results of a literature review conducted of studies related to the vibration and shock associated with the normal conditions of transport for rail shipments of used nuclear fuel from commercial light-water reactors. As discussed in Adkins (2013), the objective of this report is to determine if adequate data exist that would enable the impacts of the shock and vibration associated with the normal conditions of transport on commercial light-water reactor used nuclear fuel shipped in current generation rail transportation casksmore » to be realistically modeled.« less

  12. Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 3, Sessions 12-16

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Block, R.C.; Feiner, F.

    This document, Volume 3, includes papers presented at the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-7) September 10--15, 1995 at Saratoga Springs, N.Y. The following subjects are discussed: Progress in analytical and experimental work on the fundamentals of nuclear thermal-hydraulics, the development of advanced mathematical and numerical methods, ad the application of advancements in the field in the development of novel reactor concepts. Also combined issues of thermal-hydraulics and reactor/power-plant safety, core neutronics and/or radiation. Selected abstracts have been indexed separately for inclusion in the Energy Science and Technology Database.

  13. 78 FR 56752 - Interim Staff Guidance Specific Environmental Guidance for Integral Pressurized Water Reactors...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-13

    ... (iPWR). This guidance applies to environmental reviews associated with iPWR applications for limited... received on or before this date. ADDRESSES: You may submit comments by any of the following methods (unless... this document. You may access publicly-available information related to this document by any of the...

  14. 42 CFR 102.52 - Documentation a vaccinia contact must submit to be deemed eligible by the Secretary.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... OF HEALTH AND HUMAN SERVICES VACCINES SMALLPOX COMPENSATION PROGRAM Required Documentation To Be... in § 102.3(x)(1)-(3) (a person meeting the definition of a smallpox vaccine recipient, except for the... individual described in § 102.3(x)(1)-(3) (a person meeting the definition of a smallpox vaccine recipient...

  15. Standardized End Point Definitions for Coronary Intervention Trials: The Academic Research Consortium-2 Consensus Document.

    PubMed

    Garcia-Garcia, Hector M; McFadden, Eugène P; Farb, Andrew; Mehran, Roxana; Stone, Gregg W; Spertus, John; Onuma, Yoshinobu; Morel, Marie-Angèle; van Es, Gerrit-Anne; Zuckerman, Bram; Fearon, William F; Taggart, David; Kappetein, Arie-Pieter; Krucoff, Mitchell W; Vranckx, Pascal; Windecker, Stephan; Cutlip, Donald; Serruys, Patrick W

    2018-06-14

    The Academic Research Consortium (ARC)-2 initiative revisited the clinical and angiographic end point definitions in coronary device trials, proposed in 2007, to make them more suitable for use in clinical trials that include increasingly complex lesion and patient populations and incorporate novel devices such as bioresorbable vascular scaffolds. In addition, recommendations for the incorporation of patient-related outcomes in clinical trials are proposed. Academic Research Consortium-2 is a collaborative effort between academic research organizations in the United States and Europe, device manufacturers, and European, US, and Asian regulatory bodies. Several in-person meetings were held to discuss the changes that have occurred in the device landscape and in clinical trials and regulatory pathways in the last decade. The consensus-based end point definitions in this document are endorsed by the stakeholders of this document and strongly advocated for clinical trial purposes. This Academic Research Consortium-2 document provides further standardization of end point definitions for coronary device trials, incorporating advances in technology and knowledge. Their use will aid interpretation of trial outcomes and comparison among studies, thus facilitating the evaluation of the safety and effectiveness of these devices.

  16. DOE Office of Scientific and Technical Information (OSTI.GOV)

    M. J. Appel

    This cleanup verification package documents completion of remedial action for the 118-F-3, Minor Construction Burial Ground waste site. This site was an open field covered with cobbles, with no vegetation growing on the surface. The site received irradiated reactor parts that were removed during conversion of the 105-F Reactor from the Liquid 3X to the Ball 3X Project safety systems and received mostly vertical safety rod thimbles and step plugs.

  17. 14 CFR 77.2 - Definition of terms.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... planning document or military service military airport planning document. Precision instrument runway means... military airport layout plan; any other FAA planning document, or military service military airport planning document. Utility runway means a runway that is constructed for and intended to be used by...

  18. Differences in reporting of analyses in internal company documents versus published trial reports: comparisons in industry-sponsored trials in off-label uses of gabapentin.

    PubMed

    Vedula, S Swaroop; Li, Tianjing; Dickersin, Kay

    2013-01-01

    Details about the type of analysis (e.g., intent to treat [ITT]) and definitions (i.e., criteria for including participants in the analysis) are necessary for interpreting a clinical trial's findings. Our objective was to compare the description of types of analyses and criteria for including participants in the publication (i.e., what was reported) with descriptions in the corresponding internal company documents (i.e., what was planned and what was done). Trials were for off-label uses of gabapentin sponsored by Pfizer and Parke-Davis, and documents were obtained through litigation. For each trial, we compared internal company documents (protocols, statistical analysis plans, and research reports, all unpublished), with publications. One author extracted data and another verified, with a third person verifying discordant items and a sample of the rest. Extracted data included the number of participants randomized and analyzed for efficacy, and types of analyses for efficacy and safety and their definitions (i.e., criteria for including participants in each type of analysis). We identified 21 trials, 11 of which were published randomized controlled trials, and that provided the documents needed for planned comparisons. For three trials, there was disagreement on the number of randomized participants between the research report and publication. Seven types of efficacy analyses were described in the protocols, statistical analysis plans, and publications, including ITT and six others. The protocol or publication described ITT using six different definitions, resulting in frequent disagreements between the two documents (i.e., different numbers of participants were included in the analyses). Descriptions of analyses conducted did not agree between internal company documents and what was publicly reported. Internal company documents provide extensive documentation of methods planned and used, and trial findings, and should be publicly accessible. Reporting standards for randomized controlled trials should recommend transparent descriptions and definitions of analyses performed and which study participants are excluded.

  19. Evaluation of automated decisionmaking methodologies and development of an integrated robotic system simulation, volume 2, part 1. Appendix A: Software documentation

    NASA Technical Reports Server (NTRS)

    Lowrie, J. W.; Fermelia, A. J.; Haley, D. C.; Gremban, K. D.; Vanbaalen, J.; Walsh, R. W.

    1982-01-01

    Documentation of the preliminary software developed as a framework for a generalized integrated robotic system simulation is presented. The program structure is composed of three major functions controlled by a program executive. The three major functions are: system definition, analysis tools, and post processing. The system definition function handles user input of system parameters and definition of the manipulator configuration. The analysis tools function handles the computational requirements of the program. The post processing function allows for more detailed study of the results of analysis tool function executions. Also documented is the manipulator joint model software to be used as the basis of the manipulator simulation which will be part of the analysis tools capability.

  20. Contact Allergy Cross-reactions: Retrospective Clinical Data and Review of the Literature.

    PubMed

    Scheman, Andrew; Hipolito, Ricky; Severson, David; Youkhanis, Nineveh

    We discuss cross-reactions that can occur when a patient allergic to a specific allergen also reacts to a similar allergen. Currently, The American Contact Dermatitis Society Contact Allergy Management Program, which allows physicians to identify safe products for their patients, uses a 10% threshold to distinguish significant cross-reactors. New clinical data from a patch testing center along with previous data in the literature are analyzed to help determine whether current cross-reactor definitions are reasonable or should be altered.

  1. Nuclear Hybrid Energy Systems FY16 Modeling Efforts at ORNL

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cetiner, Sacit M.; Greenwood, Michael Scott; Harrison, Thomas J.

    A nuclear hybrid system uses a nuclear reactor as the basic power generation unit. The power generated by the nuclear reactor is utilized by one or more power customers as either thermal power, electrical power, or both. In general, a nuclear hybrid system will couple the nuclear reactor to at least one thermal power user in addition to the power conversion system. The definition and architecture of a particular nuclear hybrid system is flexible depending on local markets needs and opportunities. For example, locations in need of potable water may be best served by coupling a desalination plant to themore » nuclear system. Similarly, an area near oil refineries may have a need for emission-free hydrogen production. A nuclear hybrid system expands the nuclear power plant from its more familiar central power station role by diversifying its immediately and directly connected customer base. The definition, design, analysis, and optimization work currently performed with respect to the nuclear hybrid systems represents the work of three national laboratories. Idaho National Laboratory (INL) is the lead lab working with Argonne National Laboratory (ANL) and Oak Ridge National Laboratory. Each laboratory is providing modeling and simulation expertise for the integration of the hybrid system.« less

  2. Safe Affordable Fission Engine-(SAFE-) 100a Heat Exchanger Thermal and Structural Analysis

    NASA Technical Reports Server (NTRS)

    Steeve, B. E.

    2005-01-01

    A potential fission power system for in-space missions is a heat pipe-cooled reactor coupled to a Brayton cycle. In this system, a heat exchanger (HX) transfers the heat of the reactor core to the Brayton gas. The Safe Affordable Fission Engine- (SAFE-) 100a is a test program designed to thermally and hydraulically simulate a 95 Btu/s prototypic heat pipe-cooled reactor using electrical resistance heaters on the ground. This Technical Memorandum documents the thermal and structural assessment of the HX used in the SAFE-100a program.

  3. Benchmark experiments at ASTRA facility on definition of space distribution of {sup 235}U fission reaction rate

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bobrov, A. A.; Boyarinov, V. F.; Glushkov, A. E.

    2012-07-01

    Results of critical experiments performed at five ASTRA facility configurations modeling the high-temperature helium-cooled graphite-moderated reactors are presented. Results of experiments on definition of space distribution of {sup 235}U fission reaction rate performed at four from these five configurations are presented more detail. Analysis of available information showed that all experiments on criticality at these five configurations are acceptable for use them as critical benchmark experiments. All experiments on definition of space distribution of {sup 235}U fission reaction rate are acceptable for use them as physical benchmark experiments. (authors)

  4. Superfund record of decision (EPA region 10): Idaho National Engineering Lab, (USDOE) Operable Unit 26 (Stationary Low-Power Reactor-1 and Boiling Water Reactor Experiment-I Burial Grounds), Idaho Falls, ID, December 1, 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1997-03-01

    This document presents the selected remedial action for the Stationary Low-Power Reactor-1 (SL-1) burial ground, the Boiling Water Reactor Experiment-I (BORAX-I) burial ground, and 10 no action sites in Waste Area Group 5. Actual or threatened releases of hazardous substances from the SL-1 and BORAX-I burial grounds, if not addressed by implementing the response action selected in this Record of Decision, may present a current or potential threat to public health, welfare, or the environment. The 10 no action sites do not present a threat to human health or the environment.

  5. An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Boing, L.E.; Henley, D.R.; Manion, W.J.

    1989-12-01

    Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document inmore » their evaluation process. 73 refs., 26 figs., 69 tabs.« less

  6. Shift Verification and Validation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pandya, Tara M.; Evans, Thomas M.; Davidson, Gregory G

    2016-09-07

    This documentation outlines the verification and validation of Shift for the Consortium for Advanced Simulation of Light Water Reactors (CASL). Five main types of problems were used for validation: small criticality benchmark problems; full-core reactor benchmarks for light water reactors; fixed-source coupled neutron-photon dosimetry benchmarks; depletion/burnup benchmarks; and full-core reactor performance benchmarks. We compared Shift results to measured data and other simulated Monte Carlo radiation transport code results, and found very good agreement in a variety of comparison measures. These include prediction of critical eigenvalue, radial and axial pin power distributions, rod worth, leakage spectra, and nuclide inventories over amore » burn cycle. Based on this validation of Shift, we are confident in Shift to provide reference results for CASL benchmarking.« less

  7. New results from RENO and prospects with RENO-50

    NASA Astrophysics Data System (ADS)

    Kim, Soo-Bong

    2015-08-01

    RENO (Reactor Experiment for Neutrino Oscillation) has made a definitive measurement of the smallest mixing angle θ13 in 2012, based on the disappearance of electron antineutrinos. More precise measurements have been obtained and presented on the mixing angle and the reactor neutrino spectrum, using ˜800 days of data. We have observed an excess of inverse-beta-decay (IBD) prompt spectrum near 5 MeV with respect to the most commonly used models. The excess is found to be consistent with coming from reactors. We have also successfully measured the reactor neutrino flux with a delayed signal of neutron capture on hydrogen. A future reactor neutrino experiment of RENO-50 is proposed to determine the neutrino mass hierarchy and to make highly precise measurements of θ12, Δm212, and Δ m312. Physics goals and sensitivities of RENO-50 are presented with a strategy of obtaining an extremely good energy resolution toward the neutrino mass hierarchy.

  8. Standardized Definitions for Code Verification Test Problems

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Doebling, Scott William

    This document contains standardized definitions for several commonly used code verification test problems. These definitions are intended to contain sufficient information to set up the test problem in a computational physics code. These definitions are intended to be used in conjunction with exact solutions to these problems generated using Exact- Pack, www.github.com/lanl/exactpack.

  9. 36 CFR 220.3 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... environmental impact statement (EIS) or environmental assessment (EA). Decision notice. A concise written record... ENVIRONMENTAL POLICY ACT (NEPA) COMPLIANCE § 220.3 Definitions. The following definitions supplement, by adding... about natural resource systems is sometimes uncertain. Decision document. A record of decision, decision...

  10. WikiHyperGlossary (WHG): an information literacy technology for chemistry documents.

    PubMed

    Bauer, Michael A; Berleant, Daniel; Cornell, Andrew P; Belford, Robert E

    2015-01-01

    The WikiHyperGlossary is an information literacy technology that was created to enhance reading comprehension of documents by connecting them to socially generated multimedia definitions as well as semantically relevant data. The WikiHyperGlossary enhances reading comprehension by using the lexicon of a discipline to generate dynamic links in a document to external resources that can provide implicit information the document did not explicitly provide. Currently, the most common method to acquire additional information when reading a document is to access a search engine and browse the web. This may lead to skimming of multiple documents with the novice actually never returning to the original document of interest. The WikiHyperGlossary automatically brings information to the user within the current document they are reading, enhancing the potential for deeper document understanding. The WikiHyperGlossary allows users to submit a web URL or text to be processed against a chosen lexicon, returning the document with tagged terms. The selection of a tagged term results in the appearance of the WikiHyperGlossary Portlet containing a definition, and depending on the type of word, tabs to additional information and resources. Current types of content include multimedia enhanced definitions, ChemSpider query results, 3D molecular structures, and 2D editable structures connected to ChemSpider queries. Existing glossaries can be bulk uploaded, locked for editing and associated with multiple social generated definitions. The WikiHyperGlossary leverages both social and semantic web technologies to bring relevant information to a document. This can not only aid reading comprehension, but increases the users' ability to obtain additional information within the document. We have demonstrated a molecular editor enabled knowledge framework that can result in a semantic web inductive reasoning process, and integration of the WikiHyperGlossary into other software technologies, like the Jikitou Biomedical Question and Answer system. Although this work was developed in the chemical sciences and took advantage of open science resources and initiatives, the technology is extensible to other knowledge domains. Through the DeepLit (Deeper Literacy: Connecting Documents to Data and Discourse) startup, we seek to extend WikiHyperGlossary technologies to other knowledge domains, and integrate them into other knowledge acquisition workflows.

  11. Procedure to Generate the MPACT Multigroup Library

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kim, Kang Seog

    The CASL neutronics simulator MPACT is under development for the neutronics and T-H coupled simulation for the light water reactor. The objective of this document is focused on reviewing the current procedure to generate the MPACT multigroup library. Detailed methodologies and procedures are included in this document for further discussion to improve the MPACT multigroup library.

  12. Document control and Conduct of Operations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Collins, S.K.; Meltzer, F.L.

    1993-01-01

    Department of Energy (DOE) Order 5480.19, Conduct of operations, places stringent requirements on a wide range of activities at DOE facilities. These requirements directly affect personnel at the Advanced Test Reactor (ATR), which is located in the Test Reactor Area of the Idaho National Engineering Laboratory and operated for DOE by EG G Idaho, Inc. In order for the ATR to comply with 5480.19, the very personality of the reactor facility's document control unit has had to undergo a major change. The Facility and Administrative Support Unit (FAS) is charged with nudntenance of ATR's controlled ddcuments-diousands of operating and administrativemore » procedures. Prior to the imposition of 5480.19, FAS was content to operate in a clerical support mode, seldom questioning or seeking to improve. This numer of doing business is inappropriate within the framework of DOE 5480.19 and is also at odds with the approach to Total Quality Management (TQM) promulgated by EG G Idaho.To comply with the requirements of 5480.19, FAS has Actively applied TQM principles. Empowered personnel to unprove operations through the establishment of a teatn approach. Begun an automation process that is already paying large dividends in terms of improved procedure accuracy and compliance. A state-of-the-art text retrival system is already in place. We are vigorously pursuing fully automated document tmcidng and document management. This paper describes in detail the steps taken to date, the improvements and the lessons learned. It aLw discusses plans for the future that will enable FAS to support the ATR in inccreasing its responsiveness to the Conduct of Operations Order.« less

  13. Computer software documentation

    NASA Technical Reports Server (NTRS)

    Comella, P. A.

    1973-01-01

    A tutorial in the documentation of computer software is presented. It presents a methodology for achieving an adequate level of documentation as a natural outgrowth of the total programming effort commencing with the initial problem statement and definition and terminating with the final verification of code. It discusses the content of adequate documentation, the necessity for such documentation and the problems impeding achievement of adequate documentation.

  14. N Reactor Deactivation Program Plan. Revision 4

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Walsh, J.L.

    1993-12-01

    This N Reactor Deactivation Program Plan is structured to provide the basic methodology required to place N Reactor and supporting facilities {center_dot} in a radiologically and environmentally safe condition such that they can be decommissioned at a later date. Deactivation will be in accordance with facility transfer criteria specified in Department of Energy (DOE) and Westinghouse Hanford Company (WHC) guidance. Transition activities primarily involve shutdown and isolation of operational systems and buildings, radiological/hazardous waste cleanup, N Fuel Basin stabilization and environmental stabilization of the facilities. The N Reactor Deactivation Program covers the period FY 1992 through FY 1997. The directivemore » to cease N Reactor preservation and prepare for decommissioning was issued by DOE to WHC on September 20, 1991. The work year and budget data supporting the Work Breakdown Structure in this document are found in the Activity Data Sheets (ADS) and the Environmental Restoration Program Baseline, that are prepared annually.« less

  15. 48 CFR 4.301 - Definition.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 48 Federal Acquisition Regulations System 1 2011-10-01 2011-10-01 false Definition. 4.301 Section 4.301 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL ADMINISTRATIVE MATTERS Paper Documents 4.301 Definition. Printed or copied double-sided, as used in this subpart, means...

  16. 48 CFR 4.301 - Definition.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 48 Federal Acquisition Regulations System 1 2013-10-01 2013-10-01 false Definition. 4.301 Section 4.301 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL ADMINISTRATIVE MATTERS Paper Documents 4.301 Definition. Printed or copied double-sided, as used in this subpart, means...

  17. 48 CFR 4.301 - Definition.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 48 Federal Acquisition Regulations System 1 2014-10-01 2014-10-01 false Definition. 4.301 Section 4.301 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL ADMINISTRATIVE MATTERS Paper Documents 4.301 Definition. Printed or copied double-sided, as used in this subpart, means...

  18. 48 CFR 4.301 - Definition.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Definition. 4.301 Section 4.301 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL ADMINISTRATIVE MATTERS Paper Documents 4.301 Definition. Printed or copied double-sided, as used in this subpart, means...

  19. 48 CFR 4.301 - Definition.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 48 Federal Acquisition Regulations System 1 2012-10-01 2012-10-01 false Definition. 4.301 Section 4.301 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL ADMINISTRATIVE MATTERS Paper Documents 4.301 Definition. Printed or copied double-sided, as used in this subpart, means...

  20. 30 CFR 250.200 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... OPERATIONS IN THE OUTER CONTINENTAL SHELF Plans and Information General Information § 250.200 Definitions... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Definitions. 250.200 Section 250.200 Mineral... subpart are listed alphabetically below: CID means Conservation Information Document CZMA means Coastal...

  1. Probabilistic Fracture Mechanics of Reactor Pressure Vessels with Populations of Flaws

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Spencer, Benjamin; Backman, Marie; Williams, Paul

    This report documents recent progress in developing a tool that uses the Grizzly and RAVEN codes to perform probabilistic fracture mechanics analyses of reactor pressure vessels in light water reactor nuclear power plants. The Grizzly code is being developed with the goal of creating a general tool that can be applied to study a variety of degradation mechanisms in nuclear power plant components. Because of the central role of the reactor pressure vessel (RPV) in a nuclear power plant, particular emphasis is being placed on developing capabilities to model fracture in embrittled RPVs to aid in the process surrounding decisionmore » making relating to life extension of existing plants. A typical RPV contains a large population of pre-existing flaws introduced during the manufacturing process. The use of probabilistic techniques is necessary to assess the likelihood of crack initiation at one or more of these flaws during a transient event. This report documents development and initial testing of a capability to perform probabilistic fracture mechanics of large populations of flaws in RPVs using reduced order models to compute fracture parameters. The work documented here builds on prior efforts to perform probabilistic analyses of a single flaw with uncertain parameters, as well as earlier work to develop deterministic capabilities to model the thermo-mechanical response of the RPV under transient events, and compute fracture mechanics parameters at locations of pre-defined flaws. The capabilities developed as part of this work provide a foundation for future work, which will develop a platform that provides the flexibility needed to consider scenarios that cannot be addressed with the tools used in current practice.« less

  2. Remediation Optimization: Definition, Scope and Approach

    EPA Pesticide Factsheets

    This document provides a general definition, scope and approach for conducting optimization reviews within the Superfund Program and includes the fundamental principles and themes common to optimization.

  3. Standardized End Point Definitions for Coronary Intervention Trials: The Academic Research Consortium-2 Consensus Document.

    PubMed

    Garcia-Garcia, Hector M; McFadden, Eugène P; Farb, Andrew; Mehran, Roxana; Stone, Gregg W; Spertus, John; Onuma, Yoshinobu; Morel, Marie-Angèle; van Es, Gerrit-Anne; Zuckerman, Bram; Fearon, William F; Taggart, David; Kappetein, Arie-Pieter; Krucoff, Mitchell W; Vranckx, Pascal; Windecker, Stephan; Cutlip, Donald; Serruys, Patrick W

    2018-06-12

    The Academic Research Consortium (ARC)-2 initiative revisited the clinical and angiographic end point definitions in coronary device trials, proposed in 2007, to make them more suitable for use in clinical trials that include increasingly complex lesion and patient populations and incorporate novel devices such as bioresorbable vascular scaffolds. In addition, recommendations for the incorporation of patient-related outcomes in clinical trials are proposed. Academic Research Consortium-2 is a collaborative effort between academic research organizations in the United States and Europe, device manufacturers, and European, US, and Asian regulatory bodies. Several in-person meetings were held to discuss the changes that have occurred in the device landscape and in clinical trials and regulatory pathways in the last decade. The consensus-based end point definitions in this document are endorsed by the stakeholders of this document and strongly advocated for clinical trial purposes. This Academic Research Consortium-2 document provides further standardization of end point definitions for coronary device trials, incorporating advances in technology and knowledge. Their use will aid interpretation of trial outcomes and comparison among studies, thus facilitating the evaluation of the safety and effectiveness of these devices. © 2018 American Heart Association, Inc., and European Society of Cardiology.

  4. 77 FR 39388 - Removal of Category IIIa, IIIb, and IIIc Definitions; Confirmation of Effective Date and Response...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-03

    ...- AK03 Removal of Category IIIa, IIIb, and IIIc Definitions; Confirmation of Effective Date and Response... received on that direct final rule. In that document, the FAA proposed to remove the definitions of Category IIIa, IIIb, and IIIc operations because the definitions are outdated and no longer used for...

  5. 4 CFR 201.2 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 4 Accounts 1 2010-01-01 2010-01-01 false Definitions. 201.2 Section 201.2 Accounts RECOVERY ACCOUNTABILITY AND TRANSPARENCY BOARD PUBLIC INFORMATION AND REQUESTS § 201.2 Definitions. For words used in this document, unless the context indicates otherwise, singular includes the plural, plural includes the...

  6. 22 CFR 41.0 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 22 Foreign Relations 1 2011-04-01 2011-04-01 false Definitions. 41.0 Section 41.0 Foreign Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF NONIMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Passport and Visas Not Required for Certain Nonimmigrants § 41.0 Definitions. For...

  7. 22 CFR 41.0 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Definitions. 41.0 Section 41.0 Foreign Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF NONIMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Passport and Visas Not Required for Certain Nonimmigrants § 41.0 Definitions. For...

  8. 22 CFR 41.0 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 22 Foreign Relations 1 2014-04-01 2014-04-01 false Definitions. 41.0 Section 41.0 Foreign Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF NONIMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Passport and Visas Not Required for Certain Nonimmigrants § 41.0 Definitions. For...

  9. 22 CFR 41.0 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 22 Foreign Relations 1 2012-04-01 2012-04-01 false Definitions. 41.0 Section 41.0 Foreign Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF NONIMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Passport and Visas Not Required for Certain Nonimmigrants § 41.0 Definitions. For...

  10. 22 CFR 41.0 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 22 Foreign Relations 1 2013-04-01 2013-04-01 false Definitions. 41.0 Section 41.0 Foreign Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF NONIMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Passport and Visas Not Required for Certain Nonimmigrants § 41.0 Definitions. For...

  11. Fusion Simulation Program Definition. Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cary, John R.

    2012-09-05

    We have completed our contributions to the Fusion Simulation Program Definition Project. Our contributions were in the overall planning with concentration in the definition of the area of Software Integration and Support. We contributed to the planning of multiple meetings, and we contributed to multiple planning documents.

  12. FY16 Status Report for the Uranium-Molybdenum Fuel Concept

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bennett, Wendy D.; Doherty, Ann L.; Henager, Charles H.

    2016-09-22

    The Fuel Cycle Research and Development program of the Office of Nuclear Energy has implemented a program to develop a Uranium-Molybdenum metal fuel for light water reactors. Uranium-Molybdenum fuel has the potential to provide superior performance based on its thermo-physical properties. With sufficient development, it may be able to provide the Light Water Reactor industry with a melt-resistant, accident-tolerant fuel with improved safety response. The Pacific Northwest National Laboratory has been tasked with extrusion development and performing ex-reactor corrosion testing to characterize the performance of Uranium-Molybdenum fuel in both these areas. This report documents the results of the fiscal yearmore » 2016 effort to develop the Uranium-Molybdenum metal fuel concept for light water reactors.« less

  13. Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Demonstration. CEDT Phase 1 Preliminary Design Documentation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sanchez, Rene Gerardo; Hutchinson, Jesson D.; Mcclure, Patrick Ray

    2015-08-20

    The intent of the integral experiment request IER 299 (called KiloPower by NASA) is to assemble and evaluate the operational performance of a compact reactor configuration that closely resembles the flight unit to be used by NASA to execute a deep space exploration mission. The reactor design will include heat pipes coupled to Stirling engines to demonstrate how one can generate electricity when extracting energy from a “nuclear generated” heat source. This series of experiments is a larger scale follow up to the DUFF series of experiments1,2 that were performed using the Flat-Top assembly.

  14. Nuclear reactors built, being built, or planned, 1994

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-07-01

    This document contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1994. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE; from the US Nuclear Regulatory Commission (NRC); from the US reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from US and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: a commercial reactor locator map and tables of the characteristicmore » and statistical data that follow; a table of abbreviations; tables of data for reactors operating, being built, or planned; and tables of data for reactors that have been shut down permanently or dismantled. The reactors are subdivided into the following parts: Civilian, Production, Military, Export, and Critical Assembly. Export reactor refers to a reactor for which the principal nuclear contractor is a US company -- working either independently or in cooperation with a foreign company (Part 4). Critical assembly refers to an assembly of fuel and moderator that requires an external source of neutrons to initiate and maintain fission. A critical assembly is used for experimental measurements (Part 5).« less

  15. A Climatology of Nocturnal-Convection Initiation Over the Central Great Plains

    NASA Astrophysics Data System (ADS)

    Reif, D. W.; Bluestein, H. B.

    2015-12-01

    A nocturnal maximum in rainfall and thunderstorm activity over the central Great Plains is widely documented, but the mechanisms for understanding the development of thunderstorms over the region at night are still not well understood. Elevated convection, defined by Colman (1990) as storms formed through ascent above frontal surfaces, is one explanation, but our study shows that many thunderstorms can initiate at night without the presence of an elevated frontal inversion or nearby surface boundary. We address the following questions: Of all the events documented, what percentage fall under this definition of elevated convection, and what percentage fall outside of that definition? How do characteristics differ among the events that fall under that definition and the events that fall outside that definition? This study documents convection initiation (CI) events occurring at night over the central Great Plains from 1996 through 2014 during the months of April through July. Storm characteristics such as storm type (defined as linear, areal, or single cell), storm motion, initiation time and location, and others were documented. Once all of the cases were documented, surface data were examined to locate any nearby surface boundaries. The event's location relative to these boundaries (if they existed) was documented. Three main modes of CI were identified: formation on a surface boundary, formation on the cold side of a surface boundary, and formation without the presence of a surface boundary. A climatology of these events will be presented. There are many differences among the different modes of CI at night. One result is that there appears to be two main peaks of CI time at night: one early at night and one later at night. The later peak is likely due to the events that form in the absence of a nearby surface boundary.

  16. 10 CFR 710.5 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Ridge, Richland, and Savannah River Operations Offices and the Pittsburgh and Schenectady Naval Reactors... area cases, the Director, Office of Security Operations; and any person designated in writing to serve... Operations Office (Albuquerque, Chicago, Idaho, Nevada, Oak Ridge, Oakland, Richland, or Savannah River), the...

  17. 10 CFR 710.5 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Ridge, Richland, and Savannah River Operations Offices and the Pittsburgh and Schenectady Naval Reactors... area cases, the Director, Office of Security Operations; and any person designated in writing to serve... Operations Office (Albuquerque, Chicago, Idaho, Nevada, Oak Ridge, Oakland, Richland, or Savannah River), the...

  18. 10 CFR 710.5 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Ridge, Richland, and Savannah River Operations Offices and the Pittsburgh and Schenectady Naval Reactors... area cases, the Director, Office of Security Operations; and any person designated in writing to serve... Operations Office (Albuquerque, Chicago, Idaho, Nevada, Oak Ridge, Oakland, Richland, or Savannah River), the...

  19. 10 CFR 710.5 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Ridge, Richland, and Savannah River Operations Offices and the Pittsburgh and Schenectady Naval Reactors... area cases, the Director, Office of Security Operations; and any person designated in writing to serve... Operations Office (Albuquerque, Chicago, Idaho, Nevada, Oak Ridge, Oakland, Richland, or Savannah River), the...

  20. 10 CFR 710.5 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Ridge, Richland, and Savannah River Operations Offices and the Pittsburgh and Schenectady Naval Reactors... area cases, the Director, Office of Security Operations; and any person designated in writing to serve... Operations Office (Albuquerque, Chicago, Idaho, Nevada, Oak Ridge, Oakland, Richland, or Savannah River), the...

  1. 40 CFR 60.421 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... stream to the reactor/crystallizer for synthetic and coke oven by-product ammonium sulfate manufacturing...-product from process streams generated during caprolactam manufacture. Coke oven by-product ammonium... ammonia recovered as a by-product from the manufacture of coke. Synthetic ammonium sulfate manufacturing...

  2. 40 CFR 60.421 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... stream to the reactor/crystallizer for synthetic and coke oven by-product ammonium sulfate manufacturing...-product from process streams generated during caprolactam manufacture. Coke oven by-product ammonium... ammonia recovered as a by-product from the manufacture of coke. Synthetic ammonium sulfate manufacturing...

  3. 40 CFR 60.421 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... stream to the reactor/crystallizer for synthetic and coke oven by-product ammonium sulfate manufacturing...-product from process streams generated during caprolactam manufacture. Coke oven by-product ammonium... ammonia recovered as a by-product from the manufacture of coke. Synthetic ammonium sulfate manufacturing...

  4. 40 CFR 60.421 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... stream to the reactor/crystallizer for synthetic and coke oven by-product ammonium sulfate manufacturing...-product from process streams generated during caprolactam manufacture. Coke oven by-product ammonium... ammonia recovered as a by-product from the manufacture of coke. Synthetic ammonium sulfate manufacturing...

  5. 40 CFR 60.421 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... stream to the reactor/crystallizer for synthetic and coke oven by-product ammonium sulfate manufacturing...-product ammonium sulfate manufacturing plant means any plant which produces ammonium sulfate as a by-product from process streams generated during caprolactam manufacture. Coke oven by-product ammonium...

  6. Reflections on Documentation: A Discussion with Thought Leaders from Reggio Emilia

    ERIC Educational Resources Information Center

    Turner, Terri; Wilson, Daniel Gray

    2010-01-01

    This article presents the voices of three central thinkers in the documentation movement in a round-table discussion that explores the key questions regarding the definition of documentation, common misunderstandings of the strategy, lessons that have emerged over decades of documenting in various contexts, and puzzles that are emerging for the…

  7. Space Telecommunications Radio System (STRS) Definitions and Acronyms

    NASA Technical Reports Server (NTRS)

    Briones, Janette C.; Handler, Louis M.; Johnson, Sandra K.; Nappier, Jennifer; Gnepp, Steven; Kacpura, Thomas J.; Reinhart, Richard C.; Hall, Charles S.; Mortensen, Dale

    2008-01-01

    Software-defined radio is a relatively new technology area, and industry consensus on terminology is not always consistent. Confusion exists when the various organizations and standards bodies define different radio terms associated with the actual amount of reconfigurability of the radios. The Space Telecommunications Radio System (STRS) Definitions and Acronyms Document provides the readers of the STRS documents a common understanding of the terminology used and how they will be applied to the STRS architecture.

  8. Differences in Reporting of Analyses in Internal Company Documents Versus Published Trial Reports: Comparisons in Industry-Sponsored Trials in Off-Label Uses of Gabapentin

    PubMed Central

    Vedula, S. Swaroop; Li, Tianjing; Dickersin, Kay

    2013-01-01

    Background Details about the type of analysis (e.g., intent to treat [ITT]) and definitions (i.e., criteria for including participants in the analysis) are necessary for interpreting a clinical trial's findings. Our objective was to compare the description of types of analyses and criteria for including participants in the publication (i.e., what was reported) with descriptions in the corresponding internal company documents (i.e., what was planned and what was done). Trials were for off-label uses of gabapentin sponsored by Pfizer and Parke-Davis, and documents were obtained through litigation. Methods and Findings For each trial, we compared internal company documents (protocols, statistical analysis plans, and research reports, all unpublished), with publications. One author extracted data and another verified, with a third person verifying discordant items and a sample of the rest. Extracted data included the number of participants randomized and analyzed for efficacy, and types of analyses for efficacy and safety and their definitions (i.e., criteria for including participants in each type of analysis). We identified 21 trials, 11 of which were published randomized controlled trials, and that provided the documents needed for planned comparisons. For three trials, there was disagreement on the number of randomized participants between the research report and publication. Seven types of efficacy analyses were described in the protocols, statistical analysis plans, and publications, including ITT and six others. The protocol or publication described ITT using six different definitions, resulting in frequent disagreements between the two documents (i.e., different numbers of participants were included in the analyses). Conclusions Descriptions of analyses conducted did not agree between internal company documents and what was publicly reported. Internal company documents provide extensive documentation of methods planned and used, and trial findings, and should be publicly accessible. Reporting standards for randomized controlled trials should recommend transparent descriptions and definitions of analyses performed and which study participants are excluded. Please see later in the article for the Editors' Summary PMID:23382656

  9. 50 CFR 600.750 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... concurrence; or (2) agrees upon another specified definition. Fishery negotiation panel (FNP) means an... affected in a similar manner. Report means a document submitted by an FNP in accordance with the Magnuson...

  10. 48 CFR 211.275-1 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Documents 211.275-1 Definitions. Bulk commodities, case, palletized unit load, passive RFID tag, and radio frequency identification are defined in the clause at 252.211-7006, Passive Radio Frequency Identification...

  11. 14 CFR 16.3 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    .... Unless otherwise noted, mail also means electronic mail containing PDF copies of pleadings or documents... § 16.1 and any regulation, agreement, or document of conveyance issued or made under that statute... Civil Rights. Complainant means the person submitting a complaint. Complaint means a written document...

  12. 21 CFR 1401.3 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 21 Food and Drugs 9 2010-04-01 2010-04-01 false Definitions. 1401.3 Section 1401.3 Food and Drugs OFFICE OF NATIONAL DRUG CONTROL POLICY PUBLIC AVAILABILITY OF INFORMATION § 1401.3 Definitions. For the... paper, microform, audio-visual materials, or machine-readable documentation. ONDCP will provide a copy...

  13. 50 CFR 660.11 - General definitions.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... General definitions. These definitions are specific to the fisheries covered in subparts C through G of..., subpart C; documentation of the weighing of fish relative to the requirements of § 660.13, subpart C; and... contributing to the rebuilding of overfished West Coast groundfish species. Regulations at § 660.70, Subpart C...

  14. Requirements Specification Document

    DOT National Transportation Integrated Search

    1996-04-26

    The System Definition Document identifies the top level processes, data flows, : and system controls for the Gary-Chicago-Milwaukee (GCM) Corridor Transportation Information Center (C-TIC). This Requirements Specification establishes the requirements...

  15. 40 CFR 372.3 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ..., roasters, and foundry furnaces). (8) Titanium dioxide chloride process oxidation reactors. (9) Methane... sulfur values from spent sulfuric acid. (12) Halogen acid furnaces (HAFs) for the production of acid from halogenated hazardous waste generated by chemical production facilities where the furnace is located on the...

  16. 40 CFR 372.3 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ..., roasters, and foundry furnaces). (8) Titanium dioxide chloride process oxidation reactors. (9) Methane... sulfur values from spent sulfuric acid. (12) Halogen acid furnaces (HAFs) for the production of acid from halogenated hazardous waste generated by chemical production facilities where the furnace is located on the...

  17. 10 CFR 830.3 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... research and experimental and analytical laboratory activities, electron microscopes, and X-ray machines... research, test, and power reactors, and critical and pulsed assemblies and any assembly that is designed to... covering a topic such as: quality assurance; maintenance of safety systems; personnel training; conduct of...

  18. A Method of Retrospective Computerized System Validation for Drug Manufacturing Software Considering Modifications

    NASA Astrophysics Data System (ADS)

    Takahashi, Masakazu; Fukue, Yoshinori

    This paper proposes a Retrospective Computerized System Validation (RCSV) method for Drug Manufacturing Software (DMSW) that relates to drug production considering software modification. Because DMSW that is used for quality management and facility control affects big impact to quality of drugs, regulatory agency required proofs of adequacy for DMSW's functions and performance based on developed documents and test results. Especially, the work that explains adequacy for previously developed DMSW based on existing documents and operational records is called RCSV. When modifying RCSV conducted DMSW, it was difficult to secure consistency between developed documents and test results for modified DMSW parts and existing documents and operational records for non-modified DMSW parts. This made conducting RCSV difficult. In this paper, we proposed (a) definition of documents architecture, (b) definition of descriptive items and levels in the documents, (c) management of design information using database, (d) exhaustive testing, and (e) integrated RCSV procedure. As a result, we could conduct adequate RCSV securing consistency.

  19. 29 CFR 1610.1 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... to the request. (h) Attestation refers to the authentication of copies of Commission documents by an... refers to the authentication of copies of Commission documents by an affidavit or unsworn declaration...

  20. FY13 Summary Report on the Augmentation of the Spent Fuel Composition Dataset for Nuclear Forensics: SFCOMPO/NF

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Brady Raap, Michaele C.; Lyons, Jennifer A.; Collins, Brian A.

    This report documents the FY13 efforts to enhance a dataset of spent nuclear fuel isotopic composition data for use in developing intrinsic signatures for nuclear forensics. A review and collection of data from the open literature was performed in FY10. In FY11, the Spent Fuel COMPOsition (SFCOMPO) excel-based dataset for nuclear forensics (NF), SFCOMPO/NF was established and measured data for graphite production reactors, Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs) were added to the dataset and expanded to include a consistent set of data simulated by calculations. A test was performed to determine whether the SFCOMPO/NF dataset willmore » be useful for the analysis and identification of reactor types from isotopic ratios observed in interdicted samples.« less

  1. DR Reactor VSR channel damage

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kempf, F.J.; Rawlins, J.K.

    1961-10-30

    On July 11, 1961 the Ball 3X System at DR Reactor was inadventently tripped. All vertical safety rods dropped and all channels were filled with balls. This report has the twofold purpose of documenting borescope observations of ten vertical rod channels at DR Reactor and recording the estimated extent of graphite damage resulting from the above incident. Channel damage data are presented on appended drawings. With suitable notations, the tracings of these drawings may be revised to reflect any future graphite damage. All vertical rod channels at DR Reactor were visually examined with a closed circuit television system during ballmore » removal efforts. Typical photographs of trapped balls and ledges, as viewed on the television monitor, are shown. Photographs of typical graphite damage, obtained through the borescope are also included in this report. 3 refs., 8 figs., 1 tab.« less

  2. Advanced Reactor Technologies - Regulatory Technology Development Plan (RTDP)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moe, Wayne L.

    This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However,more » it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory importance of key DOE reactor research initiatives should be assessed early in the technology development process. Quality assurance requirements supportive of later licensing activities must also be attached to important research activities to ensure resulting data is usable in that context. Early regulatory analysis and licensing approach planning thus provides a significant benefit to the formulation of research plans and also enables the planning and development of a compatible AdvSMR licensing framework, should significant modification be required.« less

  3. Advanced Reactor Technology -- Regulatory Technology Development Plan (RTDP)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moe, Wayne Leland

    This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However,more » it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory importance of key DOE reactor research initiatives should be assessed early in the technology development process. Quality assurance requirements supportive of later licensing activities must also be attached to important research activities to ensure resulting data is usable in that context. Early regulatory analysis and licensing approach planning thus provides a significant benefit to the formulation of research plans and also enables the planning and development of a compatible AdvSMR licensing framework, should significant modification be required.« less

  4. Electronic Document Delivery: OCLC's Prototype System.

    ERIC Educational Resources Information Center

    Hickey, Thomas B.; Calabrese, Andrew M.

    1986-01-01

    Describes development of system for retrieval of documents from magnetic storage that uses stored font definition codes to control an inexpensive laser printer in the production of copies that closely resemble original document. Trends in information equipment and printing industries that will govern future application of this technology are…

  5. Nuclear power plant Generic Aging Lessons Learned (GALL). Main report and appendix A

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kaza, K.E.; Diercks, D.R.; Holland, J.W.

    The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters,more » 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This document is Volume 1, consisting of the executive summary, summary and observations, and an appendix listing the GALL literature review tables.« less

  6. 8 CFR 270.1 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 8 Aliens and Nationality 1 2011-01-01 2011-01-01 false Definitions. 270.1 Section 270.1 Aliens and... Definitions. For the purpose of this part— Document means an instrument on which is recorded, by means of letters, figures, or marks, matters which may be used to fulfill any requirement of the Act. The term...

  7. 8 CFR 270.1 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 8 Aliens and Nationality 1 2014-01-01 2014-01-01 false Definitions. 270.1 Section 270.1 Aliens and... Definitions. For the purpose of this part— Document means an instrument on which is recorded, by means of letters, figures, or marks, matters which may be used to fulfill any requirement of the Act. The term...

  8. 8 CFR 270.1 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 8 Aliens and Nationality 1 2012-01-01 2012-01-01 false Definitions. 270.1 Section 270.1 Aliens and... Definitions. For the purpose of this part— Document means an instrument on which is recorded, by means of letters, figures, or marks, matters which may be used to fulfill any requirement of the Act. The term...

  9. 75 FR 8854 - Teacher Incentive Fund Program

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-26

    ...The Secretary of Education (Secretary) proposes priorities, requirements, definitions, and selection criteria under the Teacher Incentive Fund (TIF) program. These proposed priorities, requirements, definitions, and selection criteria are designed to be used in two separate and distinct TIF grant competitions: The Main TIF competition, which will provide TIF funding to eligible entities to support their implementation of performance-based compensation systems (PBCSs) in accordance with the priorities, the Main TIF requirements, the definitions, and the selection criteria proposed in this document, and the TIF Evaluation competition, which will provide, in accordance with the priorities, the Main TIF requirements, the definitions, and the selection criteria as well as the Evaluation requirements proposed in this document, TIF funding to help pay for the costs of implementing these eligible entities' PBCS in exchange for an agreement to participate in the national evaluation. The Secretary may use these proposed TIF priorities, requirements, definitions, and selection criteria in fiscal year (FY) 2010 and subsequent years. We intend the proposed priorities, requirements, definitions, and selection criteria to improve student achievement in high-need schools by creating incentives for effective teachers and principals in these schools.

  10. 10 CFR 810.3 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... of neutrons used to effect SNM production in the “subcritical assembly.” Agreement for cooperation... International Atomic Energy Agency. Non-nuclear-weapon state is a country not recognized as a nuclear-weapon...-Proliferation of Nuclear Weapons. Nuclear reactor means an apparatus, other than a nuclear explosive device...

  11. 10 CFR 810.3 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... of neutrons used to effect SNM production in the “subcritical assembly.” Agreement for cooperation... International Atomic Energy Agency. Non-nuclear-weapon state is a country not recognized as a nuclear-weapon...-Proliferation of Nuclear Weapons. Nuclear reactor means an apparatus, other than a nuclear explosive device...

  12. 40 CFR 63.101 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Organic Hazardous Air Pollutants From the Synthetic Organic Chemical Manufacturing Industry § 63.101... 71. Organic hazardous air pollutant or organic HAP means one of the chemicals listed in table 2 of... or more organic reactants to produce one or more organic compounds. Air oxidation reactor includes...

  13. 40 CFR 63.101 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Organic Hazardous Air Pollutants From the Synthetic Organic Chemical Manufacturing Industry § 63.101... 71. Organic hazardous air pollutant or organic HAP means one of the chemicals listed in table 2 of... or more organic reactants to produce one or more organic compounds. Air oxidation reactor includes...

  14. 40 CFR 63.101 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Organic Hazardous Air Pollutants From the Synthetic Organic Chemical Manufacturing Industry § 63.101... 71. Organic hazardous air pollutant or organic HAP means one of the chemicals listed in table 2 of... or more organic reactants to produce one or more organic compounds. Air oxidation reactor includes...

  15. 10 CFR 950.3 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ..., tests, analyses and acceptance criteria established under the combined license; (2) The conduct of pre... facility the reactor design for which is approved after December 31, 1993, by the Nuclear Regulatory Commission (and such design or a substantially similar design of comparable capacity was not approved on or...

  16. 10 CFR 950.3 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ..., tests, analyses and acceptance criteria established under the combined license; (2) The conduct of pre... facility the reactor design for which is approved after December 31, 1993, by the Nuclear Regulatory Commission (and such design or a substantially similar design of comparable capacity was not approved on or...

  17. 10 CFR 950.3 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ..., tests, analyses and acceptance criteria established under the combined license; (2) The conduct of pre... facility the reactor design for which is approved after December 31, 1993, by the Nuclear Regulatory Commission (and such design or a substantially similar design of comparable capacity was not approved on or...

  18. 10 CFR 950.3 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ..., tests, analyses and acceptance criteria established under the combined license; (2) The conduct of pre... facility the reactor design for which is approved after December 31, 1993, by the Nuclear Regulatory Commission (and such design or a substantially similar design of comparable capacity was not approved on or...

  19. 10 CFR 950.3 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ..., tests, analyses and acceptance criteria established under the combined license; (2) The conduct of pre... facility the reactor design for which is approved after December 31, 1993, by the Nuclear Regulatory Commission (and such design or a substantially similar design of comparable capacity was not approved on or...

  20. 40 CFR 63.191 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... polycarbonate. Methylene chloride is used as a solvent in this polymerization reaction. Polysulfide rubber means... product of reaction of butadiene with excess furfural in a liquid phase reactor. R-11 is usually used as... is not limited to, the reaction of tetrahydrophthalimide and perchloromethyl mercaptan with caustic...

  1. 40 CFR 63.191 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... polycarbonate. Methylene chloride is used as a solvent in this polymerization reaction. Polysulfide rubber means... product of reaction of butadiene with excess furfural in a liquid phase reactor. R-11 is usually used as... is not limited to, the reaction of tetrahydrophthalimide and perchloromethyl mercaptan with caustic...

  2. 40 CFR 63.191 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... polycarbonate. Methylene chloride is used as a solvent in this polymerization reaction. Polysulfide rubber means... product of reaction of butadiene with excess furfural in a liquid phase reactor. R-11 is usually used as... is not limited to, the reaction of tetrahydrophthalimide and perchloromethyl mercaptan with caustic...

  3. 40 CFR 63.191 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... polycarbonate. Methylene chloride is used as a solvent in this polymerization reaction. Polysulfide rubber means... product of reaction of butadiene with excess furfural in a liquid phase reactor. R-11 is usually used as... is not limited to, the reaction of tetrahydrophthalimide and perchloromethyl mercaptan with caustic...

  4. 40 CFR 63.191 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... polycarbonate. Methylene chloride is used as a solvent in this polymerization reaction. Polysulfide rubber means... product of reaction of butadiene with excess furfural in a liquid phase reactor. R-11 is usually used as... is not limited to, the reaction of tetrahydrophthalimide and perchloromethyl mercaptan with caustic...

  5. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Klipstein, David H.; Robinson, Sharon

    The Reaction Engineering Roadmap is a part of an industry- wide effort to create a blueprint of the research and technology milestones that are necessary to achieve longterm industry goals. This report documents the results of a workshop focused on the research needs, technology barriers, and priorities of the chemical industry as they relate to reaction engineering viewed first by industrial use (basic chemicals; specialty chemicals; pharmaceuticals; and polymers) and then by technology segment (reactor system selection, design, and scale-up; chemical mechanism development and property estimation; dealing with catalysis; and new, nonstandard reactor types).

  6. Lower food chain community study: thermal effects and post-thermal recovery in the streams and swamps of the Savannah River Plant

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kondratieff, P.; Kondratieff, B.C.

    1985-07-01

    The effects of thermal stress on lower food chain communities of streams and swamps of the Savannah River Plant. Both the autotroph assemblages and the macro invertebrate communities were studied in streams receiving heated reactor effluent. To document stream and swamp ecosystem recovery from thermal stress, the same communities of organisms were studied in a stream/swamp ecosystem which had received heated reactor effluent in the past. (ACR)

  7. Liquid metal fast breeder reactors, 1972--1973

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1974-01-01

    Reference to 1467 publications on liquid sodium fast breeder reactors cited in Nuclear Science Abstracts Volume 26 (1972) through Volume 27 (1973 through June) are contained in this citation to provide information on the contents of the document. References are arranged in order by the original NSA abstract number which approximately places them in chronological order. Sequence numbers appear beside each reference, and the personal author index refers to these sequence numbers. The subject index refers to the original abstract numbers. (auth)

  8. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Carla J. Miller

    This report provides a summary of the literature review that was performed and based on previous work performed at the Idaho National Laboratory studying the Three Mile Island 2 (TMI-2) nuclear reactor accident, specifically the melted fuel debris. The purpose of the literature review was to document prior published work that supports the feasibility of the analytical techniques that were developed to provide quantitative results of the make-up of the fuel and reactor component debris located inside and outside the containment. The quantitative analysis provides a technique to perform nuclear fuel accountancy measurements

  9. ROMPS critical design review. Volume 3: Furnace module design documentation

    NASA Technical Reports Server (NTRS)

    Dobbs, M. E.

    1992-01-01

    As part of the furnace module design documentation, the furnace module Easylab programs definitions and command variables are described. Also included are Easylab commands flow charts and fault conditions.

  10. Development of Integrated Programs for Aerospace-Vehicle Design (IPAD)

    NASA Technical Reports Server (NTRS)

    Anderson, O. L.; Calvery, A. L.; Davis, D. A.; Dickmann, L.; Folger, D. H.; Jochem, E. N.; Kitto, C. M.; Vonlimbach, G.

    1977-01-01

    Integrated Programs for Aerospace Vehicle Design (IPAD) system design requirements are given. The information is based on the IPAD User Requirements Document (D6-IPAD-70013-D) and the Integrated Information Processing Requirements Document (D6-IPAD-70012-D). General information about IPAD and a list of the system design requirements that are to be satisfied by the IPAD system are given. The system design requirements definition is to be considered as a baseline definition of the IPAD system design requirements.

  11. Definitions of Frequency and Timing Terms, Satellite Navigation and Timing Systems, and the Behavior and Analyses of Precision Crystal and Atomic Frequency Standards and their Characteristics

    DTIC Science & Technology

    2009-05-01

    time transfer techniques has largely been due to the improvement in frequency standards. In this document, an effort was made to provide substantial...of RCC Document 214-94, contains definitions of frequency and timing terms, time transfer techniques and analysis, and behavior of crystal and atomic...Characteristics, May 2009 viii TTG Telecommunications and Timing Group TWSTFT Two-Way Satellite Time and Frequency Transfer U.S. United States USNO

  12. Astronomy sortie missions definition study. Volume 2, book 2: Appendix

    NASA Technical Reports Server (NTRS)

    1972-01-01

    An updated and coordinated baseline experiment definition document is presented for each of the candidate astronomy sortie mission telescopes and arrays. The experiment objectives, requirements, interfaces, timelines, and programmatic considerations are included.

  13. Reactor Neutronics: Impact of Fissile Material

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Heidet, F.; Hill, R. N.

    Here, given a wide variety of reactor designs and fuel types, it can be difficult to identify the underlying cause of basic performance differences such as flux level and enrichment requirement. In this paper, using solely the definitions of the core multiplication factor and core power, simple relations have been derived allowing estimates of the flux ratio and fissile material concentration ratio for any reactor concept when 235U is replaced with 239Pu or vice-versa. These relations are functions of the neutron non-leakage probability, and one only needs to know number of neutrons emitted per fission, and the fission cross-section ratiomore » between the 235U system and the 239Pu system. It is found that for a reactor concept having significant leakage, the achievable flux level when using 239Pu as fissile material can be up to 45% larger than when using 235U as fissile material, and the required fissile concentration of 239Pu is up to 48% lower than that of 235U to achieve criticality.« less

  14. Reactor Neutronics: Impact of Fissile Material

    DOE PAGES

    Heidet, F.; Hill, R. N.

    2017-06-09

    Here, given a wide variety of reactor designs and fuel types, it can be difficult to identify the underlying cause of basic performance differences such as flux level and enrichment requirement. In this paper, using solely the definitions of the core multiplication factor and core power, simple relations have been derived allowing estimates of the flux ratio and fissile material concentration ratio for any reactor concept when 235U is replaced with 239Pu or vice-versa. These relations are functions of the neutron non-leakage probability, and one only needs to know number of neutrons emitted per fission, and the fission cross-section ratiomore » between the 235U system and the 239Pu system. It is found that for a reactor concept having significant leakage, the achievable flux level when using 239Pu as fissile material can be up to 45% larger than when using 235U as fissile material, and the required fissile concentration of 239Pu is up to 48% lower than that of 235U to achieve criticality.« less

  15. SPEAKEASY HELP documents

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fink, J.K.

    1972-07-01

    The HELP documents provide SPEAKEASY users with concise definitions of most of the words available in the current processors. In this report, the documents are given in a variety of formats to enable one to find specific information quickly. The bulk of this report consists of computer read-out of the HELP library via SPEAKEASY.

  16. Terminologie de Base de la Documentation. (Basic Terminology of Documentation).

    ERIC Educational Resources Information Center

    Commission des Communautes Europeennes (Luxembourg). Bureau de Terminologie.

    This glossary is designed to aid non-specialists whose activities require that they have some familiarity with the terminology of the modern methods of documentation. Definitions have been assembled from various dictionaries, manuals, etc., with particular attention being given to the publications of UNESCO and the International Standards…

  17. 10 CFR 1016.32 - Classification and preparation of documents.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 4 2013-01-01 2013-01-01 false Classification and preparation of documents. 1016.32... of Information § 1016.32 Classification and preparation of documents. (a) Classification. Restricted... he is not positive is not within that definition and CG-UF-3 does not provide positive classification...

  18. 10 CFR 1016.32 - Classification and preparation of documents.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 4 2014-01-01 2014-01-01 false Classification and preparation of documents. 1016.32... of Information § 1016.32 Classification and preparation of documents. (a) Classification. Restricted... he is not positive is not within that definition and CG-UF-3 does not provide positive classification...

  19. 10 CFR 1016.32 - Classification and preparation of documents.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 4 2012-01-01 2012-01-01 false Classification and preparation of documents. 1016.32... of Information § 1016.32 Classification and preparation of documents. (a) Classification. Restricted... he is not positive is not within that definition and CG-UF-3 does not provide positive classification...

  20. NASA in-house Commercially Developed Space Facility (CDSF) study report. Volume 1: Concept configuration definition

    NASA Technical Reports Server (NTRS)

    Deryder, L. J.; Chiger, H. D.; Deryder, D. D.; Detweiler, K. N.; Dupree, R. L.; Gillespie, V. P.; Hall, J. B.; Heck, M. L.; Herrick, D. C.; Katzberg, S. J.

    1989-01-01

    The results of a NASA in-house team effort to develop a concept definition for a Commercially Developed Space Facility (CDSF) are presented. Science mission utilization definition scenarios are documented, the conceptual configuration definition system performance parameters qualified, benchmark operational scenarios developed, space shuttle interface descriptions provided, and development schedule activity was assessed with respect to the establishment of a proposed launch date.

  1. Grain boundary engineering for structure materials of nuclear reactors

    NASA Astrophysics Data System (ADS)

    Tan, L.; Allen, T. R.; Busby, J. T.

    2013-10-01

    Grain boundary engineering (GBE), primarily implemented by thermomechanical processing, is an effective and economical method of enhancing the properties of polycrystalline materials. Among the factors affecting grain boundary character distribution, literature data showed definitive effect of grain size and texture. GBE is more effective for austenitic stainless steels and Ni-base alloys compared to other structural materials of nuclear reactors, such as refractory metals, ferritic and ferritic-martensitic steels, and Zr alloys. GBE has shown beneficial effects on improving the strength, creep strength, and resistance to stress corrosion cracking and oxidation of austenitic stainless steels and Ni-base alloys.

  2. Space reactor power 1986 - A year of choices and transition

    NASA Technical Reports Server (NTRS)

    Wiley, R. L.; Verga, R. L.; Schnyer, A. D.; Sholtis, J. A., Jr.; Wahlquist, E. J.

    1986-01-01

    Both the SP-100 and Multimegawatt programs have made significant progress over the last year and that progress is the focus of this paper. In the SP-100 program the thermoelectric energy conversion concept powered by a compact, high-temperature, lithium-cooled, uranium-nitride-fueled fast spectrum reactor was selected for engineering development and ground demonstration testing at an electrical power level of 300 kilowatts. In the Multimegawatt program, activities moved from the planning phase into one of technology development and assessment with attendant preliminary definition and evaluation of power concepts against requirements of the Strategic Defense Initiative.

  3. Assessment of the Technical Maturity of Generation IV Concepts for Test or Demonstration Reactor Applications, Revision 2

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gougar, Hans David

    2015-10-01

    The United States Department of Energy (DOE) commissioned a study the suitability of different advanced reactor concepts to support materials irradiations (i.e. a test reactor) or to demonstrate an advanced power plant/fuel cycle concept (demonstration reactor). As part of the study, an assessment of the technical maturity of the individual concepts was undertaken to see which, if any, can support near-term deployment. A Working Group composed of the authors of this document performed the maturity assessment using the Technical Readiness Levels as defined in DOE’s Technology Readiness Guide . One representative design was selected for assessment from of each ofmore » the six Generation-IV reactor types: gas-cooled fast reactor (GFR), lead-cooled fast reactor (LFR), molten salt reactor (MSR), supercritical water-cooled reactor (SCWR), sodium-cooled fast reactor (SFR), and very high temperature reactor (VHTR). Background information was obtained from previous detailed evaluations such as the Generation-IV Roadmap but other technical references were also used including consultations with concept proponents and subject matter experts. Outside of Generation IV activity in which the US is a party, non-U.S. experience or data sources were generally not factored into the evaluations as one cannot assume that this data is easily available or of sufficient quality to be used for licensing a US facility. The Working Group established the scope of the assessment (which systems and subsystems needed to be considered), adapted a specific technology readiness scale, and scored each system through discussions designed to achieve internal consistency across concepts. In general, the Working Group sought to determine which of the reactor options have sufficient maturity to serve either the test or demonstration reactor missions.« less

  4. Documents Pertaining to Resource Conservation and Recovery Act Corrective Action Event Codes

    EPA Pesticide Factsheets

    Document containing RCRA Corrective Action event codes and definitions, including national requirements, initiating sources, dates, and guidance, from the first facility assessment until the Corrective Action is terminated.

  5. 26 CFR 1.1471-1 - Scope of chapter 4 and definitions.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... an image retrieval system (such as portable document format (.pdf) or scanned documents). (35) Entity..., custodial institution, or specified insurance company. (124) TIN. The term TIN means the tax identifying...

  6. 26 CFR 1.1471-1 - Scope of chapter 4 and definitions.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... an image retrieval system (such as portable document format (.pdf) or scanned documents). (39) Entity..., custodial institution, or specified insurance company. (133) TIN. The term TIN means the tax identifying...

  7. Emergency department operations dictionary: results of the second performance measures and benchmarking summit.

    PubMed

    Welch, Shari J; Stone-Griffith, Suzanne; Asplin, Brent; Davidson, Steven J; Augustine, James; Schuur, Jeremiah D

    2011-05-01

    The public, payers, hospitals, and Centers for Medicare and Medicaid Services (CMS) are demanding that emergency departments (EDs) measure and improve performance, but this cannot be done unless we define the terms used in ED operations. On February 24, 2010, 32 stakeholders from 13 professional organizations met in Salt Lake City, Utah, to standardize ED operations metrics and definitions, which are presented in this consensus paper. Emergency medicine (EM) experts attending the Second Performance Measures and Benchmarking Summit reviewed, expanded, and updated key definitions for ED operations. Prior to the meeting, participants were provided with the definitions created at the first summit in 2006 and relevant documents from other organizations and asked to identify gaps and limitations in the original work. Those responses were used to devise a plan to revise and update the definitions. At the summit, attendees discussed and debated key terminology, and workgroups were created to draft a more comprehensive document. These results have been crafted into two reference documents, one for metrics and the operations dictionary presented here. The ED Operations Dictionary defines ED spaces, processes, patient populations, and new ED roles. Common definitions of key terms will improve the ability to compare ED operations research and practice and provide a common language for frontline practitioners, managers, and researchers. © 2011 by the Society for Academic Emergency Medicine.

  8. Transition to intensive care nursing: establishing a starting point.

    PubMed

    Boyle, Martin; Butcher, Rand; Conyers, Vicki; Kendrick, Tina; MacNamara, Mary; Lang, Susie

    2008-11-01

    There is a shortage of intensive care (IC) nurses. A supported transition to IC nursing has been identified as a key strategy for recruitment and retention. In 2004 a discussion document relating to transition of IC nurses was presented to the New South Wales (NSW) Chief Nursing Officer (CNO). A workshop was held with key stakeholders and a Steering Group was established to develop a state-wide transition to IC nursing program. To survey orientation programs and educational resources and develop definitions, goals, learning objectives and clinical competencies relating to transition to IC nursing practice. A questionnaire and a draft document of definitions, target group, goals, learning objectives and clinical competencies for IC transition was distributed to 43 NSW IC units (ICUs). An iterative process of anonymous feedback and modification was undertaken to establish agreement on content. Responses were received from 29 units (return rate of 67%). The survey of educational resources indicated ICUs had access to educational support and there was evidence of a lack of a common standard or definition for "orientation" or "transition". The definitions, target group, goals and competency statements from the draft document were accepted with minor editorial change. Seventeen learning objectives or psychomotor skills were modified and an additional 19 were added to the draft as a result of the process. This work has established valid definitions, goals, learning objectives and clinical competencies that describe transition to intensive care nursing.

  9. SHARP pre-release v1.0 - Current Status and Documentation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mahadevan, Vijay S.; Rahaman, Ronald O.

    The NEAMS Reactor Product Line effort aims to develop an integrated multiphysics simulation capability for the design and analysis of future generations of nuclear power plants. The Reactor Product Line code suite’s multi-resolution hierarchy is being designed to ultimately span the full range of length and time scales present in relevant reactor design and safety analyses, as well as scale from desktop to petaflop computing platforms. In this report, building on a several previous report issued in September 2014, we describe our continued efforts to integrate thermal/hydraulics, neutronics, and structural mechanics modeling codes to perform coupled analysis of a representativemore » fast sodium-cooled reactor core in preparation for a unified release of the toolkit. The work reported in the current document covers the software engineering aspects of managing the entire stack of components in the SHARP toolkit and the continuous integration efforts ongoing to prepare a release candidate for interested reactor analysis users. Here we report on the continued integration effort of PROTEUS/Nek5000 and Diablo into the NEAMS framework and the software processes that enable users to utilize the capabilities without losing scientific productivity. Due to the complexity of the individual modules and their necessary/optional dependency library chain, we focus on the configuration and build aspects for the SHARP toolkit, which includes capability to autodownload dependencies and configure/install with optimal flags in an architecture-aware fashion. Such complexity is untenable without strong software engineering processes such as source management, source control, change reviews, unit tests, integration tests and continuous test suites. Details on these processes are provided in the report as a building step for a SHARP user guide that will accompany the first release, expected by Mar 2016.« less

  10. Closing the Loop in ICU Decision Support: Physiologic Event Detection, Alerts, and Documentation

    PubMed Central

    Norris, Patrick R.; Dawant, Benoit M.

    2002-01-01

    Automated physiologic event detection and alerting is a challenging task in the ICU. Ideally care providers should be alerted only when events are clinically significant and there is opportunity for corrective action. However, the concepts of clinical significance and opportunity are difficult to define in automated systems, and effectiveness of alerting algorithms is difficult to measure. This paper describes recent efforts on the Simon project to capture information from ICU care providers about patient state and therapy in response to alerts, in order to assess the value of event definitions and progressively refine alerting algorithms. Event definitions for intracranial pressure and cerebral perfusion pressure were studied by implementing a reliable system to automatically deliver alerts to clinical users’ alphanumeric pagers, and to capture associated documentation about patient state and therapy when the alerts occurred. During a 6-month test period in the trauma ICU at Vanderbilt University Medical Center, 530 alerts were detected in 2280 hours of data spanning 14 patients. Clinical users electronically documented 81% of these alerts as they occurred. Retrospectively classifying documentation based on therapeutic actions taken, or reasons why actions were not taken, provided useful information about ways to potentially improve event definitions and enhance system utility.

  11. 40 CFR 63.11398 - What definitions apply to this subpart?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... acrylonitrile units: acrylic fiber or modacrylic fiber. Acrylonitrile solution polymerization means a process where acrylonitrile and comonomers are dissolved in a solvent to form a polymer solution (typically... resulting reactor polymer solution (spin dope) is filtered and pumped directly to the fiber spinning process...

  12. 40 CFR 63.11398 - What definitions apply to this subpart?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... acrylonitrile units: acrylic fiber or modacrylic fiber. Acrylonitrile solution polymerization means a process where acrylonitrile and comonomers are dissolved in a solvent to form a polymer solution (typically... resulting reactor polymer solution (spin dope) is filtered and pumped directly to the fiber spinning process...

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

    NASA Technical Reports Server (NTRS)

    1971-01-01

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

  14. National Environmental Policy Act Hazards Assessment for the TREAT Alternative

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Boyd D. Christensen; Annette L. Schafer

    2013-11-01

    This document provides an assessment of hazards as required by the National Environmental Policy Act for the alternative of restarting the reactor at the Transient Reactor Test (TREAT) facility by the Resumption of Transient Testing Program. Potential hazards have been identified and screening level calculations have been conducted to provide estimates of unmitigated dose consequences that could be incurred through this alternative. Consequences considered include those related to use of the TREAT Reactor, experiment assembly handling, and combined events involving both the reactor and experiments. In addition, potential safety structures, systems, and components for processes associated with operating TREAT andmore » onsite handling of nuclear fuels and experiments are listed. If this alternative is selected, a safety basis will be prepared in accordance with 10 CFR 830, “Nuclear Safety Management,” Subpart B, “Safety Basis Requirements.”« less

  15. National Environmental Policy Act Hazards Assessment for the TREAT Alternative

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Christensen, Boyd D.; Schafer, Annette L.

    2014-02-01

    This document provides an assessment of hazards as required by the National Environmental Policy Act for the alternative of restarting the reactor at the Transient Reactor Test (TREAT) facility by the Resumption of Transient Testing Program. Potential hazards have been identified and screening level calculations have been conducted to provide estimates of unmitigated dose consequences that could be incurred through this alternative. Consequences considered include those related to use of the TREAT Reactor, experiment assembly handling, and combined events involving both the reactor and experiments. In addition, potential safety structures, systems, and components for processes associated with operating TREAT andmore » onsite handling of nuclear fuels and experiments are listed. If this alternative is selected, a safety basis will be prepared in accordance with 10 CFR 830, “Nuclear Safety Management,” Subpart B, “Safety Basis Requirements.”« less

  16. Analysis of reactor trips originating in balance of plant systems

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stetson, F.T.; Gallagher, D.W.; Le, P.T.

    1990-09-01

    This report documents the results of an analysis of balance-of-plant (BOP) related reactor trips at commercial US nuclear power plants of a 5-year period, from January 1, 1984, through December 31, 1988. The study was performed for the Plant Systems Branch, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission. The objectives of the study were: to improve the level of understanding of BOP-related challenges to safety systems by identifying and categorizing such events; to prepare a computerized data base of BOP-related reactor trip events and use the data base to identify trends and patterns in the population of thesemore » events; to investigate the risk implications of BOP events that challenge safety systems; and to provide recommendations on how to address BOP-related concerns in regulatory context. 18 refs., 2 figs., 27 tabs.« less

  17. RELAP-7 Software Verification and Validation Plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Smith, Curtis L.; Choi, Yong-Joon; Zou, Ling

    This INL plan comprehensively describes the software for RELAP-7 and documents the software, interface, and software design requirements for the application. The plan also describes the testing-based software verification and validation (SV&V) process—a set of specially designed software models used to test RELAP-7. The RELAP-7 (Reactor Excursion and Leak Analysis Program) code is a nuclear reactor system safety analysis code being developed at Idaho National Laboratory (INL). The code is based on the INL’s modern scientific software development framework – MOOSE (Multi-Physics Object-Oriented Simulation Environment). The overall design goal of RELAP-7 is to take advantage of the previous thirty yearsmore » of advancements in computer architecture, software design, numerical integration methods, and physical models. The end result will be a reactor systems analysis capability that retains and improves upon RELAP5’s capability and extends the analysis capability for all reactor system simulation scenarios.« less

  18. Biaxial Creep Specimen Fabrication

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    JL Bump; RF Luther

    This report documents the results of the weld development and abbreviated weld qualification efforts performed by Pacific Northwest National Laboratory (PNNL) for refractory metal and superalloy biaxial creep specimens. Biaxial creep specimens were to be assembled, electron beam welded, laser-seal welded, and pressurized at PNNL for both in-pile (JOYO reactor, O-arai, Japan) and out-of-pile creep testing. The objective of this test campaign was to evaluate the creep behavior of primary cladding and structural alloys under consideration for the Prometheus space reactor. PNNL successfully developed electron beam weld parameters for six of these materials prior to the termination of the Navalmore » Reactors program effort to deliver a space reactor for Project Prometheus. These materials were FS-85, ASTAR-811C, T-111, Alloy 617, Haynes 230, and Nirnonic PE16. Early termination of the NR space program precluded the development of laser welding parameters for post-pressurization seal weldments.« less

  19. Old-growth definition for wet pine forests, woodlands, and savannas. Forest Service general technical report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Harms, W.R.

    1996-09-01

    All Forest Service Stations and Regions began developing old-growth definitions for specific forest types. Definitions will first be developed for broad forest types and based mainly on published information and so must be viewed accordingly. Refinements will be made by the Forest Service as new information becomes available. This document represents 1 of 35 forest types for which old-growth definition will be drafted.

  20. Comprehensive kinetic model for the low-temperature oxidation of hydrocarbons

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gaffuri, P.; Faravelli, T.; Ranzi, E.

    1997-05-01

    The oxidation chemistry in the low- and intermediate-temperature regimes (600--900 K) is important and plays a significant role in the overall combustion process. Autoignition in diesel engines as well as end-gas autoignition and knock phenomena in s.i. engines are initiated at these low temperatures. The low-temperature oxidation chemistry of linear and branched alkanes is discussed with the aim of unifying their complex behavior in various experimental systems using a single detailed kinetic model. New experimental data, obtained in a pressurized flow reactor, as well as in batch- and jet-stirred reactors, are useful for a better definition of the region ofmore » cool flames and negative temperature coefficient (NTC) for pure hydrocarbons from propane up to isooctane. Thermochemical oscillations and the NTC region of the reaction rate of the low-temperature oxidation of n-heptane and isooctane in a jet-stirred flow reactor are reproduced quite well by the model, not only in a qualitative way but in terms of the experimental frequencies and intensities of cool flames. Very good agreement is also observed for fuel conversion and intermediate-species formation. Irrespective of the experimental system, the same critical reaction steps always control these phenomena. The results contribute to the definition of a limited set of fundamental kinetic parameters that should be easily extended to model heavier alkanes.« less

  1. Preliminary Assessment of the Impact on Reactor Vessel dpa Rates Due to Installation of a Proposed Low Enriched Uranium (LEU) Core in the High Flux Isotope Reactor (HFIR)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Daily, Charles R.

    2015-10-01

    An assessment of the impact on the High Flux Isotope Reactor (HFIR) reactor vessel (RV) displacements-per-atom (dpa) rates due to operations with the proposed low enriched uranium (LEU) core described by Ilas and Primm has been performed and is presented herein. The analyses documented herein support the conclusion that conversion of HFIR to low-enriched uranium (LEU) core operations using the LEU core design of Ilas and Primm will have no negative impact on HFIR RV dpa rates. Since its inception, HFIR has been operated with highly enriched uranium (HEU) cores. As part of an effort sponsored by the National Nuclearmore » Security Administration (NNSA), conversion to LEU cores is being considered for future HFIR operations. The HFIR LEU configurations analyzed are consistent with the LEU core models used by Ilas and Primm and the HEU balance-of-plant models used by Risner and Blakeman in the latest analyses performed to support the HFIR materials surveillance program. The Risner and Blakeman analyses, as well as the studies documented herein, are the first to apply the hybrid transport methods available in the Automated Variance reduction Generator (ADVANTG) code to HFIR RV dpa rate calculations. These calculations have been performed on the Oak Ridge National Laboratory (ORNL) Institutional Cluster (OIC) with version 1.60 of the Monte Carlo N-Particle 5 (MCNP5) computer code.« less

  2. Apprentices and Trainees: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2017

    2017-01-01

    This document covers the data terms used in publications sourced from the National Apprentice and Trainee Collection and their associated data tables. The primary purpose of this document is to assist users of the publications to understand the specific data terms used within them. Terms are listed in alphabetical order with the following…

  3. Students and Courses--Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2014

    2014-01-01

    This document covers the data terms used in publications sourced from the National VET Provider Collection and their associated data tables. The primary purpose of this document is to assist users of the publication to understand the specific data terms used within them. Terms that appear in the publications and data items are listed in…

  4. Indigenous VET Research and Statistics: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "Indigenous Research and Statistics" resources. It covers information contained in the "Apprentices and Trainees June Quarter 2009 report," the "Students and Courses 2009" report and the "Student Outcomes 2009" report and their associated data tables. The primary purpose of this document is to assist…

  5. 48 CFR 19.1501 - Definition.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 48 Federal Acquisition Regulations System 1 2013-10-01 2013-10-01 false Definition. 19.1501 Section 19.1501 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION SOCIOECONOMIC... Repository means a secure, Web-based application that collects, stores, and disseminates documents to the...

  6. 48 CFR 19.1501 - Definition.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 48 Federal Acquisition Regulations System 1 2011-10-01 2011-10-01 false Definition. 19.1501 Section 19.1501 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION SOCIOECONOMIC... Repository means a secure, Web-based application that collects, stores, and disseminates documents to the...

  7. 48 CFR 19.1501 - Definition.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 48 Federal Acquisition Regulations System 1 2014-10-01 2014-10-01 false Definition. 19.1501 Section 19.1501 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION SOCIOECONOMIC... Repository means a secure, Web-based application that collects, stores, and disseminates documents to the...

  8. 48 CFR 19.1501 - Definition.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 48 Federal Acquisition Regulations System 1 2012-10-01 2012-10-01 false Definition. 19.1501 Section 19.1501 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION SOCIOECONOMIC... Repository means a secure, Web-based application that collects, stores, and disseminates documents to the...

  9. 40 CFR 63.12005 - What definitions apply to this subpart?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... venting episode that is associated with a single unit operation. A unit operation may have more than one... characterized by a two-step anhydrous polymerization process: the formation of small resin particles in a pre... of the resin particles in a post-polymerization reactor using additional vinyl chloride monomer...

  10. 40 CFR 60.701 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... provided by the primary fuel. Total organic compounds or TOC means those compounds measured according to...), and TOC concentration as required in § 60.705(b)(4) and § 60.705(f)(4), those compounds which the... per unit reduction of TOC associated with a vent stream from an affected reactor process facility...

  11. 10 CFR 140.3 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... an application has been filed for a license authorizing operation at: (1) A thermal power level in excess of 10 megawatts; or (2) A thermal power level in excess of 1 megawatt, if the reactor is to... plant means a plant in which the following operations or activities are conducted: (1) Operations for...

  12. 10 CFR 140.3 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... an application has been filed for a license authorizing operation at: (1) A thermal power level in excess of 10 megawatts; or (2) A thermal power level in excess of 1 megawatt, if the reactor is to... plant means a plant in which the following operations or activities are conducted: (1) Operations for...

  13. 40 CFR 63.1579 - What definitions apply to this subpart?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... process characterized by continual batch regeneration of catalyst in situ in any one of several reactors... device that treats (in-situ) the catalytic reforming unit recirculating coke burn exhaust gases for acid... or operator's convenience for in situ catalyst regeneration. Sulfur recovery unit means a process...

  14. 40 CFR 63.1579 - What definitions apply to this subpart?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... process characterized by continual batch regeneration of catalyst in situ in any one of several reactors... device that treats (in-situ) the catalytic reforming unit recirculating coke burn exhaust gases for acid... or operator's convenience for in situ catalyst regeneration. Sulfur recovery unit means a process...

  15. Zirconium hydride reactor control reflector systems: summary report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Horton, P.H.; Kurzeka, W.J.

    1972-06-30

    The beryllium reflector control system development for SNAP reactors is documented, from the initial SNAP 10A System through the current 5-kW(e) Thermoelectric System. Described are the various reflector concepts used in these systems for shadowshielded and 4 pi -shielded nuclear systems. The development of the key components, such as the actuators, bearings, and drive mechanisms for these systems, is also traced from the SNAP 10A concept through to the current system. Developmental test results are outlined, showing the performance capability improvements made throughout the life of the SNAP programs. Component development was highly successful, as proven by a number ofmore » reactor systems tests, including the launch and operation of the SNAP 10A flight. 46 references. (auth)« less

  16. FERRET data analysis code

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Schmittroth, F.

    1979-09-01

    A documentation of the FERRET data analysis code is given. The code provides a way to combine related measurements and calculations in a consistent evaluation. Basically a very general least-squares code, it is oriented towards problems frequently encountered in nuclear data and reactor physics. A strong emphasis is on the proper treatment of uncertainties and correlations and in providing quantitative uncertainty estimates. Documentation includes a review of the method, structure of the code, input formats, and examples.

  17. AGC 2 Irradiated Material Properties Analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rohrbaugh, David Thomas

    2017-05-01

    The Advanced Reactor Technologies Graphite Research and Development Program is conducting an extensive graphite irradiation experiment to provide data for licensing of a high temperature reactor (HTR) design. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor designs. , Nuclear graphite H 451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphite grades have been developed and are considered suitable candidates for new HTR reactor designs. To support the design and licensing of HTR core componentsmore » within a commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade, with a specific emphasis on data accounting for the life limiting effects of irradiation creep on key physical properties of the HTR candidate graphite grades. Further details on the research and development activities and associated rationale required to qualify nuclear grade graphite for use within the HTR are documented in the graphite technology research and development plan.« less

  18. AGC 2 Irradiation Creep Strain Data Analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Windes, William E.; Rohrbaugh, David T.; Swank, W. David

    2016-08-01

    The Advanced Reactor Technologies Graphite Research and Development Program is conducting an extensive graphite irradiation experiment to provide data for licensing of a high temperature reactor (HTR) design. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor designs. Nuclear graphite H-451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphite grades have been developed and are considered suitable candidates for new HTR reactor designs. To support the design and licensing of HTR core components within amore » commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade, with a specific emphasis on data accounting for the life limiting effects of irradiation creep on key physical properties of the HTR candidate graphite grades. Further details on the research and development activities and associated rationale required to qualify nuclear grade graphite for use within the HTR are documented in the graphite technology research and development plan.« less

  19. Development of advanced strain diagnostic techniques for reactor environments.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fleming, Darryn D.; Holschuh, Thomas Vernon,; Miller, Timothy J.

    2013-02-01

    The following research is operated as a Laboratory Directed Research and Development (LDRD) initiative at Sandia National Laboratories. The long-term goals of the program include sophisticated diagnostics of advanced fuels testing for nuclear reactors for the Department of Energy (DOE) Gen IV program, with the future capability to provide real-time measurement of strain in fuel rod cladding during operation in situ at any research or power reactor in the United States. By quantifying the stress and strain in fuel rods, it is possible to significantly improve fuel rod design, and consequently, to improve the performance and lifetime of the cladding.more » During the past year of this program, two sets of experiments were performed: small-scale tests to ensure reliability of the gages, and reactor pulse experiments involving the most viable samples in the Annulated Core Research Reactor (ACRR), located onsite at Sandia. Strain measurement techniques that can provide useful data in the extreme environment of a nuclear reactor core are needed to characterize nuclear fuel rods. This report documents the progression of solutions to this issue that were explored for feasibility in FY12 at Sandia National Laboratories, Albuquerque, NM.« less

  20. Ambient Air Definition

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  1. Definition of Source

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  2. Specification of the Transmitted Signal of the Omega Navigation System.

    DOT National Transportation Integrated Search

    1984-01-01

    This report documents the specification of the transmitted signal to the OMEGA Navigation System. It is intended as a reference document consisting of specifications, definitions, and explanations for general use by designers, manufacturers, and user...

  3. 7 CFR 62.206 - Access to program documents and activities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... (CONTINUED) LIVESTOCK, MEAT, AND OTHER AGRICULTURAL COMMODITIES (QUALITY SYSTEMS VERIFICATION PROGRAMS) Quality Systems Verification Programs Definitions Service § 62.206 Access to program documents and... SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) REGULATIONS...

  4. Standard Generalized Markup Language for self-defining structured reports.

    PubMed

    Kahn, C E

    1999-01-01

    Structured reporting is the process of using standardized data elements and predetermined data-entry formats to record observations. The Standard Generalized Markup Language (SGML; International Standards Organization (ISO) 8879:1986)--an open, internationally accepted standard for document interchange was used to encode medical observations acquired in an Internet-based structured reporting system. The resulting report is self-documenting: it includes a definition of its allowable data fields and values encoded as a report-specific SGML document type definition (DTD). The data-entry forms, DTD, and report document instances are based on report specifications written in a simple, SGML-based language designed for that purpose. Reporting concepts can be linked with those of external vocabularies such as the Unified Medical Language System (UMLS) Metathesaurus. The use of open standards such as SGML is an important step in the creation of open, universally comprehensible structured reports.

  5. Application of TOS/AMS to TDRS E and F

    NASA Technical Reports Server (NTRS)

    1984-01-01

    The development of the Transfer Orbit Stage (TOS) and the study of an Apogee and Maneuvering Stage (AMS) to be used in conjunction with the TOS are presented. A definition of the TOS/AMS configuration is provided along with a detailed design analysis including layout drawings, component definition, performance, sts and spacecraft interface definition, schedules, cost estimates, and specifications documents.

  6. The Johnson Space Center Management Information Systems (JSCMIS). 1: Requirements Definition and Design Specifications for Versions 2.1 and 2.1.1. 2: Documented Test Scenario Environments. 3: Security Design and Specifications

    NASA Technical Reports Server (NTRS)

    1986-01-01

    The Johnson Space Center Management Information System (JSCMIS) is an interface to computer data bases at NASA Johnson which allows an authorized user to browse and retrieve information from a variety of sources with minimum effort. This issue gives requirements definition and design specifications for versions 2.1 and 2.1.1, along with documented test scenario environments, and security object design and specifications.

  7. Surplus Highly Enriched Uranium Disposition Program plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1996-10-01

    The purpose of this document is to provide upper level guidance for the program that will downblend surplus highly enriched uranium for use as commercial nuclear reactor fuel or low-level radioactive waste. The intent of this document is to outline the overall mission and program objectives. The document is also intended to provide a general basis for integration of disposition efforts among all applicable sites. This plan provides background information, establishes the scope of disposition activities, provides an approach to the mission and objectives, identifies programmatic assumptions, defines major roles, provides summary level schedules and milestones, and addresses budget requirements.

  8. 45 CFR 160.103 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ..., the following definitions apply to this subchapter: Act means the Social Security Act. Administrative..., statements, and other required documents. Electronic media means: (1) Electronic storage material on which...) and any removable/transportable digital memory medium, such as magnetic tape or disk, optical disk, or...

  9. 45 CFR 160.103 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ..., the following definitions apply to this subchapter: Act means the Social Security Act. Administrative..., statements, and other required documents. Electronic media means: (1) Electronic storage material on which...) and any removable/transportable digital memory medium, such as magnetic tape or disk, optical disk, or...

  10. 39 CFR 273.2 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Definitions. 273.2 Section 273.2 Postal Service UNITED STATES POSTAL SERVICE ORGANIZATION AND ADMINISTRATION ADMINISTRATION OF PROGRAM FRAUD CIVIL... representation, certification, affirmation, document, record, or accounting or bookkeeping entry made: (1) With...

  11. 76 FR 38992 - Approval and Promulgation of Air Quality Implementation Plans; Pennsylvania; Update to Materials...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-05

    ... Definitions 5/24/10 12/28/10, 75 FR 81555... Addition of four new definitions: Exterior panels, interior panels, flat wood panel coating, and tileboard. See Part III of the IBR document. * * * * * * Part E...

  12. 48 CFR 227.7201 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... OF DEFENSE GENERAL CONTRACTING REQUIREMENTS PATENTS, DATA, AND COPYRIGHTS Rights in Computer Software and Computer Software Documentation 227.7201 Definitions. (a) As used in this subpart, unless... subpart are defined in the clause at 252.227-7014, Rights in Noncommercial Computer Software and...

  13. 48 CFR 227.7201 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... OF DEFENSE GENERAL CONTRACTING REQUIREMENTS PATENTS, DATA, AND COPYRIGHTS Rights in Computer Software and Computer Software Documentation 227.7201 Definitions. (a) As used in this subpart, unless... subpart are defined in the clause at 252.227-7014, Rights in Noncommercial Computer Software and...

  14. 48 CFR 227.7201 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... OF DEFENSE GENERAL CONTRACTING REQUIREMENTS PATENTS, DATA, AND COPYRIGHTS Rights in Computer Software and Computer Software Documentation 227.7201 Definitions. (a) As used in this subpart, unless... subpart are defined in the clause at 252.227-7014, Rights in Noncommercial Computer Software and...

  15. 48 CFR 227.7201 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... OF DEFENSE GENERAL CONTRACTING REQUIREMENTS PATENTS, DATA, AND COPYRIGHTS Rights in Computer Software and Computer Software Documentation 227.7201 Definitions. (a) As used in this subpart, unless... subpart are defined in the clause at 252.227-7014, Rights in Noncommercial Computer Software and...

  16. 48 CFR 227.7201 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... OF DEFENSE GENERAL CONTRACTING REQUIREMENTS PATENTS, DATA, AND COPYRIGHTS Rights in Computer Software and Computer Software Documentation 227.7201 Definitions. (a) As used in this subpart, unless... subpart are defined in the clause at 252.227-7014, Rights in Noncommercial Computer Software and...

  17. 7 CFR 1718.50 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 11 2010-01-01 2010-01-01 false Definitions. 1718.50 Section 1718.50 Agriculture Regulations of the Department of Agriculture (Continued) RURAL UTILITIES SERVICE, DEPARTMENT OF AGRICULTURE LOAN SECURITY DOCUMENTS FOR ELECTRIC BORROWERS Mortgage for Distribution Borrowers § 1718.50...

  18. 8 CFR 1003.13 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... and Nationality EXECUTIVE OFFICE FOR IMMIGRATION REVIEW, DEPARTMENT OF JUSTICE GENERAL PROVISIONS EXECUTIVE OFFICE FOR IMMIGRATION REVIEW Immigration Court-Rules of Procedure § 1003.13 Definitions. As used... proceeding before an Immigration Judge. For proceedings initiated prior to April 1, 1997, these documents...

  19. CRAC2 model description

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ritchie, L.T.; Alpert, D.J.; Burke, R.P.

    1984-03-01

    The CRAC2 computer code is a revised version of CRAC (Calculation of Reactor Accident Consequences) which was developed for the Reactor Safety Study. This document provides an overview of the CRAC2 code and a description of each of the models used. Significant improvements incorporated into CRAC2 include an improved weather sequence sampling technique, a new evacuation model, and new output capabilities. In addition, refinements have been made to the atmospheric transport and deposition model. Details of the modeling differences between CRAC2 and CRAC are emphasized in the model descriptions.

  20. Manned space flight nuclear system safety. Volume 3: Reactor system preliminary nuclear safety analysis. Part 2A: Accident model document, appendix

    NASA Technical Reports Server (NTRS)

    1972-01-01

    The detailed abort sequence trees for the reference zirconium hydride (ZrH) reactor power module that have been generated for each phase of the reference Space Base program mission are presented. The trees are graphical representations of causal sequences. Each tree begins with the phase identification and the dichotomy between success and failure. The success branch shows the mission phase objective as being achieved. The failure branch is subdivided, as conditions require, into various primary initiating abort conditions.

  1. FMDP reactor alternative summary report. Volume 1 - existing LWR alternative

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Greene, S.R.; Bevard, B.B.

    1996-10-07

    Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] are becoming surplus to national defense needs in both the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. This document summarizes the results of analysis concerned with existing light water reactor plutonium disposition alternatives.

  2. Development of a Software Safety Process and a Case Study of Its Use

    NASA Technical Reports Server (NTRS)

    Knight, J. C.

    1996-01-01

    Research in the year covered by this reporting period has been primarily directed toward: continued development of mock-ups of computer screens for operator of a digital reactor control system; development of a reactor simulation to permit testing of various elements of the control system; formal specification of user interfaces; fault-tree analysis including software; evaluation of formal verification techniques; and continued development of a software documentation system. Technical results relating to this grant and the remainder of the principal investigator's research program are contained in various reports and papers.

  3. Cleanup Verification Package for the 116-K-2 Effluent Trench

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    J. M. Capron

    2006-04-04

    This cleanup verification package documents completion of remedial action for the 116-K-2 effluent trench, also referred to as the 116-K-2 mile-long trench and the 116-K-2 site. During its period of operation, the 116-K-2 site was used to dispose of cooling water effluent from the 105-KE and 105-KW Reactors by percolation into the soil. This site also received mixed liquid wastes from the 105-KW and 105-KE fuel storage basins, reactor floor drains, and miscellaneous decontamination activities.

  4. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document Volume 2, provides a discussion of: Plutonium Fuel Cycle; Technology Needs; Regulatory Considerations; Cost and Schedule Estimates; and Deployment Strategy.

  5. Multiple Irradiation Capsule Experiment (MICE)-3B Irradiation Test of Space Fuel Specimens in the Advanced Test Reactor (ATR) - Close Out Documentation for Naval Reactors (NR) Information

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    M. Chen; CM Regan; D. Noe

    2006-01-09

    Few data exist for UO{sub 2} or UN within the notional design space for the Prometheus-1 reactor (low fission rate, high temperature, long duration). As such, basic testing is required to validate predictions (and in some cases determine) performance aspects of these fuels. Therefore, the MICE-3B test of UO{sub 2} pellets was designed to provide data on gas release, unrestrained swelling, and restrained swelling at the upper range of fission rates expected for a space reactor. These data would be compared with model predictions and used to determine adequacy of a space reactor design basis relative to fission gas releasemore » and swelling of UO{sub 2} fuel and to assess potential pellet-clad interactions. A primary goal of an irradiation test for UN fuel was to assess performance issues currently associated with this fuel type such as gas release, swelling and transient performance. Information learned from this effort may have enabled use of UN fuel for future applications.« less

  6. ANOPP programming and documentation standards document

    NASA Technical Reports Server (NTRS)

    1976-01-01

    Standards defining the requirements for preparing software for the Aircraft Noise Prediction Program (ANOPP) were given. It is the intent of these standards to provide definition, design, coding, and documentation criteria for the achievement of a unity among ANOPP products. These standards apply to all of ANOPP's standard software system. The standards encompass philosophy as well as techniques and conventions.

  7. Aerial Refueling Clearance Initiation Request

    DTIC Science & Technology

    2016-07-14

    and receiver agencies. The AR Clearance Initiation Request document recognizes the requirement for definitive aerial refueling agreements between...and contractual tanker support requests from one organization or nation to another. The AR Clearance Initiation Request document is not intended to...proprietary, sensitive, classified or otherwise restricted information. ARSAG documents, as prepared, are not DOD, MOD or NATO standards, but provide

  8. Apprentice and Trainee Destinations 2010: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "Apprentice and Trainee Destinations Survey, 2010" report and its associated data tables. The primary purpose of this document is to assist users of the report to understand the specific data terms used within it. Terms that appear in the report are listed in alphabetical order with the…

  9. Apprentices and Trainees: Early Trend Estimates, December 2010: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2011

    2011-01-01

    This document covers the data terms used in the "Australian Vocational Education and Training Statistics: Apprentices and Trainees--Early Trend Estimates December 2010" publication. The primary purpose of this document is to assist users of the report to understand the specific data terms used within it. Terms that appear in the report…

  10. Apprentices and Trainees: March Quarter 2010. Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "Apprentices and Trainees: March quarter 2010" publication and its associated data tables. The primary purpose of this document is to assist users of the publication to understand the specific data terms used within it. Terms that appear in the publication are listed in alphabetical order…

  11. Students and Courses 2009: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "Students and Courses 2009" publication and its associated data tables. The primary purpose of this document is to assist users of the publication to understand the specific data terms used within it. Terms that appear in the publication are listed in alphabetical order with the following…

  12. Apprentices and Trainees: September Quarter 2010. Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2011

    2011-01-01

    This document covers the data terms used in the "Apprentices and Trainees: September Quarter 2010" publication and its associated data tables. The primary purpose of this document is to assist users of the publication to understand the specific data terms used within it. Terms that appear in the publication are listed in alphabetical…

  13. Apprentices and Trainees: Annual, 2009. Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "Apprentices and trainees: Annual 2009" publication and its associated data tables. The primary purpose of this document is to assist users of the publication to understand the specific data terms used within it. Terms that appear in the publication are listed in alphabetical order with the…

  14. 49 CFR 109.1 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ..., in the prevention, treatment, or cure of a disease or condition in human beings or animals where... same hazard communications information (marking, labeling, shipping documentation); or other reasonable... manufacturer, marking, labeling, shipping documentation, hazard communications, etc. Remove means to keep a...

  15. Source Definition for Colonial Terminals, Inc.

    EPA Pesticide Factsheets

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Policy and Guidance Database available at www2.epa.gov/title-v-operating-permits/title-v-operating-permit-policy-and-guidance-document-index. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  16. Definition of Source

    EPA Pesticide Factsheets

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Policy and Guidance Database available at www2.epa.gov/title-v-operating-permits/title-v-operating-permit-policy-and-guidance-document-index. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  17. PSD Definition of Source

    EPA Pesticide Factsheets

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Policy and Guidance Database available at www2.epa.gov/title-v-operating-permits/title-v-operating-permit-policy-and-guidance-document-index. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  18. Report on FY15 alloy 617 code rules development

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sham, Sam; Jetter, Robert I; Hollinger, Greg

    2015-09-01

    Due to its strength at very high temperatures, up to 950°C (1742°F), Alloy 617 is the reference construction material for structural components that operate at or near the outlet temperature of the very high temperature gas-cooled reactors. However, the current rules in the ASME Section III, Division 5 Subsection HB, Subpart B for the evaluation of strain limits and creep-fatigue damage using simplified methods based on elastic analysis have been deemed inappropriate for Alloy 617 at temperatures above 650°C (1200°F) (Corum and Brass, Proceedings of ASME 1991 Pressure Vessels and Piping Conference, PVP-Vol. 215, p.147, ASME, NY, 1991). The rationalemore » for this exclusion is that at higher temperatures it is not feasible to decouple plasticity and creep, which is the basis for the current simplified rules. This temperature, 650°C (1200°F), is well below the temperature range of interest for this material for the high temperature gas-cooled reactors and the very high temperature gas-cooled reactors. The only current alternative is, thus, a full inelastic analysis requiring sophisticated material models that have not yet been formulated and verified. To address these issues, proposed code rules have been developed which are based on the use of elastic-perfectly plastic (EPP) analysis methods applicable to very high temperatures. The proposed rules for strain limits and creep-fatigue evaluation were initially documented in the technical literature (Carter, Jetter and Sham, Proceedings of ASME 2012 Pressure Vessels and Piping Conference, papers PVP 2012 28082 and PVP 2012 28083, ASME, NY, 2012), and have been recently revised to incorporate comments and simplify their application. Background documents have been developed for these two code cases to support the ASME Code committee approval process. These background documents for the EPP strain limits and creep-fatigue code cases are documented in this report.« less

  19. PSD Definition of Source

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  20. PSD Definition of Modification

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  1. Guidance on the Definition of Fuel Conversion Plants

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  2. 4/5/95 Letter on Definition of Major Source

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  3. PSD Determination: Sun Oil Company and the Definition of Major Modification

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  4. Factors in Software Quality. Volume I. Concepts and Definitions of Software Quality

    DTIC Science & Technology

    1977-11-01

    FLEXIBILITY COMPLEXITY EXPANDABILITY PRECISION DOCUMENTATION TOLERANCE REPAIRABILITY COMPATABIL ITY SERVICEABILITY 2-4 AiI1I~3~I!-T A1 11 NI󈧥 AIiB 9l 0...applications. Several standard documents are required by DOD/AF’ regulations . The following references were used to compile the rFpnge of documents...documents are specified by the AF regulations or SPO-local regulations listed above. Each ot the document types for a long life/high cost software

  5. Definition of Installation in Nonattainment Regulations

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  6. Definition of Postapproval Monitoring

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  7. Plantwide Definition Of Major Stationary Sources Of Air Pollution

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  8. Request For Further Clarification on EPA's Definition of Ambient Air

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  9. EPA Definition of Pollution Prevention

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  10. Waste Package Component Design Methodology Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    D.C. Mecham

    2004-07-12

    This Executive Summary provides an overview of the methodology being used by the Yucca Mountain Project (YMP) to design waste packages and ancillary components. This summary information is intended for readers with general interest, but also provides technical readers a general framework surrounding a variety of technical details provided in the main body of the report. The purpose of this report is to document and ensure appropriate design methods are used in the design of waste packages and ancillary components (the drip shields and emplacement pallets). The methodology includes identification of necessary design inputs, justification of design assumptions, and usemore » of appropriate analysis methods, and computational tools. This design work is subject to ''Quality Assurance Requirements and Description''. The document is primarily intended for internal use and technical guidance for a variety of design activities. It is recognized that a wide audience including project management, the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission, and others are interested to various levels of detail in the design methods and therefore covers a wide range of topics at varying levels of detail. Due to the preliminary nature of the design, readers can expect to encounter varied levels of detail in the body of the report. It is expected that technical information used as input to design documents will be verified and taken from the latest versions of reference sources given herein. This revision of the methodology report has evolved with changes in the waste package, drip shield, and emplacement pallet designs over many years and may be further revised as the design is finalized. Different components and analyses are at different stages of development. Some parts of the report are detailed, while other less detailed parts are likely to undergo further refinement. The design methodology is intended to provide designs that satisfy the safety and operational requirements of the YMP. Four waste package configurations have been selected to illustrate the application of the methodology during the licensing process. These four configurations are the 21-pressurized water reactor absorber plate waste package (21-PWRAP), the 44-boiling water reactor waste package (44-BWR), the 5 defense high-level radioactive waste (HLW) DOE spent nuclear fuel (SNF) codisposal short waste package (5-DHLWDOE SNF Short), and the naval canistered SNF long waste package (Naval SNF Long). Design work for the other six waste packages will be completed at a later date using the same design methodology. These include the 24-boiling water reactor waste package (24-BWR), the 21-pressurized water reactor control rod waste package (21-PWRCR), the 12-pressurized water reactor waste package (12-PWR), the 5 defense HLW DOE SNF codisposal long waste package (5-DHLWDOE SNF Long), the 2 defense HLW DOE SNF codisposal waste package (2-MC012-DHLW), and the naval canistered SNF short waste package (Naval SNF Short). This report is only part of the complete design description. Other reports related to the design include the design reports, the waste package system description documents, manufacturing specifications, and numerous documents for the many detailed calculations. The relationships between this report and other design documents are shown in Figure 1.« less

  11. An audit of the use of definitions of sudden infant death syndrome (SIDS).

    PubMed

    Byard, Roger W; Marshall, Drew

    2007-11-01

    Given that there are a number of contradictions in the SIDS literature and that the definition of SIDS that was relied upon to authenticate cases in reports is not always specified, an audit of publications was undertaken. Fifty papers dealing with SIDS that were published in 2005 were reviewed. The majority (58%) of reports had either not specified a definition of SIDS, or had used non-standard or idiosyncratic definitions. Of the papers that had documented a definition: 30% used the 1989 NICHD definition, 10% used the 2004 San Diego definition, and 2% used the 1969 Seattle definition. Failure to use standard published definitions of SIDS and/or to clearly specify the definition that has been followed may severely hamper the evaluation of SIDS research.

  12. 45 CFR 160.103 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ..., the following definitions apply to this subchapter: Act means the Social Security Act. ANSI stands for... required documents. Electronic media means: (1) Electronic storage media including memory devices in computers (hard drives) and any removable/transportable digital memory medium, such as magnetic tape or disk...

  13. 45 CFR 160.103 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ..., the following definitions apply to this subchapter: Act means the Social Security Act. ANSI stands for... required documents. Electronic media means: (1) Electronic storage media including memory devices in computers (hard drives) and any removable/transportable digital memory medium, such as magnetic tape or disk...

  14. 12 CFR 1214.1 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Banking FEDERAL HOUSING FINANCE AGENCY ORGANIZATION AND OPERATIONS AVAILABILITY OF NON-PUBLIC INFORMATION § 1214.1 Definitions. Confidential supervisory information means information prepared or received by FHFA that meets all of the following criteria: (1) The information is not a document prepared by a regulated...

  15. 30 CFR 250.200 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Information Document CZMA means Coastal Zone Management Act DOCD means Development Operations Coordination... OFFSHORE OIL AND GAS AND SULPHUR OPERATIONS IN THE OUTER CONTINENTAL SHELF Plans and Information General Information § 250.200 Definitions. Acronyms and terms used in this subpart have the following meanings: (a...

  16. 45 CFR 160.103 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ..., the following definitions apply to this subchapter: Act means the Social Security Act. ANSI stands for... required documents. Electronic media means: (1) Electronic storage media including memory devices in computers (hard drives) and any removable/transportable digital memory medium, such as magnetic tape or disk...

  17. 12 CFR 1410.2 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... particular loan constitutes an independent credit risk and such determination is adequately documented in the... Banking FARM CREDIT SYSTEM INSURANCE CORPORATION PREMIUMS § 1410.2 Definitions. (a) Act means the Farm Credit Act of 1971, as amended. (b) Average principal outstanding means the average annual principal...

  18. 7 CFR 1944.403 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... education, community action agencies and other self-help grantees. Also, when available, regional technical... REGULATIONS (CONTINUED) HOUSING Self-Help Technical Assistance Grants § 1944.403 Definitions. (a) Agreement. The Self-Help Technical Assistance Agreement, which is a document signed by FmHA or its successor...

  19. 7 CFR 1944.403 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... education, community action agencies and other self-help grantees. Also, when available, regional technical... REGULATIONS (CONTINUED) HOUSING Self-Help Technical Assistance Grants § 1944.403 Definitions. (a) Agreement. The Self-Help Technical Assistance Agreement, which is a document signed by FmHA or its successor...

  20. 7 CFR 1944.403 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... education, community action agencies and other self-help grantees. Also, when available, regional technical... REGULATIONS (CONTINUED) HOUSING Self-Help Technical Assistance Grants § 1944.403 Definitions. (a) Agreement. The Self-Help Technical Assistance Agreement, which is a document signed by FmHA or its successor...

  1. 7 CFR 1944.403 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... education, community action agencies and other self-help grantees. Also, when available, regional technical... REGULATIONS (CONTINUED) HOUSING Self-Help Technical Assistance Grants § 1944.403 Definitions. (a) Agreement. The Self-Help Technical Assistance Agreement, which is a document signed by FmHA or its successor...

  2. 7 CFR 1944.403 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... education, community action agencies and other self-help grantees. Also, when available, regional technical... REGULATIONS (CONTINUED) HOUSING Self-Help Technical Assistance Grants § 1944.403 Definitions. (a) Agreement. The Self-Help Technical Assistance Agreement, which is a document signed by FmHA or its successor...

  3. 48 CFR 28.001 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 48 Federal Acquisition Regulations System 1 2011-10-01 2011-10-01 false Definitions. 28.001 Section 28.001 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL CONTRACTING... types of bonds and related documents are as follows: (1) An advance payment bond secures fulfillment of...

  4. 48 CFR 28.001 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 48 Federal Acquisition Regulations System 1 2012-10-01 2012-10-01 false Definitions. 28.001 Section 28.001 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL CONTRACTING... types of bonds and related documents are as follows: (1) An advance payment bond secures fulfillment of...

  5. 48 CFR 28.001 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 48 Federal Acquisition Regulations System 1 2014-10-01 2014-10-01 false Definitions. 28.001 Section 28.001 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL CONTRACTING... types of bonds and related documents are as follows: (1) An advance payment bond secures fulfillment of...

  6. 48 CFR 28.001 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 48 Federal Acquisition Regulations System 1 2013-10-01 2013-10-01 false Definitions. 28.001 Section 28.001 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION GENERAL CONTRACTING... types of bonds and related documents are as follows: (1) An advance payment bond secures fulfillment of...

  7. Closing the loop in ICU decision support: physiologic event detection, alerts, and documentation.

    PubMed Central

    Norris, P. R.; Dawant, B. M.

    2001-01-01

    Automated physiologic event detection and alerting is a challenging task in the ICU. Ideally care providers should be alerted only when events are clinically significant and there is opportunity for corrective action. However, the concepts of clinical significance and opportunity are difficult to define in automated systems, and effectiveness of alerting algorithms is difficult to measure. This paper describes recent efforts on the Simon project to capture information from ICU care providers about patient state and therapy in response to alerts, in order to assess the value of event definitions and progressively refine alerting algorithms. Event definitions for intracranial pressure and cerebral perfusion pressure were studied by implementing a reliable system to automatically deliver alerts to clinical users alphanumeric pagers, and to capture associated documentation about patient state and therapy when the alerts occurred. During a 6-month test period in the trauma ICU at Vanderbilt University Medical Center, 530 alerts were detected in 2280 hours of data spanning 14 patients. Clinical users electronically documented 81% of these alerts as they occurred. Retrospectively classifying documentation based on therapeutic actions taken, or reasons why actions were not taken, provided useful information about ways to potentially improve event definitions and enhance system utility. PMID:11825238

  8. The Paucity Problem: Where Have All the Space Reactor Experiments Gone?

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bess, John D.; Marshall, Margaret A.

    2016-10-01

    The Handbooks of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) together contain a plethora of documented and evaluated experiments essential in the validation of nuclear data, neutronics codes, and modeling of various nuclear systems. Unfortunately, only a minute selection of handbook data (twelve evaluations) are of actual experimental facilities and mockups designed specifically for space nuclear research. There is a paucity problem, such that the multitude of space nuclear experimental activities performed in the past several decades have yet to be recovered and made available in such detail that themore » international community could benefit from these valuable historical research efforts. Those experiments represent extensive investments in infrastructure, expertise, and cost, as well as constitute significantly valuable resources of data supporting past, present, and future research activities. The ICSBEP and IRPhEP were established to identify and verify comprehensive sets of benchmark data; evaluate the data, including quantification of biases and uncertainties; compile the data and calculations in a standardized format; and formally document the effort into a single source of verified benchmark data. See full abstract in attached document.« less

  9. Summary of Planned Implementation for the HTGR Lessons Learned Applicable to the NGNP

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ian Mckirdy

    2011-09-01

    This document presents a reconciliation of the lessons learned during a 2010 comprehensive evaluation of pertinent lessons learned from past and present high temperature gas-cooled reactors that apply to the Next Generation Nuclear Plant Project along with current and planned activities. The data used are from the latest Idaho National Laboratory research and development plans, the conceptual design report from General Atomics, and the pebble bed reactor technology readiness study from AREVA. Only those lessons related to the structures, systems, and components of the Next Generation Nuclear Plant (NGNP), as documented in the recently updated lessons learned report are addressed.more » These reconciliations are ordered according to plant area, followed by the affected system, subsystem, or component; lesson learned; and finally an NGNP implementation statement. This report (1) provides cross references to the original lessons learned document, (2) describes the lesson learned, (3) provides the current NGNP implementation status with design data needs associated with the lesson learned, (4) identifies the research and development being performed related to the lesson learned, and (5) summarizes with a status of how the lesson learned has been addressed by the NGNP Project.« less

  10. Microscale Heat Conduction Models and Doppler Feedback

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hawari, Ayman I.; Ougouag, Abderrafi

    2015-01-22

    The objective of this project is to establish an approach for providing the fundamental input that is needed to estimate the magnitude and time-dependence of the Doppler feedback mechanism in Very High Temperature reactors. This mechanism is the foremost contributor to the passive safety of gas-cooled, graphite-moderated high temperature reactors that use fuel based on Tristructural-Isotropic (TRISO) coated particles. Therefore, its correct prediction is essential to the conduct of safety analyses for these reactors. Since the effect is directly dependent on the actual temperature reached by the fuel during transients, the underlying phenomena of heat deposition, heat transfer and temperaturemore » rise must be correctly predicted. To achieve the above objective, this project will explore an approach that accounts for lattice effects as well as local temperature variations and the correct definition of temperature and related local effects.« less

  11. Effect of water on sulfur dioxide (SO2) and nitrogen oxides (NOx) removal from flue gas in a direct current corona discharge reactor

    NASA Astrophysics Data System (ADS)

    Yang, Jiaxiang; Chi, Xiaochun; Dong, Limin

    2007-05-01

    A direct current (dc) corona discharge reactor composed of needle-plate electrodes in a glass container filled with flue gas was designed. To clarify the influence of water on discharge characteristics, water was introduced in the plasma reactor as electrode where plate electrode is immersed, under the application of dc voltage. Experiment results show that (1) corona wind forming between high-voltage needle electrode and water by corona discharge enhances the cleaning efficiency of flue gas due to the existence of water and the cleaning efficiency will increase with the increase of applied dc voltage within definite range and (2) both removal efficiencies of NOx and SO2 increased in the presence of water, which reach up to 98% for SO2, and about 85% for NOx under suitable conditions. These results play an important role in flue gas cleanup research.

  12. Applying and adapting the Swedish regulatory system for decommissioning to nuclear power reactors - The regulator's perspective.

    PubMed

    Amft, Martin; Leisvik, Mathias; Carroll, Simon

    2017-03-16

    Half of the original 13 Swedish nuclear power reactors will be shut down by 2020. The decommissioning of these reactors is a challenge for all parties involved, including the licensees, the waste management system, the financing system, and the Swedish Radiation Safety Authority (SSM). This paper presents an overview of the Swedish regulations for decommissioning of nuclear facilities. It describes some of the experiences that SSM has gained from the application of these regulations. The focus of the present paper is on administrative aspects of decommissioning, such as SSM's guidelines, the definition of fundamental concepts in the regulatory framework, and a proposed revision of the licensing process according to the Environmental Act. These improvements will help to streamline the administration of the commercial nuclear power plant decommissioning projects that are anticipated to commence in Sweden in the near future. Copyright © 2017 Elsevier Ltd. All rights reserved.

  13. Measurement of neutrino mixing angle θ13 and mass difference Δ mee2 from reactor antineutrino disappearance in the RENO experiment

    NASA Astrophysics Data System (ADS)

    Kim, Soo-Bong

    2016-07-01

    RENO (Reactor Experiment for Neutrino Oscillation) made a definitive measurement of the smallest neutrino mixing angle θ13 in 2012, based on the disappearance of reactor electron antineutrinos. The experiment has obtained a more precise value of the mixing angle and the first result on neutrino mass difference Δ mee2 from an energy and baseline dependent reactor neutrino disappearance using ∼500 days of data. Based on the ratio of inverse-beta-decay (IBD) prompt spectra measured in two identical far and near detectors, we obtain sin2 ⁡ (2θ13) = 0.082 ± 0.009 (stat .) ± 0.006 (syst .) and | Δ mee2 | = [2.62-0.23+0.21 (stat.)-0.13+0.12 (syst .) ] ×10-3 eV2. An excess of reactor antineutrinos near 5 MeV is observed in the measured prompt spectrum with respect to the most commonly used models. The excess is found to be consistent with coming from reactors. A successful measurement of θ13 is also made in an IBD event sample with a delayed signal of neutron capture on hydrogen. A precise value of θ13 would provide important information on determination of the leptonic CP phase if combined with a result of an accelerator neutrino beam experiment.

  14. 40 CFR 63.2550 - What definitions apply to this subpart?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... series of tanks with a fixed roof that contact emissions with a solid media (such as bark) and use... at any time the intermediate is placed in equipment used solely for storage. The storage equipment is...-state reactor is followed by an operation that is designed and operated to remove HAP solvent or...

  15. 40 CFR 261.3 - Definition of hazardous waste.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... residues, such as slag, resulting from high temperature metals recovery (HTMR) processing of K061, K062 or..., slag reactors, rotary hearth furnace/electric furnace combinations or industrial furnaces (as defined....009 Nickel 1.0 Selenium 0.16 Silver 0.30 Thallium 0.020 Zinc 70 Generic exclusion levels for F006...

  16. 40 CFR 261.3 - Definition of hazardous waste.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... residues, such as slag, resulting from high temperature metals recovery (HTMR) processing of K061, K062 or..., slag reactors, rotary hearth furnace/electric furnace combinations or industrial furnaces (as defined....009 Nickel 1.0 Selenium 0.16 Silver 0.30 Thallium 0.020 Zinc 70 Generic exclusion levels for F006...

  17. 76 FR 44377 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on AP1000...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-25

    ... Design Control Document (DCD). The Subcommittee will hear presentations by and hold discussions with the... statements can be obtained from the website cited above or by contacting the identified DFO. Moreover, in...

  18. 78 FR 27443 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-10

    ...-1207), ``Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power... would result in a major inconvenience. If attending this meeting, please enter through the One White...

  19. 77 FR 27097 - LaCrosse Boiling Water Reactor, Exemption From Certain Requirements, Vernon County, WI

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-08

    ... status of LACBWR means that there are no longer interconnected operating systems which require security... System (ADAMS), which provides text and image files of NRC's public documents. If you do not have access...

  20. 77 FR 4838 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-31

    ...'' of the U.S. EPR Document Control Design (DCD) Safety Evaluation Report (SER) with Open Items. The...:30 P.M. The Subcommittee will review Chapter 3, ``Design of Structures, Components, Equipment, and...

  1. 78 FR 28001 - In the Matter of Entergy Gulf States Louisiana, LLC., and Entergy Operations, Inc., River Bend...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-13

    ... the Director of the Office of Nuclear Reactor Regulation satisfactory documentary evidence that New... September 27, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12275A013), as...

  2. Solid Waste Program technical baseline description

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Carlson, A.B.

    1994-07-01

    The system engineering approach has been taken to describe the technical baseline under which the Solid Waste Program is currently operating. The document contains a mission analysis, function analysis, system definition, documentation requirements, facility and project bases, and uncertainties facing the program.

  3. 5 CFR 1201.4 - General definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... documents associated with electronic filings under paragraph (h) of § 1201.14, on the MSPB. (l) Date of... date of electronic submission. (m) Electronic filing (e-filing). Filing and receiving documents in... of Personnel Management reconsideration decisions concerning retirement benefits, and appeals of...

  4. 5 CFR 1201.4 - General definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... documents associated with electronic filings under paragraph (h) of § 1201.14, on the MSPB. (l) Date of... date of electronic submission. (m) Electronic filing (e-filing). Filing and receiving documents in... of Personnel Management reconsideration decisions concerning retirement benefits, and appeals of...

  5. Specification of the Transmitted Signal of the U.S. Marine Radiobeacon System

    DOT National Transportation Integrated Search

    1983-01-01

    This report documents the specification of the transmitted signal of the U.S. Marine Radiobeacon System. It is intended as a reference document consisting of specifications, definitions, and explanations for general use by designers, manufacturers, a...

  6. Executive overview and introduction to the SMAP information system life-cycle and documentation standards

    NASA Technical Reports Server (NTRS)

    1989-01-01

    An overview of the five volume set of Information System Life-Cycle and Documentation Standards is provided with information on its use. The overview covers description, objectives, key definitions, structure and application of the standards, and document structure decisions. These standards were created to provide consistent NASA-wide structures for coordinating, controlling, and documenting the engineering of an information system (hardware, software, and operational procedures components) phase by phase.

  7. Redefining Myocardial Infarction: What Is New In The ESC/ACCF/AHA/WHF Third Universal Definition Of Myocardial Infarction?

    PubMed Central

    Alam, Mahboob; Virani, Salim S.; Bozkurt, Biykem

    2013-01-01

    Myocardial infarction (MI) is a major cause of mortality and morbidity worldwide. Each year, an estimated 785,000 persons will have a new MI in the United States alone, and approximately every minute an American will succumb to one.1 In addition, MI has major psychological and legal implications for patients and the society and is an important outcome measure in research studies. The prevalence of MI provides useful data regarding the burden of coronary artery disease and offers insight into health care planning, policy, and resource allocation. The importance of accurately and reproducibly defining MI is therefore self-evident. The Third Universal Definition of Myocardial Infarction (MI) expert consensus document was published in October 2012 by the global Myocardial Infarction Task Force.2 This landmark document was cosponsored by multiple cardiovascular societies and included both updated definitions and a modified classification of MI that have important clinical, epidemiological, and research implications. We hereby present a critical overview of this important document and summarize its key recommendations. PMID:24066201

  8. Redefining myocardial infarction: what is new in the ESC/ACCF/AHA/WHF Third Universal Definition of myocardial infarction?

    PubMed

    Jneid, Hani; Alam, Mahboob; Virani, Salim S; Bozkurt, Biykem

    2013-01-01

    Myocardial infarction (MI) is a major cause of mortality and morbidity worldwide. Each year, an estimated 785,000 persons will have a new MI in the United States alone, and approximately every minute an American will succumb to one.1 In addition, MI has major psychological and legal implications for patients and the society and is an important outcome measure in research studies. The prevalence of MI provides useful data regarding the burden of coronary artery disease and offers insight into health care planning, policy, and resource allocation. The importance of accurately and reproducibly defining MI is therefore self-evident. The Third Universal Definition of Myocardial Infarction (MI) expert consensus document was published in October 2012 by the global Myocardial Infarction Task Force.2 This landmark document was cosponsored by multiple cardiovascular societies and included both updated definitions and a modified classification of MI that have important clinical, epidemiological, and research implications. We hereby present a critical overview of this important document and summarize its key recommendations.

  9. Study of the Open Loop and Closed Loop Oscillator Techniques

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Imel, George R.; Baker, Benjamin; Riley, Tony

    This report presents the progress and completion of a five-year study undertaken at Idaho State University of the measurement of very small worth reactivity samples comparing open and closed loop oscillator techniques.The study conclusively demonstrated the equivalency of the two techniques with regard to uncertainties in reactivity values, i.e., limited by reactor noise. As those results are thoroughly documented in recent publications, in this report we will concentrate on the support work that was necessary. For example, we describe in some detail the construction and calibration of a pilot rod for the closed loop system. We discuss the campaign tomore » measure the required reactor parameters necessary for inverse-kinetics. Finally, we briefly discuss the transfer of the open loop technique to other reactor systems.« less

  10. Study of the open loop and closed loop oscillator techniques

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Baker, Benjamin; Riley, Tony; Langbehn, Adam

    This paper presents some aspects of a five year study undertaken at Idaho State University of the measurement of very small worth reactivity samples comparing open and closed loop oscillator techniques. The study conclusively demonstrated the equivalency of the two techniques with regard to uncertainties in reactivity values, i.e., limited by reactor noise. As those results are thoroughly documented in recent publications, in this paper we will concentrate on the support work that was necessary. For example, we describe in some detail the construction and calibration of a pilot rod for the closed loop system. We discuss the campaign tomore » measure the required reactor parameters necessary for inverse-kinetics. Finally, we briefly discuss the transfer of the open loop technique to other reactor systems. (authors)« less

  11. User's manual for COAST 4: a code for costing and sizing tokamaks

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sink, D. A.; Iwinski, E. M.

    1979-09-01

    The purpose of this report is to document the computer program COAST 4 for the user/analyst. COAST, COst And Size Tokamak reactors, provides complete and self-consistent size models for the engineering features of D-T burning tokamak reactors and associated facilities involving a continuum of performance including highly beam driven through ignited plasma devices. TNS (The Next Step) devices with no tritium breeding or electrical power production are handled as well as power producing and fissile producing fusion-fission hybrid reactors. The code has been normalized with a TFTR calculation which is consistent with cost, size, and performance data published in themore » conceptual design report for that device. Information on code development, computer implementation and detailed user instructions are included in the text.« less

  12. NGNP Data Management and Analysis System Modeling Capabilities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cynthia D. Gentillon

    2009-09-01

    Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. In addition, thermal-hydraulic experiments are conducted to validate codes used to assess reactor safety. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the thirdmore » NDMAS objective. It describes capabilities for displaying the data in meaningful ways and identifying relationships among the measured quantities that contribute to their understanding.« less

  13. Revised FINAL–REPORT NO. 2: INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT 1, NEWPORT, MICHIGAN (DOCKET NO. 50 16; RFTA 10-004) 2018-SR-02-1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Erika Bailey

    2011-10-27

    The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in Decembermore » 1960 and criticality was achieved in August 1963. The reactor was tested at low power during the first couple years of operation. Power ascension testing above 1 MW commenced in December 1965 immediately following the receipt of a high-power operating license. In October 1966 during power ascension, zirconium plates at the bottom of the reactor vessel became loose and blocked sodium coolant flow to some fuel subassemblies. Two subassemblies started to melt and the reactor was manually shut down. No abnormal releases to the environment occurred. Forty-two months later after the cause had been determined, cleanup completed, and the fuel replaced, Fermi 1 was restarted. However, in November 1972, PRDC made the decision to decommission Fermi 1 as the core was approaching its burn-up limit. The fuel and blanket subassemblies were shipped off-site in 1973. Following that, the secondary sodium system was drained and sent off-site. The radioactive primary sodium was stored on-site in storage tanks and 55 gallon (gal) drums until it was shipped off-site in 1984. The initial decommissioning of Fermi 1 was completed in 1975. Effective January 23, 1976, DPR-9 was transferred to the Detroit Edison Company (DTE) as a 'possession only' license (DTE 2010a). This report details the confirmatory activities performed during the second Oak Ridge Institute for Science and Education (ORISE) site visit to Fermi 1 in November 2010. The survey was strategically planned during a Unit 2 (Fermi 2) outage to take advantage of decreased radiation levels that were observed and attributed to Fermi 2 from the operating unit during the first site visit. However, during the second visit there were elevated radiation levels observed and attributed to the partially dismantled Fermi 1 reactor vessel and a waste storage box located on the 3rd floor of the Fermi 1 Turbine Building. Confirmatory surveys (unshielded) performed directly in the line of sight of these areas were affected. The objective of the confirmatory survey was to verify that the final radiological conditions were accurately and adequately described in Final Status Survey (FSS) documentation, relative to the established release criteria. This objective was achieved by performing document reviews, as well as independent measurements and sampling. Specifically, documentation of the planning, implementation, and results of the FSS were evaluated; side-by-side FSS measurement and source comparisons were performed; site areas were evaluated relative to appropriate FSS classification; and areas were assessed for residual, undocumented contamination.« less

  14. 7 CFR 1.302 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Under the Program Fraud Civil Remedies Act of 1986 § 1.302 Definitions. (a) Agency means a constituent organizational unit of the USDA. (b) Agency Fraud Claims Officer—(AFCO) means an officer or employee of an agency...) Statement means any representation, certification, affirmation, document, record, or accounting or...

  15. Nevada Administrative Code for Special Education Programs.

    ERIC Educational Resources Information Center

    Nevada State Dept. of Education, Carson City. Special Education Branch.

    This document presents excerpts from Chapter 388 of the Nevada Administrative Code, which concerns definitions, eligibility, and programs for students who are disabled or gifted/talented. The first section gathers together 36 relevant definitions from the Code for such concepts as "adaptive behavior,""autism,""gifted and…

  16. 30 CFR 57.6000 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    .... The following definitions apply in this subpart. Blasting agent. Any substance classified as a blasting agent by the Department of Transportation in 49 CFR 173.114a(a). This document is available at any... Metal and Nonmetal Safety and Health district office. Explosive material. Explosives, blasting agents...

  17. 30 CFR 57.6000 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    .... The following definitions apply in this subpart. Blasting agent. Any substance classified as a blasting agent by the Department of Transportation in 49 CFR 173.114a(a). This document is available at any... Metal and Nonmetal Safety and Health district office. Explosive material. Explosives, blasting agents...

  18. 30 CFR 57.6000 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    .... The following definitions apply in this subpart. Blasting agent. Any substance classified as a blasting agent by the Department of Transportation in 49 CFR 173.114a(a). This document is available at any... Metal and Nonmetal Safety and Health district office. Explosive material. Explosives, blasting agents...

  19. 30 CFR 57.6000 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    .... The following definitions apply in this subpart. Blasting agent. Any substance classified as a blasting agent by the Department of Transportation in 49 CFR 173.114a(a). This document is available at any... Metal and Nonmetal Safety and Health district office. Explosive material. Explosives, blasting agents...

  20. 30 CFR 57.6000 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    .... The following definitions apply in this subpart. Blasting agent. Any substance classified as a blasting agent by the Department of Transportation in 49 CFR 173.114a(a). This document is available at any... Metal and Nonmetal Safety and Health district office. Explosive material. Explosives, blasting agents...

  1. 22 CFR 50.1 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... Relations DEPARTMENT OF STATE NATIONALITY AND PASSPORTS NATIONALITY PROCEDURES § 50.1 Definitions. The... owing permanent allegiance to the United States. (e) Passport means a travel document issued under the authority of the Secretary of State attesting to the identity and nationality of the bearer. (f) Passport...

  2. 22 CFR 50.1 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... Relations DEPARTMENT OF STATE NATIONALITY AND PASSPORTS NATIONALITY PROCEDURES § 50.1 Definitions. The... owing permanent allegiance to the United States. (e) Passport means a travel document issued under the authority of the Secretary of State attesting to the identity and nationality of the bearer. (f) Passport...

  3. 22 CFR 50.1 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... Relations DEPARTMENT OF STATE NATIONALITY AND PASSPORTS NATIONALITY PROCEDURES § 50.1 Definitions. The... owing permanent allegiance to the United States. (e) Passport means a travel document issued under the authority of the Secretary of State attesting to the identity and nationality of the bearer. (f) Passport...

  4. 22 CFR 50.1 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... Relations DEPARTMENT OF STATE NATIONALITY AND PASSPORTS NATIONALITY PROCEDURES § 50.1 Definitions. The... owing permanent allegiance to the United States. (e) Passport means a travel document issued under the authority of the Secretary of State attesting to the identity and nationality of the bearer. (f) Passport...

  5. 22 CFR 50.1 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... Relations DEPARTMENT OF STATE NATIONALITY AND PASSPORTS NATIONALITY PROCEDURES § 50.1 Definitions. The... owing permanent allegiance to the United States. (e) Passport means a travel document issued under the authority of the Secretary of State attesting to the identity and nationality of the bearer. (f) Passport...

  6. 40 CFR 239.2 - Scope and definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... action, and financial assurance of Subtitle D regulated facilities. Permit documents means permit...) regulated facilities under the state's jurisdiction. (b) Definitions. (1) For purposes of this part... regulated under section 4010(c) of Subtitle D of RCRA comply with the requirements of the approved state...

  7. 22 CFR 42.63 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF IMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Application for Immigrant Visas § 42.63 Definitions. (a) Application forms—(1) Application on Form DS-230 or Form DS-260 required. Every alien applying for an immigrant visa must make...

  8. 22 CFR 42.63 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF IMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Application for Immigrant Visas § 42.63 Definitions. (a) Application forms—(1) Application on Form DS-230 or Form DS-260 required. Every alien applying for an immigrant visa must make...

  9. 22 CFR 42.63 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF IMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Application for Immigrant Visas § 42.63 Definitions. (a) Application forms—(1) Application on Form DS-230 or Form DS-260 required. Every alien applying for an immigrant visa must make...

  10. A Comparison of Fast-Spectrum and Moderated Space Fission Reactors

    NASA Astrophysics Data System (ADS)

    Poston, David I.

    2005-02-01

    The reactor neutron spectrum is one of the fundamental design choices for any fission reactor, but the implications of using a moderated spectrum are vastly different for space reactors as opposed to terrestrial reactors. In addition, the pros and cons of neutron spectra are significantly different among many of the envisioned space power applications. This paper begins with a discussion of the neutronic differences between fast-spectrum and moderated space reactors. This is followed by a discussion of the pros and cons of fast-spectrum and moderated space reactors separated into three areas—technical risk, performance, and safety/safeguards. A mix of quantitative and qualitative arguments is presented, and some conclusions generally can be made regarding neutron spectrum and space power application. In most cases, a fast-spectrum system appears to be the better alternative (mostly because of simplicity and higher potential operating temperatures); however, in some cases, such as a low-power (<100-kWt) surface reactor, a moderated spectrum could provide a better approach. In all cases, the determination of which spectrum is preferred is a strong function of the metrics provided by the "customer"— i.e., if a certain level of performance is required, it could provide a different solution than if a certain level of safeguards is required (which in some cases could produce a null solution). The views expressed in this document are those of the author and do not necessarily reflect agreement by the Government.

  11. Evaluating the Informative Quality of Documents in SGML Format from Judgements by Means of Fuzzy Linguistic Techniques Based on Computing with Words.

    ERIC Educational Resources Information Center

    Herrera-Viedma, Enrique; Peis, Eduardo

    2003-01-01

    Presents a fuzzy evaluation method of SGML documents based on computing with words. Topics include filtering the amount of information available on the Web to assist users in their search processes; document type definitions; linguistic modeling; user-system interaction; and use with XML and other markup languages. (Author/LRW)

  12. The Forest Inventory and Analysis Database: Database description and users manual version 4.0 for Phase 2

    Treesearch

    Sharon W. Woudenberg; Barbara L. Conkling; Barbara M. O' Connell; Elizabeth B. LaPoint; Jeffery A. Turner; Karen L. Waddell

    2010-01-01

    This document is based on previous documentation of the nationally standardized Forest Inventory and Analysis database (Hansen and others 1992; Woudenberg and Farrenkopf 1995; Miles and others 2001). Documentation of the structure of the Forest Inventory and Analysis database (FIADB) for Phase 2 data, as well as codes and definitions, is provided. Examples for...

  13. Apprentices and Trainees: December Quarter 2009: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the Apprentices and trainees December quarter 2009 report and its associated data tables. The primary purpose of this document is to assist users of the report to understand the specific data terms used within it. Terms that appear in the report are listed in alphabetical order with the following…

  14. Apprentices and Trainees: September Quarter 2009. Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "Apprentices and trainees September" quarter 2009 report and its associated data tables. The primary purpose of this document is to assist users of the report to understand the specific data terms used within it. Terms that appear in the report are listed in alphabetical order with the following…

  15. Apprentices and Trainees: Early Trend Estimates. June 2010: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2010

    2010-01-01

    This document covers the data terms used in the "Apprentices and trainees early trend estimates June 2010" publication. The primary purpose of this document is to assist users of the report to understand the specific data terms used within it. Terms that appear in the report are listed in alphabetical order with the following information…

  16. Outcomes from the Productivity Places Program 2009: Terms and Definitions. Support Document

    ERIC Educational Resources Information Center

    National Centre for Vocational Education Research (NCVER), 2009

    2009-01-01

    This document covers the data terms used in the "Outcomes from the Productivity Places Program 2009" report and its associated data tables. The primary purpose of this document is to assist users of the report to understand the specific data terms used within it. Terms that appear in the report are listed in alphabetical order with the…

  17. U-10Mo Baseline Fuel Fabrication Process Description

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hubbard, Lance R.; Arendt, Christina L.; Dye, Daniel F.

    This document provides a description of the U.S. High Power Research Reactor (USHPRR) low-enriched uranium (LEU) fuel fabrication process. This document is intended to be used in conjunction with the baseline process flow diagram (PFD) presented in Appendix A. The baseline PFD is used to document the fabrication process, communicate gaps in technology or manufacturing capabilities, convey alternatives under consideration, and as the basis for a dynamic simulation model of the fabrication process. The simulation model allows for the assessment of production rates, costs, and manufacturing requirements (manpower, fabrication space, numbers and types of equipment, etc.) throughout the lifecycle ofmore » the USHPRR program. This document, along with the accompanying PFD, is updated regularly« less

  18. An approach to model reactor core nodalization for deterministic safety analysis

    NASA Astrophysics Data System (ADS)

    Salim, Mohd Faiz; Samsudin, Mohd Rafie; Mamat @ Ibrahim, Mohd Rizal; Roslan, Ridha; Sadri, Abd Aziz; Farid, Mohd Fairus Abd

    2016-01-01

    Adopting good nodalization strategy is essential to produce an accurate and high quality input model for Deterministic Safety Analysis (DSA) using System Thermal-Hydraulic (SYS-TH) computer code. The purpose of such analysis is to demonstrate the compliance against regulatory requirements and to verify the behavior of the reactor during normal and accident conditions as it was originally designed. Numerous studies in the past have been devoted to the development of the nodalization strategy for small research reactor (e.g. 250kW) up to the bigger research reactor (e.g. 30MW). As such, this paper aims to discuss the state-of-arts thermal hydraulics channel to be employed in the nodalization for RTP-TRIGA Research Reactor specifically for the reactor core. At present, the required thermal-hydraulic parameters for reactor core, such as core geometrical data (length, coolant flow area, hydraulic diameters, and axial power profile) and material properties (including the UZrH1.6, stainless steel clad, graphite reflector) have been collected, analyzed and consolidated in the Reference Database of RTP using standardized methodology, mainly derived from the available technical documentations. Based on the available information in the database, assumptions made on the nodalization approach and calculations performed will be discussed and presented. The development and identification of the thermal hydraulics channel for the reactor core will be implemented during the SYS-TH calculation using RELAP5-3D® computer code. This activity presented in this paper is part of the development of overall nodalization description for RTP-TRIGA Research Reactor under the IAEA Norwegian Extra-Budgetary Programme (NOKEBP) mentoring project on Expertise Development through the Analysis of Reactor Thermal-Hydraulics for Malaysia, denoted as EARTH-M.

  19. Lessons Learned about Liquid Metal Reactors from FFTF Experience

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wootan, David W.; Casella, Andrew M.; Omberg, Ronald P.

    2016-09-20

    The Fast Flux Test Facility (FFTF) is the most recent liquid-metal reactor (LMR) to operate in the United States, from 1982 to 1992. FFTF is located on the DOE Hanford Site near Richland, Washington. The 400-MWt sodium-cooled, low-pressure, high-temperature, fast-neutron flux, nuclear fission test reactor was designed specifically to irradiate Liquid Metal Fast Breeder Reactor (LMFBR) fuel and components in prototypical temperature and flux conditions. FFTF played a key role in LMFBR development and testing activities. The reactor provided extensive capability for in-core irradiation testing, including eight core positions that could be used with independent instrumentation for the test specimens.more » In addition to irradiation testing capabilities, FFTF provided long-term testing and evaluation of plant components and systems for LMFBRs. The FFTF was highly successful and demonstrated outstanding performance during its nearly 10 years of operation. The technology employed in designing and constructing this reactor, as well as information obtained from tests conducted during its operation, can significantly influence the development of new advanced reactor designs in the areas of plant system and component design, component fabrication, fuel design and performance, prototype testing, site construction, and reactor operations. The FFTF complex included the reactor, as well as equipment and structures for heat removal, containment, core component handling and examination, instrumentation and control, and for supplying utilities and other essential services. The FFTF Plant was designed using a “system” concept. All drawings, specifications and other engineering documentation were organized by these systems. Efforts have been made to preserve important lessons learned during the nearly 10 years of reactor operation. A brief summary of Lessons Learned in the following areas will be discussed: Acceptance and Startup Testing of FFTF FFTF Cycle Reports« less

  20. An approach to model reactor core nodalization for deterministic safety analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Salim, Mohd Faiz, E-mail: mohdfaizs@tnb.com.my; Samsudin, Mohd Rafie, E-mail: rafies@tnb.com.my; Mamat Ibrahim, Mohd Rizal, E-mail: m-rizal@nuclearmalaysia.gov.my

    Adopting good nodalization strategy is essential to produce an accurate and high quality input model for Deterministic Safety Analysis (DSA) using System Thermal-Hydraulic (SYS-TH) computer code. The purpose of such analysis is to demonstrate the compliance against regulatory requirements and to verify the behavior of the reactor during normal and accident conditions as it was originally designed. Numerous studies in the past have been devoted to the development of the nodalization strategy for small research reactor (e.g. 250kW) up to the bigger research reactor (e.g. 30MW). As such, this paper aims to discuss the state-of-arts thermal hydraulics channel to bemore » employed in the nodalization for RTP-TRIGA Research Reactor specifically for the reactor core. At present, the required thermal-hydraulic parameters for reactor core, such as core geometrical data (length, coolant flow area, hydraulic diameters, and axial power profile) and material properties (including the UZrH{sub 1.6}, stainless steel clad, graphite reflector) have been collected, analyzed and consolidated in the Reference Database of RTP using standardized methodology, mainly derived from the available technical documentations. Based on the available information in the database, assumptions made on the nodalization approach and calculations performed will be discussed and presented. The development and identification of the thermal hydraulics channel for the reactor core will be implemented during the SYS-TH calculation using RELAP5-3D{sup ®} computer code. This activity presented in this paper is part of the development of overall nodalization description for RTP-TRIGA Research Reactor under the IAEA Norwegian Extra-Budgetary Programme (NOKEBP) mentoring project on Expertise Development through the Analysis of Reactor Thermal-Hydraulics for Malaysia, denoted as EARTH-M.« less

  1. Thinking about Thinking.

    ERIC Educational Resources Information Center

    Gough, Deborah

    1991-01-01

    This document summarizes five studies that offer insight into the nature of higher-order thinking skills and the most effective methods for teaching them to students. The reviews outline the conclusions, definitions, recommendations, specific methods of teaching, instructional strategies, and programs detailed in the documents themselves.…

  2. 28 CFR 79.61 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    .... The term includes in situ lung cancers. (m) Readily available documentation means documents in the... injury means structural or functional damage to the kidney tubules that results in renal disease and... resulting in chronic renal dysfunction. (j) Nonmalignant respiratory disease means fibrosis of the lung...

  3. Final report, PT IP-535-C: Test of smaller VSR`s in DR reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vaughn, A.D.

    1963-04-17

    Because of rod-sticking problems at DR Reactor, a knuckle rod of B Reactor design was installed in vertical safety channel number 28. The substitute VSR, which has a smaller diameter than the original DR rod, has been tested for its operational feasibility including both drop time and reactivity effect. The reactivity effect of the rod was estimated by comparison of the reactivity transient caused by insertion of the specific B-type rod after scramming into the pile, with similar transients caused by normal vertical safety rod in an adjacent channel. This document lists the indicated relative control strength of the rodmore » as an empirical basis for future safety calculations. Results indicate that the B-type knuckel rod in DR reactor is about 80% as strong as a normal DR vertical safety rod if used in equivalent flux distribution and location; this makes it reasonable to assume that the local control strength of the B-type knuckel rod is 98 {mu}b.« less

  4. 76 FR 11525 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on U.S...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-02

    ... the U.S. EPR Document Control Design (DCD) Safety Evaluation Report (SER) with Open Items. The... from the website cited above or by contacting the identified DFO. Moreover, in view of the possibility...

  5. 78 FR 7465 - Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-01

    ..., and applicants for facility (i.e., nuclear power and non-power research and test reactor) operating... the final supporting statement, at the NRC's Public Document Room, Room O-1F21, One White Flint North...

  6. Ontology for Life-Cycle Modeling of Electrical Distribution Systems: Application of Model View Definition Attributes

    DTIC Science & Technology

    2013-06-01

    Building in- formation exchange (COBie), Building Information Modeling ( BIM ) 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF...to develop a life-cycle building model have resulted in the definition of a “core” building information model that contains general information de...develop an information -exchange Model View Definition (MVD) for building electrical systems. The objective of the current work was to document the

  7. Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Smith, Cyrus M; Nanstad, Randy K; Clayton, Dwight A

    2012-09-01

    The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin nextmore » year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.« less

  8. Monographs in Environmental Education and Environmental Studies. Volume I.

    ERIC Educational Resources Information Center

    Sacks, Arthur B., Ed.

    The first section of this document contains definitional papers prepared by three sections of the North American Association for Environmental Education (NAEE). They are: (1) "The Challenges of K-12 Environmental Education" (Harold Hungerford and Trudi Volk); (2) "'Environmental Studies': Towards a Definition" (Royal Harde);…

  9. 78 FR 5330 - Proposed Priorities and Definitions-NIDRR DRRP-Community Living and Participation, Health and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-25

    ... observational findings, and creating other sources of research-based information. This research stage may... definitions for the Disability and Rehabilitation Research Projects and Centers Program administered by the National Institute on Disability and Rehabilitation Research (NIDRR). Specifically, this document proposes...

  10. 30 CFR 250.1402 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Definitions. Terms used in this subpart have the following meaning: Case file means an MMS document file... fine. It is an MMS regulatory enforcement tool used in addition to Notices of Incidents of... employee assigned to review case files and assess civil penalties. Violation means failure to comply with...

  11. 40 CFR 350.1 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... INFORMATION: AND TRADE SECRET DISCLOSURES TO HEALTH PROFESSIONALS Trade Secrecy Claims § 350.1 Definitions... secret. Sanitized means a version of a document from which information claimed as trade secret or... support of a claim that chemical identity is a trade secret. Title III means Title III of the Superfund...

  12. 40 CFR 350.1 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... INFORMATION: AND TRADE SECRET DISCLOSURES TO HEALTH PROFESSIONALS Trade Secrecy Claims § 350.1 Definitions... secret. Sanitized means a version of a document from which information claimed as trade secret or... support of a claim that chemical identity is a trade secret. Title III means Title III of the Superfund...

  13. 40 CFR 350.1 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... INFORMATION: AND TRADE SECRET DISCLOSURES TO HEALTH PROFESSIONALS Trade Secrecy Claims § 350.1 Definitions... secret. Sanitized means a version of a document from which information claimed as trade secret or... support of a claim that chemical identity is a trade secret. Title III means Title III of the Superfund...

  14. 40 CFR 350.1 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... INFORMATION: AND TRADE SECRET DISCLOSURES TO HEALTH PROFESSIONALS Trade Secrecy Claims § 350.1 Definitions... secret. Sanitized means a version of a document from which information claimed as trade secret or... support of a claim that chemical identity is a trade secret. Title III means Title III of the Superfund...

  15. 22 CFR 42.63 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... Relations DEPARTMENT OF STATE VISAS VISAS: DOCUMENTATION OF IMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Application for Immigrant Visas § 42.63 Definitions. (a) Application forms—(1) Application on Form DS-230 or Form DS-260 Required.—Every alien applying for an immigrant visa must make...

  16. 19 CFR 111.1 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    .... “Broker” means a customs broker. Corporate compliance activity. “Corporate compliance activity” means activity performed by a business entity to ensure that documents for a related business entity or entities... definition, a “business entity” is an entity that is registered or otherwise on record with an appropriate...

  17. Informed Consent: Does Anyone Really Understand What Is Contained In The Medical Record?

    PubMed

    Fenton, S H; Manion, F; Hsieh, K; Harris, M

    2015-01-01

    Despite efforts to provide standard definitions of terms such as "medical record", "computer-based patient record", "electronic medical record" and "electronic health record", the terms are still used interchangeably. Initiatives like data and information governance, research biorepositories, and learning health systems require availability and reuse of data, as well as common understandings of the scope for specific purposes. Lacking widely shared definitions, utilization of the afore-mentioned terms in research informed consent documents calls to question whether all participants in the research process - patients, information technology and regulatory staff, and the investigative team - fully understand what data and information they are asking to obtain and agreeing to share. This descriptive study explored the terminology used in research informed consent documents when describing patient data and information, asking the question "Does the use of the term "medical record" in the context of a research informed consent document accurately represent the scope of the data involved?" Informed consent document templates found on 17 Institutional Review Board (IRB) websites with Clinical and Translational Science Awards (CTSA) were searched for terms that appeared to be describing the data resources to be accessed. The National Library of Medicine's (NLM) Terminology Services was searched for definitions provided by key standards groups that deposit terminologies with the NLM. The results suggest research consent documents are using outdated terms to describe patient information, health care terminology systems need to consider the context of research for use cases, and that there is significant work to be done to assure the HIPAA Omnibus Rule is applied to contemporary activities such as biorepositories and learning health systems. "Medical record", a term used extensively in research informed consent documents, is ambiguous and does not serve us well in the context of contemporary information management and governance.

  18. Definitions and methods of measuring and reporting on injurious falls in randomised controlled fall prevention trials: a systematic review

    PubMed Central

    2012-01-01

    Background The standardisation of the assessment methodology and case definition represents a major precondition for the comparison of study results and the conduction of meta-analyses. International guidelines provide recommendations for the standardisation of falls methodology; however, injurious falls have not been targeted. The aim of the present article was to review systematically the range of case definitions and methods used to measure and report on injurious falls in randomised controlled trials (RCTs) on fall prevention. Methods An electronic literature search of selected comprehensive databases was performed to identify injurious falls definitions in published trials. Inclusion criteria were: RCTs on falls prevention published in English, study population ≥ 65 years, definition of injurious falls as a study endpoint by using the terms "injuries" and "falls". Results The search yielded 2089 articles, 2048 were excluded according to defined inclusion criteria. Forty-one articles were included. The systematic analysis of the methodology applied in RCTs disclosed substantial variations in the definition and methods used to measure and document injurious falls. The limited standardisation hampered comparability of study results. Our results also highlight that studies which used a similar, standardised definition of injurious falls showed comparable outcomes. Conclusions No standard for defining, measuring, and documenting injurious falls could be identified among published RCTs. A standardised injurious falls definition enhances the comparability of study results as demonstrated by a subgroup of RCTs used a similar definition. Recommendations for standardising the methodology are given in the present review. PMID:22510239

  19. Definition of Regulated Pollutant for Particulate Matter for Purposes of Title V

    EPA Pesticide Factsheets

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Policy and Guidance Database available at www2.epa.gov/title-v-operating-permits/title-v-operating-permit-policy-and-guidance-document-index. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  20. 4/5/95 Letter on Definition of Major Source

    EPA Pesticide Factsheets

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Policy and Guidance Database available at www2.epa.gov/title-v-operating-permits/title-v-operating-permit-policy-and-guidance-document-index. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  1. Definition of Regulated Air Pollutant for Purposes of Title V

    EPA Pesticide Factsheets

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Policy and Guidance Database available at www2.epa.gov/title-v-operating-permits/title-v-operating-permit-policy-and-guidance-document-index. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  2. Interpretation of the Definition of Fugitive Emissions in Parts 70 and 71

    EPA Pesticide Factsheets

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Policy and Guidance Database available at www2.epa.gov/title-v-operating-permits/title-v-operating-permit-policy-and-guidance-document-index. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  3. Source Definition Issue for KN Power - Front Range Energy Associates, LLC/PSCo Generating Facility

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  4. PSD Guidance, 40 CFR 52.21 (b)(2)(d) - Definition of Capable of Accommodating

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  5. Response to Request for Guidance on PSD Definition Referencing Cogeneration Gas Turbines that are Separated by One-Half Mile

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  6. Interpretation of the Definition of Fugitive Emissions in Parts 70 and 71

    EPA Pesticide Factsheets

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  7. 45 CFR 1602.2 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... electronic documents, among others. (c) Educational institution means a preschool, a public or private... will look to the use to which a requester will put the documents requested. When the Corporation has... documentary materials, regardless of whether the format is physical or electronic, made or received by the...

  8. VOTable Format Definition Version 1.3

    NASA Astrophysics Data System (ADS)

    Ochsenbein, Francois; Taylor, Mark; Williams, Roy; Davenhall, Clive; Demleitner, Markus; Durand, Daniel; Fernique, Pierre; Giaretta, David; Hanisch, Robert; McGlynn, Tom; Szalay, Alex; Wicenec, Andreas; Ochsenbein, Francois; Taylor, Mark

    2013-09-01

    This document describes the structures making up the VOTable standard. The main part of this document describes the adopted part of the VOTable standard; it is followed by appendices presenting extensions which have been proposed and/or discussed, but which are not part of the standard.

  9. 28 CFR 79.41 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... includes in situ lung cancers. (j) Readily available documentation means documents in the possession... or uranium mine worker means a person who operated or otherwise worked in a uranium mine. (f... means a chronic lung disease resulting from inhalation and deposition in the lung of particulate matter...

  10. 28 CFR 79.51 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... includes in situ lung cancers. (m) Readily available documentation means documents in the possession... or functional damage to the kidney tubules that results in renal disease and dysfunction. (g) Miller or uranium mill worker means a person who operated or otherwise worked in a uranium mill. (h...

  11. 28 CFR 79.51 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... includes in situ lung cancers. (m) Readily available documentation means documents in the possession... or functional damage to the kidney tubules that results in renal disease and dysfunction. (g) Miller or uranium mill worker means a person who operated or otherwise worked in a uranium mill. (h...

  12. Variable & Recode Definitions - SEER Documentation

    Cancer.gov

    Resources that define variables and provide documentation for reporting using SEER and related datasets. Choose from SEER coding and staging manuals plus instructions for recoding behavior, site, stage, cause of death, insurance, and several additional topics. Also guidance on months survived, calculating Hispanic mortality, and site-specific surgery.

  13. Documentation of probabilistic fracture mechanics codes used for reactor pressure vessels subjected to pressurized thermal shock loading: Parts 1 and 2. Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Balkey, K.; Witt, F.J.; Bishop, B.A.

    1995-06-01

    Significant attention has been focused on the issue of reactor vessel pressurized thermal shock (PTS) for many years. Pressurized thermal shock transient events are characterized by a rapid cooldown at potentially high pressure levels that could lead to a reactor vessel integrity concern for some pressurized water reactors. As a result of regulatory and industry efforts in the early 1980`s, a probabilistic risk assessment methodology has been established to address this concern. Probabilistic fracture mechanics analyses are performed as part of this methodology to determine conditional probability of significant flaw extension for given pressurized thermal shock events. While recent industrymore » efforts are underway to benchmark probabilistic fracture mechanics computer codes that are currently used by the nuclear industry, Part I of this report describes the comparison of two independent computer codes used at the time of the development of the original U.S. Nuclear Regulatory Commission (NRC) pressurized thermal shock rule. The work that was originally performed in 1982 and 1983 to compare the U.S. NRC - VISA and Westinghouse (W) - PFM computer codes has been documented and is provided in Part I of this report. Part II of this report describes the results of more recent industry efforts to benchmark PFM computer codes used by the nuclear industry. This study was conducted as part of the USNRC-EPRI Coordinated Research Program for reviewing the technical basis for pressurized thermal shock (PTS) analyses of the reactor pressure vessel. The work focused on the probabilistic fracture mechanics (PFM) analysis codes and methods used to perform the PTS calculations. An in-depth review of the methodologies was performed to verify the accuracy and adequacy of the various different codes. The review was structured around a series of benchmark sample problems to provide a specific context for discussion and examination of the fracture mechanics methodology.« less

  14. Spent fuel data base: commercial light water reactors. [PWR; BWR

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hauf, M.J.; Kniazewycz, B.G.

    1979-12-01

    As a consequence of this country's non-proliferation policy, the reprocessing of spent nuclear fuel has been delayed indefinitely. This has resulted in spent light water reactor (LWR) fuel being considered as a potential waste form for disposal. Since the Nuclear Regulatory Commission (NRC) is currently developing methodologies for use in the regulation of the management and disposal of high-level and transuranic wastes, a comprehensive data base describing LWR fuel technology must be compiled. This document provides that technology baseline and, as such, will support the development of those evaluation standards and criteria applicable to spent nuclear fuel.

  15. Rover nuclear rocket engine program: Overview of rover engine tests

    NASA Technical Reports Server (NTRS)

    Finseth, J. L.

    1991-01-01

    The results of nuclear rocket development activities from the inception of the ROVER program in 1955 through the termination of activities on January 5, 1973 are summarized. This report discusses the nuclear reactor test configurations (non cold flow) along with the nuclear furnace demonstrated during this time frame. Included in the report are brief descriptions of the propulsion systems, test objectives, accomplishments, technical issues, and relevant test results for the various reactor tests. Additionally, this document is specifically aimed at reporting performance data and their relationship to fuel element development with little or no emphasis on other (important) items.

  16. NASA Docking System (NDS) Interface Definitions Document (IDD)

    NASA Technical Reports Server (NTRS)

    Tabakman, Alexander; England, Warren

    2013-01-01

    The contents of this document define the integrated performance and interface design for NASA Docking System (NDS) Block 1 and the International Docking Adapter. The intent of this IDD is to provide the interface design for using, installing, and interfacing to the NDS Block 1 that will enable successful docking to the IDA. This document is under the control of the ISS Development Projects Office (OG).

  17. 19 CFR 103.21 - Purpose and definitions.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 19 Customs Duties 1 2011-04-01 2011-04-01 false Purpose and definitions. 103.21 Section 103.21 Customs Duties U.S. CUSTOMS AND BORDER PROTECTION, DEPARTMENT OF HOMELAND SECURITY; DEPARTMENT OF THE... followed with respect to the production or disclosure of any documents contained in Customs files, any...

  18. 19 CFR 103.21 - Purpose and definitions.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 19 Customs Duties 1 2013-04-01 2013-04-01 false Purpose and definitions. 103.21 Section 103.21 Customs Duties U.S. CUSTOMS AND BORDER PROTECTION, DEPARTMENT OF HOMELAND SECURITY; DEPARTMENT OF THE... followed with respect to the production or disclosure of any documents contained in Customs files, any...

  19. 19 CFR 103.21 - Purpose and definitions.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 19 Customs Duties 1 2012-04-01 2012-04-01 false Purpose and definitions. 103.21 Section 103.21 Customs Duties U.S. CUSTOMS AND BORDER PROTECTION, DEPARTMENT OF HOMELAND SECURITY; DEPARTMENT OF THE... followed with respect to the production or disclosure of any documents contained in Customs files, any...

  20. 50 CFR 300.101 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... returns to port and at all points in between. Real-time means as soon as possible, but at least every 4... paragraph (1) of this definition. Centralized Vessel Monitoring System (C-VMS) means a system that uses... weight, at any time, of the catch on board the vessel. Dissostichus catch document (DCD) means the...

  1. 50 CFR 300.101 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... returns to port and at all points in between. Real-time means as soon as possible, but at least every 4... paragraph (1) of this definition. Centralized Vessel Monitoring System (C-VMS) means a system that uses... weight, at any time, of the catch on board the vessel. Dissostichus catch document (DCD) means the...

  2. 75 FR 78897 - Definition of Omission From Gross Income

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-17

    ... Definition of Omission From Gross Income AGENCY: Internal Revenue Service (IRS), Treasury. ACTION: Final regulations. SUMMARY: This document contains final regulations defining an omission from gross income for... overstatement of basis in a sold asset results in an omission from gross income. The regulations will affect any...

  3. Schools and Programs of Choice: Voluntary Desegregation in Massachusetts.

    ERIC Educational Resources Information Center

    Missal, Gerald E., Ed.

    Described in this document are a number of magnet school programs developed and operating in Massachusetts as part of a voluntary school desegregation plan. A historical perspective of magnet school development is provided along with definitions and guidelines of both magnet schools and magnet education programs. These definitions and guidelines…

  4. 41 CFR 102-118.35 - What definitions apply to this part?

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... between computers instead of paper documents. These electronic transmissions must use established and... 41 Public Contracts and Property Management 3 2012-01-01 2012-01-01 false What definitions apply to this part? 102-118.35 Section 102-118.35 Public Contracts and Property Management Federal Property...

  5. 41 CFR 102-118.35 - What definitions apply to this part?

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... between computers instead of paper documents. These electronic transmissions must use established and... 41 Public Contracts and Property Management 3 2011-01-01 2011-01-01 false What definitions apply to this part? 102-118.35 Section 102-118.35 Public Contracts and Property Management Federal Property...

  6. 41 CFR 102-118.35 - What definitions apply to this part?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... between computers instead of paper documents. These electronic transmissions must use established and... 41 Public Contracts and Property Management 3 2013-07-01 2013-07-01 false What definitions apply to this part? 102-118.35 Section 102-118.35 Public Contracts and Property Management Federal Property...

  7. 41 CFR 102-118.35 - What definitions apply to this part?

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... between computers instead of paper documents. These electronic transmissions must use established and... 41 Public Contracts and Property Management 3 2014-01-01 2014-01-01 false What definitions apply to this part? 102-118.35 Section 102-118.35 Public Contracts and Property Management Federal Property...

  8. Official Publication Section. Collections and Services Division. Papers.

    ERIC Educational Resources Information Center

    International Federation of Library Associations, The Hague (Netherlands).

    Papers on the collection and processing of official or government documents which were presented at the 1982 International Federation of Library Associations (IFLA) conference include: (1) "The Definition of Official Publications" by E. Johansson (United Kingdom), which provides a proposed definition and a 1979 IFLA discussion paper on…

  9. 50 CFR 300.101 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... returns to port and at all points in between. Real-time means as soon as possible, but at least every 4... paragraph (1) of this definition. Centralized Vessel Monitoring System (C-VMS) means a system that uses... weight, at any time, of the catch on board the vessel. Dissostichus catch document (DCD) means the...

  10. 29 CFR 1690.107 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 29 Labor 4 2010-07-01 2010-07-01 false Definitions. 1690.107 Section 1690.107 Labor Regulations... of advice and opinions on a subject occurring among the EEOC and affected agencies before formal... document by the issuing agency to the EEOC and other affected agencies for at least 15 working days from...

  11. 29 CFR 1690.107 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 29 Labor 4 2012-07-01 2012-07-01 false Definitions. 1690.107 Section 1690.107 Labor Regulations... of advice and opinions on a subject occurring among the EEOC and affected agencies before formal... document by the issuing agency to the EEOC and other affected agencies for at least 15 working days from...

  12. 29 CFR 1690.107 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 29 Labor 4 2014-07-01 2014-07-01 false Definitions. 1690.107 Section 1690.107 Labor Regulations... of advice and opinions on a subject occurring among the EEOC and affected agencies before formal... document by the issuing agency to the EEOC and other affected agencies for at least 15 working days from...

  13. 29 CFR 1690.107 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 29 Labor 4 2013-07-01 2013-07-01 false Definitions. 1690.107 Section 1690.107 Labor Regulations... of advice and opinions on a subject occurring among the EEOC and affected agencies before formal... document by the issuing agency to the EEOC and other affected agencies for at least 15 working days from...

  14. 29 CFR 1690.107 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 29 Labor 4 2011-07-01 2011-07-01 false Definitions. 1690.107 Section 1690.107 Labor Regulations... of advice and opinions on a subject occurring among the EEOC and affected agencies before formal... document by the issuing agency to the EEOC and other affected agencies for at least 15 working days from...

  15. Martian Atmospheric Dust Mitigation for ISRU Intakes via Electrostatic Precipitation

    NASA Technical Reports Server (NTRS)

    Phillips, James R., III; Pollard, Jacob R. S.; Johansen, Michael R.; Mackey, Paul J.; Clements, Sid; Calle, Carlos I.

    2016-01-01

    This document is the presentation to be given at the 2016 American Society of Civil Engineers Earth and Space Conference to examine the concept of using electrostatic precipitation for Martian atmospheric dust mitigation of the intakes of in-situ resource utilization reactors.

  16. 76 FR 80409 - Draft Supplement 2 to Final Environmental Statement Related to the Operation of Watts Bar Nuclear...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-23

    ... image files of the NRC's public documents. If you do not have access to ADAMS or if there are problems.... Stephen J. Campbell, Chief, Watts Bar Special Projects Branch, Division of Operating Reactor Licensing...

  17. Preliminary Concept of Operations for the Spent Fuel Management System--WM2017

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cumberland, Riley M; Adeniyi, Abiodun Idowu; Howard, Rob L

    The Nuclear Fuels Storage and Transportation Planning Project (NFST) within the U.S. Department of Energy s Office of Nuclear Energy is tasked with identifying, planning, and conducting activities to lay the groundwork for developing interim storage and transportation capabilities in support of an integrated waste management system. The system will provide interim storage for commercial spent nuclear fuel (SNF) from reactor sites and deliver it to a repository. The system will also include multiple subsystems, potentially including; one or more interim storage facilities (ISF); one or more repositories; facilities to package and/or repackage SNF; and transportation systems. The project teammore » is analyzing options for an integrated waste management system. To support analysis, the project team has developed a Concept of Operations document that describes both the potential integrated system and inter-dependencies between system components. The goal of this work is to aid systems analysts in the development of consistent models across the project, which involves multiple investigators. The Concept of Operations document will be updated periodically as new developments emerge. At a high level, SNF is expected to travel from reactors to a repository. SNF is first unloaded from reactors and placed in spent fuel pools for wet storage at utility sites. After the SNF has cooled enough to satisfy loading limits, it is placed in a container at reactor sites for storage and/or transportation. After transportation requirements are met, the SNF is transported to an ISF to store the SNF until a repository is developed or directly to a repository if available. While the high level operation of the system is straightforward, analysts must evaluate numerous alternative options. Alternative options include the number of ISFs (if any), ISF design, the stage at which SNF repackaging occurs (if any), repackaging technology, the types of containers used, repository design, component sizing, and timing of events. These alternative options arise due to technological, economic, or policy considerations. As new developments regularly emerge, the operational concepts will be periodically updated. This paper gives an overview of the different potential alternatives identified in the Concept of Operations document at a conceptual level.« less

  18. Manned space flight nuclear system safety. Volume 3: Reactor system preliminary nuclear safety analysis. Part 3: Nuclear Safety Analysis Document (NSAD)

    NASA Technical Reports Server (NTRS)

    1972-01-01

    Nuclear safety analysis as applied to a space base mission is presented. The nuclear safety analysis document summarizes the mission and the credible accidents/events which may lead to nuclear hazards to the general public. The radiological effects and associated consequences of the hazards are discussed in detail. The probability of occurrence is combined with the potential number of individuals exposed to or above guideline values to provide a measure of accident and total mission risk. The overall mission risk has been determined to be low with the potential exposure to or above 25 rem limited to less than 4 individuals per every 1000 missions performed. No radiological risk to the general public occurs during the prelaunch phase at KSC. The most significant risks occur from prolonged exposure to reactor debris following land impact generally associated with the disposal phase of the mission where fission product inventories can be high.

  19. 2D Thermal Hydraulic Analysis and Benchmark in Support of HFIR LEU Conversion using COMSOL

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Freels, James D; Bodey, Isaac T; Lowe, Kirk T

    2010-09-01

    The research documented herein was funded by a research contract between the Research Reactors Division (RRD) of Oak Ridge National Laboratory (ORNL) and the University of Tennessee, Knoxville (UTK) Mechanical, Aerospace and Biomedical Engineering Department (MABE). The research was governed by a statement of work (SOW) which clearly defines nine specific tasks. This report is outlined to follow and document the results of each of these nine specific tasks. The primary goal of this phase of the research is to demonstrate, through verification and validation methods, that COMSOL is a viable simulation tool for thermal-hydraulic modeling of the High Fluxmore » Isotope Reactor (HFIR) core. A secondary goal of this two-dimensional phase of the research is to establish methodology and data base libraries that are also needed in the full three-dimensional COMSOL simulation to follow. COMSOL version 3.5a was used for all of the models presented throughout this report.« less

  20. NRC (Nuclear Regulatory Commission) editorial style guide

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Beeson, J.F.; Calure, B.A.; Gable, D.

    1989-10-01

    Editorial style refers to the choices that writers, editors, and secretaries make to eliminate inconsistencies in their documents. These choices apply to the recurrent features of a document such as abbreviations, capitalization, compound words, numbers, symbols, and punctuation, as well as to references and footnotes. Making these choices is sometimes difficult because usage changes as the language evolves. Consider the use of hyphens, for example. Do we write non-power reactor or nonpower reactor Is it on-site incident or onsite incident Although usage is moving away from the use of hyphens with prefixes, the authorities who compile style guides do notmore » always agree about which choice to use at a given time. Moreover, each discipline -- law, physics, mathematics -- has specific standards that apply to the publications for that discipline. Even in an area as seemingly certain as spelling, overlapping usage exists. Reputable dictionaries show both align'' and aline'' as correct spellings. Likewise, disc, disk, and diskette'' currently coexist as equally valid choices.« less

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