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Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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1

Nuclear criticality safety guide  

SciTech Connect

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

Pruvost, N.L.; Paxton, H.C. [eds.] [eds.

1996-09-01T23:59:59.000Z

2

Nuclear Engineering Nuclear Criticality Safety  

E-Print Network (OSTI)

Nuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear, and neutron spectra. The NE nuclear criticality safety (NCS) capabilities are based on a staff with decades

Kemner, Ken

3

Nuclear Engineer (Criticality Safety)  

Energy.gov (U.S. Department of Energy (DOE))

This position is located in the Nuclear Safety Division (NSD) which has specific responsibility for managing the development, analysis, review, and approval of non-reactor nuclear facility safety...

4

Autoclave nuclear criticality safety analysis  

SciTech Connect

Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

D`Aquila, D.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Tayloe, R.W. Jr. [Battelle, Columbus, OH (United States)

1991-12-31T23:59:59.000Z

5

Nuclear Criticality Safety | More Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Criticality Safety Criticality Safety SHARE Criticality Safety Nuclear Criticality Safety ORNL is the lead national laboratory responsible for supporting the National Nuclear Security Administration (NNSA) in managing the US Nuclear Criticality Safety Program. NCSP is chartered to maintain the technical infrastructure (integral experiments, computational tools, training, data, etc.) needed to support safe, efficient fissionable material operations. ORNL has extensive expertise in the area of nuclear criticality safety (NCS) based upon years of experience in the following areas: Operations Support: providing fissionable material operations support for enrichment, fabrication, production, and research; Critical Experiments: performing experiments at the Y-12 Critical Experiment Facility;

6

DOE Nuclear Criticality Safety Program - Nuclear Engineering Division  

NLE Websites -- All DOE Office Websites (Extended Search)

DOE Nuclear Criticality Safety Program DOE Nuclear Criticality Safety Program Nuclear Criticality Safety Overview Experience Analysis Tools Current NCS Activities Current R&D Activities DOE Criticality Safety Support Group (CSSG) Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr The DOE Nuclear Criticality Safety Program Bookmark and Share J. Morman and R. Bucher load J. Morman and R. Bucher load samples into the ZPR-6 critical assembly for material worth measurements. Click on image to view larger image. The DOE Nuclear Criticality Safety Program (NCSP) is focused on maintaining fundamental infrastructure that enables retention of DOE capabilities and expertise in nuclear criticality safety necessary to support line

7

Nuclear criticality safety: 300 Area  

SciTech Connect

This Standard applies to the receipt, processing, storage, and shipment of fissionable material in the 300 Area and in any other facility under the control of the Reactor Materials Project Management Team (PMT). The objective is to establish practices and process conditions for the storage and handling of fissionable material that prevent the accidental assembly of a critical mass and that comply with DOE Orders as well as accepted industry practice.

Not Available

1991-07-31T23:59:59.000Z

8

Proceedings of the Nuclear Criticality Technology and Safety Project Workshop  

SciTech Connect

This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

Sanchez, R.G. [comp.

1994-01-01T23:59:59.000Z

9

CRITICALITY SAFETY (CS)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

OBJECTIVE CS.1 The LANL criticality safety program provides the required technical guidance and oversight capabilities to ensure a comprehensive criticality safety program for the storage of nuclear materials in SSTs. (Core Requirements 3, 4, 8) Criteria * The Criticality Safety Program is an administrative TSR and meets the General and * Specific Requirements of DOE O 420.1A, Section 4.3 Nuclear Criticality Safety. * All processes and operations involving significant quantities of fissile materials are * described in current procedures approved by line management. * Procedures contain approved criticality controls and limits, based on HSR-6 evaluations and recommendations. * Supervisors, operations personnel, and criticality safety officers have received

10

Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant  

SciTech Connect

This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested.

Sheaffer, M.K.; Keeton, S.C.

1993-09-20T23:59:59.000Z

11

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities  

SciTech Connect

This document contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE non-reactor nuclear facilities. Adherence to these guidelines will provide consistency and uniformity in criticality safety evaluations (CSEs) across the complex and will document compliance with the requirements of DOE Order 5480.24.

Not Available

1993-11-01T23:59:59.000Z

12

PLC-Based Safety Critical Software Development for Nuclear Power Plants  

E-Print Network (OSTI)

PLC-Based Safety Critical Software Development for Nuclear Power Plants Junbeom Yoo1 , Sungdeok Cha}@kaeri.re.kr Abstract. This paper proposes a PLC(Programmable Logic Controller)-based safety critical software(FBD), a widely used PLC programming language. Finally, we manually refine the FBD programs so that redundant

13

Nuclear criticality safety program development using necessary and sufficient standards  

SciTech Connect

The U.S. Department of Energy`s (DOE`s) Necessary and Sufficient Standards Closure Process has been used to develop a new criticality, safety program manual for the Rocky Flats Environmental Technology Site (RFETS). Standards define and communicate the expectations for performance of work. The purpose of the necessary and sufficient standards closure process is to apply standards determined to be necessary and sufficient for protecting the workers, the public, and the environment. This ensures that the applied standards add value to the performance of the activity; work effectiveness is increased. The purpose of this paper is to briefly describe the process and the results for the selection of national criticality safety standards for use at the Rocky Flats facilities.

Croucher, D.W.; Stachowiak, R.V. [Kaiser-Hill Co., LLC, Golden, CO (United States); Wilson, R.E. [Safe Sites of Colorado, Golden, CO (United States)

1996-12-31T23:59:59.000Z

14

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities  

SciTech Connect

This Department of Energy (DOE) is approved for use by all components of DOE. It contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE Non-Reactor Nuclear Facilities. Adherence with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs.

NONE

1998-09-01T23:59:59.000Z

15

Criticality Safety | Department of Energy  

Office of Environmental Management (EM)

at Department of Energy Non Reactor Nuclear Facilities DOE-STD-1135-99, Guidance for Nuclear Criticality Safety Engineer Training and Qualification Contact Garrett Smith...

16

Nuclear criticality safety experiments, calculations, and analyses: 1958 to 1982. Volume 1. Lookup tables  

SciTech Connect

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains - in chronological order - the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

Koponen, B.L.; Hampel, V.E.

1982-10-21T23:59:59.000Z

17

Office of Nuclear Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Nuclear Safety (HS-30) Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home » Directives » Nuclear and Facility Safety Policy Rules » Nuclear Safety Workshops Technical Standards Program » Search » Approved Standards » Recently Approved » RevCom for TSP » Monthly Status Reports » Archive » Feedback DOE Nuclear Safety Research & Development Program Office of Nuclear Safety Basis & Facility Design (HS-31) Office of Nuclear Safety Basis & Facility Design - About Us » Nuclear Policy Technical Positions/Interpretations » Risk Assessment Working Group » Criticality Safety » DOE O 420.1C Facility Safety » Beyond Design Basis Events Office of Nuclear Facility Safety Programs (HS-32) Office of Nuclear Facility Safety Programs - About Us

18

Y-12's 1958 nuclear criticality accident and increased safety...  

NLE Websites -- All DOE Office Websites (Extended Search)

signage, responsibility and programs for increased safety. Signs were required to make workers aware of hazards that had not been used before. Emergency response organizations...

19

Nuclear criticality safety program at the University of Tennessee-Knoxville  

SciTech Connect

This paper presents an overview of the nuclear criticality safety (NCS) educational program at the University of Tennessee-Knoxville. The program is an academic specialization for nuclear engineering graduate students pursuing either the MS or PhD degree and includes special NCS courses and NCS research projects. Both the courses and the research projects serve as partial fulfillment of the requirements for the degree being pursued.

Basoglu, B.; Bentley, C.; Brewer, R.; Dunn, M.; Haught, C.; Plaster, M.; Wilkinson, A.; Dodds, H. (Univ. of Tennessee, Knoxville, TN (United States)); Elliott, E.; Waddell, W. (Martin Marietta Energy Systems Inc., Oak Ridge, TN (United States))

1993-01-01T23:59:59.000Z

20

Validation of Nuclear Criticality Safety Software and 27 energy group ENDF/B-IV cross sections  

SciTech Connect

The validation documented in this report is based on calculations that were executed during June through August 1992, and was completed in June 1993. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Martin Marietta Nuclear Criticality Safety Software. The first portion of the document outlines basic information in regard to validation of NCSS using ENDF/B-IV 27-group cross sections on the IBM 3090 at ORNL. A basic discussion of the NCSS system is provided, some discussion on the validation database and validation in general. Then follows a detailed description of the statistical analysis which was applied. The results of this validation indicate that the NCSS software may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant. When the validation results are treated as a single group, there is 95% confidence that 99.9% of future calculations of similar critical systems will have a calculated K{sub eff} > 0.9616. Based on this result the Portsmouth Nuclear Criticality Safety Department has adopted the calculational acceptance criteria that a k{sub eff} + 2{sigma} {le} 0.95 is safety subcritical. The validation of NCSS on the IBM 3090 at ORNL was extended to include NCSS on the IBM 3090 at K-25.

Lee, B.L. Jr.

1994-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Rockwell International's Nuclear Criticality Safety Program at the Rocky Flats Plant  

SciTech Connect

This paper describes the criticality safety program at the Rocky Flats Plant. The groups responsible for safety are named and their functions outlined. (JDH)

McCarthy, J.D.

1987-01-01T23:59:59.000Z

22

DOE-STD-1135-99 Guidance for Nuclear Criticality Safety Engineer Training and Qualification  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5-99 5-99 September 1999 DOE STANDARD GUIDANCE FOR NUCLEAR CRITICALITY SAFETY ENGINEER TRAINING AND QUALIFICATION U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-1135-99 iii FOREWORD This Department of Energy Standard is required for use by all DOE Contractor criticality safety personnel. It contains guidelines that should be followed for NCS training and qualification

23

BFS, a Legacy to the International Reactor Physics, Criticality Safety, and Nuclear Data Communities  

SciTech Connect

Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. Two Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA) activities, the International Criticality Safety Benchmark Evaluation Project (ICSBEP), initiated in 1992, and the International Reactor Physics Experiment Evaluation Project (IRPhEP), initiated in 2003, have been identifying existing integral experiment data, evaluating those data, and providing integral benchmark specifications for methods and data validation for nearly two decades. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. Data provided by these two projects will be of use to the international reactor physics, criticality safety, and nuclear data communities for future decades The Russian Federation has been a major contributor to both projects with the Institute of Physics and Power Engineering (IPPE) as the major contributor from the Russian Federation. Included in the benchmark specifications from the BFS facilities are 34 critical configurations from BFS-49, 61, 62, 73, 79, 81, 97, 99, and 101; spectral characteristics measurements from BFS-31, 42, 57, 59, 61, 62, 73, 97, 99, and 101; reactivity effects measurements from BFS-62-3A; reactivity coefficients and kinetics measurements from BFS-73; and reaction rate measurements from BFS-42, 61, 62, 73, 97, 99, and 101.

J. Blair Briggs; Anatoly Tsibulya; Yevgeniy Rozhikhin

2012-03-01T23:59:59.000Z

24

Privatization of the gaseous diffusion plants and impacts on nuclear criticality safety administration  

SciTech Connect

The Energy Policy Act of 1992 created the United States Enrichment Corporation (USEC) on July 1, 1993. The USEC is a government-owned business that leases those Gaseous Diffusion Plant (GDP) facilities at the Portsmouth, Ohio, and Paducah, Kentucky, sites from the U.S. Department of Energy (DOE) that are required for enriching uranium. Lockheed Martin Utility Services is the operating contractor for the USEC-leased facilities. The DOE has retained use of, and regulation over, some facilities and areas at the Portsmouth and Paducah sites for managing legacy wastes and environmental restoration activities. The USEC is regulated by the DOE, but is currently changing to regulation under the U.S. Nuclear Regulatory Commission (NRC). The USEC is also preparing for privatization of the uranium enrichment enterprise. These changes have significantly affected the nuclear criticality safety (NCS) programs at the sites.

D`Aquila, D.M.; Holliday, R.T. [Lockheed Martin Utility Services, Inc., Piketon, OH (United States); Dean, J.C. [Lockheed Martin Utility Services, Inc., Paducah, KY (United States)

1996-12-31T23:59:59.000Z

25

Submersion Criticality Safety Analysis of Tungsten-Based Fuel for Nuclear Power and Propulsion Applications  

SciTech Connect

The Center for Space Nuclear Research (CSNR) is developing tungsten-encapsulated fuels for space nuclear applications. Aims to develop NTP fuels that are; Affordable Low impact on production and testing environment Producible on a large scale over suitable time period Higher-performance compared to previous graphite NTP fuel elements Space nuclear reactors remain subcritical before and during launch, and do not go critical until required by its mission. A properly designed reactor will remain subcritical in any launch abort scenario, where the reactor falls back to Earth and becomes submerged in terrestrial material. Submersion increases neutron reflection and thermalizes the neutrons, which typically increases the reactivity of the core. This effect is usually very significant for fast-spectrum reactors. This research provided a submersion criticality safety analysis for a representative tungsten/uranium oxide fueled reactor. Determine the submersion behavior of a reactor fueled by tungsten-based fuel. Considered fuel compositions with varying: Rhenium content (wt% rhenium in tungsten) Fuel loading fractions (UO2 vol%)

A.E. Craft; R. C. O'Brien; S. D. Howe; J. C. King

2014-07-01T23:59:59.000Z

26

CRITICALITY SAFETY (CS)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Objective CS.1 - A criticality safety program is established, sufficient numbers of qualified personnel are provided, and adequate facilities and equipment are available to ensure criticality safety support services are adequate for safe operations. (Core Requirements 1, 2, and 6) Criteria * Functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented. * Operations support personnel for the criticality safety area are adequately staffed and trained. Approach Record Review: Review the documentation that establishes the Criticality Safety Requirements (CSRs) for appropriateness and completeness. Review for adequacy and completion the criticality safety personnel training records that indicate training on facility procedures and systems under

27

Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel  

SciTech Connect

Commercial used nuclear fuel (UNF) in the United States is expected to remain in storage for periods potentially greater than 40 years. Extended storage (ES) time and irradiation to high-burnup values (>45 GWd/t) may increase the potential for fuel failure during normal and accident conditions involving storage and transportation. Fuel failure, depending on the severity, could result in changes to the geometric configuration of the fuel, which has safety and regulatory implications. The likelihood and extent of fuel reconfiguration and its impact on the safety of the UNF is not well understood. The objective of this work is to assess and quantify the impact of fuel reconfiguration due to fuel failure on criticality safety of UNF in storage and transportation casks. Criticality analyses are conducted considering representative UNF designs covering a range of enrichments and burnups in multiple cask systems. Prior work developed a set of failed fuel configuration categories and specific configurations were evaluated to understand trends and quantify the consequences of worst-case potential reconfiguration progressions. These results will be summarized here and indicate that the potential impacts on subcriticality can be rather significant for certain configurations (e.g., >20% keff). It can be concluded that the consequences of credible fuel failure configurations from ES or transportation following ES are manageable (e.g., <5% keff). The current work expands on these efforts and examines some modified scenarios and modified approaches to investigate the effectiveness of some techniques for reducing the calculated increase in keff. The areas included here are more realistic modeling of some assembly types and the effect of reconfiguration of some assemblies in the storage and transportation canister.

Marshall, William BJ J [ORNL] [ORNL; Wagner, John C [ORNL] [ORNL

2013-01-01T23:59:59.000Z

28

Nuclear Criticality Safety Evaluation of the 9965, 9968, 9972, 9973, 9974, and 9975 Shipping Casks  

SciTech Connect

A Nuclear Criticality Safety Evaluation (NCSE) has been performed for the 9965, 9968, 9972, 9973, 9974, and 9975 SRS-designed shipping casks. This was done in support of the recertification effort for the 9965 and 9968, and the certification of the newly designed 9972-9975 series. The analysis supports the use of these packages as Fissile Class I for shipment of fissionable material from the SRS FB-Line, HB-Line, and from Lawrence Livermore national Laboratory. six different types of material were analyzed with varying Isotopic composition, of both oxide and metallic form. The mass limits required to support the fissile Class I rating for each of the envelopes are given in the Table below. These mass limits apply if DOE approves an exception as described in 10 CFR 71.55(c), such that water leakage into the primary containment vessel does not need to be considered in the criticality analysis. If this exception is not granted, the mass limits are lower than those shown below. this issue is discussed in detail in sections 5 and 6 of the report.One finding from this work is important enough to highlight in the abstract. The fire tests performed for this family of shipping casks indicates only minimal charring of the Celotex thermal insulation. Analysis of the casks with no Celotex insulation (assuming it has all burned away), results in values of k-eff that exceed 1.0. Therefore, the Celotex insulation must remain intact in order to guarantee sub criticality of the 9972-9975 family of shipping casks.

Frost, R.L.

1999-02-26T23:59:59.000Z

29

Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society  

SciTech Connect

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

Koponen, B.L.; Hampel, V.E.

1982-10-21T23:59:59.000Z

30

CRITICALITY SAFETY TRAINING AT FLUOR HANFORD (FH)  

SciTech Connect

The Fluor Hanford Criticality Safety engineers are extensively trained. The objectives and requirements for training are derived from Department of Energy (DOE) and American National Standards Institute/American Nuclear Society Standards (ANSI/ANS), and are captured in the Hanford Criticality Safety Program manual, HNF-7098. Qualification cards have been established for the general Criticality Safety Engineer (CSE) analyst, CSEs who support specific facilities, and for the facility Criticality Safety Representatives (CSRs). Refresher training and continuous education in the discipline are emphasized. Weekly Brown Bag Sessions keep the criticality safety engineers informed of the latest developments and historic perspectives.

TOFFER, H.

2005-05-02T23:59:59.000Z

31

Criticality safety aspects of decontamination and decommissioning at defense nuclear facilities  

SciTech Connect

Defense nuclear facilities have operated for forty years with a well-defined mission to produce weapons components for the nation. With the end of the cold war, the facilities` missions have changed to one of decontamination and decommissioning. Off-normal operations and use of new procedures, such as will exist during these activities, have often been among the causal factors in previous criticality accidents at process facilities. This paper explores the similarities in causal factors in previous criticality accidents to the conditions existing in current defense nuclear facilities undergoing the transition to decontamination and decommissioning. Practices to reduce the risk to workers, the public, and the environment are recommended.

Croucher, D.W.

1994-02-01T23:59:59.000Z

32

Nuclear Safety Regulatory Framework  

Energy Savers (EERE)

Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946...

33

Tank farms criticality safety manual  

SciTech Connect

This document defines the Tank Farms Contractor (TFC) criticality safety program, as required by Title 10 Code of Federal Regulations (CFR), Subpart 830.204(b)(6), ''Documented Safety Analysis'' (10 CFR 830.204 (b)(6)), and US Department of Energy (DOE) 0 420.1A, Facility Safety, Section 4.3, ''Criticality Safety.'' In addition, this document contains certain best management practices, adopted by TFC management based on successful Hanford Site facility practices. Requirements in this manual are based on the contractor requirements document (CRD) found in Attachment 2 of DOE 0 420.1A, Section 4.3, ''Nuclear Criticality Safety,'' and the cited revisions of applicable standards published jointly by the American National Standards Institute (ANSI) and the American Nuclear Society (ANS) as listed in Appendix A. As an informational device, requirements directly imposed by the CRD or ANSI/ANS Standards are shown in boldface. Requirements developed as best management practices through experience and maintained consistent with Hanford Site practice are shown in italics. Recommendations and explanatory material are provided in plain type.

FORT, L.A.

2003-03-27T23:59:59.000Z

34

Criticality safety considerations in the geologic disposal of spent nuclear fuel assemblies  

SciTech Connect

Features of geologic disposal which hamper the demonstration that criticality cannot occur therein include possible changes of shape and form, intrusion of water as a neutron moderator, and selective leaching of spent fuel constituents. If the criticality safety of spent fuel disposal depends on burnup, independent measurements verifying the burnup should be performed prior to disposal. The status of nondestructive analysis method which might provide such verification is discussed. Calculations were performed to assess the potential for increasing the allowed size of a spent fuel disposal canister if potential water intrusion were limited by close-packing the enclosed rods. Several factors were identified which severely limited the potential of this application. The theoretical limit of hexagonal close-packing cannot be achieved due to fuel rod bowing. It is concluded that disposal canisters should be sized on the basis of assumed optimum moderation. Several topics for additional research were identified during this limited study.

Gore, B.F.; McNair, G.W.; Heaberlin, S.W.

1980-05-01T23:59:59.000Z

35

Tank farm nuclear criticality review  

SciTech Connect

The technical basis for the nuclear criticality safety of stored wastes at the Hanford Site Tank Farm Complex was reviewed by a team of senior technical personnel whose expertise covered all appropriate aspects of fissile materials chemistry and physics. The team concluded that the detailed and documented nucleonics-related studies underlying the waste tanks criticality safety basis were sound. The team concluded that, under current plutonium inventories and operating conditions, a nuclear criticality accident is incredible in any of the Hanford single-shell tanks (SST), double-shell tanks (DST), or double-contained receiver tanks (DCRTS) on the Hanford Site.

Bratzel, D.R., Westinghouse Hanford

1996-09-11T23:59:59.000Z

36

Office of Nuclear Facility Safety Programs: Nuclear Facility Training  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety (HS-30) Safety (HS-30) Office of Nuclear Safety Home » Directives » Nuclear and Facility Safety Policy Rules » Nuclear Safety Workshops Technical Standards Program » Search » Approved Standards » Recently Approved » RevCom for TSP » Monthly Status Reports » Archive » Feedback DOE Nuclear Safety Research & Development Program Office of Nuclear Safety Basis & Facility Design (HS-31) Office of Nuclear Safety Basis & Facility Design - About Us » Nuclear Policy Technical Positions/Interpretations » Risk Assessment Working Group » Criticality Safety » DOE O 420.1C Facility Safety » Beyond Design Basis Events Office of Nuclear Facility Safety Programs (HS-32) Office of Nuclear Facility Safety Programs - About Us » Facility Representative Program

37

General Engineer (Nuclear Safety)  

Energy.gov (U.S. Department of Energy (DOE))

The Chief of Nuclear Safety (CNS) reports the US/M&P; in serving as the Central Technical Authority (CTA) for M&P; activities, ensuring the Departments nuclear safety policies and...

38

Nuclear Safety Regulatory Framework  

NLE Websites -- All DOE Office Websites (Extended Search)

Department of Energy Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946 Atomic Energy Act 1954 Energy Reorganization Act 1974 DOE Act 1977 Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural Rules ISMS-QA; Operating Experience; Metrics and Analysis Cross Cutting DOE Directives & Manuals DOE Standards Central Technical Authorities (CTA) Office of Health, Safety, and Security (HSS) Line Management SSO/ FAC Reps 48 CFR 970 48 CFR 952 Federal Acquisition Regulations External Oversight *Defense Nuclear Facility

39

Nuclear Explosive Safety Manual  

Directives, Delegations, and Requirements

This Manual provides supplemental details to support the requirements of DOE O 452.2D, Nuclear Explosive Safety.

2009-04-14T23:59:59.000Z

40

Criticality Safety Controls Implementation Inspection Criteria, Approach,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety Controls Implementation Inspection Criteria, Criticality Safety Controls Implementation Inspection Criteria, Approach, and Lines of Inquiry, October 23, 2009, (HSS CRAD 64-18, Rev 0 ) Criticality Safety Controls Implementation Inspection Criteria, Approach, and Lines of Inquiry, October 23, 2009, (HSS CRAD 64-18, Rev 0 ) DOE has set expectations for implementing criticality safety controls that are selected to provide preventive and/or mitigative functions for specific potential accident scenarios. There are additional expectations for criticality safety controls that are also designated as Specific Administrative Controls (SACs) (see HSS CRAD 64-32). Also, in instances when the review addresses functionality and operability of structures, systems, and components (SSCs) of nuclear facilities specifically required

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Nuclear Engineer (Nuclear Safety Specialist)  

Energy.gov (U.S. Department of Energy (DOE))

A successful candidate of this position will serve as a Nuclear Engineer (Nuclear Safety Specialist) responsible for day-to-day technical monitoring, and evaluation of aspects of authorization...

42

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

The Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs).

2014-07-10T23:59:59.000Z

43

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, or successor directive, for routine and planned nuclear explosive operations (NEOs).

2015-01-26T23:59:59.000Z

44

FAQS Reference Guide Criticality Safety  

Energy.gov (U.S. Department of Energy (DOE))

This reference guide addresses the competency statements in the April 2009 edition of DOE-STD-1173-2009, Criticality Safety Functional Area Qualification Standard.

45

The International Criticality Safety Benchmark Evaluation Project  

SciTech Connect

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the U.S. Department of Energy. The ICSBEP became an official activity of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Yugoslavia, Kazakhstan, Spain, and Israel are now participating. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled "International Handbook of Evaluated Criticality Safety Benchmark Experiments" (ICSBEP Handbook). The 2002 edition of the ICSBEP Handbook contains benchmark model specifications for 2881 critical or subcritical configurations that are intended for validating computer codes that calculate effective neutron multiplication and for testing basic nuclear data.

J. Blair Briggs

2003-09-01T23:59:59.000Z

46

Promulgating Nuclear Safety Requirements  

Directives, Delegations, and Requirements

Applies to all Nuclear Safety Requirements Adopted by the Department to Govern the Conduct of its Nuclear Activities. Cancels DOE P 410.1. Canceled by DOE N 251.85.

1996-05-15T23:59:59.000Z

47

Nuclear Facility Safety Basis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Basis Safety Basis FUNCTIONAL AREA GOAL: A fully compliant Nuclear Facility Safety Basis. Program is implemented and maintained across the site. REQUIREMENTS:  10 CFR 830 Subpart B Guidance:  DOE STD 3009  DOE STD 1104  DOE STD  DOE G 421.1-2 Implementation Guide For Use in Developing Documented Safety Analyses To Meet Subpart B Of 10 CFR 830  DOE G 423.1-1 Implementation Guide For Use In Developing Technical Safety Requirements  DOE G 424.1-1 Implementation Guide For Use In Addressing Unreviewed Safety Question Requirements Performance Objective 1: Contractor Program Documentation The site contractor has developed an up-to-date, comprehensive, compliant, documented nuclear facility safety basis and associated implementing mechanisms and procedures for all required nuclear facilities and activities (10 CFR

48

Nuclear criticality safety evaluation of {sup 233}U storage configurations using ENDF/B-V cross sections  

SciTech Connect

Uranium-233 is currently stored in various chemical and physical forms in the Radiochernical Processing Plant (building 3019) and the Molten Salt Reactor (MSR) Facility (building 7503) at Oak Ridge National Laboratory (ORNL). Criticality safety is an important concern that must be addressed in the storage of this fissile material for both normal and credible abnormal conditions. The purpose of the current work is to perform a criticality safety evaluation of the {sup 233}U inventory at ORNL using KENO V.a with ENDF/B-V cross sections.

Dunn, M.E.; Basoglu, B.; Bentley, C.L.; Goluoglu, S.; Haught, C.; Plaster, M.J.; Wilkinson, A.D.; Yamamoto, T.; Dodds, H.L. [Univ. of Tennessee, Knoxville, TN (United States)

1994-12-31T23:59:59.000Z

49

Criticality Safety Controls Implementation Inspection Criteria...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety Controls Implementation Inspection Criteria, Approach, and Lines of Inquiry, October 23, 2009, (HSS CRAD 64-18, Rev 0 ) Criticality Safety Controls...

50

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs). Cancels DOE O 452.2C. Admin Chg 1, dated 7-10-13, cancels DOE O 452.2D.

2009-04-14T23:59:59.000Z

51

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

This Order establishes requirements to implement the nuclear explosive safety elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations. Cancels DOE O 452.2C. Admin Chg 1, 7-10-13

2009-04-14T23:59:59.000Z

52

Surveillance Guide - NSS 18.1 Criticality Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CRITICALITY SAFETY CRITICALITY SAFETY 1.0 Objective The objective of this surveillance is to ensure that effective programs have been developed and implemented to protect the public and DOE's workers from unplanned criticality. The programs should minimize the potential for inadvertent criticality, provide appropriate training for personnel on criticality hazards and procedures for preventing inadvertent criticality, and provide appropriate systems to detect such criticalities and warn workers. The surveillance activities provide a basis for evaluating the effectiveness of policies, programs, and procedures and for reviewing compliance with specific DOE requirements. 2.0 References 2.1 DOE 5480.24, Nuclear Criticality Safety

53

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

The directive provides supplemental details to support the requirements of DOE O 452.2C, Nuclear Explosive Safety, dated 6-12-06. Canceled by DOE M 452.2-1A.

2006-06-12T23:59:59.000Z

54

Office of Nuclear Facility Safety Programs  

Energy.gov (U.S. Department of Energy (DOE))

The Office of Nuclear Facility Safety Programs establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities.

55

CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP  

SciTech Connect

With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5, Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified i

Kessler, S

2009-04-21T23:59:59.000Z

56

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

The directive establishes specific nuclear explosive safety (NES) program requirements to implement the DOE NES standards and other NES criteria for routine and planned nuclear explosive operations. Cancels DOE O 452.2B. Canceled by DOE O 452.2D.

2006-06-12T23:59:59.000Z

57

Nuclear Safety Workshop Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Workshop Summary Workshop Summary September 19-20, 2012 1 Nuclear Safety Workshop Summary On September 19-20, 2012, the U.S. Department of Energy (DOE) held a second Nuclear Safety Workshop covering the results of the Department's actions to improve its posture for analyzing and responding to severe accidents in light of lessons learned from the March 2011 nuclear accident in Japan. Sponsored by DOE and championed by Deputy Secretary of Energy Daniel Poneman, the two-day workshop discussed the lessons learned in a national and international context. The workshop's theme

58

CRAD, Nuclear Safety Delegations for Documented Safety Analysis...  

Office of Environmental Management (EM)

Nuclear Safety Delegations for Documented Safety Analysis Approval - January 8, 2015 (EA CRAD 31-09, Rev. 0) CRAD, Nuclear Safety Delegations for Documented Safety Analysis...

59

Nuclear Safety Management  

NLE Websites -- All DOE Office Websites (Extended Search)

[6450-01-P] [6450-01-P] DEPARTMENT OF ENERGY 10 CFR Part 830 Nuclear Safety Management AGENCY: Department of Energy (DOE). ACTION: Final Rule. SUMMARY: The Department of Energy (DOE) is issuing a final rule regarding Nuclear Safety Management. This Part establishes requirements for the safe management of DOE contractor and subcontractor work at the Department's nuclear facilities. Today's rule adopts the sections that will make up the generally applicable provisions for Part 830. It also adopts the specific section on provisions for developing and implementing a formalized quality assurance program. EFFECTIVE DATE: This regulation becomes effective [insert 30 days after publication in the Federal Register.] FOR FURTHER INFORMATION CONTACT: Frank Hawkins, U.S. Department of Energy, Nuclear Safety

60

Safety Lifecycle for Developing Safety Critical Artificial Neural Networks  

E-Print Network (OSTI)

Safety Lifecycle for Developing Safety Critical Artificial Neural Networks Zeshan Kurd, Tim Kelly. There are many techniques that aim to improve the performance of neural networks for safety-critical systems. Consequently, their role in safety-critical applications, if any, is typically restricted to advisory systems

Kelly, Tim

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the CHF and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the CHF is included in the Q-List (BSC 2005 [DIRS 171190], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

C.E. Sanders

2005-04-07T23:59:59.000Z

62

A nuclear criticality safety assessment of the loss of moderation control in 2 1/2 and 10-ton cylinders containing enriched UF{sub 6}  

SciTech Connect

Moderation control for maintaining nuclear criticality safety in 2 {1/2}-ton, 10-ton, and 14-ton cylinders containing enriched uranium hexafluoride (UF{sub 6}) has been used safely within the nuclear industry for over thirty years, and is dependent on cylinder integrity and containment. This assessment evaluates the loss of moderation control by the breaching of containment and entry of water into the cylinders. The first objective of this study was to estimate the required amounts of water entering these large UF{sub 6} cylinders to react with, and to moderate the uranium compounds sufficiently to cause criticality. Hypothetical accident situations were modeled as a uranyl fluoride (UO{sub 2}F{sub 2}) slab above a UF{sub 6} hemicylinder, and a UO{sub 2}F{sub 2} sphere centered within a UF{sub 6} hemicylinder. These situations were investigated by computational analyses utilizing the KENO V.a Monte Carlo Computer Code. The results were used to estimate both the masses of water required for criticality, and the limiting masses of water that could be considered safe. The second objective of the assessment was to calculate the time available for emergency control actions before a criticality would occur, i.e., a {open_quotes}safetime{close_quotes}, for various sources of water and different size openings in a breached cylinder. In the situations considered, except the case for a fire hose, the safetime appears adequate for emergency control actions. The assessment shows that current practices for handling moderation controlled cylinders of low enriched UF{sub 6}, along with the continuation of established personnel training programs, ensure nuclear criticality safety for routine and emergency operations.

Newvahner, R.L. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Pryor, W.A. [PAI Corp., Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

63

Nuclear Safety News | Department of Energy  

Office of Environmental Management (EM)

Nuclear Safety News Nuclear Safety News October 4, 2012 Department of Energy Cites Battelle Energy Alliance, LLC for Nuclear Safety and Radiation Protection Violations The U.S....

64

Nuclear Explosive Safety Manual  

Directives, Delegations, and Requirements

This Department of Energy (DOE) Manual provides supplemental details on selected topics to support the requirements of DOE O 452.2D, Nuclear Explosive Safety, dated 4/14/09. Cancels DOE M 452.2-1. Admin Chg 1, dated 7-10-13, cancels DOE M 452.2-1A.

2009-04-14T23:59:59.000Z

65

CRITICALITY SAFETY QUALIFICATION STANDARD REFERENCE GUIDE  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Criticality Safety Qualification Standard Reference Guide APRIL 2011 This page is intentionally blank. Table of Contents i FIGURES ...................................................................................................................................... iii PURPOSE ...................................................................................................................................... 1 SCOPE ........................................................................................................................................... 1 PREFACE ...................................................................................................................................... 1 ACKNOWLEDGEMENTS ......................................................................................................... 2

66

Nuclear Explosive Safety Evaluation Processes  

Directives, Delegations, and Requirements

This Manual provides supplemental details to support the nuclear explosive safety evaluation requirement of DOE O 452.2D, Nuclear Explosive Safety. Does not cancel other directives. Admin Chg 1, 7-10-13.

2009-04-14T23:59:59.000Z

67

Software Quality Assurance for Nuclear Safety Systems  

SciTech Connect

The US Department of Energy has undertaken an initiative to improve the quality of software used to design and operate their nuclear facilities across the United States. One aspect of this initiative is to revise or create new directives and guides associated with quality practices for the safety software in its nuclear facilities. Safety software includes the safety structures, systems, and components software and firmware, support software and design and analysis software used to ensure the safety of the facility. DOE nuclear facilities are unique when compared to commercial nuclear or other industrial activities in terms of the types and quantities of hazards that must be controlled to protect workers, public and the environment. Because of these differences, DOE must develop an approach to software quality assurance that ensures appropriate risk mitigation by developing a framework of requirements that accomplishes the following goals: {sm_bullet} Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe {sm_bullet} Considers the larger system that uses the software and its impacts {sm_bullet} Ensures that the software failures do not create unsafe conditions Software designers for nuclear systems and processes must reduce risks in software applications by incorporating processes that recognize, detect, and mitigate software failure in safety related systems. It must also ensure that fail safe modes and component testing are incorporated into software design. For nuclear facilities, the consideration of risk is not necessarily sufficient to ensure safety. Systematic evaluation, independent verification and system safety analysis must be considered for software design, implementation, and operation. The software industry primarily uses risk analysis to determine the appropriate level of rigor applied to software practices. This risk-based approach distinguishes safety-critical software and applies the highest level of rigor for those systems. DOE has further defined a risk approach to nuclear safety system software consistent with the analyses required for operation of nuclear facilities. This requires the grading of software in terms of safety class and safety significant structures, systems and components (SSCs). Safety-class SSCs are related to public safety where as safety-significant SSCs are identified for specific aspects of defense-in-depth and worker safety. Industry standards do not directly categorize nuclear safety software and DOE sites are not consistent in their approach to nuclear safety software quality assurance. DOE is establishing a more detailed graded approach for software associated with safety class and safety significant systems. This paper presents the process and results that DOE utilized to develop a detailed classification scheme for nuclear safety software.

Sparkman, D R; Lagdon, R

2004-05-16T23:59:59.000Z

68

CRITICALITY SAFETY QUALIFICATION STANDARD REFERENCE GUIDE  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9, 2010 Page 1 of 47 9, 2010 Page 1 of 47 Criticality Safety Qualification Standard Reference Guide 2010 For use with DOE-STD 1173-2009, CRITICALITY SAFETY FUNCTIONAL AREA QUALIFICATION STANDARD September 9, 2010 Page 2 of 47 PURPOSE....................................................................................................................... 5 SCOPE............................................................................................................................ 5 1. Criticality safety personnel must demonstrate a working-level knowledge of the fission process. .......................................................................................................... 6 2. Criticality safety personnel must demonstrate a working-level knowledge of the

69

CRAD, Criticality Safety Controls Implementation - May 31, 2013...  

Office of Environmental Management (EM)

Criticality Safety Controls Implementation - May 31, 2013 CRAD, Criticality Safety Controls Implementation - May 31, 2013 May 31, 2013 Criticality Safety Controls Implementation...

70

Enhancing nuclear power safety  

Science Journals Connector (OSTI)

Through its ClydeUnion Pumps brand, SPX has a long history of providing pumps to the nuclear power industry and is working to help provide solutions that enhance vital safety systems on these plants. Compared with traditional alternatives, its TWL steam turbine driven pump is designed to increase the reliability of systems that provide heat removal from pressurised water reactors and boiling water reactors during extended emergency periods.

2014-01-01T23:59:59.000Z

71

Applicability of ZPR critical experiment data to criticality safety  

SciTech Connect

More than a hundred zero power reactor (ZPR) critical assemblies were constructed, over a period of about three decades, at the Argonne National Laboratory ZPR-3, ZPR-6, ZPR-9 and ZPPR fast critical assembly facilities. To be sure, the original reason for performing these critical experiments was to support fast reactor development. Nevertheless, data from some of the assemblies are well suited to form the basis for valuable, new criticality safety benchmarks. The purpose of this paper is to describe the ZPR data that would be of benefit to the criticality safety community and to explain how these data could be developed into practical criticality safety benchmarks.

Schaefer, R.W.; Aumeier, S.E.; McFarlane, H.F.

1995-12-31T23:59:59.000Z

72

CRAD, Criticality Safety - Y-12 Enriched Uranium Operations Oxide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CRAD, Criticality Safety - Y-12 Enriched Uranium Operations Oxide CRAD, Criticality Safety - Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Criticality Safety - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a January 2005 assessment of the Criticality Safety program at the Y-12 - Enriched Uranium Facility. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Criticality Safety - Y-12 Enriched Uranium Operations Oxide Conversion Facility More Documents & Publications CRAD, DOE Oversight - Y-12 Enriched Uranium Operations Oxide Conversion

73

CRAD, Criticality Safety - Los Alamos National Laboratory TA 55 SST  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety - Los Alamos National Laboratory TA 55 SST Criticality Safety - Los Alamos National Laboratory TA 55 SST Facility CRAD, Criticality Safety - Los Alamos National Laboratory TA 55 SST Facility June 2005 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Criticality Safety program at the Los Alamos National Laboratory, TA 55 SST Facility. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Criticality Safety - Los Alamos National Laboratory TA 55 SST Facility More Documents & Publications CRAD, Configuration Management - Los Alamos National Laboratory TA 55 SST

74

CRAD, Criticality Safety - Idaho Accelerated Retrieval Project Phase II |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety - Idaho Accelerated Retrieval Project Criticality Safety - Idaho Accelerated Retrieval Project Phase II CRAD, Criticality Safety - Idaho Accelerated Retrieval Project Phase II February 2006 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2006 Commencement of Operations assessment of the Criticality Safety program at the Idaho National Laboratory, Idaho Accelerated Retrieval Project Phase II. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Criticality Safety - Idaho Accelerated Retrieval Project Phase II More Documents & Publications CRAD, Emergency Management - Idaho Accelerated Retrieval Project Phase II

75

In-Situ Radiological Surveys to Address Nuclear Criticality Safety Requirements During Remediation Activities at the Shallow Land Disposal Area, Armstrong County, Pennsylvania - 12268  

SciTech Connect

Cabrera Services Inc. (CABRERA) is the remedial contractor for the Shallow Land Disposal Area (SLDA) Site in Armstrong County Pennsylvania, a United States (US) Army Corps of Engineers - Buffalo District (USACE) contract. The remediation is being completed under the USACE's Formerly Utilized Sites Remedial Action Program (FUSRAP) which was established to identify, investigate, and clean up or control sites previously used by the Atomic Energy Commission (AEC) and its predecessor, the Manhattan Engineer District (MED). As part of the management of the FUSRAP, the USACE is overseeing investigation and remediation of radiological contamination at the SLDA Site in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), 42 US Code (USC), Section 9601 et. seq, as amended and, the National Oil and Hazardous Substance Pollution Contingency Plan (NCP), Title 40 of the Code of Federal Regulations (CFR) Section 300.430(f) (2). The objective of this project is to clean up radioactive waste at SLDA. The radioactive waste contains special nuclear material (SNM), primarily U-235, in 10 burial trenches, Cabrera duties include processing, packaging and transporting the waste to an offsite disposal facility in accordance with the selected remedial alternative as defined in the Final Record of Decision (USACE, 2007). Of particular importance during the remediation is the need to address nuclear criticality safety (NCS) controls for the safe exhumation and management of waste containing fissile materials. The partnership between Cabrera Services, Inc. and Measutronics Corporation led to the development of a valuable survey tool and operating procedure that are essential components of the SLDA Criticality Safety and Material Control and Accountability programs. Using proven existing technologies in the design and manufacture of the Mobile Survey Cart, the continued deployment of the Cart will allow for an efficient and reliable methodology to allow for the safe exhumation of the Special Nuclear Material in existing SLDA trenches. (authors)

Norris, Phillip; Mihalo, Mark; Eberlin, John; Lambert, Mike [Cabrera Services (United States); Matthews, Brian [Nuclear Safety Associates (United States)

2012-07-01T23:59:59.000Z

76

Facility Safety  

Directives, Delegations, and Requirements

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

1996-10-24T23:59:59.000Z

77

Facility Safety  

Directives, Delegations, and Requirements

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

1995-11-16T23:59:59.000Z

78

DOE-STD-3007-93 CN-1; DOE Standard Guidelines For Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7-93 7-93 November 1993 CHANGE NOTICE NO. 1 September 1998 DOE STANDARD GUIDELINES FOR PREPARING CRITICALITY SAFETY EVALUATIONS AT DEPARTMENT OF ENERGY NON-REACTOR NUCLEAR FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (423) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Order No. DE98003918 Change Notice No. 1 DOE-STD-3007-93 September 1998

79

CRAD, Facility Safety- Nuclear Facility Safety Basis  

Energy.gov (U.S. Department of Energy (DOE))

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis.

80

Nuclear Safety and Global Cooperation.  

E-Print Network (OSTI)

??The thesis of is to strengthen the capacity building of nuclear safety and disaster prevention all over the world from a preventive perspective, and to (more)

Chang, Yu-shan

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Safety Reports Series No. 11, Developing Safety Culture in Nuclear...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

in Nuclear Activities: Practical Suggestions to Assist Progress, International Atomic Energy Agency Safety Reports Series No. 11, Developing Safety Culture in Nuclear Activities:...

82

Office of Nuclear Safety - Directives  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear and Facility Safety Directives Nuclear and Facility Safety Directives The HSS Office of Nuclear Safety is the responsible office for the development, interpretation, and revision of the following Department of Energy (DOE) directives. Go to DOE's Directives Web Page to view these directives. DOE Order (O) 252.1A, Technical Standards Program DOE O 252.1A promotes DOE's use of Voluntary Consensus Standards (VCS) as the primary method for application of technical standards and establishes and manages the DOE Technical Standards Program (TSP) including technical standards development, information, activities, issues, and interactions. HS-30 Contact: Jeff Feit DOE Policy (P) 420.1, Department of Energy Nuclear Safety Policy DOE P 420.1, documents the Department's nuclear safety policy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment.

83

Office of Nuclear Safety Enforcement | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enforcement Office of Nuclear Safety Enforcement Office of Nuclear Safety Enforcement MISSION The Office of Nuclear Safety Enforcement implements the Department's nuclear safety...

84

Nuclear Safety Policy, Guidance & Reports | Department of Energy  

Office of Environmental Management (EM)

Nuclear Safety Policy, Guidance & Reports Nuclear Safety Policy, Guidance & Reports The Office of Nuclear Safety establishes and maintains nuclear safety policy, requirements, and...

85

Nuclear Reactor Safety Design Criteria  

Directives, Delegations, and Requirements

The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Certified 11-18-10.

1993-01-19T23:59:59.000Z

86

Nuclear Explosive Safety Evaluation Processes  

Directives, Delegations, and Requirements

This Manual provides supplemental details to support the nuclear explosive safety (NES) evaluation requirement of Department of Energy (DOE) Order (O) 452.2D, Nuclear Explosive Safety, dated 4/14/09. Admin Chg 1, dated 7-10-13, cancels DOE M 452.2-2.

2009-04-14T23:59:59.000Z

87

Office of Nuclear Safety and Environmental Assessments  

Energy.gov (U.S. Department of Energy (DOE))

The Office of Nuclear Safety and Environmental Assessments conducts assessments to provide critical feedback and objective information on programs and performance in protecting our workers, the public and environment from radiological hazards with a focus on hazardous nuclear facilities and operations. This information provides assurance to our stakeholders and identifies areas for improvement to our leadership to support the safe performance of the Departments mission.

88

Criticality Safety Functional Area Qualification Standard  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-1173-2009 April 2009 DOE STANDARD CRITICALITY SAFETY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1173-2009 ii This document is available on the Department of Energy Technical Standards Program Web Page at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1173-2009 iii APPROVAL The Federal Technical Capability Panel consists of senior U.S. Department of Energy (DOE) managers responsible for overseeing the Federal Technical Capability Program. This Panel is responsible for reviewing and approving the qualification standard for Department-wide

89

Nuclear safety | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

safety Subscribe to RSS - Nuclear safety Actions taken to prevent nuclear and radiation accidents or to limit their consequences. A farewell to arms? Scientists developing a novel...

90

Nuclear Safety Reporting Criteria | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reporting Criteria Nuclear Safety Reporting Criteria January 1, 2012 Nuclear Safety Noncompliances Associated With Occurrences (DOE Order 232.2) These tables provide the criteria...

91

Independent Activity Report, Defense Nuclear Facilities Safety...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October...

92

Nuclear Safety Regulatory Framework | Department of Energy  

Energy Savers (EERE)

Presentation that outlines the rules, policies and orders that comprise the Department of Energy Nuclear Safety Regulatory Framework. Nuclear Safety Regulatory Framework More...

93

Preservation and Dissemination of the Hardcopy Documentation Portion of the NCSP Nuclear Criticality Bibliographic Database  

SciTech Connect

The U.S. Department of Energy supports a nuclear criticality safety bibliographic internet database that contains approximately 15,000 records. We are working to ensure that a substantial portion of the corresponding hardcopy documents are preserved, digitized, and made available to criticality safety practitioners via the Nuclear Criticality Safety Program web site.

Koponen, B L; Heinrichs, D

2009-05-18T23:59:59.000Z

94

CRAD, Facility Safety - Nuclear Facility Safety Basis | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Facility Safety - Nuclear Facility Safety Basis More Documents & Publications CRAD, Facility Safety - Unreviewed Safety Question Requirements Site Visit Report, Livermore Site Office - February 2011 FAQS Job Task Analyses - Nuclear Safety Specialist

95

Criticality safety assessment of tank 241-C-106 remediation  

SciTech Connect

A criticality safety assessment was performed in support of Project 320 for the retrieval of waste from tank 241-C-106 to tank 241-AY-102. The assessment was performed by a multi-disciplined team consisting of expertise covering the range of nuclear engineering, plutonium and nuclear waste chemistry,and physical mixing hydraulics. Technical analysis was performed to evaluate the physical and chemical behavior of fissile material in neutralized Hanford waste as well as modeling of the fluid dynamics for the retrieval activity. The team has not found evidence of any credible mechanism to attain neutronic criticality in either tank and has concluded that a criticality accident is incredible.

Waltar, A.E., Westinghouse Hanford

1996-07-19T23:59:59.000Z

96

Criticality Safety Basics for INL FMHs and CSOs  

SciTech Connect

Nuclear power is a valuable and efficient energy alternative in our energy-intensive society. However, material that can generate nuclear power has properties that require this material be handled with caution. If improperly handled, a criticality accident could result, which could severely harm workers. This document is a modular self-study guide about Criticality Safety Principles. This guide's purpose it to help you work safely in areas where fissionable nuclear materials may be present, avoiding the severe radiological and programmatic impacts of a criticality accident. It is designed to stress the fundamental physical concepts behind criticality controls and the importance of criticality safety when handling fissionable materials outside nuclear reactors. This study guide was developed for fissionable-material-handler and criticality-safety-officer candidates to use with related web-based course 00INL189, BEA Criticality Safety Principles, and to help prepare for the course exams. These individuals must understand basic information presented here. This guide may also be useful to other Idaho National Laboratory personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. This guide also includes additional information that will not be included in 00INL189 tests. The additional information is in appendices and paragraphs with headings that begin with 'Did you know,' or with, 'Been there Done that'. Fissionable-material-handler and criticality-safety-officer candidates may review additional information at their own discretion. This guide is revised as needed to reflect program changes, user requests, and better information. Issued in 2006, Revision 0 established the basic text and integrated various programs from former contractors. Revision 1 incorporates operation and program changes implemented since 2006. It also incorporates suggestions, clarifications, and additional information from readers and from personnel who took course 00INL189. Revision 1 also completely reorganized the training to better emphasize physical concepts behind the criticality controls that fissionable material handlers and criticality safety officers must understand. The reorganization is based on and consistent with changes made to course 00INL189 due to a review of course exam results and to discussions with personnel who conduct area-specific training.

V. L. Putman

2012-04-01T23:59:59.000Z

97

CRAD, Criticality Safety- Idaho Accelerated Retrieval Project Phase II  

Energy.gov (U.S. Department of Energy (DOE))

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2006 Commencement of Operations assessment of the Criticality Safety program at the Idaho Accelerated Retrieval Project Phase II.

98

Criticality safety management during the new mission at Rocky Flats  

SciTech Connect

Under the cleanup and waste management missions at the former United States Department of Energy (DOE) production sites, a redirection of nuclear criticality safety programs has to take place to accommodate new objectives and reduced resources. The Rocky Flats Environmental Technology Site (RFETS) provides innovative approaches to respond to the needs of its new mission. The paper provides some background on the changes in the DOE complex and expands on the steps undertaken at RFETS with the hope that some of the novel approaches could be of use at other facilities. With the demise of the Cold War, the United States Department of Energy weapons complex has transitioned from the production of nuclear material to the disposition of weapons and cleanup of former production sites. Fissionable material in stored waste, contaminated facilities and equipment, and left over inventories presents nuclear criticality safety challenges that requires careful management.

Toffer, H.; Wilson, R.E. [Safe Sites of Colorado, Golden, CO (United States)

1996-12-31T23:59:59.000Z

99

An assessment of criticality safety at the Department of Energy Rocky Flats Plant, Golden, Colorado, July--September 1989  

SciTech Connect

This is a report on the 1989 independent Criticality Safety Assessment of the Rocky Flats Plant, primarily in response to public concerns that nuclear criticality accidents involving plutonium may have occurred at this nuclear weapon component fabrication and processing plant. The report evaluates environmental issues, fissile material storage practices, ventilation system problem areas, and criticality safety practices. While no evidence of a criticality accident was found, several recommendations are made for criticality safety improvements. 9 tabs.

Not Available

1989-09-01T23:59:59.000Z

100

Nuclear Safety: Software Quality Assurance  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety: Software Quality Assurance Nuclear Safety: Software Quality Assurance cd Welcome to the Department of Energy's Office of Health, Safety and Security (HSS) Software Quality Assurance (SQA) homepage. The purpose of this Web site is to promote continuous improvement and the sharing of knowledge of safety software quality assurance among interested parties across the DOE complex. It consolidates information and contains links to subject matter experts, procedures, training material, program descriptions, good practices, lessons learned and the Central Registry Toolbox Codes. The Portal also provides capabilities for member collaboration in product development and threaded discussions. Central Registry: The Central Registry provides a library of DOE "Toolbox" Codes covering site boundary accident dose consequences, fire accident source terms, leakpath factors, chemical release/dispersion and consequence, and radiological dispersion and consequence.

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

FAQS Qualification Card - Criticality Safety | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety Criticality Safety FAQS Qualification Card - Criticality Safety A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-CriticalitySafety.docx Description Criticality Safety Qualification Card More Documents & Publications FAQS Gap Analysis Qualification Card - Criticality Safety

102

Nuclear Safety Information | Department of Energy  

Office of Environmental Management (EM)

Safety Information Nuclear Safety Information Idaho National Laboratory's Advanced Test Reactor (ATR) | April 8, 2009 Idaho National Laboratory's Advanced Test Reactor (ATR) |...

103

Nuclear Energy Institute (NEI) Attachment, Integrated Safety...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Energy Institute (NEI) Attachment, Integrated Safety Analysis Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis This paper addresses why the use of an...

104

A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu Former Secretary of Energy The Blue Ribbon Commission on America's Nuclear Future was formed at the direction of the President to conduct a comprehensive review of polices for managing the back end of the nuclear fuel cycle. If we are going to ensure that the United States remains at the forefront of nuclear safety and security, non-proliferation, and nuclear energy technology we must develop an effective strategy and workable plan for the safe and secure management and disposal of used nuclear fuel and nuclear waste. That is why I asked General Scowcroft and Representative Hamilton to draw on their

105

Nuclear Safety (Pennsylvania) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety (Pennsylvania) Nuclear Safety (Pennsylvania) Nuclear Safety (Pennsylvania) < Back Eligibility Utility Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Program Info State Pennsylvania Program Type Environmental Regulations Safety and Operational Guidelines Provider Pennsylvania Department of Environmental Protection The Nuclear Safety Division conducts a comprehensive nuclear power plant oversight review program of the nine reactors at the five nuclear power sites in Pennsylvania. It also monitors the activities associated with management and disposal of a low-level radioactive waste disposal facility in Pennsylvania and provides planning and support for Bureau response to incidents involving nuclear power plants and/or radioactive material in

106

NRC - regulator of nuclear safety  

SciTech Connect

The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations.

NONE

1997-05-01T23:59:59.000Z

107

Safety of Nuclear Explosive Operations  

Directives, Delegations, and Requirements

This directive establishes responsibilities and requirements to ensure the safety of routine and planned nuclear explosive operations and associated activities and facilities. Cancels DOE O 452.2A and DOE G 452.2A-1A. Canceled by DOE O 452.2C.

2001-08-07T23:59:59.000Z

108

2012 Nuclear Safety Workshop | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety » 2012 Nuclear Safety Workshop Nuclear Safety » 2012 Nuclear Safety Workshop 2012 Nuclear Safety Workshop Glenn Podonsky 1 of 13 Glenn Podonsky Glenn Podonsky (DOE Chief Health, Safety and Security Officer) provides his welcoming remarks. Daniel Poneman 2 of 13 Daniel Poneman DOE Deputy Secretary Daniel Poneman discusses maintaining our focus on nuclear safety. Akira Kawano 3 of 13 Akira Kawano Akira Kawano, Tokyo Electric Power Company, provides lessons learned from the Fukushima nuclear accident. Bill Ostendorff 4 of 13 Bill Ostendorff NRC Commissioner Bill Ostendorff gives his perspective on the NRC's response to the Fukushima nuclear accident. Miroslav Lipar 5 of 13 Miroslav Lipar Miroslav Lipar, IAEA, provides an international perspective on the Fukushima nuclear accident. Dr. Sonja Haber 6 of 13

109

IDAHO STATE UNIVERSITY Chad Pope Department of Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

of nuclear safety, nuclear criticality safety, nuclear facility operations and pyroprocessing. He teaches courses in reactor physics, nuclear criticality safety, Monte Carlo...

110

Physics of nuclear reactor safety  

Science Journals Connector (OSTI)

Provides a concise review of the physical aspects of safety of nuclear fission reactors. It covers the developments of roughly the last decade. The introductory chapter contains an analysis of the changes in safety philosophy that are characteristic of the last decade and that have given rise to an increased importance of physical aspects because of the emphasis on passive or natural safety. The second chapter focuses on the basics of reactor safety, identifying the main risk sources and the main principles for a safe design. The third chapter concerns a systematic treatment of the physical processes that are fundamental for the properties of fission chain reacting processes and the control of those processes. Because of the rather specialized nature of the field of reactor physics, each paragraph contains a very concise description of the theory of the phenomenon under consideration, before presenting a review of the developments. Chapter 4 contains a short review of the thermal aspects of reactor safety, restricted to those aspects that are characteristic of the nuclear reactor field, because thermal hydraulics of fission reactors is not principally different from that of other physical systems. In chapter 5 the consequences of the physics treated in the preceding chapters for the dynamics and safety of actual reactors are reviewed. The systematics of the treatment is mainly based on a division of reactors into three categories according to the type of coolant, which to a large extent determines the safety properties of the reactors. The last chapter contains a physical analysis of the Chernobyl accident that occurred in 1986. The reason for an attempt to give a review of this accident, as complete as possible within the space limits set by the editors, is twofold: the Chernobyl accident is the most severe accident in history and physical properties of the reactor played a decisive role, thereby serving as an illustration of the material of the preceding chapters.

H van Dam

1992-01-01T23:59:59.000Z

111

Nuclear Safety Information Dashboard | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reporting » Analytical Dashboards » Nuclear Safety Reporting » Analytical Dashboards » Nuclear Safety Information Dashboard Nuclear Safety Information Dashboard The Nuclear Safety Information (NSI) Dashboard provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into ORPS. The NSI Dashboard displays information developed from occurrence information reported into DOE's ORPS database. Events or conditions associated with nuclear safety are reported into ORPS, assigned unique ORPS reporting criteria and used for trending. ORPS reporting criteria are assigned a weighted value to indicate their relative importance to nuclear safety; associated ORPS reporting criteria are combined in key groups and charted over time to index trends in nuclear

112

Criticality Safety Basics for INL Emergency Responders  

SciTech Connect

This document is a modular self-study guide about criticality safety principles for Idaho National Laboratory emergency responders. This guide provides basic criticality safety information for people who, in response to an emergency, might enter an area that contains much fissionable (or fissile) material. The information should help responders understand unique factors that might be important in responding to a criticality accident or in preventing a criticality accident while responding to a different emergency.

This study guide specifically supplements web-based training for firefighters (0INL1226) and includes information for other Idaho National Laboratory first responders. However, the guide audience also includes other first responders such as radiological control personnel.

For interested readers, this guide includes clearly marked additional information that will not be included on tests. The additional information includes historical examples (Been there. Done that.), as well as facts and more in-depth information (Did you know ).

INL criticality safety personnel revise this guide as needed to reflect program changes, user requests, and better information. Revision 0, issued May 2007, established the basic text. Revision 1 incorporates operation, program, and training changes implemented since 2007. Revision 1 increases focus on first responders because later responders are more likely to have more assistance and guidance from facility personnel and subject matter experts. Revision 1 also completely reorganized the training to better emphasize physical concepts behind the criticality controls that help keep emergency responders safe. The changes are based on and consistent with changes made to course 0INL1226.

Valerie L. Putman

2012-08-01T23:59:59.000Z

113

Derivation of criticality safety benchmarks from ZPR fast critical assemblies  

SciTech Connect

Scores of critical assemblies were constructed, over a period of about three decades, at the Argonne National Laboratory ZPR-3, ZPR-6, ZPR-9, and ZPPR fast critical assembly facilities. Most of the assemblies were mockups of various liquid-metal fast breeder reactor designs. These tended to be complex, containing, for example, mockups of control rods and control rod positions. Some assemblies, however, were `physics benchmarks`. These relatively `clean` assemblies had uniform compositions and simple geometry and were designed to test fast reactor physics data and methods. Assemblies in this last category are well suited to form the basis for new criticality safety benchmarks. The purpose of this paper is to present an overview of some of these benchmark candidates and to describe the strategy being used to create the benchmarks.

Schaefer, R.W.; McKnight, R.D.

1997-09-01T23:59:59.000Z

114

Chapter 30 - Nuclear Energy and Safety  

Science Journals Connector (OSTI)

Safety in nuclear industries is a very serious topic due to its greater accident consequence as seen in Chernobyl, and also due to the pictorial perceptions of nuclear accidents being similar to the Hiroshima and Nagasaki nuclear explosions. This chapter points out some important safety aspects of the nuclear industry. Beginning with the current laws and regulations of nuclear safety, this chapter reviews different types of nuclear reactors, nuclear waste treatment systems, reliability of nuclear system, operations of reactors, incident reporting, and a short review of previous accident history. Finally, historical Rasmussen reports are reviewed.

Sam Mannan

2014-01-01T23:59:59.000Z

115

The Office of Nuclear Energy Announces Central Europe Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

The Office of Nuclear Energy Announces Central Europe Nuclear The Office of Nuclear Energy Announces Central Europe Nuclear Safety Workshop in Prague The Office of Nuclear Energy Announces Central Europe Nuclear Safety Workshop in Prague October 3, 2011 - 2:04pm Addthis The Office of Nuclear Energy, in partnership with Czech Republic Ministry of Industry and Trade, Ministry of Foreign Affairs, the State Agency for Nuclear Safety of the Czech Republic, and Argonne National Laboratory, is conducting a regional Nuclear Safety Workshop on Trends in Nuclear Power Plant Safety for Robust Civil Nuclear Programs on Oct. 10-13, 2011 in Prague. U.S. Ambassador Norman Eisen and Department of Energy Assistant Secretary for Nuclear Energy Dr. Pete Lyons will deliver speeches welcoming participants. Representatives from the Czech Republic, Bulgaria, Lithuania,

116

Criticality Safety Controls Implementation, May 31, 2013 (HSS...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety Controls Implementation, May 31, 2013 (HSS CRAD 45-18, Rev. 1) Criticality Safety Controls Implementation, May 31, 2013 (HSS CRAD 45-18, Rev. 1) The Department...

117

TRANSPORTATION CASK RECEIPT/RETURN FACILITY CRITICALITY SAFETY EVALUATIONS  

SciTech Connect

The purpose of this design calculation is to demonstrate that the handling operations of transportation casks performed in the Transportation Cask Receipt and Return Facility (TCRRF) and Buffer Area meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC [Bechtel SAIC Company] 2004 [DIRS 171599], Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''Transportation Cask Receipt/Return Facility Description Document'' (BSC 2004 [DIRS 170217], Section 3.2.3). Specific scope of work contained in this activity consists of the following items: (1) Evaluate criticality effects for both dry and fully flooded conditions pertaining to TCRRF and Buffer Area operations for defense in depth. (2) Evaluate Category 1 and 2 event sequences for the TCRRF as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). This evaluation includes credible fuel reconfiguration conditions. In addition to the scope of work listed above, an evaluation was also performed of modeling assumptions for commercial spent nuclear fuel (CSNF) regarding inclusion of plenum and end regions of the active fuel. This calculation is limited to CSNF and US Department of Energy (DOE) SNF. it should be mentioned that the latter waste form is evaluated more in depth in the ''Canister Handling Facility Criticality Safety Calculations (BSC 2004 [DIRS 167614]). Further, the design and safety analyses of the naval SNF canisters are the responsibility of the US Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the TCRRF and Buffer Area and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the TCRRF is included in the Q-List (BSC 2004 [DIRS 168361], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

C.E. Sanders

2005-04-26T23:59:59.000Z

118

Nuclear safety information sharing agreement between NRC and...  

Office of Environmental Management (EM)

Nuclear safety information sharing agreement between NRC and DOE's Office of Environment, Health, Safety and Security Nuclear safety information sharing agreement between NRC and...

119

CRAD, New Nuclear Facility Documented Safety Analysis and Technical...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements - December 2, 2014 (EA CRAD 31-07, Rev. 0) CRAD, New Nuclear Facility Documented Safety Analysis...

120

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks  

SciTech Connect

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

ROGERS, C.A.

2000-02-17T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Impacts of criticality safety on hot fuel examination facility operations  

SciTech Connect

The Hot Fuel Examination Facility (HFEF) complex comprises four large hot cells. These cells are used to support the nation's nuclear energy program, especially the liquid-metal fast breeder reactor, by providing nondestructive and destructive testing of irradiated reactor fuels and furnishing the hot cell services required for operation of Experimental Breeder Reactor II (EBR-II). Because it is a research rather than a production facility, HFEF assignments are varied and change from time to time to meet the requirements of our experimenters. Such a variety of operations presents many challenges, especially for nuclear criticality safety. The following operations are reviewed to assure that accidental criticality is not possible, and that all rules and regulations are met: transportation, temporary storage, examinations, and disposition.

Garcia, A.S.; Courtney, J.C.; Bacca, J.P.

1985-11-01T23:59:59.000Z

122

Anomalies of Nuclear Criticality, Revision 6  

SciTech Connect

This report is revision 6 of the Anomalies of Nuclear Criticality. This report is required reading for the training of criticality professionals in many organizations both nationally and internationally. This report describes many different classes of nuclear criticality anomalies that are different than expected.

Clayton, E. D.; Prichard, Andrew W.; Durst, Bonita E.; Erickson, David; Puigh, Raymond J.

2010-02-19T23:59:59.000Z

123

Validation of Criticality Safety Calculations with SCALE 6.2  

SciTech Connect

SCALE 6.2 provides numerous updates in nuclear data, nuclear data processing, and computational tools utilized in the criticality safety calculational sequences relative to SCALE 6.1. A new 252-group ENDF/B-VII.0 multigroup neutron library, improved ENDF/B-VII.0 continuous energy data, as well as the previously deployed 238-group ENDF/B-VII.0 neutron library are included in SCALE 6.2 for criticality safety analysis. The performance of all three libraries for keff calculations is examined with a broad sampling of critical experiment models covering a range of fuels and moderators. Critical experiments from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE) that are available in the SCALE Verified, Archived Library of Inputs and Data (VALID) are used in this validation effort. Over 300 cases are used in the validation of KENO V.a, and a more limited set of approximately 50 configurations are used for KENO-VI validation. Additionally, some KENO V.a cases are converted to KENO-VI models so that an equivalent set of experiments can be used to validate both codes. For continuous-energy calculations, SCALE 6.2 provides improved performance relative to SCALE 6.1 in most areas with notable improvements in fuel pin lattice cases, particularly those with mixed oxide fuel. Multigroup calculations with the 252-group library also demonstrate improved performance for fuel lattices, uranium (high and intermediate enrichment) and plutonium metal experiments, and plutonium solution systems. Overall, SCALE 6.2 provides equivalent or smaller biases than SCALE 6.1, and the two versions of KENO provide similar results on the same suite of problems.

Marshall, William BJ J [ORNL] [ORNL; Wiarda, Dorothea [ORNL] [ORNL; Celik, Cihangir [ORNL] [ORNL; Rearden, Bradley T [ORNL] [ORNL

2013-01-01T23:59:59.000Z

124

A Safety Case Approach to Assuring Configurable Architectures of Safety-Critical Product Lines  

E-Print Network (OSTI)

A Safety Case Approach to Assuring Configurable Architectures of Safety-Critical Product Lines to the development of safety-critical systems. A product line offers large-scale reuse by exploiting common features the safety of architectural configurations and variation when developing product-line safety cases. We

Kelly, Tim

125

SCALE 6: Comprehensive Nuclear Safety Analysis Code System  

SciTech Connect

Version 6 of the Standardized Computer Analyses for Licensing Evaluation (SCALE) computer software system developed at Oak Ridge National Laboratory, released in February 2009, contains significant new capabilities and data for nuclear safety analysis and marks an important update for this software package, which is used worldwide. This paper highlights the capabilities of the SCALE system, including continuous-energy flux calculations for processing multigroup problem-dependent cross sections, ENDF/B-VII continuous-energy and multigroup nuclear cross-section data, continuous-energy Monte Carlo criticality safety calculations, Monte Carlo radiation shielding analyses with automated three-dimensional variance reduction techniques, one- and three-dimensional sensitivity and uncertainty analyses for criticality safety evaluations, two- and three-dimensional lattice physics depletion analyses, fast and accurate source terms and decay heat calculations, automated burnup credit analyses with loading curve search, and integrated three-dimensional criticality accident alarm system analyses using coupled Monte Carlo criticality and shielding calculations.

Bowman, Stephen M [ORNL

2011-01-01T23:59:59.000Z

126

Inherent safety concepts in nuclear power reactors  

Science Journals Connector (OSTI)

Different inherent safety concepts being considered in fast and thermal reactors are presented after outlining the basic goals of nuclear reactor safety, the defence in depth philosophy to achieve these goal...

O M Pal Singh; R Shankar Singh

1989-06-01T23:59:59.000Z

127

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

128

Nuclear Safety Research and Development Committee Charter  

Energy.gov (U.S. Department of Energy (DOE))

This Nuclear Safety Research & Development (NSR&D) Committee Charter provides the membership, roles, and responsibilities of the NSR&D Committee.

129

NUCLEAR SAFETY SPECIALIST QUALIFICATION STANDARD REFERENCE GUIDE  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Nuclear Safety Specialist Qualification Standard Reference Guide AUGUST 2008 This page is intentionally blank. i Table of Contents LIST OF FIGURES ..................................................................................................................... iv LIST OF TABLES ........................................................................................................................ v ACRONYMS ................................................................................................................................ vi PURPOSE...................................................................................................................................... 1 SCOPE ...........................................................................................................................................

130

Analysis of Fundamental NIST Sphere Experiments Related to Criticality Safety  

SciTech Connect

A series of neutron transport experiments was performed in 1989 and 1990 at NIST (National Institute of Standards and Technology) using a spherical stainless steel container and fission chambers. These experiments were performed to help understand errors observed in criticality calculations for arrays of individually subcritical components, particularly solution arrays [1-3]. They were supported by the U.S. Department of Energy, Environment and Health, Nuclear Criticality Technology and Safety Project. The intent was to evaluate the possibility that the criticality prediction errors stem from errors in the calculation of neutron leakage from individual components of the array. Thus, the explicit product of the experiments was the measurement of the leakage flux, as characterized by various Cd-shielded and unshielded fission rates. Because the various fission rates have different neutron-energy sensitivities, collectively they give an indication of the energy dependence of the leakage flux. Leakage and moderation were varied systematically through the use of different diameter spheres, with and without water. Some of these experiments with bare fission chambers have been evaluated by the International Criticality Safety Benchmark Evaluation Project (ICSBEP)[4].

Kim, Soon S.

2007-06-01T23:59:59.000Z

131

Identification of Integral Benchmarks for Nuclear Data Testing Using DICE (Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments)  

SciTech Connect

Typical users of the International Criticality Safety Evaluation Project (ICSBEP) Handbook have specific criteria to which they desire to find matching experiments. Depending on the application, those criteria may consist of any combination of physical or chemical characteristics and/or various neutronic parameters. The ICSBEP Handbook contains a structured format helping the user narrow the search for experiments of interest. However, with nearly 4300 different experimental configurations and the ever increasing addition of experimental data, the necessity to perform multiple criteria searches have rendered these features insufficient. As a result, a relational database was created with information extracted from the ICSBEP Handbook. A users interface was designed by OECD and DOE to allow the interrogation of this database. The database and the corresponding users interface are referred to as DICE. DICE currently offers the capability to perform multiple criteria searches that go beyond simple fuel, physical form and spectra and includes expanded general information, fuel form, moderator/coolant, neutron-absorbing material, cladding, reflector, separator, geometry, benchmark results, spectra, and neutron balance parameters. DICE also includes the capability to display graphical representations of neutron spectra, detailed neutron balance, sensitivity coefficients for capture, fission, elastic scattering, inelastic scattering, nu-bar and mu-bar, as well as several other features.

J. Blair Briggs; A. Nichole Ellis; Yolanda Rugama; Nicolas Soppera; Manuel Bossant

2011-08-01T23:59:59.000Z

132

Nuclear Safety Information Agreement Between the U.S. Nuclear...  

Office of Environmental Management (EM)

Operations (NRC)), Jim O'Brien, Director, Office of Nuclear Safety (EHSS DOE), Robert Johnson (Chief, Fuel Manufacturing Branch (NRC)) Front Row: Matt Moury, Associate Under...

133

Nuclear Explosive Safety Study Process  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3015-2001 3015-2001 February 2001 Superseding DOE-STD-3015-97 January 1997 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY PROCESS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-3015-2001 iii CONTENTS FOREWORD . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v 1. PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2. SCOPE . . . . . . . . . . . . . . . . . . . . . . .

134

The history of nuclear weapon safety devices  

SciTech Connect

The paper presents the history of safety devices used in nuclear weapons from the early days of separables to the latest advancements in MicroElectroMechanical Systems (MEMS). Although the paper focuses on devices, the principles of Enhanced Nuclear Detonation Safety implementation will also be presented.

Plummer, D.W.; Greenwood, W.H.

1998-06-01T23:59:59.000Z

135

CRAD, Criticality Safety Controls Implementation - May 31, 2013 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety Controls Implementation - May 31, 2013 Criticality Safety Controls Implementation - May 31, 2013 CRAD, Criticality Safety Controls Implementation - May 31, 2013 May 31, 2013 Criticality Safety Controls Implementation with DOE activities and sites (HSS CRAD 45-18) Within the Office of Health, Safety and Security (HSS), the Office of Enforcement and Overs ight, Office of Safety and Emergency Management Evaluations' (HS-45) mission is to assess the effectiveness of the environment, safety, health and emergency management systems and practices used by line and contractor organ izations in implementing Integrated Safety Management; and to provide clear, concise,and independent evaluations of performance in protecting our workers, the public, and the environment from the hazards associated with Department of Energy (DOE)

136

CRAD, Nuclear Safety Component - June 29, 2011 | Department of...  

Office of Environmental Management (EM)

CRAD, Nuclear Safety Component - June 29, 2011 CRAD, Nuclear Safety Component - June 29, 2011 June 29, 2011 Nuclear Safety Component and Services Procurement (HSS CRAD 45-12, Rev....

137

Documentation Integrity for Safety-Critical Applications: The COHERE Project  

E-Print Network (OSTI)

. Keywords Authoring interface, documentation integrity, consistency 1. INTRODUCTION This paper reportsDocumentation Integrity for Safety-Critical Applications: The COHERE Project David G. Novick-critical systems. Following a set of documentation integrity maxims, the project developed two generations

Novick, David G.

138

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of...

139

Nuclear Safety Enforcement Letter issued to Sandia Corporation...  

Energy Savers (EERE)

Nuclear Safety Enforcement Letter issued to Sandia Corporation Nuclear Safety Enforcement Letter issued to Sandia Corporation 9222014 Enforcement Letter, Sandia Corporation,...

140

Summary Pamphlet, Nuclear Safety at the Department of Energy...  

Office of Environmental Management (EM)

Summary Pamphlet, Nuclear Safety at the Department of Energy Summary Pamphlet, Nuclear Safety at the Department of Energy September 2010 This pamphlet is developed as part of the...

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Nuclear Safety Research and Development Program Operating Plan...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Operating Plan Nuclear Safety Research and Development Program Operating Plan July 5, 2012 Nuclear Safety Research and Development Program Operating Plan This operating...

142

Nuclear Safety Research and Development Annual Report, December...  

NLE Websites -- All DOE Office Websites (Extended Search)

Research and Development Annual Report, December 2014 Nuclear Safety Research and Development Annual Report, December 2014 December 8, 2014 - 1:22pm Addthis Nuclear Safety Research...

143

Comparison of radiation safety and nuclear explosive safety disciplines  

SciTech Connect

In August 1945, U.S. Navy Captain William Parsons served as the weaponeer aboard the Enola Gay for the mission to Hiroshima (Shelton 1988). In view of the fact that four B-29s had crashed and burned on takeoff from Tinian the night before, Captain Parsons made the decision to arm the gun-type weapon after takeoff for safety reasons (15 kilotons of TNT equivalent). Although he had no control over the success of the takeoff, he could prevent the possibility of a nuclear detonation on Tinian by controlling what we now call the nuclear explosive. As head of the Ordnance Division at Los Alamos and a former gunnery officer, Captain Parsons clearly understood the role of safety in his work. The advent of the pre-assembled implosion weapon where the high explosive and nuclear materials are always in an intimate configuration meant that nuclear explosive safety became a reality at a certain point in development and production not just at the time of delivery by the military. This is the only industry where nuclear materials are intentionally put in contact with high explosives. The agency of the U.S. Government responsible for development and production of U.S. nuclear weapons is the Department of Energy (DOE) (and its predecessor agencies). This paper will be limited to nuclear explosive safety as it is currently practiced within the DOE nuclear weapons

Winstanley, J. L.

1998-10-10T23:59:59.000Z

144

COG - Special Features of Interest to Criticality Safety Practitioners  

SciTech Connect

COG is a modern, general-purpose, high fidelity, multi-particle transport code developed at the Lawrence Livermore National Laboratory specifically for use in deep penetration (shielding) and criticality safety calculations. This paper describes some features in COG of special interest to criticality safety practitioners.

Buck, R M; Heinrichs, D P; Krass, A W; Lent, E M

2010-01-14T23:59:59.000Z

145

The Activities of the International Criticality Safety Benchmark Evaluation Project (ICSBEP)  

SciTech Connect

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the United States Department of Energy. The ICSBEP became an official activity of the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA) in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Yugoslavia, Kazakhstan, Spain, and Israel are now participating. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled International Handbook of Evaluated Criticality Safety Benchmark Experiments. The 2001 Edition of the Handbook contains benchmark specifications for 2642 critical or subcritical configurations that are intended for use in validation efforts and for testing basic nuclear data.

Briggs, Joseph Blair

2001-10-01T23:59:59.000Z

146

Neutron absorbing coating for nuclear criticality control  

DOE Patents (OSTI)

A neutron absorbing coating for use on a substrate, and which provides nuclear criticality control is described and which includes a nickel, chromium, molybdenum, and gadolinium alloy having less than about 5% boron, by weight.

Mizia, Ronald E. (Idaho Falls, ID); Wright, Richard N. (Idaho Falls, ID); Swank, William D. (Idaho Falls, ID); Lister, Tedd E. (Idaho Falls, ID); Pinhero, Patrick J. (Idaho Falls, ID)

2007-10-23T23:59:59.000Z

147

Criticality Safety Evaluation of Hanford Tank Farms Facility  

SciTech Connect

Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste.

WEISS, E.V.

2000-12-15T23:59:59.000Z

148

Nuclear Safety Workshop Summary | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Workshop Summary Workshop Summary Nuclear Safety Workshop Summary September 19-20, 2012 Nuclear Safety Workshop Summary On September 19-20, 2012, the U.S. Department of Energy (DOE) held a second Nuclear Safety Workshop covering the results of the Department's actions to improve its posture for analyzing and responding to severe accidents in light of lessons learned from the March 2011 nuclear accident in Japan. Sponsored by DOE and championed by Deputy Secretary of Energy Daniel Poneman, the two-day workshop discussed the lessons learned in a national and international context. The workshop's theme was Post Fukushima Initiatives and Results, and included technical breakout sessions focused on beyond design basis events (BDBEs) analysis and response, safety culture, and risk assessment and management.

149

Code of Federal Regulations NUCLEAR SAFETY MANAGEMENT  

Energy.gov (U.S. Department of Energy (DOE))

This part governs the conduct of DOE contractors, DOE personnel, and other persons conducting activities (including providing items and services) that affect, or may affect, the safety of DOE nuclear facilities.

150

FAQS Reference Guide Nuclear Safety Specialist  

Energy.gov (U.S. Department of Energy (DOE))

This reference guide has been developed to address the competency statements in the November 2007 edition of DOE Standard DOE-STD-1183-2007, Nuclear Safety Specialist Functional Area Qualification Standard.

151

Nuclear Safety Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2001 Issued to CH2M Hill Hanford Group, Inc., related to Nuclear Safety Management at the Hanford Site Tank Farms March 19, 2001 Preliminary Notice of Violation, BNFL, Inc -...

152

Nuclear waste plans enter critical phase  

Science Journals Connector (OSTI)

... London. Britain's newly privatized nuclear power industry is facing a critical few months as it contemplates how to dispose of ... as it contemplates how to dispose of up to 300,000 cubic metres of radioactive waste by early next century " and answer critics who claim that its plans are ...

Ehsan Masood

1996-10-31T23:59:59.000Z

153

Nuclear-waste programme criticized by scientists  

Science Journals Connector (OSTI)

... The report underscores many of the criticisms that have been levelled at the Global Nuclear Energy Partnership since it was unveiled by the White House in 2006, namely that ... . The US Department of Energy (DOE) is seeking $405 million for the Global Nuclear Energy Partnership for the 2008 fiscal year, but key Democrats have vowed to put ...

2007-10-31T23:59:59.000Z

154

FAQS Qualification Card - Nuclear Safety Specialist | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety Specialist Nuclear Safety Specialist FAQS Qualification Card - Nuclear Safety Specialist A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NuclearSafetySpecialist-2007.docx Description Nuclear Safety Specialist Qualification Card - 2007 FAQC-NuclearSafetySpecialist-2004.docx

155

Nuclear and Facility Safety Policy Rules | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear and Facility Safety Policy Rules Nuclear and Facility Safety Policy Rules DOE provides safety requirements and guidance in a number of forms. One form in which we publish...

156

Nuclear Safety Research and Development (NSR&D) Program | Department...  

Office of Environmental Management (EM)

Safety Research and Development (NSR&D) Program Nuclear Safety Research and Development (NSR&D) Program The Nuclear Safety Research and Development (NSR&D) Program is managed by...

157

Criticality Safety Validation of SCALE 6.1 with ENDF/B-VII.0 Libraries  

SciTech Connect

ANSI/ANS-8.1-1998;2007, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, and ANSI/ANS-8.24-2007, Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations, require validation of a computer code and the associated data through benchmark evaluations based on physical experiments. The performance of the code and data are validated by comparing the calculated and the benchmark results. A SCALE procedure has been established to generate a Verified, Archived Library of Inputs and Data (VALID). This procedure provides a framework for preparing, peer reviewing, and controlling models and data sets derived from benchmark definitions so that the models and data can be used with confidence. The procedure ensures that the models and data were correctly generated using appropriate references with documented checks and reviews. Configuration management is implemented to prevent inadvertent modification of the models and data or inclusion of models that have not been subjected to the rigorous review process. VALID entries for criticality safety are based on critical experiments documented in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE). The findings of a criticality safety validation of SCALE 6.1 utilizing the benchmark models vetted in the VALID library at Oak Ridge National Laboratory are summarized here.

Marshall, William BJ J [ORNL] [ORNL; Rearden, Bradley T [ORNL] [ORNL

2012-01-01T23:59:59.000Z

158

Nuclear Explosive Safety Study Functional Area Qualification Standard  

Directives, Delegations, and Requirements

A Nuclear Explosive Safety Study (NESS) is performed on all DOE Nuclear Explosive Operations (NEOs) in accordance with DOE O 452.1D, Nuclear Explosive and Weapon Surety Program; DOE O 452.2D, Nuclear Explosive Safety; and DOE M 452.2-2, Nuclear Explosive Safety Evaluation Processes.

2010-05-27T23:59:59.000Z

159

Nuclear Safety Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enforcement » Nuclear Safety Enforcement Documents Enforcement » Nuclear Safety Enforcement Documents Nuclear Safety Enforcement Documents Documents Available for Download July 22, 2013 Enforcement Letter, NEL-2013-03 Issued to Lawrence Livermore National Security, LLC related to Programmatic Deficiencies in the Software Quality Assurance Program at the Lawrence Livermore National Laboratory February 12, 2013 Enforcement Letter, NEL-2013-02 Issued to Los Alamos National Security, LLC related to a Radiological Contamination Event at the Los Alamos Neutron Science Center at Los Alamos National Laboratory January 7, 2013 Enforcement Letter, NEL-2013-01 Issued to B&W Pantex, LLC related to the Conduct of Nuclear Explosive Operations at the Pantex Plant October 23, 2012 Enforcement Letter, Controlled Power Company - WEL-2012-02

160

Office of Nuclear Safety Basis and Facility Design  

Energy.gov (U.S. Department of Energy (DOE))

The Office of Nuclear Safety Basis & Facility Design establishes safety basis and facility design requirements and expectations related to analysis and design of nuclear facilities to ensure protection of workers and the public from the hazards associated with nuclear operations.

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

CRAD, Criticality Safety- Los Alamos National Laboratory TA 55 SST Facility  

Energy.gov (U.S. Department of Energy (DOE))

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Criticality Safety program at the Los Alamos National Laboratory, TA 55 SST Facility.

162

CRAD, Criticality Safety- Y-12 Enriched Uranium Operations Oxide Conversion Facility  

Energy.gov (U.S. Department of Energy (DOE))

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a January 2005 assessment of the Criticality Safety program at the Y-12 - Enriched Uranium Facility.

163

Fault tree synthesis for software design analysis of PLC based safety-critical systems  

SciTech Connect

As a software verification and validation should be performed for the development of PLC based safety-critical systems, a software safety analysis is also considered in line with entire software life cycle. In this paper, we propose a technique of software safety analysis in the design phase. Among various software hazard analysis techniques, fault tree analysis is most widely used for the safety analysis of nuclear power plant systems. Fault tree analysis also has the most intuitive notation and makes both qualitative and quantitative analyses possible. To analyze the design phase more effectively, we propose a technique of fault tree synthesis, along with a universal fault tree template for the architecture modules of nuclear software. Consequently, we can analyze the safety of software on the basis of fault tree synthesis. (authors)

Koo, S. R.; Cho, C. H. [Corporate R and D Inst., Doosan Heavy Industries and Construction Co., Ltd., 39-3, Seongbok-Dong, Yongin-Si, Gyeonggi-Do 449-795 (Korea, Republic of); Seong, P. H. [Dept. of Nuclear and Quantum Engineering, Korea Advanced Inst. of Science and Technology, 373-3 Guseong-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)

2006-07-01T23:59:59.000Z

164

Nuclear Safety Research and Development Annual Report, December 2014  

Energy.gov (U.S. Department of Energy (DOE))

This document is the first annual report of DOEs Nuclear Safety Research and Development (NSR&D) Program, managed by the Office of Nuclear Safety in the Office of Environment, Health, Safety and Security. The report includes a description of the program and summaries of R&D projects related to DOE (including NNSA) nuclear facility and operational safety.

165

2012 Nuclear Safety Workshop Presentations | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2012 Nuclear Safety Workshop Presentations 2012 Nuclear Safety Workshop Presentations 2012 Nuclear Safety Workshop Presentations Wednesday, September 19 - Plenary Session September 19, 2012 Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company September 19, 2012 A Commissioner's Perspective on USNRC Actions in Response to the Fukushima Nuclear Accident Presenter: Honorable William C. Ostendorff, Commissioner US Nuclear Regulatory Commission September 19, 2012 International Perspective on Fukushima Accident Presenter: Miroslav Lipár, Head, Operational Safety Section, Department of

166

FAQS Qualification Card - Nuclear Explosive Safety Study | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Explosive Safety Study Nuclear Explosive Safety Study FAQS Qualification Card - Nuclear Explosive Safety Study A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NuclearExplosiveSafetyStudy.docx Description Nuclear Explosive Safety Study Qualification Card More Documents & Publications

167

DOE's Approach to Nuclear Facility Safety Analysis and Management  

Energy.gov (U.S. Department of Energy (DOE))

Presenter: Dr. James O'Brien, Director, Office of Nuclear Safety, Office of Health, Safety and Security, US Department of Energy

168

Civil liberties and the nuclear critics  

Science Journals Connector (OSTI)

... page 774) has written a thoughtful and stimulating article on the alleged threat to civil liberties presented by an extended nuclear power programme. Unlike many (even most) critics of ... At what point would these methods become an "impact . . . . on civil liberties"? If kidnappings start? Or assassinations? This is by no means a rhetorical question ...

J. F. CRAWFORD

1980-01-31T23:59:59.000Z

169

Chapter 6 - Nuclear-Powered Payload Safety  

Science Journals Connector (OSTI)

Abstract This chapter introduces the concepts of Space Nuclear Power Systems (SNPSs), describes the history and nature of these ingenious energy-generating machines. The basic principles of the Radioisotope Thermoelectric Generator (RTG) and the recently developed Stirling Radioisotope Generator (SRG) are explored and an account of their application in several extra-terrestrial missions is presented. Nuclear fission power as a promising alternative for future outer planet and extra-solar explorations is discussed. The flight safety review and launch approval processes for U.S., as well as the failures and accidents for U.S. and U.S.S.R. (Russian) nuclear powered space missions since 1961 are presented chronologically. A comprehensive probabilistic consequence analysis of all conceivable potential hazards associated with nuclear powered space flights is set out. The chapter concludes with how \\{SNPSs\\} must be designed with the built-in safety features to minimize accidents and to prevent radiation exposure.

Firooz A. Allahdadi; Sayavur I. Bakhtiyarov; Gregory D. Wyss; Gary F. Polansky; Joseph A. Sholtis; Curt D. Botts

2013-01-01T23:59:59.000Z

170

June 2010, Risk Assessment in Support of DOE Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Office of Nuclear Safety Policy and Assistance Office of Nuclear Safety Policy and Assistance Nuclear Safety, Quality Assurance and Environment Information Notice June 2010 1 BACKGROUND & PURPOSE: On August 12, 2009, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 2009-1, Risk Assessment Methodologies at Defense Nuclear Facilities. This recommendation focused on the need for clear direction on use of quantitative risk assessments in nuclear safety applications at defense nuclear facilities. The Department of Energy (DOE) is presently analyzing directives, standards, training, and other tools that may support more effective development and use of

171

Nuclear safety lies in greater transparency  

Science Journals Connector (OSTI)

... Chinas nuclear expansion relies on generation III reactors, such as the Westinghouse AP1000 and the Areva European Pressurized Reactor (EPR). The industry promises that these models ... work and cost-cutting often flourish, will sacrifice safety for speed. To date, the AP1000 reactors in the Zhejiang and Shandong provinces are the only commercial units worldwide. Of ...

Qiang Wang

2013-02-26T23:59:59.000Z

172

SAFETY AND RELIABILITY ANALYSIS OF NUCLEAR REACTORS  

Science Journals Connector (OSTI)

Abstract A survey of the various aspects of safety and reliability analysis of nuclear reactors is presented with particular emphasis on the interrelation between structural reliability and systems reliability. In reactor design this interrelation is of overriding importance since it is the task of the control, protective and containment systems to protect the mechanical system and the structure from accidental overloading.

T.A. JAEGER

1972-01-01T23:59:59.000Z

173

Management of National Nuclear Power Programs for assured safety  

SciTech Connect

Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

Connolly, T.J. (ed.)

1985-01-01T23:59:59.000Z

174

Nuclear Safety Research and Development Status Workshop Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NSR&D STATUS WORKSHOP SUMMARIES Caroline Garzon Chief of Nuclear Safety Staff NUCLEAR SAFETY R&D Perform a peer review of Risk Assessment Corporation WTP analysis by a team and...

175

DOE Cites Fluor Fernald Inc. for Nuclear Safety Violations |...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

DOE Cites Fluor Fernald Inc. for Nuclear Safety Violations DOE Cites Fluor Fernald Inc. for Nuclear Safety Violations August 25, 2005 - 2:43pm Addthis Washington, D.C. - The...

176

Nuclear Safety Research and Development Annual Report, December...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

This document is the first annual report of DOE's Nuclear Safety Research and Development (NSR&D) Program, managed by the Office of Nuclear Safety in the Office of Environment,...

177

Nuclear Safety Research and Development Committee Charter  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Research and Development Committee Charter Research and Development Committee Charter I. Purpose The intent of the Nuclear Safety Research and Development (NSR&D) Committee is to identify nuclear safety research needs and opportunities within the Department of Energy (DOE) and National Nuclear Security Administration (NNSA) and their program offices. The Committee promotes communication and coordination among DOE and NNSA program offices to enhance synergy on NSR&D efforts that can benefit the Department. The Committee will foster and facilitate networking and information exchange on NSR&D needs and activities across DOE/NNSA programs and with external national and international organizations. The Committee should not be construed to have any authority to direct DOE and/or NNSA program

178

Safety of Decommissioning of Nuclear Facilities  

SciTech Connect

Full text of publication follows: ensuring safety during all stages of facility life cycle is a widely recognised responsibility of the operators, implemented under the supervision of the regulatory body and other competent authorities. As the majority of the facilities worldwide are still in operation or shutdown, there is no substantial experience in decommissioning and evaluation of safety during decommissioning in majority of Member States. The need for cooperation and exchange of experience and good practices on ensuring and evaluating safety of decommissioning was one of the outcomes of the Berlin conference in 2002. On this basis during the last three years IAEA initiated a number of international projects that can assist countries, in particular small countries with limited resources. The main IAEA international projects addressing safety during decommissioning are: (i) DeSa Project on Evaluation and Demonstration of Safety during Decommissioning; (ii) R{sup 2}D{sup 2}P project on Research Reactors Decommissioning Demonstration Project; and (iii) Project on Evaluation and Decommissioning of Former Facilities that used Radioactive Material in Iraq. This paper focuses on the DeSa Project activities on (i) development of a harmonised methodology for safety assessment for decommissioning; (ii) development of a procedure for review of safety assessments; (iii) development of recommendations on application of the graded approach to the performance and review of safety assessments; and (iv) application of the methodology and procedure to the selected real facilities with different complexities and hazard potentials (a nuclear power plant, a research reactor and a nuclear laboratory). The paper also outlines the DeSa Project outcomes and planned follow-up activities. It also summarises the main objectives and activities of the Iraq Project and introduces the R{sup 2}D{sup 2} Project, which is a subject of a complementary paper.

Batandjieva, B.; Warnecke, E.; Coates, R. [International Atomic Energy Agency, Vienna (Austria)

2008-01-15T23:59:59.000Z

179

Central Technical Authority Responsibilities Regarding Nuclear Safety Requirements  

Directives, Delegations, and Requirements

The order establishes Central Technical Authority and Chief of Nuclear Safety/Chief of Defense Nuclear Safety responsibilities and requirements directed by the Secretary of Energy in the development and issuance of Department of Energy regulations and directives that affect nuclear safety. No cancellations.

2007-08-28T23:59:59.000Z

180

Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety  

Directives, Delegations, and Requirements

This Guide provides guidance on the application of requirements for nonreactor nuclear facilities and explosives facilities of Department of Energy (DOE) O 420.1, Facility Safety, Section 4.1, Nuclear and Explosives Safety Design Criteria. No cancellation.

2000-03-28T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Nuclear and Facility Safety Directives | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety » Nuclear and Facility Safety Nuclear Safety » Nuclear and Facility Safety Directives Nuclear and Facility Safety Directives DOE Order (O) 252.1A, Technical Standards Program DOE O 252.1A promotes DOE's use of Voluntary Consensus Standards (VCS) as the primary method for application of technical standards and establishes and manages the DOE Technical Standards Program (TSP) including technical standards development, information, activities, issues, and interactions. HS-30 Contact: Jeff Feit DOE Policy (P) 420.1, Department of Energy Nuclear Safety Policy DOE P 420.1, documents the Department's nuclear safety policy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment. HS-30 Contact: James O'Brien

182

The development of regulatory expectations for computer-based safety systems for the UK nuclear programme  

SciTech Connect

The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

2006-07-01T23:59:59.000Z

183

Critical Nuclear Charges for N-Electron Atoms  

E-Print Network (OSTI)

Critical Nuclear Charges for N-Electron Atoms ALEXEI V. SERGEEV, SABRE KAIS Department of Chemistry is proposed to describe the motion of a loosely bound electron in a multielectron atom when the nuclear charge, which is treated as a continuous parameter, approaches its critical value. The critical nuclear charge

Kais, Sabre

184

Nuclear Safety Specialist Functional Area Qualification Standard  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

83-2007 83-2007 November 2007 DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1183-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1183-2007 iv INTENTIONALLY BLANK DOE-STD-1183-2007 v TABLE OF CONTENTS ACKNOWLEDGMENT ................................................................................................................ vii PURPOSE ....................................................................................................................................9

185

Double-clad nuclear fuel safety rod  

DOE Patents (OSTI)

A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

McCarthy, William H. (Los Altos, CA); Atcheson, Donald B. (Cupertino, CA); Vaidyanathan, Swaminathan (San Jose, CA)

1984-01-01T23:59:59.000Z

186

DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety and Ecology Corp. for Violating Nuclear Safety Safety and Ecology Corp. for Violating Nuclear Safety Rules DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules June 14, 2005 - 4:53pm Addthis WASHINGTON, D.C. -- The Department of Energy (DOE) today notified Safety and Ecology Corporation, the contractor responsible for radiological safety at the Portsmouth Gaseous Diffusion Project in Portsmouth, Ohio, that it will fine the company $55,000 for violating the department's regulations prohibiting retaliation against employees who raise nuclear safety concerns. "We take safety very seriously at the Department of Energy," said Assistant Secretary for Environment, Safety and Health John Shaw. "Today's action illustrates the department's commitment to ensuring that any and all valid

187

Nuclear power's threat to health, safety, and freedom  

Science Journals Connector (OSTI)

Nuclear power's threat to health, safety, and freedom ... In particular, they may differ on whether the nuclear power plants that are the result of the 1953 Atoms for Peace movement help or hinder the control of nuclear weapons. ...

1980-10-13T23:59:59.000Z

188

Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Culture in the US Nuclear Regulatory Commission's Reactor Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process September 19, 2012 Presenter: Undine Shoop, Chief, Health Physics and Human Performance Branch, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission Topics covered: Purpose of the Reactor Oversight Process (ROP) ROP Framework Safety Culture within the ROP Safety Culture Assessments Safety Culture in the US Nuclear Regulatory Commission's Reactor Oversight Process More Documents & Publications A Commissioner's Perspective on USNRC Actions in Response to the Fukushima Nuclear Accident Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11

189

GROWTH OF THE INTERNATIONAL CRITICALITY SAFETY AND REACTOR PHYSICS EXPERIMENT EVALUATION PROJECTS  

SciTech Connect

Since the International Conference on Nuclear Criticality Safety (ICNC) 2007, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) have continued to expand their efforts and broaden their scope. Eighteen countries participated on the ICSBEP in 2007. Now, there are 20, with recent contributions from Sweden and Argentina. The IRPhEP has also expanded from eight contributing countries in 2007 to 16 in 2011. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments1' have increased from 442 evaluations (38000 pages), containing benchmark specifications for 3955 critical or subcritical configurations to 516 evaluations (nearly 55000 pages), containing benchmark specifications for 4405 critical or subcritical configurations in the 2010 Edition of the ICSBEP Handbook. The contents of the Handbook have also increased from 21 to 24 criticality-alarm-placement/shielding configurations with multiple dose points for each, and from 20 to 200 configurations categorized as fundamental physics measurements relevant to criticality safety applications. Approximately 25 new evaluations and 150 additional configurations are expected to be added to the 2011 edition of the Handbook. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Reactor Physics Benchmark Experiments2' have increased from 16 different experimental series that were performed at 12 different reactor facilities to 53 experimental series that were performed at 30 different reactor facilities in the 2011 edition of the Handbook. Considerable effort has also been made to improve the functionality of the searchable database, DICE (Database for the International Criticality Benchmark Evaluation Project) and verify the accuracy of the data contained therein. DICE will be discussed in separate papers at ICNC 2011. The status of the ICSBEP and the IRPhEP will be discussed in the full paper, selected benchmarks that have been added to the ICSBEP Handbook will be highlighted, and a preview of the new benchmarks that will appear in the September 2011 edition of the Handbook will be provided. Accomplishments of the IRPhEP will also be highlighted and the future of both projects will be discussed. REFERENCES (1) International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03/I-IX, Organisation for Economic Co-operation and Development-Nuclear Energy Agency (OECD-NEA), September 2010 Edition, ISBN 978-92-64-99140-8. (2) International Handbook of Evaluated Reactor Physics Benchmark Experiments, NEA/NSC/DOC(2006)1, Organisation for Economic Co-operation and Development-Nuclear Energy Agency (OECD-NEA), March 2011 Edition, ISBN 978-92-64-99141-5.

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

2011-09-01T23:59:59.000Z

190

Safety Reports Series No. 11, Developing Safety Culture in Nuclear Activities: Practical Suggestions to Assist Progress, International Atomic Energy Agency  

Energy.gov (U.S. Department of Energy (DOE))

Safety Reports Series No. 11, Developing Safety Culture in Nuclear Activities: Practical Suggestions to Assist Progress, International Atomic Energy Agency

191

Nuclear safety information sharing agreement between NRC and DOEs Office of Environment, Health, Safety and Security  

Energy.gov (U.S. Department of Energy (DOE))

Nuclear safety information sharing agreement between NRC and DOEs Office of Environment, Health, Safety and Security.

192

CRAD, Nuclear Safety Delegations for Documented Safety Analysis Approval January 8, 2015 (EA CRAD 31-09, Rev. 0)  

Energy.gov (U.S. Department of Energy (DOE))

CRAD, Nuclear Safety Delegations for Documented Safety Analysis Approval January 8, 2015 (EA CRAD 31-09, Rev. 0)

193

Overview of imporved criticality safety limits at the Rocky Flats plant  

SciTech Connect

This paper provides an overview of improved criticality safety limits developed for nuclear operations at the Rocky Flats plant. A concern that some limits were ambiguous and too complex has been resolved by involving the process operators (addressing human factors) in the limit development process. In the summer of 1989, there was a public concern that a criticality accident may have occurred and gone undetected at the Rocky Flats plant near Golden, Colorado. To resolve this concern, the US Department of Energy (DOE) asked Scientech, Inc., to assemble an independent review team and assess the concern. The Scientech team concluded that there was no indication that a criticality accident had ever occurred at the Rocky Flats plant. However, the team did identify inadequate safety conditions and practices and recommended corrective actions.

Grethel, T.E.; Moon, N.A. (Department of Energy, Golden, CO (United States)); Brown, C.L. (M.H. Chew Associates, Inc., Golden, CO (United States))

1993-01-01T23:59:59.000Z

194

Implementation of an Enhanced Measurement Control Program for handling nuclear safety samples at WSRC  

SciTech Connect

In the separation and purification of nuclear material, nuclear criticality safety (NCS) is of primary concern. The primary nuclear criticality safety controls utilized by the Savannah River Site (SRS) Separations Facilities involve administrative and process equipment controls. Additional assurance of NCS is obtained by identifying key process hold points where sampling is used to independently verify the effectiveness of production control. Nuclear safety measurements of samples from these key process locations provide a high degree of assurance that processing conditions are within administrative and procedural nuclear safety controls. An enhanced procedure management system aimed at making improvements in the quality, safety, and conduct of operation was implemented for Nuclear Safety Sample (NSS) receipt, analysis, and reporting. All procedures with nuclear safety implications were reviewed for accuracy and adequate detail to perform the analytical measurements safely, efficiently, and with the utmost quality. Laboratory personnel worked in a Deliberate Operating'' mode (a systematic process requiring continuous expert oversight during all phases of training, testing, and implementation) to initiate the upgrades. Thus, the effort to revise and review nuclear safety sample procedures involved a team comprised of a supervisor, chemist, and two technicians for each procedure. Each NSS procedure was upgraded to a Use Every Time'' (UET) procedure with sign-off steps to ensure compliance with each step for every nuclear safety sample analyzed. The upgrade program met and exceeded both the long and short term customer needs by improving measurement reliability, providing objective evidence of rigid adherence to program principles and requirements, and enhancing the system for independent verification of representative sampling from designated NCS points.

Boler-Melton, C.; Holland, M.K.

1991-01-01T23:59:59.000Z

195

Implications of Monte Carlo Statistical Errors in Criticality Safety Assessments  

SciTech Connect

Most criticality safety calculations are performed using Monte Carlo techniques because of Monte Carlo's ability to handle complex three-dimensional geometries. For Monte Carlo calculations, the more histories sampled, the lower the standard deviation of the resulting estimates. The common intuition is, therefore, that the more histories, the better; as a result, analysts tend to run Monte Carlo analyses as long as possible (or at least to a minimum acceptable uncertainty). For Monte Carlo criticality safety analyses, however, the optimization situation is complicated by the fact that procedures usually require that an extra margin of safety be added because of the statistical uncertainty of the Monte Carlo calculations. This additional safety margin affects the impact of the choice of the calculational standard deviation, both on production and on safety. This paper shows that, under the assumptions of normally distributed benchmarking calculational errors and exact compliance with the upper subcritical limit (USL), the standard deviation that optimizes production is zero, but there is a non-zero value of the calculational standard deviation that minimizes the risk of inadvertently labeling a supercritical configuration as subcritical. Furthermore, this value is shown to be a simple function of the typical benchmarking step outcomes--the bias, the standard deviation of the bias, the upper subcritical limit, and the number of standard deviations added to calculated k-effectives before comparison to the USL.

Pevey, Ronald E.

2005-09-15T23:59:59.000Z

196

Enforcement Regulations and Directives - Nuclear Safety | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety Nuclear Safety Enforcement Regulations and Directives - Nuclear Safety 10 C.F.R. Part 820 and Amendments 10 C.F.R. Part 820 - Procedural Rules for DOE Nuclear Activities 10 C.F.R. Part 820 - Procedural Rules for DOE Nuclear Activities; General Statement of Enforcement Policy; Final rule; amendment of enforcement policy statement and confirmation of interim rule 10 C.F.R. Part 830 10 C.F.R. Part 830 - Nuclear Safety Management; Final Rule Office of General Counsel Interpretation regarding the Application of DOE Technical Standard 1027-92 under 10 C.F.R. Part 830 Office of General Counsel Interpretation regarding Noncompliant Documented Safety Analyses and Exemption Relief (9/28/2011) Related Guidance DOE-STD-1083-2009, Processing Exemptions to Nuclear Safety Rules and

197

Facility Safety  

Directives, Delegations, and Requirements

The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

2000-11-20T23:59:59.000Z

198

Princeton Plasma Physics Lab - Nuclear safety  

NLE Websites -- All DOE Office Websites (Extended Search)

safety Actions taken to safety Actions taken to prevent nuclear and radiation accidents or to limit their consequences. en Celebrating the 20th anniversary of the tritium shot heard around the world http://www.pppl.gov/news/2013/12/celebrating-20th-anniversary-tritium-shot-heard-around-world-2

Tensions rose in the U.S. Department of Energy's (DOE) Princeton Plasma Physics Laboratory (PPPL) as the seconds counted down. At stake was the first crucial test of a high-powered mixture of fuel for producing fusion energy. As the control-room clock reached "zero," a flash of light on a closed-circuit television monitor marked a historic achievement:

199

Ris-R-679(EN) Nuclear Safety Research  

E-Print Network (OSTI)

of the nuclear facilities at Risø. The activities include personnel dosimetry, maintenance and calibra- tionRisø-R-679(EN) mil Nuclear Safety Research Department Annual Progress Report 1992 Edited by B March 1993 #12;Nuclear Safety Research K«*«i Department Annual Progress Report 1992 Edited by B

200

Propagation of Isotopic Bias and Uncertainty to Criticality Safety Analyses of PWR Waste Packages  

SciTech Connect

Burnup credit methodology is economically advantageous because significantly higher loading capacity may be achieved for spent nuclear fuel (SNF) casks based on this methodology as compared to the loading capacity based on a fresh fuel assumption. However, the criticality safety analysis for establishing the loading curve based on burnup credit becomes increasingly complex as more parameters accounting for spent fuel isotopic compositions are introduced to the safety analysis. The safety analysis requires validation of both depletion and criticality calculation methods. Validation of a neutronic-depletion code consists of quantifying the bias and the uncertainty associated with the bias in predicted SNF compositions caused by cross-section data uncertainty and by approximations in the calculational method. The validation is based on comparison between radiochemical assay (RCA) data and calculated isotopic concentrations for fuel samples representative of SNF inventory. The criticality analysis methodology for commercial SNF disposal allows burnup credit for 14 actinides and 15 fission product isotopes in SNF compositions. The neutronic-depletion method for disposal criticality analysis employing burnup credit is the two-dimensional (2-D) depletion sequence TRITON (Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion)/NEWT (New ESC-based Weighting Transport code) and the 44GROUPNDF5 crosssection library in the Standardized Computer Analysis for Licensing Evaluation (SCALE 5.1) code system. The SCALE 44GROUPNDF5 cross section library is based on the Evaluated Nuclear Data File/B Version V (ENDF/B-V) library. The criticality calculation code for disposal criticality analysis employing burnup credit is General Monte Carlo N-Particle (MCNP) Transport Code. The purpose of this calculation report is to determine the bias on the calculated effective neutron multiplication factor, k{sub eff}, due to the bias and bias uncertainty associated with predicted spent fuel compositions (i.e., determine the penalty in reactivity due to isotopic composition bias and uncertainty) for use in disposal criticality analysis employing burnup credit. The method used in this calculation to propagate the isotopic bias and bias-uncertainty values to k{sub eff} is the Monte Carlo uncertainty sampling method. The development of this report is consistent with 'Test Plan for: Isotopic Validation for Postclosure Criticality of Commercial Spent Nuclear Fuel'. This calculation report has been developed in support of burnup credit activities for the proposed repository at Yucca Mountain, Nevada, and provides a methodology that can be applied to other criticality safety applications employing burnup credit.

Radulescu, Georgeta [ORNL

2010-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

CRITICALITY HAZOP EFFICIENTLY EVALUATING HAZARDS OF NEW OR REVISED CRITICALITY SAFETY EVALUATIONS  

SciTech Connect

The 'Criticality HazOp' technique, as developed at Hanford's Plutonium Finishing Plant (PFP), has allowed for efficiencies enabling shortening of the time necessary to complete new or revised criticality safety evaluation reports (CSERs). For example, in the last half of 2007 at PFP, CSER revisions undergoing the 'Criticality HazOp' process were completed at a higher rate than previously achievable. The efficiencies gained through use of the 'Criticality HazOp' process come from the preliminary narrowing of potential scenarios for the Criticality analyst to fully evaluate in preparation of the new or revised CSER, and from the use of a systematized 'Criticality HazOp' group assessment of the relevant conditions to show which few parameter/condition/deviation combinations actually require analytical effort. The 'Criticality HazOp' has not only provided efficiencies of time, but has brought to criticality safety evaluation revisions the benefits of a structured hazard evaluation method and the enhanced insight that may be gained from direct involvement of a team in the process. In addition, involved personnel have gained a higher degree of confidence and understanding of the resulting CSER product.

CARSON DM

2008-04-15T23:59:59.000Z

202

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

203

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

204

Independent Activity Report, Defense Nuclear Facilities Safety Board Public  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Defense Nuclear Facilities Safety Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October 2012 Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02] The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12 Technical Services, LLC (B&W Y-12) design project team leadership; and an open public

205

Microsoft Word - Nuclear Safety Pamphlet Final September 1 2010...  

Energy Savers (EERE)

A Basic Overview of NUCLEAR SAFETY AT THE DEPARTMENT OF ENERGY Outreach & Awareness Series Office of Health, Safety and Security (HSS) U.S. Department of Energy September 2010...

206

Self-Assessment Standard for DOE Contractor Criticality Safety Programs  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

10 10 March 2010 DOE STANDARD SELF-ASSESSMENT STANDARD FOR DOE CONTRACTOR CRITICALITY SAFETY PROGRAMS DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document is available on the Department of Energy Technical Standards Program Web Page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1158-2010 iii TABLE OF CONTENTS FOREWORD ................................................................................................................... v ACKNOWLEDGEMENT ..................................................................................................vi DEFINITIONS ................................................................................................................ vii

207

Safety Series No. 75-INSAG-4, Safety Culture: A report by the International Nuclear Safety Advisory Group, International Atomic Energy Agency  

Energy.gov (U.S. Department of Energy (DOE))

Safety Series No. 75-INSAG-4, Safety Culture: A report by the International Nuclear Safety Advisory Group, International Atomic Energy Agency, IAEA, 1991

208

Tutorial on nuclear thermal propulsion safety for Mars  

SciTech Connect

Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

Buden, D.

1992-01-01T23:59:59.000Z

209

Tutorial on nuclear thermal propulsion safety for Mars  

SciTech Connect

Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

Buden, D.

1992-08-01T23:59:59.000Z

210

Review of Nevada Site Office Criticality Safety Assessments at the Criticality Experiments Facility and Training Assembly for Criticality Safety and Appraisal of the Criticality Experiments Facility Startup Plan, October 2011  

Energy.gov (U.S. Department of Energy (DOE))

This report provides the results of an independent oversight review of criticality safety assessment activities conducted by the Department of Energy's (DOE) Nevada Site Office

211

Nuclear Safety Component and Services Procurement, June 29, 2011...  

Office of Environmental Management (EM)

Office of Enforcement and Oversight Criteria Review and Approach Document Subject: Nuclear Safety Component and Services Procurement Inspection Criteria, Inspection Activities, and...

212

10 CFR Part 830 Nuclear Safety Technical Positions  

Energy.gov (U.S. Department of Energy (DOE))

Technical Positions to directives issued by Nuclear and Facility Safety Policy provide clarification for specific applications of the requirements in DOE orders, rules, and other directives.

213

Development of Probabilistic Risk Assessments for Nuclear Safety...  

Office of Environmental Management (EM)

OF PROBABILISTIC RISK ASSESSMENTS FOR NUCLEAR SAFETY APPLICATIONS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release;...

214

Safety Analysis, Hazard and Risk Evaluations [Nuclear Waste Management  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Analysis, Hazard Safety Analysis, Hazard and Risk Evaluations Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Safety Analysis, Hazard and Risk Evaluations Bookmark and Share NE Division personnel had a key role in the creation of the FCF Final Safety Analysis Report (FSAR), FCF Technical Safety Requirements (TSR)

215

Operating Experience Level 3, Importance of Conduct of Operations and Training for Effective Criticality Safety Programs  

Energy.gov (U.S. Department of Energy (DOE))

OE-3 2012-07: Importance of Conduct of Operations and Training for Effective Criticality Safety Programs

216

Senior Technical Safety Manager Qualification Program Self-Assessment- Chief of Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE))

This Chief of Nuclear Safety (CNS) Report was prepared to summarize the results of the July 2013 CNS self-assessment of the Senior Technical Safety Manager Qualification Program.

217

Improved dose estimates for nuclear criticality accidents  

SciTech Connect

Slide rules are improved for estimating doses and dose rates resulting from nuclear criticality accidents. The original slide rules were created for highly enriched uranium solutions and metals using hand calculations along with the decades old Way-Wigner radioactive decay relationship and the inverse square law. This work uses state-of-the-art methods and better data to improve the original slide rules and also to extend the slide rule concept to three additional systems; i.e., highly enriched (93.2 wt%) uranium damp (H/{sup 235}U = 10) powder (U{sub 3}O{sub 8}) and low-enriched (5 wt%) uranium mixtures (UO{sub 2}F{sub 2}) with a H/{sup 235}U ratio of 200 and 500. Although the improved slide rules differ only slightly from the original slide rules, the improved slide rules and also the new slide rules can be used with greater confidence since they are based on more rigorous methods and better nuclear data.

Wilkinson, A.D.; Basoglu, B.; Bentley, C.L.; Dunn, M.E.; Plaster, M.J.; Dodds, H.L. [Univ. of Tennessee, Knoxville, TN (United States). Nuclear Engineering Dept.; Haught, C.F. [Martin Marietta Utility Systems, Piketon, OH (United States); Yamamoto, T. [Japan Atomic Energy Research Inst., Tokai (Japan). Tokai Research Establishment; Hopper, C.M. [Oak Ridge National Lab., TN (United States)

1995-08-01T23:59:59.000Z

218

Criticality safety evaluation report for the multi-canister overpack  

SciTech Connect

This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both KE and KW Basins, and loaded into multiple canister overpack (MCO) containers with specially built baskets containing a maximum of either 54 Mark 1V or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operations at the Cold Vacuum Drying Facility, and storage in the Canister Storage Building. Many conservatisms have been built into this analysis, the primary one being the selection of the k{sub eff} = 0.95 criticality safety limit. Additional analyses in this revision include partial fuel basket loadings, loading 26.1 inch Mark IA fuel assemblies into Mark IV fuel baskets, and the revised fuel and scrap basket designs. The MCO MCNP model was revised to include the shield plug assembly.

KESSLER, S.F.

1999-05-21T23:59:59.000Z

219

Nuclear Safety Information Dashboard QuickStart Guide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety Information Dashboard Nuclear Safety Information Dashboard QuickStart Guide September 2012 Office of Analysis (HS-24) Office of Environmental Protection, Sustainability Support and Corporate Safety Analysis Office of Health, Safety and Security (HSS) Purpose of Nuclear Safety Information (NSI) Dashboard * The NSI Dashboard provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into ORPS. * ORPS reporting criteria associated with events at nuclear facilities have pre-assigned weighting factors according to their relative importance and are placed into groups. * This information can be evaluated to identify trends and, using insights from current events and nature of operations, enable

220

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Nuclear Safety Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Application of Risk Assessment and Management to Nuclear Safety |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Application of Risk Assessment and Management to Nuclear Safety Application of Risk Assessment and Management to Nuclear Safety Application of Risk Assessment and Management to Nuclear Safety September 20, 2012 Presenter: Commissioner George Apostolakis US Nuclear Regulatory Commission Topics covered: Management of (unquantified at the time) uncertainty was always a concern. Defense-in-depth and safety margins became embedded in the regulations. "Defense-in-Depth is an element of the NRC's safety philosophy that employs successive compensatory measures to prevent accidents or mitigate damage if a malfunction, accident, or naturally caused event occurs at a nuclear facility." [Commission's White Paper, February 1999] Design Basis Accidents are postulated accidents that a nuclear facility must be designed and built to withstand without loss to the

222

Chief of Nuclear Safety (CNS) Senior Technical Safety Manager (STSM) Qualification Program Self-Assessment Report - August 2013  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Chief of Nuclear Safety (CNS) Chief of Nuclear Safety (CNS) Self-Assessment Report Senior Technical Safety Manager Qualification Program CONTENTS Background ................................................................................................................................ 1 Results ....................................................................................................................................... 1 Assessment Criteria ................................................................................................................... 1 Finding ....................................................................................................................................... 2 Observation ............................................................................................................................... 2

223

Nuclear Safety Information Agreement Between the U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, and the U.S. Department of Energy, Office of Environment, Health, Safety and Security  

Energy.gov (U.S. Department of Energy (DOE))

On December 15, Matt Moury, Associate Under Secretary, Office of Environment, Health, Safety and Security (EHSS DOE) and EHSS Office of Nuclear Safety staff met with the NRC Executive Director for Operations, the Deputy Executive Director for Operations, and the Director, Office of Nuclear Materials Safety and Safeguards to sign a nuclear safety information exchange agreement between NRC Office of Nuclear Materials Safety and Safeguards and the Office of Environment, Health, Safety and Security.

224

New enhancements to SCALE for criticality safety analysis  

SciTech Connect

As the speed, available memory, and reliability of computer hardware increases and the cost decreases, the complexity and usability of computer software will increase, taking advantage of the new hardware capabilities. Computer programs today must be more flexible and user friendly than those of the past. Within available resources, the SCALE staff at Oak Ridge National Laboratory (ORNL) is committed to upgrading its computer codes to keep pace with the current level of technology. This paper examines recent additions and enhancements to the criticality safety analysis sections of the SCALE code package. These recent additions and enhancements made to SCALE can be divided into nine categories: (1) new analytical computer codes, (2) new cross-section libraries, (3) new criticality search sequences, (4) enhanced graphical capabilities, (5) additional KENO enhancements, (6) enhanced resonance processing capabilities, (7) enhanced material information processing capabilities, (8) portability of the SCALE code package, and (9) other minor enhancements, modifications, and corrections to SCALE. Each of these additions and enhancements to the criticality safety analysis capabilities of the SCALE code system are discussed below.

Hollenbach, D.F.; Bowman, S.M.; Petrie, L.M.; Parks, C.V. [Oak Ridge National Lab., TN (United States). Computational Physics and Engineering Div.

1995-09-01T23:59:59.000Z

225

Nuclear Safety Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

14, 2002 14, 2002 Preliminary Notice of Violation, Fluor Hanford, Incorporated - EA-2002-03 Preliminary Notice of Violation issued to Fluor Hanford, Incorporated, related to Quality Assurance issues at the Hanford Site. June 19, 2002 Enforcement Letter, Kaiser-Hill Company, L.L.C. - June 19, 2002 Enforcement Letter issued to Kaiser-Hill Company, LLC related to Unplanned Radioactive Material Uptakes at the Rocky Flats Environmental Technology Site October 22, 2001 Special Report Order, CH2M Hill Hanford Group, Inc. - October 22, 2001 Special Report Order issued to CH2M Hill Hanford Group, Inc., related to Multiple Nuclear Safety Issues at the Hanford Site October 9, 2001 Enforcement Letter, LANL - October 9, 2001 Enforcement Letter issued to Los Alamos National Laboratory related to

226

FAQS Job Task Analyses - Nuclear Safety Specialist  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

JOB / TASK ANALYSIS for JOB / TASK ANALYSIS for Nuclear Safety Specialist (NSS) Functional Area Qualification Standard (FAQS) DOE-STD-1183-2007 Instructions for Step 1: Step 1 Identify and evaluate tasks - Develop a comprehensive list of tasks that define the job. o A great starting point is the list of Duties and Responsibilities from the FAQS. o Give careful thought to additional tasks that could be considered. o Don't worry about deleting tasks at this point - that is a part of the process further down. - List the tasks (and their sources, e.g., Duties and Responsibilities #1) in the chart below. - Discuss each task as a group and come to a consensus pertaining to Importance and Frequency of the task (i.e., each team member can consent to the assigned value, even

227

Defense Nuclear Facilities Safety Board's enabling legislation  

NLE Websites -- All DOE Office Websites (Extended Search)

ENABLING STATUTE OF THE ENABLING STATUTE OF THE DEFENSE NUCLEAR FACILITIES SAFETY BOARD 42 U.S.C. § 2286 et seq. NATIONAL DEFENSE AUTHORIZATION ACT, FISCAL YEAR 1989 (Pub. L. No. 100-456, September 29, 1988), AS AMENDED BY NATIONAL DEFENSE AUTHORIZATION ACT, FISCAL YEAR 1991 (Pub. L. No. 101-510, November 5, 1990), NATIONAL DEFENSE AUTHORIZATION ACT FISCAL YEARS 1992 AND 1993 (Pub. L. No. 102-190, December 5, 1991), ENERGY POLICY ACT OF 1992 (Pub. L. No. 102-486, October 24, 1992), NATIONAL DEFENSE AUTHORIZATION ACT FISCAL YEAR 1994 (Pub. L. No. 103-160, November 30, 1993), FEDERAL REPORTS ELIMINATION ACT OF 1998 (Pub. L. No. 105-362, November 10, 1998), NATIONAL DEFENSE AUTHORIZATION ACT FISCAL YEAR 2001 (Pub. L. No. 106-398, October 30, 2000), AND

228

NNSA issues Preliminary Notice of Violation to National Security Technologies, LLC, for Nuclear Safety Violations, Fact Sheet  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sheet Sheet NNSA issues Preliminary Notice of Violation to National Security Technologies, LLC, for Nuclear Safety Violations On August 22, 2011, the National Nuclear Security Administration (NNSA) issued a Preliminary Notice of Violation (PNOV) to National Security Technologies, LLC (NSTec) for violations of Department of Energy's (DOE) nuclear safety regulations. NSTec is the operating contractor of NNSA's Nevada National Security Site (NNSS) located 65 miles northwest of Las Vegas, Nevada. The PNOV cites four violations of DOE regulations governing nuclear safety management. The violations are associated with quality assurance (QA) related deficiencies in the inspection and installation of penetration fire seals and other components at the Criticality Experiments Facility

229

NUCLEAR SAFETY WORKSHOP AGENDA Post Fukushima Initiatives and Results  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NUCLEAR SAFETY WORKSHOP AGENDA NUCLEAR SAFETY WORKSHOP AGENDA Post Fukushima Initiatives and Results September 19-20, 2012 - Bethesda North Marriott TUESDAY, SEPTEMBER 18 - Grand Ballroom, Salons F/G/H 1 9/14/12 6:00 - 8:00 pm Registration WEDNESDAY, SEPTEMBER 19 - Grand Ballroom, Salons F/G/H 7:00 - 8:00 am Registration 8:00 - 8:05 am Logistics Stephen A. Kirchhoff, Office of Health, Safety and Security US Department of Energy 8:05 - 8:15 am Welcoming Remarks and Workshop Objectives Glenn S. Podonsky, Chief Health, Safety and Security Officer US Department of Energy 8:15 - 8:45 am Maintaining Our Focus on Nuclear Safety Daniel B. Poneman, Deputy Secretary US Department of Energy 8:45 - 9:30 am Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - the

230

DOE Cites Bechtel Jacobs Company for Nuclear Safety Violations | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Jacobs Company for Nuclear Safety Violations Jacobs Company for Nuclear Safety Violations DOE Cites Bechtel Jacobs Company for Nuclear Safety Violations August 4, 2005 - 2:36pm Addthis WASHINGTON, D.C. - The Department of Energy (DOE) today notified the Bechtel Jacobs Company (BJC) that it will fine the company $247,500 for violations of the department's nuclear safety requirements. The company is the department's contractor responsible for environmental cleanup and waste management at its Oak Ridge Reservation in Tennessee. "One of our top safety priorities is to improve the performance of subcontractors, and to do that we need to hold prime contractors responsible," said John Shaw, Assistant Secretary for Environment, Safety and Health. "Our goal is to have work conducted in a manner that protects

231

Packaging Strategies for Criticality Safety for "Other" DOE Fuels in a Repository  

SciTech Connect

Since 1998, there has been an ongoing effort to gain acceptance of U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in the national repository. To accomplish this goal, the fuel matrix was used as a discriminating feature to segregate fuels into nine distinct groups. From each of those groups, a characteristic fuel was selected and analyzed for criticality safety based on a proposed packaging strategy. This report identifies and quantifies the important criticality parameters for the canisterized fuels within each criticality group to: (1) demonstrate how the other fuels in the group are bounded by the baseline calculations or (2) allow identification of individual type fuels that might require special analysis and packaging.

Larry L Taylor

2004-06-01T23:59:59.000Z

232

Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety  

SciTech Connect

Utilization of burnup credit in criticality safety analysis for long-term disposal of spent nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile material that will be present in the repository. Burnup-credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents (in terms of criticality potential), followed by criticality calculations to assess the value of the effective neutron multiplication factor (k(sub)eff) for the a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models.

DeHart, M.D.

1999-08-01T23:59:59.000Z

233

Review and Approval of Nuclear Facility Safety Basis Documents (Documented Safety Analyses and Technical Safety Requirements)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

February 1996 February 1996 CHANGE NOTICE NO. 2 Date November 2005 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS DOCUMENTS (DOCUMENTED SAFETY ANALYSES AND TECHNICAL SAFETY REQUIREMENTS) U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, Fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Adminis tration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000.

234

Hybrid reliability model for nuclear reactor safety system  

Science Journals Connector (OSTI)

The dependability of critical safety systems needs to be quantitatively determined in order to verify their effectiveness, e.g. with regard to regulatory requirements. Since modular redundant safety systems are not required for normal operation, their reliability is strongly dependent on periodic inspection. Several modeling methods for the quantitative assessment of dependability are described in the literature, with a broad variation in complexity and modeling power. Static modeling techniques such as fault tree analysis (FTA) or reliability block diagrams (RBD) are not capable of capturing redundancy and repair or test activities. Dynamic state space based models such as continuous time Markov chains (CTMC) are more powerful but often result in very large, intractable models. Moreover, exponentially distributed state residence times are not a correct representation of actual residence times associated with repair activities or periodic inspection. In this study, a hybrid model combines a system level RBD with a CTMC to describe the dynamics. The effects of periodic testing are modeled by redistributing state probabilities at deterministic test times. Applying the method to the primary safety shutdown system of the BR2(Belgian Reactor 2)nuclear research reactor, resulted in a quantitative as well as a qualitative assessment of its reliability.

Steven Verlinden; Geert Deconinck; Bernard Coup

2012-01-01T23:59:59.000Z

235

Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches  

SciTech Connect

The U.S. Department of Energy, through its agents the Next Generation Nuclear Plant Project and the Nuclear Hydrogen Initiative, is working on developing the technologies to enable the large scale production of hydrogen using nuclear power. A very important consideration in the design of a co-located and connected nuclear plant/hydrogen plant facility is safety. This study provides an overview of the safety issues associated with a combined plant and discusses approaches for categorizing, quantifying, and addressing the safety risks.

Steven R. Sherman

2007-06-01T23:59:59.000Z

236

Criticality safety of an annular tank for fissile solution  

SciTech Connect

Experiments performed to determine the criticality safety of annular tanks for storing fissile solutions are described. Six annular tanks were built in four nesting sizes to obtain experimental criticality data which could be used to validate computer codes employed in the design of such a safe storage system for an industrial plant. Each tank had an annular solution region thickness of 38 mm. The height of this region was 2.13 m, held 0.3 m off the floor by a stainless steel skirting. Walls were 6.4 mm-thick type 304L stainless steel. The uranyl nitrate solution contained 357 g U/l and had a density of 1.5 kg/m/sup 3/. The uranium was enriched to 93.2% /sup 235/U with other isotopes: 5.4% /sup 238/U, 1.0% /sup 234/U, and 0.4% /sup 236/U. The solution contained 0.5 molar nitric acid and a total impurity content of less than 1500 ppM. Important neutron absorbers, boron and cadmium, averaged 10 ppM and 30 ppM, respectively. Boron-loaded concrete and boron-loaded plaster were selected for the neutron moderator/absorber interior to the annular tank. Three configurations of tanks and reflector were taken to criticality and are reported. The critical uranium solution height in all tanks containing solution as a function of boron content in earthen interior material, tank array configuration, and other variables. (LCL)

Rothe, R.E.

1981-01-01T23:59:59.000Z

237

2012 Nuclear Safety Workshop Photos | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

You are here You are here Home » 2012 Nuclear Safety Workshop Photos 2012 Nuclear Safety Workshop Photos Addthis Glenn Podonsky 1 of 13 Glenn Podonsky Glenn Podonsky (DOE Chief Health, Safety and Security Officer) provides his welcoming remarks. Daniel Poneman 2 of 13 Daniel Poneman DOE Deputy Secretary Daniel Poneman discusses maintaining our focus on nuclear safety. Akira Kawano 3 of 13 Akira Kawano Akira Kawano, Tokyo Electric Power Company, provides lessons learned from the Fukushima nuclear accident. Bill Ostendorff 4 of 13 Bill Ostendorff NRC Commissioner Bill Ostendorff gives his perspective on the NRC's response to the Fukushima nuclear accident. Miroslav Lipar 5 of 13 Miroslav Lipar Miroslav Lipar, IAEA, provides an international perspective on the Fukushima nuclear accident.

238

Microsoft Word - Nuclear Safety Reporting Criteria.docx  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Noncompliance Reporting Criteria (as of January 1, 2012) Safety Noncompliance Reporting Criteria (as of January 1, 2012) Nuclear Safety Noncompliances Associated With Occurrences (DOE Order 232.2) Consult the DOE Order for the full text of each occurrence criterion 1 Reporting Criteria Group Subgroup Occurrence Category and Summary Description 2 1. Operational Emergencies 3 N/A (1) Operational Emergency (2) Alert (3) Site Area Emergency (4) General Emergency 2. Personnel Safety and Health C. Fires (1) Fire within primary confinement/containment (2d) Self-extinguishing fires D. Explosions (1) Unplanned explosion within primary confinement/containment 3. Nuclear Safety Basis A. Technical Safety Requirement (TSR) Violations (1) Violation of TSR/Operational Safety Requirement (OSR) Safety Limit (2) Violation of other TSR/OSR requirement

239

An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems  

SciTech Connect

The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated toolkit consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

Timothy J. Leahy

2010-06-01T23:59:59.000Z

240

Nuclear Safety Reserch and Development Program Operating Plan  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Research and Development Safety Research and Development Program Operating Plan Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy June 2012 INTENTIONALLY BLANK NSR&D Program Operating Plan June 2012 Table of Contents 1.0 INTRODUCTION................................................................................................................. 1 2.0 BACKGROUND ................................................................................................................... 1 3.0 OBJECTIVES ....................................................................................................................... 2 4.0 NSR&D PROGRAM PROCESSES .................................................................................... 3

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

SRTC criticality safety technical review: Phase 1 criticality analysis for the 9972-9975 family of shipping casks: (SRT-CMA-940003)  

SciTech Connect

Review of SRT-CMA-940003, ``Phase I Criticality Analysis For The 9972-9975 Family Of Shipping Casks (U). (SRT-CMA-940003).`` January 22, 1994, has been performed by the SRTC Applied Physics Group. The NCSE is a criticality assessment of the 9972-9975 family of shipping casks. This work is a follow-on of a previous criticality safety evaluation, with the differences between this and the previous evaluation are that now wall tolerances are modeled and more sophisticated analytical methods are applied. The NCSE under review concludes that, with one exception, the previously specified plutonium and uranium mass limits for 9972-9975 family of shipping casks do ensure that WSRC Nuclear Criticality Safety Manual requirements (ref. 1) are satisfied. The one exception is that the plutonium mass limit for the 9974 cask had to be reduced from 4.4 to 4.3 kg. In contrast, the 7.5 kg uranium mass limit for the 9974 cask was raised to 14.5 kg, making the uranium mass identical for all casks in this family. This technical review consisted of an independent check of the methods and models employed, application of ANSI/ANS 8.1 and 8.15, and verification of WSRC Nuclear Criticality Safety Manual procedures.

Rathbun, R.

1994-03-02T23:59:59.000Z

242

Work for Nuclear Regulatory Commission, Safety Related Applications  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Regulatory Nuclear Regulatory Commission Capabilities Sensors and Instrumentation and Nondestructive Evaluation Overview Energy System Applications Safety-Related Applications Overview DOE Office of Nuclear Energy, Science, and Technology Nuclear Regulatory Commission National Aeronautics and Space Administration (NASA) Homeland Security Applications Biomedical Applications Millimiter Wave Group Papers Other NPNS Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sensors and Instrumentation and Nondestructive Evaluation Safety Related Applications Bookmark and Share Nuclear Regulatory Commission International Steam Generator Tube Integrity Program Key objectives of the International Steam Generator Tube Integrity Program

243

Safety Related Applications (Sensors and Instrumentation and NDE) - Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

DOE Office of DOE Office of Nuclear Energy, Science, and Technology Capabilities Sensors and Instrumentation and Nondestructive Evaluation Overview Energy System Applications Safety-Related Applications Overview DOE Office of Nuclear Energy, Science, and Technology Nuclear Regulatory Commission National Aeronautics and Space Administration (NASA) Homeland Security Applications Biomedical Applications Millimiter Wave Group Papers Other NPNS Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sensors and Instrumentation and Nondestructive Evaluation Safety Related Applications Bookmark and Share DOE Office of Nuclear Energy, Science, and Technology The objective of this Nuclear Energy Plant Optimization Project is to

244

Pantex sets safety record | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

sets safety record | National Nuclear Security Administration sets safety record | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Pantex sets safety record Pantex sets safety record Posted By Office of Public Affairs Pantex has set a new safety record with the lowest recordable case rate in the plant's history. The record total recordable case rate of 0.26 is a fitting end to an

245

Pantex receives two safety awards | National Nuclear Security  

National Nuclear Security Administration (NNSA)

two safety awards | National Nuclear Security two safety awards | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Pantex receives two safety awards Pantex receives two safety awards Posted By Office of Public Affairs B&W Pantex was honored last week with a pair of awards for its exemplary safety record. The President's Award for Best Performing Business Unit and the Target

246

The Defense Nuclear Facilities Safety Board's first decade  

Science Journals Connector (OSTI)

Concern over the safety of the United States' defense nuclear reactors in the late 1980s led to congressional creation of an independent oversight board. The Defense Nuclear Facility Safeties Board (DNFSB) is responsible for overseeing safety issues at the U.S. Department of Energy's nuclear facilities and issuing recommendations on operations and safety at these facilities, which include South Carolina's Savannah River Site, Texas' Pantex facility, Colorado's Rocky Flats Depot, and others. This article provides an historical overview of the DNFSB's first decade and discusses its relationship and interaction with the Department of Energy and congressional oversight committees as well as the recommendations it has issued on nuclear safety. An assessment of DNFSB's future prospects concludes the article.

Bert Chapman

2000-01-01T23:59:59.000Z

247

DOE Cites University of Chicago for Nuclear Safety Violations | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

University of Chicago for Nuclear Safety Violations University of Chicago for Nuclear Safety Violations DOE Cites University of Chicago for Nuclear Safety Violations March 7, 2006 - 11:42am Addthis WASHINGTON , DC - The Department of Energy (DOE) today issued a Preliminary Notice of Violation (PNOV) to the University of Chicago (University), the Management and Operating contractor for DOE's Argonne National Laboratory (ANL), for nuclear safety violations identified through several safety reviews and inspections conducted by DOE. A series of reviews and inspections, the most recent of which occurred in 2005, identified breakdowns in the contractor's quality improvement, radiation protection, work process, and independent and management assessment programs. Prior to 2005, senior contractor management at ANL

248

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment...  

Energy Savers (EERE)

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste...

249

Deputy Secretary Poneman Discusses Nuclear Safety at the IAEA | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Discusses Nuclear Safety at the IAEA Discusses Nuclear Safety at the IAEA Deputy Secretary Poneman Discusses Nuclear Safety at the IAEA June 20, 2011 - 12:00am Addthis Washington, D.C. - U.S. Deputy Secretary of Energy Daniel Poneman today addressed the plenary session at the International Atomic Energy Agency's Ministerial Conference on Nuclear Safety. Deputy Secretary Poneman emphasized the importance of international cooperation and information sharing for developing lessons learned from the Fukushima accident. The IAEA is leading the process to develop these international best practices, which will help strengthen the international nuclear regulatory regime. Remarks as prepared for delivery are below. Thank you, Mr. Ambassador, for your work in organizing this important Conference and to Director General Amano and his staff for convening it.

250

Nuclear Safety Research and Development Program Operating Plan | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Operating Plan Program Operating Plan Nuclear Safety Research and Development Program Operating Plan July 5, 2012 Nuclear Safety Research and Development Program Operating Plan This operating plan outlines the mission, goals, and processes for the Department of Energy's (DOE) Nuclear Safety Research & Development (NSR&D) Program. This first version of the operating plan also discusses the startup phase of the program. NSR&D involves a systematic search for knowledge to advance the fundamental understanding of nuclear safety science and technology through scientific study, analysis, modeling, and experiments. Maintaining an effective NSR&D program will support DOE and the National Nuclear Security Administration (NNSA) in standards development, validation of analytical models and

251

Nuclear Safety Research and Development Committee Charter | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Research and Development Committee Charter Research and Development Committee Charter Nuclear Safety Research and Development Committee Charter July 5, 2012 Nuclear Safety Research and Development Committee Charter The intent of the Nuclear Safety Research and Development (NSR&D) Committee is to identify nuclear safety research needs and opportunities within the Department of Energy (DOE) and National Nuclear Security Administration (NNSA) and their program offices. The Committee promotes communication and coordination among DOE and NNSA program offices to enhance synergy on NSR&D efforts that can benefit the Department. The Committee will foster and facilitate networking and information exchange on NSR&D needs and activities across DOE/NNSA programs and with external national and international organizations. The Committee should not be construed to have

252

Criticality Safety Controls Implementation, May 31, 2013 (HSS CRAD 45-18,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Criticality Safety Controls Implementation, May 31, 2013 (HSS CRAD Criticality Safety Controls Implementation, May 31, 2013 (HSS CRAD 45-18, Rev. 1) Criticality Safety Controls Implementation, May 31, 2013 (HSS CRAD 45-18, Rev. 1) The Department of Energy (DOE) has set expectations for implementing criticality safety controls that are selected to provide preventive and/or mitigative functions for specific potential accident scenarios. There are additional expectations for criticality safety controls that are also designated as Specific Administrative Controls (see HSS CRAD 64-32). The following provides a set of criteria and typical activities with representative lines of inquiry to assess criticality control implementation as an integral part of the review of the core functions and implementation of integrated safety management.

253

Supplemnental Volume - Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Volume Volume Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS i Independent Oversight Assessment of Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant Supplemental Volume Table of Contents Foreword ...................................................................................................................................................... iii Acronyms ...................................................................................................................................................... v

254

Development of the Nuclear Safety Information Dashboard - September 2012 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Development of the Nuclear Safety Information Dashboard - September Development of the Nuclear Safety Information Dashboard - September 2012 Development of the Nuclear Safety Information Dashboard - September 2012 September 2012 A working group with nuclear safety expertise used paired pairing computer software to develop first, a severity-weighted factor for the 17 Groups of ORPS Reporting Criteria and then, a severity-weighted factor for the sixty-five ORPS reporting criteria. The sum of the severity-weighted factors for the sixty-five ORPS Reporting Criteria equals 100%. Paired pairing is an analytical tool used to determine weighted factors. A team evaluated pairs of ORPS reporting criteria and concurred on the relative importance of each pair. Each ORPS reporting criterion in a group was compared with one other ORPS reporting

255

Development of the Nuclear Safety Information Dashboard - September 2012 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Development of the Nuclear Safety Information Dashboard - September Development of the Nuclear Safety Information Dashboard - September 2012 Development of the Nuclear Safety Information Dashboard - September 2012 September 2012 A working group with nuclear safety expertise used paired pairing computer software to develop first, a severity-weighted factor for the 17 Groups of ORPS Reporting Criteria and then, a severity-weighted factor for the sixty-five ORPS reporting criteria. The sum of the severity-weighted factors for the sixty-five ORPS Reporting Criteria equals 100%. Paired pairing is an analytical tool used to determine weighted factors. A team evaluated pairs of ORPS reporting criteria and concurred on the relative importance of each pair. Each ORPS reporting criterion in a group was compared with one other ORPS reporting

256

FAQS Job Task Analyses - Nuclear Explosive Safety Study  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Explosive Safety Study FAQS Nuclear Explosive Safety Study FAQS STEP 1: Job Task Analysis for Tasks Task (and Number) Source Importance Frequency (1) Serves as a member or chair of the NESSG. FAQS Duties and Responsibilities Paragraph A 5 3 (2) Provides guidance on and interpretation of nuclear explosive safety (NES) requirements and policy. FAQS Duties and Responsibilities Paragraph B 5 4 (3) Drafts policy directives for the DOE/NNSA, Nuclear Explosive Safety Operations Branch (NESB) and reviews DOE/NNSA policies on NES. FAQS Duties and Responsibilities Paragraph D 5 3 (4) Provides instruction and guidance regarding NES to individuals assigned NES responsibilities. FAQS Duties and Responsibilities Paragraph E 5 3-4 (5) Monitors ongoing NEOs to ensure compliance with NES standards and

257

DOE Cites Washington TRU Solutions for Nuclear Safety Violations |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Washington TRU Solutions for Nuclear Safety Violations Washington TRU Solutions for Nuclear Safety Violations DOE Cites Washington TRU Solutions for Nuclear Safety Violations December 22, 2005 - 4:53pm Addthis WASHINGTON, D.C. -- The Department of Energy (DOE) today notified Washington TRU Solutions (WTS) that it will fine the company $192,500 for violations of the department's nuclear safety requirements. The Preliminary Notice of Violation (PNOV) issued today cites a number of deficiencies that led to a series of low-level plutonium uptakes by workers at a WTS mobile facility (MOVER) stationed at the Lawrence Livermore National Laboratory (LLNL) in Livermore, Calif. The violations reflected WTS' limited understanding of the design and operational limitations of the MOVER facility, a portable waste processing facility designed to be

258

Exelon Statement Regarding Nuclear Safety and 10 CFR 810  

Energy.gov (U.S. Department of Energy (DOE))

Exelon respectfully submits that the existing 810 rule, as currently interpreted, and the proposed revised rule, both work as deterrents to improving safety in nuclear operations around the world.

259

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

......System for Research Reactor (IRSRR). Available...System for Research Reactor (IRSRR). Available...76. 7 Manual on reliability data collection for research reactor PSAs. (1992) IAEA...probabilistic safety analysis of incidents in nuclear......

Valdir Maciel Lopes; Gian Maria Agostinho Angelo Sordi; Mauricio Moralles; Tufic Madi Filho

2012-06-01T23:59:59.000Z

260

Interface with the Defense Nuclear Facilities Safety Board  

Directives, Delegations, and Requirements

This Manual presents the process the Department of Energy will use to interface with the Defense Nuclear Facilities Safety Board (DNFSB) and its staff. Cancels DOE M 140.1-1A.

2001-03-30T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Interface with the Defense Nuclear Facilities Safety Board  

Directives, Delegations, and Requirements

The manual defines the process DOE will use to interface with the Defense Nuclear Facilities Safety Board and its staff. Canceled by DOE M 140.1-1A. Does not cancel other directives.

1996-12-30T23:59:59.000Z

262

Interface with the Defense Nuclear Facilities Safety Board  

Directives, Delegations, and Requirements

This Manual presents the process the Department of Energy will use to interface with the Defense Nuclear Facilities Safety Board (DNFSB) and its staff. Cancels DOE M 140.1-1.

1999-01-26T23:59:59.000Z

263

The unique signal concept for detonation safety in nuclear weapons  

SciTech Connect

The purpose of a unique signal (UQS) in a nuclear weapon system is to provide an unambiguous communication of intent to detonate from the UQS information input source device to a stronglink safety device in the weapon in a manner that is highly unlikely to be duplicated or simulated in normal environments and in a broad range of ill-defined abnormal environments. This report presents safety considerations for the design and implementation of UQSs in the context of the overall safety system.

Spray, S.D.; Cooper, J.A.

1993-06-01T23:59:59.000Z

264

THE IMPACT OF THE GLOBAL NUCLEAR SAFETY REGIME IN BRAZIL  

SciTech Connect

A turning point of the world nuclear industry with respect to safety occurred due to the accident at Chernobyl, in 1986. A side from the tragic personal losses and the enormous financial damage, the Chernobyl accident has literally demonstrated that ''a nuclear accident anywhere is an accident everywhere''. The impact was felt immediately by the nuclear industry, with plant cancellations (e.g. Austria), elimination of national programs (e.g. Italy) and general construction delays. However, the reaction of the nuclear industry was equally immediate, which led to the proposal and establishment of a Global Nuclear Safety Regime. This regime is composed of biding international safety conventions, globally accepted safety standard, and a voluntary peer review system. In a previous work, the author has presented in detail the components of this Regime, and briefly discussed its impact in the Brazilian nuclear power organizations, including the Regulatory Body. This work, on the opposite, briefly reviews the Global Nuclear Safety Regime, and concentrates in detail in the discussion of its impact in Brazil, showing how it has produced some changes, and where the peer pressure regime has failed to produce real results.

Almeida, C.

2004-10-06T23:59:59.000Z

265

Preliminary Criticality Safety Evaluation for In Situ Grouting in the Subsurface Disposal Area  

SciTech Connect

A preliminary criticality safety evaluation is presented for in situ grouting in the Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory. The grouting materials evaluated are cement and paraffin. The evaluation determines physical and administrative controls necessary to preclude criticality and identifies additional information required for a final criticality safety evaluation. The evaluation shows that there are no criticality concerns with cementitious grout but a neutron poison such as boron would be required for the use of the paraffin matrix.

Slate, Lawrence J; Taylor, Joseph Todd

2000-08-01T23:59:59.000Z

266

Preliminary Criticality Safety Evaluation for In Situ Grouting in the Subsurface Disposal Area  

SciTech Connect

A preliminary criticality safety evaluation is presented for in situ grouting in the Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory. The grouting materials evaluated are cement and paraffin. The evaluation determines physical and administrative controls necessary to preclude criticality and identifies additional information required for a final criticality safety evaluation. The evaluation shows that there are no criticality concerns with cementitious grout but a neutron poison such as boron would be required for the use of the paraffin matrix.

Slate, L.J.; Taylor, J.T.

2000-08-31T23:59:59.000Z

267

THE RADIATION SAFETY INFORMATION COMPUTATIONAL CENTER (RSICC) - A RESOURCE FOR COMPUTATIONAL TOOLS FOR NUCLEAR APPLICATIONS  

SciTech Connect

The Radiation Safety Information Computational Center (RSICC), which has been in existence since 1963, is the principal source and repository in the United States for computational tools for nuclear applications. RSICC collects, organizes, evaluates and distributes nuclear software and data involving the transport of neutral and charged particle radiation, and shielding and protection from radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste. RSICC serves over 12,000 scientists and engineers from 94 countries. RSICC software provides in-depth coverage of radiation related topics: the physics of the interaction of radiation with matter, radiation production and sources, criticality safety, radiation protection and shielding, radiation detectors and measurements, shielding materials properties, radiation waste management, atmospheric dispersion and environmental dose, medical applications, macro- and micro-dosimetry calculations.

Kirk, Bernadette Lugue [ORNL] [ORNL

2009-01-01T23:59:59.000Z

268

Nonreactor Nuclear Safety Design Guide for use with DOE O 420.1C, Facility Safety  

Directives, Delegations, and Requirements

This Guide provides an acceptable approach for safety design of DOE hazard category 1, 2 and 3 nuclear facilities for satisfying the requirements of DOE O 420.1C. Cancels DOE G 420.1-1.

2012-12-04T23:59:59.000Z

269

A Safer Nuclear Enterprise - Application to Nuclear Explosive Safety (NES)(U)  

SciTech Connect

Activities and infrastructure that support nuclear weapons are facing significant challenges. Despite an admirable record and firm commitment to make safety a primary criterion in weapons design, production, handling, and deployment - there is growing apprehension about terrorist acquiring weapons or nuclear material. At the NES Workshop in May 2012, Scott Sagan, who is a proponent of the normal accident cycle, presented. Whether a proponent of the normal accident cycle or High Reliability Organizations - we have to be diligent about our safety record. Constant vigilance is necessary to maintain our admirable safety record and commitment to Nuclear Explosive Safety.

Morris, Tommy J. [Los Alamos National Laboratory

2012-07-05T23:59:59.000Z

270

Nuclear Safety Research and Development (NSR&D) Program | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety » Nuclear Safety Research and Nuclear Safety » Nuclear Safety Research and Development (NSR&D) Program Nuclear Safety Research and Development (NSR&D) Program In 2011, the Office of Health, Safety and Security (HSS) created the Nuclear Safety Research and Development (NSR&D) Program within the Office of Nuclear Safety to provide corporate-level leadership supporting nuclear safety research and development throughout the Department of Energy (DOE). The NSR&D Program solicits input from the Nuclear Safety Council which includes membership of senior management from each program office. NSR&D Program Objectives: To establish an enduring Departmental commitment and capability to utilize NSR&D in preventing and reducing the hazards and risks posed by DOE/NNSA nuclear facilities;

271

Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Energy Institute (NEI) Attachment, Integrated Safety Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis Nuclear Energy Institute (NEI) Attachment, Integrated Safety Analysis This paper addresses why the use of an Integrated Safety Analysis ("ISA") is appropriate for fuel recycling facilities1 which would be licensed under new regulations currently being considered by NRC. The use of the ISA for fuel facilities under Part 70 is described and compared to the use of a Probabilistic Risk Assessment ("PRA") for reactor facilities. A basis is provided for concluding that future recycling facilities - which will possess characteristics similar to today's fuel cycle facilities and distinct from reactors - can best be assessed using established qualitative or semi-quantitative ISA techniques to achieve and

272

Department of Energy Office of Nuclear Safety and Environmental Policy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Department of Energy Office of Nuclear Safety and Environmental Department of Energy Office of Nuclear Safety and Environmental Policy Technical Position NSEP-TP-2007- 1, Technical Position on the Requirement in DOE 0 420.1B to Use National Consensus Industry Standards and the Model Building CodesTechnical Position NS Department of Energy Office of Nuclear Safety and Environmental Policy Technical Position NSEP-TP-2007- 1, Technical Position on the Requirement in DOE 0 420.1B to Use National Consensus Industry Standards and the Model Building CodesTechnical Position NS All new construction required to follow the provisions of Department of Energy (DOE) Order 420. lB, Facility Safety, must comply with national consensus industry standards and the model building codes applicable for the state or region in which the facility is located. Certain individuals in the fire community requested

273

Facility Safety  

Directives, Delegations, and Requirements

The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

2005-12-22T23:59:59.000Z

274

Energy Department and Catholic University Improve Safety of Nuclear Waste |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Catholic University Improve Safety of Nuclear Catholic University Improve Safety of Nuclear Waste Energy Department and Catholic University Improve Safety of Nuclear Waste January 30, 2013 - 12:51pm Addthis Secretary of Energy Steven Chu participates in a tour of Catholic University's Vitreous State Laboratory. | Photo courtesy of the Office of Environmental Management. Secretary of Energy Steven Chu participates in a tour of Catholic University's Vitreous State Laboratory. | Photo courtesy of the Office of Environmental Management. David Sheeley David Sheeley Editor/Writer What does this project do? Hanford treats and immobilizes significant quantities of legacy nuclear waste left from the manufacture of plutonium during World War II and the Cold War. Secretary Steven Chu recently visited Catholic University's Vitreous

275

Reactor Physics and Criticality Benchmark Evaluations for Advanced Nuclear Fuel - Final Technical Report  

SciTech Connect

The nuclear industry interest in advanced fuel and reactor design often drives towards fuel with uranium enrichments greater than 5 wt% 235U. Unfortunately, little data exists, in the form of reactor physics and criticality benchmarks, for uranium enrichments ranging between 5 and 10 wt% 235U. The primary purpose of this project is to provide benchmarks for fuel similar to what may be required for advanced light water reactors (LWRs). These experiments will ultimately provide additional information for application to the criticality-safety bases for commercial fuel facilities handling greater than 5 wt% 235U fuel.

William Anderson; James Tulenko; Bradley Rearden; Gary Harms

2008-09-11T23:59:59.000Z

276

A model-based framework for flexible safety-critical software development: a design study  

Science Journals Connector (OSTI)

This paper presents the findings from a design study of a model-based framework for safety-critical software development, called SimPal. The objective of the study was to better understand the necessary properties of such a framework and to learn ... Keywords: frameworks and tools, real-time systems, safety-critical development, service-oriented computing, verification

Jesper Pedersen Notander; Per Runeson; Martin Hst

2013-03-01T23:59:59.000Z

277

SimPal: a design study on a framework for flexible safety-critical software development  

Science Journals Connector (OSTI)

This paper presents the findings from a design study on a framework for flexible safety-critical software development, called SimPal. It is an extended version of a paper that was published in SAC'13 Proceedings of the 2013 ACM Symposium on Applied ... Keywords: frameworks and tools, real-time systems, safety-critical development, service-oriented computing, verification

Jesper Pedersen Notander; Per Runeson; Martin Hst

2013-12-01T23:59:59.000Z

278

Safety - Vulnerability Assessment Team - Nuclear Engineering Division  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Safety VAT Projects Introducing the VAT Adversarial Vulnerability Assessments Safety Tags & Product Counterfeiting Election Security Spoofing GPS Defeating Existing Tamper-Indicating Seals Specialty Field Tools & Sampling Tools Insider Threat Mitigation Drug Testing Security Microprocessor Prototypes The Journal of Physical Security Vulnerability Assessments Vulnerability Assessments Insanely Fast µProcessor Shop Insanely Fast µProcessor Shop Seals About Seals Applications of Seals Common Myths about Tamper Indicating Seals Definitions Findings and Lessons Learned New Seals Types of Seals Seals References Selected VAT Papers Selected VAT Papers Selected Invited Talks Self-Assessment Survey Security Maxims Devil's Dictionary of Security Terms Argonne's VAT (brochure)

279

Criticality Safety Information Meeting for the Hanford Plutonium Finihsing Plant, May 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2-05-14 2-05-14 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Criticality Safety Information Meeting for the Plutonium Finishing Plant Dates of Activity : May 14, 2012 Report Preparer: Ivon Fergus Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety issues and experiences principally with respect to the Decontamination and Decommissioning (D&D) activities at the Plutonium Finishing Plant (PFP). These discussions also included aspects of Non-

280

Criticality Safety Information Meeting for the Hanford Plutonium Finihsing Plant, May 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

2-05-14 2-05-14 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Criticality Safety Information Meeting for the Plutonium Finishing Plant Dates of Activity : May 14, 2012 Report Preparer: Ivon Fergus Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety issues and experiences principally with respect to the Decontamination and Decommissioning (D&D) activities at the Plutonium Finishing Plant (PFP). These discussions also included aspects of Non-

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Review of the Nevada National Security Site Criticality Safety Program Corrective Action Plan Closure, May 2013  

NLE Websites -- All DOE Office Websites (Extended Search)

Nevada National Security Site Nevada National Security Site Criticality Safety Program Corrective Action Plan Closure May 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................ 1 2.0 Scope.................................................................................................................................................. 1 3.0 Background ......................................................................................................................................... 1 4.0 Methodology ....................................................................................................................................... 2

282

Review of the Nevada National Security Site Criticality Safety Program Corrective Action Plan Closure, May 2013  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nevada National Security Site Nevada National Security Site Criticality Safety Program Corrective Action Plan Closure May 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................ 1 2.0 Scope.................................................................................................................................................. 1 3.0 Background ......................................................................................................................................... 1 4.0 Methodology ....................................................................................................................................... 2

283

Adapting the FMEA for Safety Critical Design Processes  

Science Journals Connector (OSTI)

Functional safety standards (ISO 26262, IEC 61508) require a safety life cycle which demands additional design and engineering tasks to be managed. This paper addresses how the existing FMEAs have to be extended ...

Ovi Bachmann; Bernhardt Messner

2011-01-01T23:59:59.000Z

284

Nuclear Power - Operation, Safety and Environment  

E-Print Network (OSTI)

as operation, safety, environment and radiation effects. The book is not offering a comprehensive coverage of the material in each area. Instead, selected themes are highlighted by authors of individual chapters representing contemporary interests worldwide...

285

Office of Nuclear Safety | Department of Energy  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

and Security Officer regarding concurrence in the final decision to startup or restart a nuclear facility. Serves as the Standards Executive for the Department of Energy and...

286

Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facts and Lessons of the Fukushima Nuclear Accident and Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints September 19, 2012 Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company Topics Covered: How Tsunami Struck Fukushima Sites Tsunami Height Estimation How we responded in the Recovery Process Safety Improvement and Further Enhancement of Nuclear Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints More Documents & Publications January2005 NNSANews Meeting Materials: June 15, 2011

287

DOE-STD-1173-2003; Criticality Safety Functional Area Qualification Standard  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

73-2003 73-2003 December 2003 DOE STANDARD CRITICALITY SAFETY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1173-2003 ii This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-1173-2003

288

Guidance for identifying, reporting and tracking nuclear safety noncompliances  

SciTech Connect

This document provides Department of Energy (DOE) contractors, subcontractors and suppliers with guidance in the effective use of DOE`s Price-Anderson nuclear safety Noncompliance Tracking System (NTS). Prompt contractor identification, reporting to DOE, and correction of nuclear safety noncompliances provides DOE with a basis to exercise enforcement discretion to mitigate civil penalties, and suspend the issuance of Notices of Violation for certain violations. Use of this reporting methodology is elective by contractors; however, this methodology is intended to reflect DOE`s philosophy on effective identification and reporting of nuclear safety noncompliances. To the extent that these expectations are met for particular noncompliances, DOE intends to appropriately exercise its enforcement discretion in considering whether, and to what extent, to undertake enforcement action.

NONE

1995-12-01T23:59:59.000Z

289

Facility Safety  

Directives, Delegations, and Requirements

Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

1995-10-13T23:59:59.000Z

290

Facility Safety  

Directives, Delegations, and Requirements

The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

2012-12-04T23:59:59.000Z

291

Facility Safety  

Directives, Delegations, and Requirements

This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

2005-12-22T23:59:59.000Z

292

Department of Energy Nuclear Safety Policy  

Directives, Delegations, and Requirements

It is the policy of the Department of Energy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment. Cancels SEN-35-91.

2011-02-08T23:59:59.000Z

293

Nuclear Safety Enforcement Documents | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Letter, NEL-2013-01 - January 7, 2013 Issued to B&W Pantex, LLC related to the Conduct of Nuclear Explosive Operations at the Pantex Plant October 4, 2012 Preliminary Notice of...

294

E-Print Network 3.0 - aerospace nuclear safety Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

and Nuclear Technologies 2 A Systematic Approach to Safety Case Management Dr Tim Kelly Summary: The concept of the safety case' has already been adopted across many...

295

Processing Exemptions to Nuclear Safety Rules and Approval of Alternative Methods for Documented Safety Analysis  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

STD-1083-2009 STD-1083-2009 June 2009 DOE STANDARD PROCESSING EXEMPTIONS TO NUCLEAR SAFETY RULES AND APPROVAL OF ALTERNATIVE METHODS FOR DOCUMENTED SAFETY ANALYSES U.S. Department of Energy AREA SAFT Washington D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document is available on the Department of Energy Technical Standards Program Web Page at http://www.hss.energy.gov/nuclearsafety/techstds DOE-STD-1083-2009 iii FOREWORD 1. This Department of Energy (DOE) Standard has been prepared by the Office of Quality Assurance Policy and Assistance to provide acceptable processes for: a. requesting and granting exemptions to DOE nuclear safety rules and b. requesting and approving alternate methodologies for documented safety analyses

296

Criticality Safety Controls Implementation, May 31, 2013 (HSS CRAD 45-18, Rev. 1)  

Energy.gov (U.S. Department of Energy (DOE))

The Department of Energy (DOE) has set expectations for implementing criticality safety controls that are selected to provide preventive and/or mitigative functions for specific potential accident scenarios. There are additional expectations for criticality safety controls that are also designated as Specific Administrative Controls (see HSS CRAD 64-32). The following provides a set of criteria and typical activities with representative lines of inquiry to assess criticality control implementation as an integral part of the review of the core functions and implementation of integrated safety management.

297

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Health and Safety Aspects of Pro- posed Nuclear, Geothermal, and Fossil-FuelHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel

Nero, A.V.

2010-01-01T23:59:59.000Z

298

Improved nuclear safety through international standards  

Science Journals Connector (OSTI)

In this shrinking world what happens in an industry in one country can significantly affect the same industry elsewhere around the globe. In April 1986 a nuclear accident destroyed Unit 4 of Ukraines Chernobyl nuclear power plant focusing worldwide attention on the dozens of Soviet-designed reactors still in operation. The Chemobyl accident led to public concerns about all operating nuclear power plants and in some countries (e.g. Italy and Sweden) to proposals for nationwide plant closures or moratoriums on new construction. However for most former Soviet Union countries plant shutdown was and still is not a viable optionthe plants produce a significant percentage of each nations total electricity and those countries do not have sufficient economic resources to develop alternative power sources. In cooperation with similar programs initiated in Canada Japan and western European countries the U.S. Department of Energy (DOE) is conducting a comprehensive effort to reduce risks at Soviet-designed nuclear power plants until they can be shut down or brought into compliance with international standards. This paper describes DOE-supported initiatives with participating host countries to: improve reliability and accuracy of nondestructive evaluation equipment used for in-service inspection transfer technologies and infrastructure to improve in-service inspections enhance management systems for training and certifying host-country in-service inspection personnel The goal of these initiatives to enhance the use of international standards (ASME ASNT European Standards EN and ISO) in operating and regulatory practices at Soviet-designed nuclear power plants.

S. R. Doctor; R. L. Moffitt; T. T. Taylor; G. Trosman

2000-01-01T23:59:59.000Z

299

Safety system augmentation at Russian nuclear power plants  

SciTech Connect

This paper describes the design and procurement of a Class IE DC power supply system to upgrade plant safety at the Kola Nuclear Power Plant (NPP). Kola NPP is located above the Arctic circle at Polyarnie Zorie, Murmansk, Russia. Kola NPP consists of four units. Units 1 and 2 have VVER-440/230 type reactors: Units 3 and 4 have VVER-440/213 type reactors. The VVER-440 reactor design is similar to the pressurized water reactor design used in the US. This project provided redundant, Class 1E DC station batteries and DC switchboards for Kola NPP, Units 1 and 2. The new DC power supply system was designed and procured in compliance with current nuclear design practices and requirements. Technical issues that needed to be addressed included reconciling the requirements in both US and Russian codes and satisfying the requirements of the Russian nuclear regulatory authority. Close interface with ATOMENERGOPROEKT (AEP), the Russian design organization, KOLA NPP plant personnel, and GOSATOMNADZOR (GAN), the Russian version of US Nuclear Regulatory Commission, was necessary to develop a design that would assure compliance with current Russian design requirements. Hence, this project was expected to serve as an example for plant upgrades at other similar VVER-440 nuclear plants. In addition to technical issues, the project needed to address language barriers and the logistics of shipping equipment to a remote section of the Former Soviet Union (FSU). This project was executed by Burns and Roe under the sponsorship of the US DOE as part of the International Safety Program (INSP). The INSP is a comprehensive effort, in cooperation with partners in other countries, to improve nuclear safety worldwide. A major element within the INSP is the improvement of the safety of Soviet-designed nuclear reactors.

Scerbo, J.A.; Satpute, S.N.; Donkin, J.Y.; Reister, R.A. [Burns and Roe, Oradell, NJ (United States); [Department of Energy, Germantown, MD (United States)

1996-12-31T23:59:59.000Z

300

Development of the Nuclear Safety Information Dashboard- September 2012  

Energy.gov (U.S. Department of Energy (DOE))

A working group with nuclear safety expertise used paired pairing computer software to develop first, a severity-weighted factor for the 17 Groups of ORPS Reporting Criteria and then, a severity-weighted factor for the sixty-five ORPS reporting criteria.

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Critical processes and performance measures for patient safety systems in healthcare institutions: a Delphi study  

E-Print Network (OSTI)

This dissertation study presents a conceptual framework for implementing and assessing patient safety systems in healthcare institutions. The conceptual framework consists of critical processes and performance measures identified in the context...

Akins, Ralitsa B.

2004-11-15T23:59:59.000Z

302

Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010  

Energy.gov (U.S. Department of Energy (DOE))

On August 12, 2009, the Defense Nuclear Facilities Safety Board(DNFSB) issued Recommendation 2009?1, Risk Assessment Methodologies at Defense Nuclear Facilities. Thisrecommendation focused on the...

303

Review of Nevada Site Office Criticality Safety Assessments at...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

an independent review of the National Nuclear Security AdministrationNevada Site Office Conduct of Operations Management Assessment Final Report, dated October 2011. The subject...

304

Pipeline Safety Our goal is to provide standard test methods and critical data to  

E-Print Network (OSTI)

Pipeline Safety METALS Our goal is to provide standard test methods and critical data to the pipeline industry to improve safety and reliability. Of particular interest is the testing of high-strength pipeline steels, which could enable higher volume gas transport and reduce energy costs. However

305

Pipeline Safety Our goal is to provide standard test methods and critical data to  

E-Print Network (OSTI)

Pipeline Safety METALS Our goal is to provide standard test methods and critical data to the pipeline industry to improve safety and reliability. Of particular interest is the testing of high strength pipeline steels, which could enable higher volume gas transport and reduce energy costs. However

306

Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Risk Assessment in Support of DOE Nuclear Safety, Risk Information Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010 Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010 On August 12, 2009, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 2009-1, Risk Assessment Methodologies at Defense Nuclear Facilities. This recommendation focused on the need for clear direction on use of quantitative risk assessments in nuclear safety applications at defense nuclear facilities. The Department of Energy (DOE) is presently analyzing directives, standards, training, and other tools that may support more effective development and use of risk assessment. Working with the Chief of Defense Nuclear Safety and the Chief of Nuclear Safety, staff from the Office of Health,

307

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

NLE Websites -- All DOE Office Websites (Extended Search)

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

308

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

309

Secure Safety: Secure Remote Access to Critical Safety Systems in Offshore Installations  

Science Journals Connector (OSTI)

Safety Instrumented Systems (SIS) as defined in IEC 61508 and IEC 61511 are very important for the safety of offshore oil & natural gas installations. SIS typically include the Emergency Shutdown System (ESD) that ensures that process systems return ... Keywords: Offshore, Process Control, Safety Instrumented Systems, Secure remote access

Martin Gilje Jaatun; Tor Olav Grtan; Maria B. Line

2008-06-01T23:59:59.000Z

310

Criticality Safety Controls Implementation, May 31, 2013 (HSS CRAD 45-18, Rev. 1)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Energy Office of Safety and Emergency Management Evaluations Criteria and Review Approach Document 1.0 PURPOSE Subj ect: Criticality Safety Controls lmplementation - Criteria and Review Approach Document Acting D ~·ector, Office of Safety and Emergency Management Eva luations Date: May 3 I, 2013 Date: May 3 I, 2013 Page 1 of 5 H S: HSS CRAD 45- 18 Rev: I E ff. Date : May 3 I, 201 3 Page I of 5 Within the Office of Health, Safety and Security (HSS), the Office of Enforcement and Overs ight, Office of Safety and Emergency Management Evaluations ' (HS-45) mission is to assess the effectiveness of the environment, safety, health and emergency management systems and practices used by line and contractor organ izations in implementing Integrated Safety Management; and to provide clear, concise,

311

Safety assessment of a robotic system handling nuclear material  

SciTech Connect

This paper outlines the use of a Failure Modes and Effects Analysis for the safety assessment of a robotic system being developed at Sandia National Laboratories. The robotic system, The Weigh and Leak Check System, is to replace a manual process at the Department of Energy facility at Pantex by which nuclear material is inspected for weight and leakage. Failure Modes and Effects Analyses were completed for the robotics process to ensure that safety goals for the system had been meet. These analyses showed that the risks to people and the internal and external environment were acceptable.

Atcitty, C.B.; Robinson, D.G.

1996-02-01T23:59:59.000Z

312

Illustrating the AADL error modeling annex (v.2) using a simple safety-critical medical device  

Science Journals Connector (OSTI)

Developing and certifying safety-critical and highly reliable systems almost always includes significant emphasis on hazard analysis and risk assessment. There have been substantial improvements in automation and formalization of other aspects of critical ... Keywords: aadl, error analysis, error modeling, formal architecture, hazard analysis, risk assessment

Brian Larson; John Hatcliff; Kim Fowler; Julien Delange

2013-11-01T23:59:59.000Z

313

Nuclear Criticality as a Contributor to Gamma Ray Burst Events  

E-Print Network (OSTI)

Most gamma ray bursts are able to be explained using supernovae related phenomenon. Some measured results still lack compelling explanations and a contributory cause from nuclear criticality is proposed. This is shown to have general properties consistent with various known gamma ray burst properties. The galactic origin of fast rise exponential decay gamma ray bursts is considered a strong candidate for these types of events.

Robert Bruce Hayes

2013-01-15T23:59:59.000Z

314

Nuclear Explosives Safety Study Functional Area Qualification Standard  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

85-2007 85-2007 September 2007 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DRAFT DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DRAFT DOE-STD-1185-2007 iv INTENTIONALLY BLANK DRAFT DOE-STD-1185-2007 v TABLE OF CONTENTS ACKNOWLEDGMENT ................................................................................................................ vii PURPOSE ....................................................................................................................................1

315

History of US nuclear weapon safety assessment: The early years  

SciTech Connect

From the beginnings of the U.S. nuclear weapons program, military and civilian dual- agency judgment has been fundamental to achieving nuclear weapon and weapon system safety. This interaction was initiated by the Atomic Energy Act of 1946, which created the Atomic Energy Commission (AEC). The principle of using dual-agency judgment has been perpetuated in the design and assessment of the weapon and weapon system acceptance process since that time. This fundamental approach is still used today in all phases of the weapon life. In this paper, an overview of the history and philosophy of the approach is described.

Spray, S.D.

1996-06-01T23:59:59.000Z

316

Double-clad nuclear-fuel safety rod  

DOE Patents (OSTI)

A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

McCarthy, W.H.; Atcheson, D.B.

1981-12-30T23:59:59.000Z

317

Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SENSITIVE DOE-STD-1104-2009 May 2009 Superseding DOE-STD-1104-96 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2009 ii Available on the Department of Energy Technical Standards web page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1104-2009 iii CONTENTS FOREWORD .................................................................................................................................. v INTRODUCTION ..........................................................................................................................

318

On the Integration of Requirements Analysis and Safety Analysis for Safety-Critical Software  

E-Print Network (OSTI)

this is acceptable within the context of system risk. The advantage of conducting the safety analysis during is acceptable within the overall #12;2 system risk. If the risk is not acceptable the safety specification has analysis is to determine the risk associated with requirements specifications and assess whether

Newcastle upon Tyne, University of

319

Criticality safety analysis of a borated-concrete absorber  

SciTech Connect

Fuel cycle facilities use slab tanks to store fissile solutions, because these tanks have both a high volume-to-floorspace efficiency and an easily verifiable, criticality control (thickness). The results of preliminary criticality analyses using a validated computer code and cross-section library, indicate that a slab tank designed without a solid neutron absorber is not economical in view of process requirements (inventory) and space limitations (layout). A subsequent calculational study assessed the possible increase in the thickness of a single, isolated slab tank using a solid neutron absorber. Finally, an analysis was performed to evaluate the maximum slab thickness for an array of tank/absorbers. The result of these studies showed the potential for expansion of slab tank thickness. 7 refs., 5 figs., 7 tabs.

Funabashi, H.; Oka, T.; Matsumoto, T.; Smolen, G.R. (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan); Oak Ridge National Lab., TN (USA))

1989-01-01T23:59:59.000Z

320

CRAD, New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements- December 2, 2014 (EA CRAD 31-07, Rev. 0)  

Energy.gov (U.S. Department of Energy (DOE))

New Nuclear Facility Documented Safety Analysis and Technical Safety Requirements Criteria Review and Approach Document (EA CRAD 31-07, Rev. 0)

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Major safety and operational concerns for fuel debris criticality control  

SciTech Connect

It can be seen from the criticality control viewpoint that the requirement divides the decommissioning work into two parts. One is the present condition where it is requested to prevent criticality and to monitor subcritical condition while the debris is untouched. The other is future work where the subcritical condition shall be ensured even if the debris condition is changed intentionally by raising water level, debris retrieval, etc. Repair of damages on the containment vessel (CV) walls is one of the most important objectives at present in the site. On completion of this task, it will become possible to raise water levels in the CVs and to shield the extremely high radiation emitted from the debris but there is a dilemma: raising the water level in the CVs implies to bring the debris closer to criticality because of the role of water for slowing down neutrons. This may be solved if the coolant water will start circulating in closed loops, and if a sufficient concentration of soluble neutron poison (borated water for instance) will be introduced in the loop. It should be still noted that this solution has a risk of worsening corrosion of the CV walls. Design of the retrieval operation of debris should be proposed as early as possible, which must include a neutron poison concentration required to ensure that the debris chunk is subcritical. In parallel, the development of the measurement system to monitor subcritical condition of the debris chunk should be conducted in case the borated water cannot be used continuously. The system would be based on a neutron counter with a high sensitivity and an appropriate shield for gamma-rays, and the adequate statistical signal processing.

Tonoike, K.; Sono, H.; Umeda, M.; Yamane, Y.; Kugo, T.; Suyama, K. [Fukushima Project Team, Japan Atomic Energy Agency Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 (Japan)

2013-07-01T23:59:59.000Z

322

DOE-STD-1134-99 Review Guide for Criticality Safety Evaluations  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4-99 4-99 September 1999 DOE STANDARD REVIEW GUIDE FOR CRITICALITY SAFETY EVALUATIONS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-1134-99 iii FOREWORD This Department of Energy Standard is approved for use by all DOE criticality safety personnel. It contains guidelines that should be followed when reviewing Criticality Safety Evaluations that

323

Nuclear Facility Safety Basis Fundamentals Self-Study Guide - November 2002  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Operations Office Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)] November 2002 Nuclear Facility Safety Basis Fundamentals Self-Study Guide TABLE OF CONTENTS Acronyms and Abbreviations ......................................................................................... iii List of Figures ....................................................................................................................iv List of Tables......................................................................................................................iv INTRODUCTION..............................................................................................................1

324

Iterative methods for solving nonlinear problems of nuclear reactor criticality  

SciTech Connect

The paper presents iterative methods for calculating the neutron flux distribution in nonlinear problems of nuclear reactor criticality. Algorithms for solving equations for variations in the neutron flux are considered. Convergence of the iterative processes is studied for two nonlinear problems in which macroscopic interaction cross sections are functionals of the spatial neutron distribution. In the first problem, the neutron flux distribution depends on the water coolant density, and in the second one, it depends on the fuel temperature. Simple relationships connecting the vapor content and the temperature with the neutron flux are used.

Kuz'min, A. M., E-mail: mephi.kam@mail.ru [National Research Nuclear University MEPhI (Russian Federation)

2012-12-15T23:59:59.000Z

325

DICE: Database for the International Criticality Safety Benchmark Evaluation Program Handbook  

SciTech Connect

The 2002 edition of the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments' (ICSBEP Handbook) spans more than 26 000 pages and contains 330 evaluations with benchmark specifications for 2881 critical or near-critical configurations. With such a large content, it became evident that the users needed more than a broad and qualitative classification of experiments to make efficient use of the ICSBEP Handbook. This paper describes the features of Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments (DICE), which is a database for the ICSBEP Handbook. The DICE program contains a relational database loaded with selected information from each configuration and a users' interface that enables one to query the database and to extract specific parameters. Summary descriptions of each experimental configuration can also be obtained. In addition, plotting capabilities provide the means of comparing neutron spectra and sensitivity coefficients for a set of configurations.

Nouri, Ali [Organization for Economic Co-operation and Development Nuclear Energy Agency (France); Nagel, Pierre [Organization for Economic Co-operation and Development Nuclear Energy Agency (France); Briggs, J. Blair [Idaho National Engineering and Environmental Laboratory (United States); Ivanova, Tatiana [Institute of Physics and Power Engineering (Russian Federation)

2003-09-15T23:59:59.000Z

326

Spent nuclear fuel project - criteria document spent nuclear fuel final safety analysis report  

SciTech Connect

The criteria document provides the criteria and planning guidance for developing the Spent Nuclear Fuel (SNF) Final Safety Analysis Report (FSAR). This FSAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, installation acceptance testing, startup, and operation of the SNF Project facilities (K Basins, Cold Vacuum Drying Facility, and Canister Storage Building).

MORGAN, R.G.

1999-02-23T23:59:59.000Z

327

DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: 2-08-2011  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: 2-08-2011 DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: 2-08-2011 PURPOSE: To document the Department of Energy's (DOE) nuclear safety policy. SCOPE: The provisions of this policy apply to all Departmental elements with responsibility for a nuclear facility, except the Naval Nuclear Propulsion Program, which is separately covered under Executive Order 12344, Title 50 United States Code, sections 2406 and 2511. This Policy cancels Secretary of Energy Notice 35-91, Nuclear Safety Policy, dated 9-9-91. POLICY: It is the policy of the Department of Energy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment.

328

Price-Anderson Nuclear Safety Enforcement Program. 1997 annual report  

SciTech Connect

This report summarizes activities in the Department of Energy's Price-Anderson Amendments Act (PAAA) Enforcement Program in calendar year 1997 and highlights improvements planned for 1998. The DOE Enforcement Program involves the Office of Enforcement and Investigation in the DOE Headquarters Office of Environment, Safety and Health, as well as numerous PAAA Coordinators and technical advisors in DOE Field and Program Offices. The DOE Enforcement Program issued 13 Notices of Violation (NOV`s) in 1997 for cases involving significant or potentially significant nuclear safety violations. Six of these included civil penalties totaling $440,000. Highlights of these actions include: (1) Brookhaven National Laboratory Radiological Control Violations / Associated Universities, Inc.; (2) Bioassay Program Violations at Mound / EG and G, Inc.; (3) Savannah River Crane Operator Uptake / Westinghouse Savannah River Company; (4) Waste Calciner Worker Uptake / Lockheed-Martin Idaho Technologies Company; and (5) Reactor Scram and Records Destruction at Sandia / Sandia Corporation (Lockheed-Martin).

NONE

1998-01-01T23:59:59.000Z

329

Implementing 10 CFR 830 at the FEMP Silos: Nuclear Health and Safety Plans as Documented Safety Analysis  

SciTech Connect

The objective of the Silos Project at the Fernald Closure Project (FCP) is to safely remediate high-grade uranium ore residues (Silos 1 and 2) and metal oxide residues (Silo 3). The evolution of Documented Safety Analyses (DSAs) for these facilities has reflected the changes in remediation processes. The final stage in silos DSAs is an interpretation of 10 CFR 830 Safe Harbor Requirements that combines a Health and Safety Plan with nuclear safety requirements. This paper will address the development of a Nuclear Health and Safety Plan, or N-HASP.

Fisk, Patricia; Rutherford, Lavon

2003-06-01T23:59:59.000Z

330

THE RADIATION SAFETY INFORMATION COMPUTATIONAL CENTER: A RESOURCE FOR REACTOR DOSIMETRY SOFTWARE AND NUCLEAR DATA  

SciTech Connect

The Radiation Safety Information Computational Center (RSICC) was established in 1963 to collect and disseminate computational nuclear technology in the form of radiation transport, shielding and safety software and corresponding nuclear cross sections. Approximately 1700 nuclear software and data packages are in the RSICC collection, and the majority are applicable to reactor dosimetry.

Kirk, Bernadette Lugue [ORNL] [ORNL

2009-01-01T23:59:59.000Z

331

ROBERT J. BUDNITZ Occupation: Physicist in Energy/Environmental Research and Nuclear Safety  

E-Print Network (OSTI)

ROBERT J. BUDNITZ Occupation: Physicist in Energy/Environmental Research and Nuclear Safety Birth December 2004 to September 2007 (in Livermore): Leader, Nuclear & Risk Science Group, Energy & Environment Directorate Associate Program Leader for Nuclear Systems Safety and Security, E&E Directorate October 2002

Ajo-Franklin, Jonathan

332

Criticality safety concerns of uranium deposits in cascade equipment  

SciTech Connect

The Paducah and Portsmouth Gaseous Diffusion Plants enrich uranium in the {sup 235}U isotope by diffusing gaseous uranium hexafluoride (UF{sub 6}) through a porous barrier. The UF{sub 6} gaseous diffusion cascade utilized several thousand {open_quotes}stages{close_quotes} of barrier to produce highly enriched uranium (HEU). Historically, Portsmouth has enriched the Paducah Gaseous Diffusion Plant`s product (typically 1.8 wt% {sup 235}U) as well as natural enrichment feed stock up to 97 wt%. Due to the chemical reactivity of UF{sub 6}, particularly with water, the formation of solid uranium deposits occur at a gaseous diffusion plant. Much of the equipment operates below atmospheric pressure, and deposits are formed when atmospheric air enters the cascade. Deposits may also be formed from UF{sub 6} reactions with oil, UF{sub 6} reactions with the metallic surfaces of equipment, and desublimation of UF{sub 6}. The major deposits form as a result of moist air in leakage due to failure of compressor casing flanges, blow-off plates, seals, expansion joint convolutions, and instrument lines. This report describes criticality concerns and deposit disposition.

Plaster, M.J. [Lockheed Martin Utility Services, Inc., Piketon, OH (United States)

1996-12-31T23:59:59.000Z

333

Reliability Engineering and System Safety 92 (2007) 609618 The nuclear industry's transition to risk-informed regulation and  

E-Print Network (OSTI)

Reliability Engineering and System Safety 92 (2007) 609­618 The nuclear industry's transition a Nuclear Science and Engineering Department, Massachusetts Institute of Technology, Cambridge, MA 02139, USA b Nuclear Power Engineering, Quality and Safety Management Department, Tokyo Electric Power

334

Safety culture in the nuclear power industry : attributes for regulatory assessment  

E-Print Network (OSTI)

Safety culture refers to the attitudes, behaviors, and conditions that affect safety performance and often arises in discussions following incidents at nuclear power plants. As it involves both operational and management ...

Alexander, Erin L

2004-01-01T23:59:59.000Z

335

Nuclear Explosive Safety Study Functional Area Qualification Standard  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT SENSITIVE DOE-STD-1185-2007 CHANGE NOTICE No.1 April 2010 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/ns/techstds DOE-STD-1185-2007 iii APPROVAL The Federal Technical Capability Panel consists of senior U.S. Department of Energy (DOE) managers responsible for overseeing the Federal Technical Capability Program. This Panel is

336

Renovated Korean nuclear safety and security system: A review and suggestions to successful settlement  

SciTech Connect

Questions of whether past nuclear regulatory body of Korea is not a proper system to monitor and check the country's nuclear energy policy and utilization have been raised. Moreover, a feeling of insecurity regarding nuclear safety after the nuclear accident in Japan has spread across the public. This has stimulated a renovation of the nuclear safety regime in Korea. The Nuclear Safety and Security Commission (NSSC) was launched on October 26, 2011 as a regulatory body directly under the President in charge of strengthening independence and nuclear safety. This was a meaningful event as the NSSC it is a much more independent regulatory system for Korea. However, the NSSC itself does not guarantee an enhanced public acceptance of the nuclear policy and stable use nuclear energy. This study introduces the new NSSC system and its details in terms of organization structure, appropriateness of specialty, budget stability, and management system. (authors)

Chung, W. S.; Yun, S. W.; Lee, D. S. [Korea Atomic Energy Research Inst., Dukjin-dong 150, Yusung-gu, Daejon, R.O., 305-353 (Korea, Republic of); Go, D. Y. [Kyung Hee Univ., Kyung Hee daero 26, Dongdaemoon-gu, Seoul, R.O., 130-701 (Korea, Republic of)

2012-07-01T23:59:59.000Z

337

Standards-based Assessment of Development Toolchains in Safety-Critical Systems  

E-Print Network (OSTI)

Standards-based Assessment of Development Toolchains in Safety-Critical Systems Zolt´an Szatm in (domain-specific) standards that define criteria for the selection of techniques and measures on the basis of the standard, and a reasoning tool is applied to check whether the criteria are satisfied. I

Paris-Sud XI, Université de

338

Testing of Safety-Critical Software Embedded in an Artificial Heart  

E-Print Network (OSTI)

Testing of Safety-Critical Software Embedded in an Artificial Heart Sungdeok Cha1 , Sehun Jeong1 frequently to control medical devices such as artificial heart or robotic surgery system. While much (KAOC). It is a state-of-the-art artificial heart which completed animal testing phase. We per- formed

339

Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review Plan  

Energy.gov (U.S. Department of Energy (DOE))

This SRP, Nuclear Safety Basis Program Review, consists of five volumes. It provides information to help strengthen the technical rigor of line management oversight and federal monitoring of DOE nuclear facilities. It provides a primer on the safety basis development and documentation process used by the DOE. It also provides a set of LOIs for the review of safety basis programs and documents of nuclear facilities at various stages of the facility life cycle.

340

Safety Criticality Standards Using the French CRISTAL Code Package: Application to the AREVA NP UO{sub 2} Fuel Fabrication Plant  

SciTech Connect

Criticality safety evaluations implement requirements to proof of sufficient sub critical margins outside of the reactor environment for example in fuel fabrication plants. Basic criticality data (i.e., criticality standards) are used in the determination of sub critical margins for all processes involving plutonium or enriched uranium. There are several criticality international standards, e.g., ARH-600, which is one the US nuclear industry relies on. The French Nuclear Safety Authority (DGSNR and its advising body IRSN) has requested AREVA NP to review the criticality standards used for the evaluation of its Low Enriched Uranium fuel fabrication plants with CRISTAL V0, the recently updated French criticality evaluation package. Criticality safety is a concern for every phase of the fabrication process including UF{sub 6} cylinder storage, UF{sub 6}-UO{sub 2} conversion, powder storage, pelletizing, rod loading, assembly fabrication, and assembly transportation. Until 2003, the accepted criticality standards were based on the French CEA work performed in the late seventies with the APOLLO1 cell/assembly computer code. APOLLO1 is a spectral code, used for evaluating the basic characteristics of fuel assemblies for reactor physics applications, which has been enhanced to perform criticality safety calculations. Throughout the years, CRISTAL, starting with APOLLO1 and MORET 3 (a 3D Monte Carlo code), has been improved to account for the growth of its qualification database and for increasing user requirements. Today, CRISTAL V0 is an up-to-date computational tool incorporating a modern basic microscopic cross section set based on JEF2.2 and the comprehensive APOLLO2 and MORET 4 codes. APOLLO2 is well suited for criticality standards calculations as it includes a sophisticated self shielding approach, a P{sub ij} flux determination, and a 1D transport (S{sub n}) process. CRISTAL V0 is the result of more than five years of development work focusing on theoretical approaches and the implementation of user-friendly graphical interfaces. Due to its comprehensive physical simulation and thanks to its broad qualification database with more than a thousand benchmark/calculation comparisons, CRISTAL V0 provides outstanding and reliable accuracy for criticality evaluations for configurations covering the entire fuel cycle (i.e. from enrichment, pellet/assembly fabrication, transportation, to fuel reprocessing). After a brief description of the calculation scheme and the physics algorithms used in this code package, results for the various fissile media encountered in a UO{sub 2} fuel fabrication plant will be detailed and discussed. (authors)

Doucet, M.; Durant Terrasson, L.; Mouton, J. [AREVA-NP (France)

2006-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

DOE P 420.1 Department of Energy Nuclear Safety Policy, Approved: 2-08-2011  

Energy.gov (U.S. Department of Energy (DOE))

PURPOSE: To document the Department of Energys (DOE) nuclear safety policy.SCOPE: The provisions of this policy apply to all Departmental elements with responsibility for a nuclear facility,...

342

Fuzzy Failure Rate for Nuclear Power Plant Probabilistic Safety Assessment by Fault Tree Analysis  

Science Journals Connector (OSTI)

Reliability data is essential for a nuclear power plant probabilistic safety assessment by fault tree analysis ... a failure possibility-based reliability algorithm to assess nuclear event reliability data from f...

Julwan Hendry Purba; Jie Lu; Guangquan Zhang

2012-01-01T23:59:59.000Z

343

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1 This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOE's operation of nuclear facilities. In developing the revised Policy and performing this analysis, DOE reviewed the current Nuclear Safety Policy (Secretary of Energy Notice [SEN] 35-91, Nuclear Safety Policy) and safety policies established by other safety

344

On the Criticality Safety of Transuranic Sodium Fast Reactor Fuel Transport Casks  

SciTech Connect

This work addresses the neutronic performance and criticality safety issues of transport casks for fuel pertaining to low conversion ratio sodium cooled fast reactors, conventionally known as Advanced Burner Reactors. The criticality of a one, three, seven and 19-assembly cask capacity is presented. Both dry helium and flooded water filled casks are considered. No credit for fuel burnup or fission products was assumed. As many as possible of the conservatisms used in licensing light water reactor universal transport casks were incorporated into this SFR cask criticality design and analysis. It was found that at 7-assemblies or more, adding moderator to the SFR cask increases criticality margin. Also, removal of MAs from the fuel increases criticality margin of dry casks and takes a slight amount of margin away for wet casks. Assuming credit for borated fuel tube liners, this design analysis suggests that as many as 19 assemblies can be loaded in a cask if limited purely by criticality safety. If no credit for boron is assumed, the cask could possibly hold seven assemblies if low conversion ratio fast reactor grade fuel and not breeder reactor grade fuel is assumed. The analysis showed that there is a need for new cask designs for fast reactors spent fuel transportation. There is a potential of modifying existing transportation cask design as the starting point for fast reactor spent fuel transportation.

Samuel Bays; Ayodeji Alajo

2010-05-01T23:59:59.000Z

345

INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT  

SciTech Connect

Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR06 are highlighted, and the future of the two projects is discussed.

J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

2008-09-01T23:59:59.000Z

346

Investigation on the Benefits of Safety Margin Improvement in CANDU Nuclear Power Plant Using an FPGA-based Shutdown System.  

E-Print Network (OSTI)

??The relationship between response time and safety margin of CANadian Deuterium Uranium (CANDU) nuclear power plant (NPP) is investigated in this thesis. Implementation of safety (more)

She, Jingke

2012-01-01T23:59:59.000Z

347

THE NUCLEAR ARJUNA: A NARRATIVE CRITICISM OF VAJPAYEE'S LOK SABHA ADDRESS.  

E-Print Network (OSTI)

??The thesis is a rhetorical and narrative criticism of Atal Bihari Vajpayee's 1998 pro-nuclear Lok Sabha address. Through Walter Fisher's narrative paradigm, I argue that (more)

DeLong, Brian LaMonte

2010-01-01T23:59:59.000Z

348

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Health and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel3 of HEALTH AND SAFETY IMPACTS OF FOSSIL-FUEL NUCLEAR,HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL

Nero, A.V.

2010-01-01T23:59:59.000Z

349

Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety and Security HSS Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Enforcement and Oversight Abbreviations Used in this Report i Executive Summary iii Recommendations xi 1.0 Introduction 1 1.1 Background 2 1.2 Scope and Methodology 6 2.0 Current Safety Culture 9 2.1 Background 9 2.2 Scope and Methods 10 2.3 ORP (including DOE-WTP) 11 2.4 BNI 11 2.5 WTP Project 12 3.0 ORP Management of Safety Concerns 15 3.1 Corrective Actions for the 2010 HSS Review 15 3.2 Processes for Managing Issues 16

350

Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety and Security HSS Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Enforcement and Oversight Abbreviations Used in this Report i Executive Summary iii Recommendations xi 1.0 Introduction 1 1.1 Background 2 1.2 Scope and Methodology 6 2.0 Current Safety Culture 9 2.1 Background 9 2.2 Scope and Methods 10 2.3 ORP (including DOE-WTP) 11 2.4 BNI 11 2.5 WTP Project 12 3.0 ORP Management of Safety Concerns 15 3.1 Corrective Actions for the 2010 HSS Review 15 3.2 Processes for Managing Issues 16

351

China's approach to nuclear safety From the perspective of policy and institutional system  

Science Journals Connector (OSTI)

Abstract Nuclear energy plays an important role in the energy sector in the world. It has achieved a rapid development during the past six decades and contributes to over 11% of the world's electricity supply. On the other side, nuclear accidents have triggered substantial debates with a growing public concern on nuclear facilities. Followed by the Fukushima nuclear accident, some developed countries decided to shut down the existing nuclear power plants or to abandon plans to build new ones. Given this background, accelerating the development of nuclear power on the basis of safety in China will make it a bellwether for other countries. China assigns the top priority to the nuclear safety in nuclear energy development and has maintained a good record in this field. The policy and institutional system provide the necessary guarantee for the nuclear energy development and safety management. Furthermore, China's approach to nuclear safety provides a benchmark for the safe development and utilization of nuclear power. This research draws an overall picture of the nuclear energy development and nuclear safety in China from the policy and institutional perspective.

Ruimin Mu; Jian Zuo; Xueliang Yuan

2015-01-01T23:59:59.000Z

352

Alternative off-site power supply improves nuclear power plant safety  

Science Journals Connector (OSTI)

Abstract A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source.

Blae Gjorgiev; Andrija Volkanovski; Duko Kan?ev; Marko ?epin

2014-01-01T23:59:59.000Z

353

Nuclear Safety Regulatory Assistance Reviews | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

August 14, 2002 August 14, 2002 Preliminary Notice of Violation, Fluor Hanford, Incorporated - EA-2002-03 Preliminary Notice of Violation issued to Fluor Hanford, Incorporated, related to Quality Assurance issues at the Hanford Site. June 19, 2002 Enforcement Letter, Kaiser-Hill Company, L.L.C. - June 19, 2002 Enforcement Letter issued to Kaiser-Hill Company, LLC related to Unplanned Radioactive Material Uptakes at the Rocky Flats Environmental Technology Site October 22, 2001 Special Report Order, CH2M Hill Hanford Group, Inc. - October 22, 2001 Special Report Order issued to CH2M Hill Hanford Group, Inc., related to Multiple Nuclear Safety Issues at the Hanford Site October 9, 2001 Enforcement Letter, LANL - October 9, 2001 Enforcement Letter issued to Los Alamos National Laboratory related to

354

DOE Standard 3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis, Roll Out Training  

Energy.gov (U.S. Department of Energy (DOE))

The Office of Nuclear Safety is performing a series of site visits to provide roll-out training and assistance to Program and Site Offices and their contractors on effective implementation of the new revision to DOE Standard 3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis.

355

Enforcement handbook: Enforcement of DOE nuclear safety requirements  

SciTech Connect

This Handbook provides detailed guidance and procedures to implement the General Statement of DOE Enforcement Policy (Enforcement Policy or Policy). A copy of this Enforcement Policy is included for ready reference in Appendix D. The guidance provided in this Handbook is qualified, however, by the admonishment to exercise discretion in determining the proper disposition of each potential enforcement action. As discussed in subsequent chapters, the Enforcement and Investigation Staff will apply a number of factors in assessing each potential enforcement situation. Enforcement sanctions are imposed in accordance with the Enforcement Policy for the purpose of promoting public and worker health and safety in the performance of activities at DOE facilities by DOE contractors (and their subcontractors and suppliers) who are indemnified under the Price-Anderson Amendments Act. These indemnified contractors, and their suppliers and subcontractors, will be referred to in this Handbook collectively as DOE contractors. It should be remembered that the purpose of the Department`s enforcement policy is to improve nuclear safety for the workers and the public, and this goal should be the prime consideration in exercising enforcement discretion.

NONE

1995-06-01T23:59:59.000Z

356

Criticality safety evaluation of Rocky Flats Plant one-gallon shipping containers  

SciTech Connect

Criticality safety calculations have been performed to provide an analytical basis for handling, storage and transport of Rocky Flats Plant (RFP) one-gallon shipping containers. A mass limit was establish for metal (solid uranium or plutonium) and slurries (undissolved U or Pu solids in a ``mud,`` ``sludge,`` or ``slurry``). A separate volume limit was developed for plutonium solutions (liquids, either aqueous or organic, containing no visible undissolved solids).

Shaw, M.E.

1991-12-01T23:59:59.000Z

357

Criticality safety evaluation of Rocky Flats Plant one-gallon shipping containers  

SciTech Connect

Criticality safety calculations have been performed to provide an analytical basis for handling, storage and transport of Rocky Flats Plant (RFP) one-gallon shipping containers. A mass limit was establish for metal (solid uranium or plutonium) and slurries (undissolved U or Pu solids in a mud,'' sludge,'' or slurry''). A separate volume limit was developed for plutonium solutions (liquids, either aqueous or organic, containing no visible undissolved solids).

Shaw, M.E.

1991-12-01T23:59:59.000Z

358

CY 2012 Annual Workforce Analysis and Staffing Plan - Chief of Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2 2 Reporting Office: Chief of Nuclear Safety . Section One: Current Mission(s) of the Organization and Potential Changes Revision 2 of U.S. Department of Energy Implementation Plan for DNFSB Recommendation 2004-1 established the seven core CTA responsibilities. The Office of the Chief of Nuclear Safety (CNS) performs to following functions in support of the CTA meeting these responsibilities: 1. Nuclear Safety Requirement Concurrence and Exemption * Concur with the determination of the applicability of DOE directives involving nuclear safety included in Energy and Science contracts pursuant to Department of Energy Acquisition Regulation (DEAR), 48 CFR 970.5204-2, Laws, regulations, and DOE directives, item (b). * Concur with nuclear safety requirements included in Energy and Science contracts pursuant to

359

CY 2011 Annual Workforce Analysis and Staffing Plan - Chief of Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1 1 Reporting Office: Chief of Nuclear Safety . Section One: Current Mission(s) of the Organization and Potential Changes Revision 2 of U.S. Department of Energy Implementation Plan for DNFSB Recommendation 2004-1 established the seven core CTA responsibilities. The Office of the Chief of Nuclear Safety (CNS) performs to following functions in support of the CTA meeting these responsibilities: 1. Nuclear Safety Requirement Concurrence and Exemption * Concur with the determination of the applicability of DOE directives involving nuclear safety included in Energy and Science contracts pursuant to Department of Energy Acquisition Regulation (DEAR), 48 CFR 970.5204-2, Laws, regulations, and DOE directives, item (b). * Concur with nuclear safety requirements included in Energy and Science contracts pursuant to

360

Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 1  

SciTech Connect

Separate abstracts are included for each of the papers presented concerning current issues in nuclear power plant safety; national programs in nuclear power plant safety; radiological source terms; probabilistic risk assessment methods and techniques; non LOCA and small-break-LOCA transients; safety goals; pressurized thermal shocks; applications of reliability and risk methods to probabilistic risk assessment; human factors and man-machine interface; and data bases and special applications.

none,

1983-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Nuclear Data Capabilities Supported by the DOE NCSP  

E-Print Network (OSTI)

Nuclear Data Capabilities Supported by the DOE NCSP Symposium on Nuclear Data for Criticality responsible for developing, implementing, and maintaining nuclear criticality safety. 3 #12;NCSP Technical the Production Codes and Methods for Criticality Safety Engineers (e.g. MCNP, SCALE, & COG) · Nuclear Data

Danon, Yaron

362

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

......errors, computational models (software), management, communication, safety culture, plant ageing, maintenance...Energy Power Plants Probability Radiation Monitoring Radiation Protection Radioactive Hazard Release Safety Management...

Valdir Maciel Lopes; Gian Maria Agostinho Angelo Sordi; Mauricio Moralles; Tufic Madi Filho

2012-06-01T23:59:59.000Z

363

Safety Culture in Nuclear Installations | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Guidance for Use in the Enhancement of Safety Culture, International Atomic Energy Agency IAEA, December 2002. Developed for use in the IAEA's Safety Culture Services....

364

Private nuclear waste plan faces critics in Australia  

Science Journals Connector (OSTI)

... now based in Seattle, Washington State, and is backed by two organizations active in nuclear ...

Peter Pockley

1999-04-22T23:59:59.000Z

365

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010  

Energy.gov (U.S. Department of Energy (DOE))

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010

366

2015 Call for Proposals for the Department of Energy (DOE) Nuclear Safety Research and Development (NSR&D) Program  

Energy.gov (U.S. Department of Energy (DOE))

2015 Call for Proposals for the Department of Energy (DOE) Nuclear Safety Research and Development (NSR&D) Program.

367

DOE Standard on Development and Use of Probabilistic Risk Assessment in DOE Nuclear Safety Applications (draft), December 2010  

Energy.gov (U.S. Department of Energy (DOE))

There have been significant developments with regard to the risk assessment and risk informed decision making, as it applies to nuclear and other safety areas, since the Department of Energy (DOE) developed its approach to managing nuclear safety. The developments and associated technical insights may be of use to DOE in its efforts to continuously improve safety performance at its nuclear facilities.

368

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel

Nero, jA.V.

2010-01-01T23:59:59.000Z

369

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- FuelHealth and Safety Aspects of Pro- posed Nuclear, Geothermal, and Fossil-Fuel

Yen, W.W.S.

2010-01-01T23:59:59.000Z

370

International Symposium on Fusion Nuclear Technology (ISFNT-5) SAFETY ISSUES ASSOCIATED WITH MOBILIZED ACTIVATION  

E-Print Network (OSTI)

International Symposium on Fusion Nuclear Technology (ISFNT-5) SAFETY ISSUES ASSOCIATED;International Symposium on Fusion Nuclear Technology (ISFNT-5) heat from in-vessel systems with high neutron Symposium on Fusion Nuclear Technology (ISFNT-5) A design must adequately transfer heat from plasma

California at Los Angeles, University of

371

September 10, 2010 HSS Briefing to the Defense Nuclear Facilities Safety Board (DNFSB) on Union Activities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Labor Union and Stakeholder Labor Union and Stakeholder Outreach and Collaboration Office of Health, Safety and Security Briefing to the Defense Nuclear Facilities Safety Board Briefing to the Defense Nuclear Facilities Safety Board Leadership Commitment Leadership Commitment " h "It is imperative that we communicate and establish relationships with those elements that train manage and elements that train, manage and represent our workforce to improve the safety culture at DOE sites." safety culture at DOE sites. Glenn S. Podonsky Chief Health, Safety and Security Officer 2 History History History History October 2006: Formation of HSS to provide an integrated DOE HQ-level function for health, safety, environment, and security into one unified office. February 2007: Established HSS Focus Group -

372

Forecast of criticality experiments and experimental programs needed to support nuclear operations in the United States of America: 1994--1999  

SciTech Connect

This Forecast is generated by the Chair of the Experiment Needs Identification Workgroup (ENIWG), with input from Department of Energy and the nuclear community. One of the current concerns addressed by ENIWG was the Defense Nuclear Facilities Safety Board`s Recommendation 93-2. This Recommendation delineated the need for a critical experimental capability, which includes (1) a program of general-purpose experiments, (2) improving the information base, and (3) ongoing departmental programs. The nuclear community also recognizes the importance of criticality theory, which, as a stepping stone to computational analysis and safety code development, needs to be benchmarked against well-characterized critical experiments. A summary project of the Department`s needs with respect to criticality information includes (1) hands-on training, (2) criticality and nuclear data, (3) detector systems, (4) uranium- and plutonium-based reactors, and (5) accident analysis. The Workgroup has evaluated, prioritized, and categorized each proposed experiment and program. Transportation/Applications is a new category intended to cover the areas of storage, training, emergency response, and standards. This category has the highest number of priority-1 experiments (nine). Facilities capable of performing experiments include the Los Alamos Critical Experiment Facility (LACEF) along with Area V at Sandia National Laboratory. The LACEF continues to house the most significant collection of critical assemblies in the Western Hemisphere. The staff of this facility and Area V are trained and certified, and documentation is current. ENIWG will continue to work with the nuclear community to identify and prioritize experiments because there is an overwhelming need for critical experiments to be performed for basic research and code validation.

Rutherford, D.

1994-03-01T23:59:59.000Z

373

DOE P 420.1 Department of Energy Nuclear Safety Policy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

POLICY POLICY Washington, D.C. Approved: 2-08-2011 SUBJECT: DEPARTMENT OF ENERGY NUCLEAR SAFETY POLICY PURPOSE: To document the Department of Energy's (DOE) nuclear safety policy. SCOPE: The provisions of this policy apply to all Departmental elements with responsibility for a nuclear facility, except the Naval Nuclear Propulsion Program, which is separately covered under Executive Order 12344, Title 50 United States Code, sections 2406 and 2511. This Policy cancels Secretary of Energy Notice 35-91, Nuclear Safety Policy, dated 9-9-91. POLICY: It is the policy of the Department of Energy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the

374

Office of Nuclear Safety and Environmental Assessments | Department...  

Energy Savers (EERE)

operation, deactivation, decontamination, decommissioning and environmental restoration. Conduct assessments of changes to operations, safety basis and modifications. Conducts...

375

A probabilistic safety analysis of incidents in nuclear research reactors  

Science Journals Connector (OSTI)

......ICRP-64. INTRODUCTION Nuclear research reactors are considered important tools in nuclear science. For more than...as well as prevention policy, have stimulated the development...level 3 in the International Nuclear Events Scale (INES) of......

Valdir Maciel Lopes; Gian Maria Agostinho Angelo Sordi; Mauricio Moralles; Tufic Madi Filho

2012-06-01T23:59:59.000Z

376

Confirmation of 10 CFR Part 830, nuclear safety rule (66 FR 19717), Fed Reg  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Confirmation of 10 CFR Part 830, nuclear safety rule (66 FR 19717), Confirmation of 10 CFR Part 830, nuclear safety rule (66 FR 19717), Fed Reg 4/17/01 Confirmation of 10 CFR Part 830, nuclear safety rule (66 FR 19717), Fed Reg 4/17/01 In accordance with the memorandum of January 20, 2001, from the Assistant to the President and Chief of Staff, entitled ''Regulatory Review Plan,'' published in the Federal Register on January 24, 2001 (66 FR 7702), DOE temporarily delayed for 60 days (66 FR 8746, February 2, 2001) the effective date of the rule entitled ''Nuclear Safety Management'' published in the Federal Register on January 10, 2001 (66 FR 1810). DOE has now completed its review of that regulation, and does not intend to initiate any further rulemaking action to modify its provisions and confirms the effective date of April 10,

377

Nuclear Safety R&D in the Waste Processing Technology Development & Deployment Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

R&D in the Waste Processing R&D in the Waste Processing Technology Development & Deployment Program Presentation to the DOE High Level Waste Corporate Board July 29, 2009 Al Baione Office of Waste Processing DOE-EM Office of Engineering & Technology 2 Outline Nuclear Safety Research & Development Overview Summary of EM- NSR&D Presentations from February 2009 Evaluating Performance of Nuclear Grade HEPA Filters under Fire/Smoke Challenge Conditions Structural Integrity Initiative for HLW Tanks Pipeline Plugging and Prevention Advanced Mixing Models Basic Science Opportunities in HLW Storage and Processing Safety Cementitious Barriers Partnership 3 Nuclear Safety Research & Development Overview DNFSB 2004-1 identified need for renewed DOE attention to nuclear safety R&D

378

6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety 6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety Management, AGENCY: Department of Energy (DOE). 6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety Management, AGENCY: Department of Energy (DOE). The Department of Energy (DOE) has issued Ruling 1995-1 which interprets certain regulatory provisions relating to DOE's nuclear safety requirements. This Ruling is intended to be a generally applicable clarification that addresses questions concerning the applicability and effect of these provisions. Ruling 1995-1; Ruling concerning 10 CFR Parts 830 and 835 More Documents & Publications Appendix A. Notice of Inquiry: Preparation of Report to Congress on Price-Anderson Act. 62 Federal Register 68,272 (December 31, 1997) Report to Congress on the Price-Anderson Act

379

Nuclear Safety Management, Final Rule; Delay of Effective Date (66 FR  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety Management, Final Rule; Delay of Effective Date (66 Nuclear Safety Management, Final Rule; Delay of Effective Date (66 FR 8746), Fed Reg, 2/2/01 Nuclear Safety Management, Final Rule; Delay of Effective Date (66 FR 8746), Fed Reg, 2/2/01 Nuclear Safety Management, Final Rule; Delay of Effective Date (66 FR 8746), Fed Reg, 2/2/01 In accordance with the memorandum of January 20, 2001, from the Assistant to the President and Chief of Staff, entitled ''Regulatory Review Plan,'' published in the Federal Register on January 24, 2001 (66 FR 7702), this action temporarily delays for 60 days the effective date of the rule entitled ''Alternate Fuel Transportation Program; Biodiesel Fuel Use Credit'' published in the Federal Register on January 11, 2001 (66 FR 2207). DATES: The effective date of the rule amending 10 CFR part 490

380

Manual of functions, assignments, and responsibilities for nuclear safety: Revision 2  

SciTech Connect

The FAR Manual is a convenient easy-to-use collection of the functions, assignments, and responsibilities (FARs) of DOE nuclear safety personnel. Current DOE directives, including Orders, Secretary of Energy Notices, and other assorted policy memoranda, are the source of this information and form the basis of the FAR Manual. Today, the majority of FARs for DOE personnel are contained in DOE`s nuclear safety Orders. As these Orders are converted to rules in the Code of Federal Regulations, the FAR Manual will become the sole source for information relating to the functions, assignments, responsibilities of DOE nuclear safety personnel. The FAR Manual identifies DOE directives that relate to nuclear safety and the specific DOE personnel who are responsible for implementing them. The manual includes only FARs that have been extracted from active directives that have been approved in accordance with the procedures contained in DOE Order 1321.1B.

Not Available

1994-10-15T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Superconducting Magnet Safety Nuclear Magnetic Resonance (NMR) facilities present unique hazards not found in most  

E-Print Network (OSTI)

Superconducting Magnet Safety Nuclear Magnetic Resonance (NMR) facilities present unique hazards or steel reinforced concrete, these ferromagnetic materials may have an effect on the magnetic field environmental temperature control is required (2) Structural support for heavy equipment and vibration control

Maroncelli, Mark

382

Job Opening Research Associate/Post-Doctoral Fellow for Interdisciplinary Study on Nuclear Safety  

E-Print Network (OSTI)

public opinion surveys; experience in organizing and conducting focus group meetings; good journal to work independently. The appointee will assist in designing public opinion surveys, focusing for Interdisciplinary Study on Nuclear Safety Governance, University of Hong Kong

Leung, Ka-Cheong

383

DOE Cites CH2M Hill Hanford for Violating Nuclear Safety Rules | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

for Violating Nuclear Safety Rules for Violating Nuclear Safety Rules DOE Cites CH2M Hill Hanford for Violating Nuclear Safety Rules March 10, 2005 - 10:44am Addthis Hanford Tank Farm Contractor Faces Fine of more than $300,000 WASHINGTON, DC - The Department of Energy (DOE) today notified the CH2M Hill Hanford Group, Inc. (CH2M Hill) - that it will fine the company $316,250 for violations of the department's nuclear safety requirements. CH2M Hill is the department's contractor responsible for storage of highly radioactive and hazardous liquid waste at the Hanford Tank Farms near Richland, Wash. The Preliminary Notice of Violation (PNOV) issued today, cites four events that took place in 2003 and 2004. These events include the contamination of several workers while removing equipment from a valve pit

384

Uncertainty analysis of criticality safety for the plate type fuel assembly storage rack  

Science Journals Connector (OSTI)

To evaluate the criticality safety of the fresh and the spent fuel storage racks in an open pool type research reactor designed by KAERI, the upper subcriticality limit (USL) analysis was carried out. First, the bias and its uncertainty of MCNP code system with ENDF/B-VII library were evaluated using the calculation results of the 183 benchmark experiments. The criticality calculations for the fuel storage rack are carried out under a normal state, an increased water temperature, a fuel assembly drop, and an eccentric insertion which can affect the criticality. Considering biases and uncertainties for the MCNP code system, abnormal conditions, and the manufacturing tolerance of the cell tube thickness, the USL value that can guarantee sufficient subcriticality is determined. It was found that the criticality of the fresh and the spent fuel storage racks currently designed satisfy the USL condition. Additionally, it was concluded that the pitch size of a fresh fuel storage rack can be reduced for efficient space availability, and even under a worst case in which the fresh storage rack is surrounded by a lower water density and the smallest pitch size satisfies the USL conditions.

Tae Young Han; Chang Je Park; Byung Chul Lee; Jae Man Noh

2013-01-01T23:59:59.000Z

385

Nuclear Safety Component and Services Procurement, June 29, 2011 (HSS CRAD 45-12, Rev. 1)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Office Office of Enforcement and Oversight Criteria Review and Approach Document Subject: Nuclear Safety Component and Services Procurement Inspection Criteria, Inspection Activities, and Lines of Inquiry HS: HSSCRAD 45-12 Rev.: 1 Eff.Date: 06/29/2011 Page 1 of 15 Acting Director, Office of Safety and Emergency Management Evaluations Date: G> |W ^ Criteria Lead, Nuclear Safety Component Procurement Date: G>/z9/z<>// 1.0 PURPOSE Within the Office of Enforcement and Oversight, the Office of Safety and Emergency Management Evaluations' mission is to assess the effectiveness of those environment, safety, and health systems and practices used by line and contractor organizations in implementing Integrated Safety Management; and to provide clear, concise, and independent evaluations of performance in protecting our workers, the public, and the environment from

386

Reactor and Nuclear Systems Division (RNSD)  

NLE Websites -- All DOE Office Websites (Extended Search)

RNSD Home RNSD Home Research Groups Advanced Reactor Systems & Safety Nuclear Data & Criticality Safety Nuclear Security Modeling Radiation Safety Information Computational Center Radiation Transport Reactor Physics Thermal Hydraulics & Irradiation Engineering Used Fuel Systems Staff Details (CV/Bios) Publications Org Chart Contact Us ORNL Staff Only Research Groups Advanced Reactor Systems & Safety Nuclear Data & Criticality Safety Nuclear Security Modeling Radiation Safety Information Computational Center Radiation Transport Reactor Physics Thermal Hydraulics & Irradiation Engineering Used Fuel Systems Reactor and Nuclear Systems Division News Highlights U.S. Rep. Fleischmann touts ORNL as national energy treasure Martin Peng wins Fusion Power Associates Leadership Award

387

Assessment of Nuclear Safety Culture at the Pantex Plant, November 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Pantex Plant Pantex Plant May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Pantex Plant Table of Contents 1.0 Introduction........................................................................................................................................... 1 2.0 Scope and Methodology ....................................................................................................................... 2 3.0 Results and Conclusions ....................................................................................................................... 3 4.0 Recommendations................................................................................................................................. 5

388

CSER 94-004: Criticality safety of double-shell waste storage tanks  

SciTech Connect

This criticality safety evaluation covers double-shell waste storage tanks (DSTs), double-contained receiver tanks (DCRTs), vault tanks, and the 242-A Evaporator located in the High Level Waste (HLW) Tank Farms on the Hanford Site. Limits and controls are specified and the basis for ensuring criticality safety is discussed. A minimum limit of 1,000 is placed upon the solids/plutonium mass ratio in incoming waste. The average solids/Pu mass ratio over all waste in tank farms is estimated to be about 74,500, about 150 times larger than required to assure subcriticality in homogeneous waste. PFP waste in Tank-102-SY has an estimated solids/Pu mass ratio of 10,000. Subcriticality is assured whenever the plutonium concentration is less than 2.6 g. The median reported plutonium concentration for 200 samples of waste solids is about 0.01 g (0.038 g/gal). A surveillance program is proposed to increase the knowledge of the waste and provide added assurance of the high degree of subcriticality.

Rogers, C.A.

1994-09-22T23:59:59.000Z

389

Tornado vs. Hurricane Which is More Critical for Design of U.S. Nuclear Power Plants?  

Energy.gov (U.S. Department of Energy (DOE))

Tornado vs. Hurricane Which is More Critical for Design of U.S. Nuclear Power Plants? Javad Moslemian Sargent & Lundy, LLC U. S. Department of Energy Natural Phenomena Hazards Meeting October 21-22, 2014

390

U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

U.S. Department of Energy Oak Ridge Operations Nuclear Facility U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals, Self-Study Guide U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals, Self-Study Guide This is an open-book evaluation. Complete the questions, and submit your answers (hand-written or electronically) to the Training Center. Someone will check and grade your answers. If you achieve a score of at least 80%, you will receive a completion certificate. Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions More Documents & Publications Requirements in DOE O 5480.19, Conduct of Operations Requirements for DOE Facilities Cross-referenced to DOE O 422.1, Conduct of Operations. U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility

391

Criticality Safety Evaluations on the Use of 200-gram Pu Mass Limit for RHWM Waste Storage Operations  

SciTech Connect

This work establishes the criticality safety technical basis to increase the fissile mass limit from 120 grams to 200 grams for Type A 55-gallon drums and their equivalents. Current RHWM fissile mass limit is 120 grams Pu for Type A 55-gallon containers and their equivalent. In order to increase the Type A 55-gallon drum limit to 200 grams, a few additional criticality safety control requirements are needed on moderators, reflectors, and array controls to ensure that the 200-gram Pu drums remain criticality safe with inadvertent criticality remains incredible. The purpose of this work is to analyze the use of 200-gram Pu drum mass limit for waste storage operations in Radioactive and Hazardous Waste Management (RHWM) Facilities. In this evaluation, the criticality safety controls associated with the 200-gram Pu drums are established for the RHWM waste storage operations. With the implementation of these criticality safety controls, the 200-gram Pu waste drum storage operations are demonstrated to be criticality safe and meet the double-contingency-principle requirement per DOE O 420.1.

Chou, P

2011-12-14T23:59:59.000Z

392

Y-12 hosts safety workshop | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

and Knoxville Building and Construction Trades Council. NNSA Blog About the photo Advisor Rizwan Shah and CNS Safety Culture Program Manager Paul Wasilko welcome participants...

393

CRAD, Nuclear Facility Safety System - September 25, 2009 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facility Safety System Functionality Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-17, Rev 0 ) This document establishes the protocols used by...

394

Growth and Expansion of the International Criticality Safety Benchmark Evaluation Project and the Newly Organized International Reactor Physics Experiment Evaluation Project  

SciTech Connect

Since ICNC 2003, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has continued to expand its efforts and broaden its scope. Criticality-alarm / shielding type benchmarks and fundamental physics measurements that are relevant to criticality safety applications are not only included in the scope of the project, but benchmark data are also included in the latest version of the handbook. A considerable number of improvements have been made to the searchable database, DICE and the criticality-alarm / shielding benchmarks and fundamental physics measurements have been included in the database. There were 12 countries participating on the ICSBEP in 2003. That number has increased to 18 with recent contributions of data and/or resources from Brazil, Czech Republic, Poland, India, Canada, and China. South Africa, Germany, Argentina, and Australia have been invited to participate. Since ICNC 2003, the contents of the International Handbook of Evaluated Criticality Safety Benchmark Experiments have increased from 350 evaluations (28,000 pages) containing benchmark specifications for 3070 critical or subcritical configurations to 442 evaluations (over 38,000 pages) containing benchmark specifications for 3957 critical or subcritical configurations, 23 criticality-alarm-placement / shielding configurations with multiple dose points for each, and 20 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications in the 2006 Edition of the ICSBEP Handbook. Approximately 30 new evaluations and 250 additional configurations are expected to be added to the 2007 Edition of the Handbook. Since ICNC 2003, a reactor physics counterpart to the ICSBEP, The International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. Beginning in 1999, the IRPhEP was conducted as a pilot activity by the by the Organization of Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC). The project was endorsed as an official activity of the NSC in June of 2003. The IRPhEP is patterned after its predecessor, the ICSBEP, but focuses on other integral measurements such as buckling, spectral characteristics, reactivity effects, reactivity coefficients, kinetics measurements, reaction-rate and power distributions, nuclide compositions and other miscellaneous types of measurements in addition to the critical configuration. The two projects are closely coordinated to avoid duplication of effort and to leverage limited resources to achieve a common goal. The purpose of the IRPhEP is to provide an extensively peer reviewed set of reactor physics related integral benchmark data that can be used by reactor designers and safety analysts to validate the analytical tools used to design next generation reactors and establish the safety basis for operation of these reactors. While coordination and administration of the IRPhEP takes place at an international level, each participating country is responsible for the administration, technical direction, and priorities of the project within their respective countries. The work of the IRPhEP is documented in an OECD NEA Handbook entitled, International Handbook of Evaluated Reactor Physics Benchmark Experiments. The first edition of this Handbook, the 2006 Edition spans over 2000 pages and contains data from 16 different experimental series that were

J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

2007-05-01T23:59:59.000Z

395

Screening for Colorectal Cancer in a Safety-Net Health Care System: Access to Care Is Critical and Has Implications for Screening Policy  

Science Journals Connector (OSTI)

...Cancer in a Safety-Net Health Care System: Access to Care Is Critical and Has Implications for Screening Policy...cancer in a safety-net health care system: access to care is critical and has implications for screening policy...sparse for safety-net health systems. A retrospective...

Samir Gupta; Liyue Tong; James E. Allison; Elizabeth Carter; Mark Koch; Don C. Rockey; Paula Anderson; Chul Ahn; Keith Argenbright; and Celette Sugg Skinner

2009-09-01T23:59:59.000Z

396

CRAD, Nuclear Safety- Oak Ridge National Laboratory High Flux Isotope Reactor  

Energy.gov (U.S. Department of Energy (DOE))

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Nuclear Safety Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

397

ccsd00001474, Model-independent tracking of criticality signals in nuclear multifragmentation data  

E-Print Network (OSTI)

parameter, de#28;ning two di#27;erent regimes at low and high incident energy, respectively, according of nuclear mul- tifragmentation reactions as observed in intermediate en- ergy heavy-ion collisions [1ccsd­00001474, version 2 ­ 6 Sep 2004 Model-independent tracking of criticality signals in nuclear

398

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications  

SciTech Connect

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

Kirk, Bernadette Lugue [ORNL] [ORNL

2009-01-01T23:59:59.000Z

399

New Research Center to Increase Safety and Power Output of U.S. Nuclear  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

New Research Center to Increase Safety and Power Output of U.S. New Research Center to Increase Safety and Power Output of U.S. Nuclear Reactors New Research Center to Increase Safety and Power Output of U.S. Nuclear Reactors May 3, 2011 - 3:41pm Addthis Oak Ridge, Tenn. - Today the Department of Energy dedicated the Consortium for Advanced Simulation of Light Water Reactors (CASL), an advanced research facility that will accelerate the advancement of nuclear reactor technology. CASL researchers are using supercomputers to study the performance of light water reactors and to develop highly sophisticated modeling that will help accelerate upgrades at existing U.S. nuclear plants. These upgrades could improve the energy output of our existing reactor fleet by as much as seven reactors' worth at a fraction of the cost of building new reactors, while providing continued improvements in

400

Safety of Department of Energy-Owned Nuclear Reactors  

Directives, Delegations, and Requirements

To establish reactor safety program requirements assure that the safety of each Department of Energy-owned (DOE-owned) reactor is properly analyzed, evaluated, documented, and approved by DOE; and reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate protection for health and safety and will be in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. Cancels Chap. 6 of DOE O 5480.1A. Paragraphs 7b(3), 7e(3) & 8c canceled by DOE O 5480.23 & canceled by DOE N 251.4 of 9-29-95.

1986-09-23T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

DOE-STD-1158-2002; Self-Assessment Standard for DOE Contractor Criticality Safety Programs  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

02 02 November 2002 DOE STANDARD SELF-ASSESSMENT STANDARD FOR DOE CONTRACTOR CRITICALITY SAFETY PROGRAMS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-1158-2202 iii FOREWARD 1. This Department of Energy standard is approved for use by all DOE Components and their

402

Independent Oversight Assessment of the Nuclear Safety Culture...  

Office of Environmental Management (EM)

has also been effectively implemented in non-nuclear organizations, such as mining, health care, research, engineering, and transportation. The methodology entails collecting...

403

Nuclear waste criticality analysis quarterly progress report, 1 July 1995--30 September 1995  

SciTech Connect

Control of criticality in spent nuclear fuel is necessary during all phases of fuel management during storage, transportation, and permanent disposal. Work completed to date is described. Tasks in the original proposal include: seek coverage by an approved quality control program, review documents related to criticality, attend criticality meetings and workshops, and maintain an expertise in criticality. Current work is covered by Univ. of Nevada QA plan, however, coverage under a more thorough plan will be sought in order that the results can be used during NRC licensing.

Culbreth, W.G.

1995-10-19T23:59:59.000Z

404

ACCELERATED TESTING OF NEUTRON-ABSORBING ALLOYS FOR NUCLEAR CRITICALITY CONTROL  

SciTech Connect

The US Department of Energy requires nuclear criticality control materials be used for storage of highly enriched spent nuclear fuel used in government programs and the storage of commercial spent nuclear fuel at the proposed High-Level Nuclear Waste Geological Repository located at Yucca Mountain, Nevada. Two different metallic alloys (Ni-Cr-Mo-Gd and borated stainless steel) have been chosen for this service. An accelerated corrosion test program to validate these materials for this application is described and a performance comparison is made.

Ronald E. Mizia

2011-10-01T23:59:59.000Z

405

A new DOE standard for transuranic waste nuclear safety analysis  

SciTech Connect

The DOE Office of Environmental Management (EM) observed through onsite assessments and a review of site-specific lessons learned that transuranic (TRU) waste operations could benefit from standardization of assumptions and approaches used to analyze hazards and select controls. EM collected and compared safety analysis information from DOE sites, including a comparison of the type of TRU waste accidents evaluated and controls selected, as well as specific Airborne Release Fractions (ARFs), Respirable Fractions (RFs), and Damage Ratios (DRs) assumed in accident analyses. This paper recounts the efforts by the DOE and its contractors to bring consistency to the safety analysis process supporting TRU waste operations through an integrated re-engineering effort. EM embarked on a process to re-engineer and standardize TRU safety analysis activities complex-wide. The effort involved DOE headquarters, field offices, and contractors. Five teams were formed to analyze and develop the necessary technical basis for a DOE Technical Standard. The teams looked at general issues including Safety Basis (SB), drum integrity and inspection criteria, hazard controls and analysis, safety analysis review and approval process, and implementation of hazard controls. (authors)

Triay, I.; Chung, D. [U.S. Department of Energy, Washington, D.C. (United States); Woody, J. [Atlas Consulting, Knoxville, TN (United States); Foppe, T. [Carlsbad Technical Assistance Contractor, Carlsbad, NM (United States); Mewhinney, C. [Sandia National Laboratories, Carlsbad, NM (United States); Jennings, S. [Los Alamos National Laboratories, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

406

Morsleben Nuclear Waste Repository Probabilistic Safety Assessment of the Long-Term Safety  

Science Journals Connector (OSTI)

The probabilistic safety assessment for a radioactive waste repository in a former salt mine is presented. Even with a simplified model, the number of parameters is high. Uncertainties in the parameter values ...

Georg Resele; Matthias Niemeyer

2004-01-01T23:59:59.000Z

407

Defense Nuclear Facilities Safety Board Review at the Nevada National Security Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSS-2011-001 NNSS-2011-001 Site: Nevada National Security Site Subject: Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the Defense Nuclear Facilities Safety Board Review at the Nevada National Security Site Dates of Activity 02/14/2011 - 02/17/2011 Report Preparer William Macon Activity Description/Purpose: The U.S. Department of Energy Office of Independent Oversight, within the Office of Health, Safety and Security (HSS), visited the Nevada Site Office (NSO) and the Nevada National Security Site (NNSS) from February 14-17, 2011. The purpose of the visit was to observe the Defense Nuclear Facilities Safety Board (DNFSB) review and maintain operational awareness of NNSS activities. Result:

408

Dynamical safety assessment of hydrogen production nuclear power plants using system dynamics method  

Science Journals Connector (OSTI)

Nuclear power plants for hydrogen production are investigated in the aspect of nuclear safety. The non-linear dynamical safety assessment is introduced for the analysis of the high temperature gas cooled reactor (HTGR) which is used for hydrogen production as well as electricity generation. The dynamical algorithm is adjusted for the safety assessment with an easier and reliable output. A feedback of power increase affects to the temperature decrease. The top event of the event is power and temperature stable. It is affected by the human factor, poison, and some other physical variables. There are several factors including the economic and safety factors which are considered for the reliability of the modelling simulations. Using the system dynamics (SD) method, the event quantification is performed for the event flows, stocks, and feedback by the single and double arrow lines.

Taeho Woo; Soonho Lee

2013-01-01T23:59:59.000Z

409

Safety Aspects of Wet Storage of Spent Nuclear Fuel, OAS-L-13-11  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Aspects of Wet Storage of Safety Aspects of Wet Storage of Spent Nuclear Fuel OAS-L-13-11 July 2013 Department of Energy Washington, DC 20585 July 10, 2013 MEMORANDUM FOR THE SENIOR ADVISOR FOR ENVIRONMENTAL MANAGEMENT FROM: Daniel M. Weeber Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Safety Aspects of Wet Storage of Spent Nuclear Fuel" BACKGROUND The Department of Energy (Department) is responsible for managing and storing spent nuclear fuel (SNF) generated by weapons and research programs and recovered through nonproliferation programs. The SNF consists of irradiated reactor fuel and cut up assemblies containing uranium, thorium and/or plutonium. The Department stores 34 metric tons of heavy metal SNF primarily

410

Nuclear Safety Management, Final Rule amending 10 CFR Part 830 (66 FR  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Management, Final Rule amending 10 CFR Part 830 (66 Management, Final Rule amending 10 CFR Part 830 (66 FR 1810), Federal Register (Fed Reg), 1/10/2001 Nuclear Safety Management, Final Rule amending 10 CFR Part 830 (66 FR 1810), Federal Register (Fed Reg), 1/10/2001 SUMMARY: The Department of Energy (DOE) adopts, with minor changes, the interim final rule published on October 10, 2000, to amend the DOE Nuclear Safety Management regulations. EFFECTIVE DATE: This final rule is effective on February 9, 2001. FOR FURTHER INFORMATION CONTACT: Richard Black, Director, Office of Nuclear and Facility Safety Policy, 270CC, Department of Energy, 19901 Germantown Road, Germantown, MD 20874; telephone: 301-903-3465; email: Richard.Black@eh.doe.gov SUPPLEMENTARY INFORMATION: I. Introduction and Summary On October 10, 2000, the Department of Energy (DOE) published an

411

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report  

SciTech Connect

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01T23:59:59.000Z

412

A critical review of nuclear power plant decommissioning planning studies  

Science Journals Connector (OSTI)

During the past decade there have been at least ten major efforts to perform comprehensive, analytical studies of the complex issues associated with decommissioning civilian nuclear power plants. These planning efforts are reviewed, using the standard framework of technology assessment. In particular, each study is analysed to determine the degree to which formal methods of decision analysis have been employed to evaluate options and make recommendations and the degree to which formal methods of consensus have been employed to engage citizen involvement and promote public acceptance. Not unexpectedly, we find that the greatest strides in decommissioning analyses have been made in forecasting the economic costs of decommissioning to licensees. Comparatively few improvements have been made in the processes used to compare the impacts of alternative technologies more broadly, or to address the legitimate concerns of interested parties more widely.

W.Timothy Lough; K.Preston White Jr.

1990-01-01T23:59:59.000Z

413

The Nuclear Education and Staffing Challenge: Rebuilding Critical Skills in Nuclear Science and Technology.  

SciTech Connect

The United States, the Department of Energy (DOE) and its National Laboratories, including the Pacific Northwest National Laboratory (PNNL), are facing a serious attrition of nuclear scientists and engineers and their capabilities through the effects of aging staff. Within the DOE laboratories, 75% of nuclear personnel will be eligible to retire by 2010. It is expected that there will be a significant loss of senior nuclear science and technology staff at PNNL within five years. PNNL's nuclear legacy is firmly rooted in the DOE Hanford site, the World War II Manhattan Project, and subsequent programs. Historically, PNNL was a laboratory where 70% of its activities were nuclear/radiological, and now just under 50% of its current business science and technology are nuclear and radiologically oriented. Programs in the areas of Nuclear Legacies, Global Security, Nonproliferation, Homeland Security and National Defense, Radiobiology and Nuclear Energy still involve more than 1,000 of the 3,800 current laboratory staff, and these include more than 420 staff who are certified as nuclear/radiological scientists and engineers. This paper presents the current challenges faced by PNNL that require an emerging strategy to solve the nuclear staffing issues through the maintenance and replenishment of the human nuclear capital needed to support PNNL nuclear science and technology programs.

Wogman, Ned A.; Bond, Leonard J.; Waltar, Alan E.; Leber, R. E.

2005-01-01T23:59:59.000Z

414

Los Alamos and NNSS team to resume critical experiments at new...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear safety test runs on planet device Los Alamos and NNSS team to resume critical experiments at new location This experiment demonstrated the restoration of a national...

415

Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel  

SciTech Connect

The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform postclosure criticality calculations. The validation process applies the criticality analysis methodology approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report. The application systems for this validation consist of waste packages containing transport, aging, and disposal canisters (TAD) loaded with commercial spent nuclear fuel (CSNF) of varying assembly types, initial enrichments, and burnup values that are expected from the waste stream and of varying degree of internal component degradation that may occur over the 10,000-year regulatory time period. The criticality computational tool being evaluated is the general-purpose Monte Carlo N-Particle (MCNP) transport code. The nuclear cross-section data distributed with MCNP 5.1.40 and used to model the various physical processes are based primarily on the Evaluated Nuclear Data File/B Version VI (ENDF/B-VI) library. Criticality calculation bias and bias uncertainty and lower bound tolerance limit (LBTL) functions for CSNF waste packages are determined based on the guidance in ANSI/ANS 8.1-1998 (Ref. 4) and ANSI/ANS 8.17-2004 (Ref. 5), as described in Section 3.5.3 of Ref. 1. The development of this report is consistent with Test Plan for: Range of Applicability and Bias Determination for Postclosure Criticality. This calculation report has been developed in support of licensing activities for the proposed repository at Yucca Mountain, Nevada, and the results of the calculation may be used in the criticality evaluation for CSNF waste packages based on a conceptual TAD canister.

Radulescu, Georgeta [ORNL; Mueller, Don [ORNL; Goluoglu, Sedat [ORNL; Hollenbach, Daniel F [ORNL; Fox, Patricia B [ORNL

2007-10-01T23:59:59.000Z

416

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)  

SciTech Connect

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

Cottrell, W.B.; Passiakos, M.

1982-06-01T23:59:59.000Z

417

Criticality safety assessment of a TRIGA reactor spent-fuel pool under accident conditions  

SciTech Connect

Additional criticality safety analysis of a pool-type storage for TRIGA spent fuel at the Jozef Stefan Institute in Ljubljana, Slovenia, is presented. Previous results have shown that subcriticality is not guaranteed for some postulated accidents (earthquake with subsequent fuel rack disintegration resulting in contact fuel pitch) under the assumption that the fuel rack is loaded with fresh 12 wt% standard fuel. To mitigate this deficiency, a study was done on replacing a certain number of fuel elements in the rack with cadmium-loaded absorber rods. The Monte Carlo computer code MCNP4A with an ENDF/B-V library and detailed three-dimensional geometrical model of the spent-fuel rack was used for this purpose. First, a minimum critical number of fuel elements was determined for contact pitch, and two possible geometries of rack disintegration were considered. Next, it was shown that subcriticality can be ensured when pitch is decreased from a rack design pitch of 8 cm to contact, if a certain number of fuel elements (8 to 20 out of 70) are replaced by absorber rods, which are uniformly mixed into the lattice. To account for the possibility that random mixing of fuel elements and absorber rods can occur during rack disintegration and result in a supercritical configuration, a probabilistic study was made to sample the probability density functions for random absorber rod lattice loadings. Results of the calculations show that reasonably low probabilities for supercriticality can be achieved (down to 10{sup {minus}6} per severe earthquake, which would result in rack disintegration and subsequent maximum possible pitch decrease) even in the case where fresh 12 wt% standard TRIGA fuel would be stored in the spent-fuel pool.

Glumac, B; Ravnik, M. [Jozef Stefan Inst., Ljubljana (Slovenia); Logar, M. [Univ. of Maribor (Slovenia). Faculty of Electrical Engineering and Computer Sciences

1997-02-01T23:59:59.000Z

418

Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1  

Energy.gov (U.S. Department of Energy (DOE))

This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOEs operation of nuclear facilities.

419

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

nuclear tors. for of of These studies can examine safety systems or safety research programsnuclear power plants, and at risk. to reduce population The Light-water Reactor Safety Research Program

Nero, A.V.

2010-01-01T23:59:59.000Z

420

Safety issues in robotic handling of nuclear weapon parts  

SciTech Connect

Robotic systems are being developed by the Intelligent Systems and Robotics Center at Sandia National Laboratories to perform automated handling tasks with radioactive weapon parts. These systems will reduce the occupational radiation exposure to workers by automating operations that are currently performed manually. The robotic systems at Sandia incorporate several levels of mechanical, electrical, and software safety for handling hazardous materials. For example, tooling used by the robot to handle radioactive parts has been designed with mechanical features that allow the robot to release its payload only at designated locations in the robotic workspace. In addition, software processes check for expected and unexpected situations throughout the operations. Incorporation of features such as these provides multiple levels of safety for handling hazardous or valuable payloads with automated intelligent systems.

Drotning, W.; Wapman, W.; Fahrenholtz, J.

1993-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Criticality Safety Controls for 55-Gallon Drums with a Mass Limit of 200 grams Pu-239  

SciTech Connect

The following 200-gram Pu drum criticality safety controls are applicable to RHWM drum storage operations: (1) Mass (Fissile/Pu) - each 55-gallon drum or its equivalent shall be limited to 200 gram Pu or Pu equivalent; (2) Moderation - Hydrogen materials with a hydrogen density greater than that (0.133 g H/cc) of polyethylene and paraffin are not allowed and hydrogen materials with a hydrogen density no greater than that of polyethylene and paraffin are allowed with unlimited amounts; (3) Interaction - a spacing of 30-inches (76 cm) is required between arrays and 200-gram Pu drums shall be placed in arrays for 200-gram Pu drums only (no mingling of 200-gram Pu drums with other drums not meeting the drum controls associated with the 200-gram limit); (4) Reflection - no beryllium and carbon/graphite (other than the 50-gram waiver amount) is allowed, (note that Nat-U exceeding the waiver amount is allowed when its U-235 content is included in the fissile mass limit of 200 grams); and (5) Geometry - drum geometry, only 55-gallon drum or its equivalent shall be used and array geometry, 55-gallon drums are allowed for 2-high stacking. Steel waste boxes may be stacked 3-high if constraint.

Chou, P

2011-12-14T23:59:59.000Z

422

Mapping the Impact of Security Threats on Safety-Critical Global Navigation Satellite Systems Chris W. Johnson (1), A. Atencia Yepez (2)  

E-Print Network (OSTI)

Mapping the Impact of Security Threats on Safety-Critical Global Navigation Satellite Systems Chris of attack scenarios can be used to assess the resilience of safety cases to the impact of external security accident advocated the development of safety argumentation across the oil and gas industry (US Presidential

Johnson, Chris

423

Productivity Techniques and Quality Aspects in the Criticality Safety Evaluation of Y-12 Type-B Fissile Material Packages  

SciTech Connect

The inventory of certified Type-B fissile material packages consists of ten performance-based packages for offsite transportation purposes, serving transportation programs at the Y-12 National Security Complex. The containment vessels range from 5 to 19 in. in diameter and from 17 to 58 in. in height. The drum assembly external to the containment vessel ranges from 18 to 34 in. in diameter and from 26 to 71 in. in height. The weight of the packaging (drum assembly and containment vessel) ranges from 239 to 1550 lb. The older DT-nn series of Cellotex-based packages are being phased-out and replaced by a new generation of Kaolite-based ('Y-12 patented insulation') packages capable of withstanding the dynamic crush test 10 CFR 71.73(c)(2). Three replacement packages are in various stages of development; two are in use. The U.S. Department of Transportation (DOT) 6M specification package, which does not conform to the U.S. Nuclear Regulatory Commission requirements for Type-B packages, is no longer authorized for service on public roads. The ES-3100 shipping package is an example of a Kaolite-based Type-B fissile material package developed as a replacement package for the DOT 6M. With expanded utility, the ES-3100 is designed and licensed for transporting highly enriched uranium and plutonium materials on public roads. The ES-3100 provides added capability for air transport of up to 7-kg quantities of uranium material. This paper presents the productivity techniques and quality aspects in the criticality safety evaluation of Y-12 packages using the ES-3100 as an example.

DeClue, J. F.

2011-06-28T23:59:59.000Z

424

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

NLE Websites -- All DOE Office Websites (Extended Search)

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

425

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

426

Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who  

SciTech Connect

The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs.

Forsberg, C.W.; Reich, W.J.

1991-09-01T23:59:59.000Z

427

Safety Aspects of Nuclear Desalination with Innovative Systems; the EURODESAL Project  

SciTech Connect

The proposed paper reports the results of a preliminary investigation on safety impact deriving from the coupling of a desalination plant with a 600 MWe Passive Design PWR like the AP600 Nuclear Power Plant. This evaluation was performed in the frame of the EURODESAL Project of the 5. EURATOM Framework Programme. (authors)

Alessandroni, C.; Cinotti, L.; Mini, G. [Ansaldo Nucleare, C.so Perrone, 25 - Genova (Italy); Nisan, S. [CEA-CEN Cadarache, F-13108 Saint Paul-lez-Durance (France)

2002-07-01T23:59:59.000Z

428

Opportunities for improving regulations governing the seismic safety of large nuclear installations  

Energy.gov (U.S. Department of Energy (DOE))

Opportunities for Improving Regulations Governing the Seismic Safety of Large Nuclear Installations Robert J. Budnitz, Ph.D. LBNL University of California, Berkeley, CA 94720 Andrew S. Whittaker, Ph.D., S.E. MCEER University at Buffalo, Buffalo, NY 14260

429

Price-Anderson Nuclear Safety Enforcement Program. 1996 Annual report  

SciTech Connect

This first annual report on DOE`s Price Anderson Amendments Act enforcement program covers the activities, accomplishments, and planning for calendar year 1996. It also includes the infrastructure development activities of 1995. It encompasses the activities of the headquarters` Office of Enforcement in the Office of Environment, Safety and Health (EH) and Investigation and the coordinators and technical advisors in DOE`s Field and Program Offices and other EH Offices. This report includes an overview of the enforcement program; noncompliances, investigations, and enforcement actions; summary of significant enforcement actions; examples where enforcement action was deferred; and changes and improvements to the program.

NONE

1996-01-01T23:59:59.000Z

430

Frequently Asked Questions Regarding DOE-STD-1195-2011, Design of Safety Significant Safety Instrumented Systems Used at DOE Non-Reactor Nuclear Facilities  

Energy.gov (U.S. Department of Energy (DOE))

Frequently Asked Questions Regarding DOE-STD-1195-2011 which provides requirements and guidance for the design, procurement, installation, testing, maintenance, operation, and quality assurance of safety instrumented systems (SIS) that may be used at Department of Energy (DOE) nonreactor nuclear facilities for safety significant (SS) functions.

431

Lessons learnt from ITER safety & licensing for DEMO and future nuclear fusion facilities  

E-Print Network (OSTI)

One of the strong motivations for pursuing the development of fusion energy is its potentially low environmental impact and very good safety performance. But this safety and environmental potential can only be fully realized by careful design choices. For DEMO and other fusion facilities that will require nuclear licensing, S&E objectives and criteria should be set at an early stage and taken into account when choosing basic design options and throughout the design process. Studies in recent decades of the safety of fusion power plant concepts give a useful basis on which to build the S&E approach and to assess the impact of design choices. The experience of licensing ITER is of particular value, even though there are some important differences between ITER and DEMO. The ITER project has developed a safety case, produced a preliminary safety report and had it examined by the French nuclear safety authorities, leading to the licence to construct the facility. The key technical issues that arose during ...

Taylor, Neill

2013-01-01T23:59:59.000Z

432

Nuclear waste criticality analysis. Final report, 1 July 1995--30 June 1996  

SciTech Connect

The natural reactors that occurred in Gabon, Africa over 2 billion years ago present an interesting analog to the underground repositories proposed around the world for the long-term storage of high-level spent nuclear fuel. Many articles have been written concerning the low migration rates of actinides and fission products from the Oklo reactor sites, but Oklo also presents researchers with an opportunity to discover the conditions that led to nuclear criticality in uranium oxides with low enrichments. A computer model was developed to predict the conditions that were necessary to lead to criticality in the Oklo reactors. Critical core dimensions and infinite multiplication factors are presented as a function of time, the porosity of the host rock, and the water and uranium content of the sandstone deposits at Oklo.

Culbreth, W.G.

1996-07-03T23:59:59.000Z

433

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- FuelHealth and Safety Aspects of Pro- posed Nuclear, Geothermal, and Fossil-Fuel

Nero, A.V.

2010-01-01T23:59:59.000Z

434

A REVIEW OF AIR QUALITY MODELING TECHNIQUES. VOLUME 8 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUELHealth and Safety Impacts of Nuclear, Geothermal, and Fossil- Fuel

Rosen, L.C.

2010-01-01T23:59:59.000Z

435

Nuclear Explosives Safety Evaluation Process (DOE-STD-3015-2004)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SENSITIVE DOE-STD-3015-2004 November 2004 Superseding DOE-STD-3015-2001 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY EVALUATION PROCESS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Available on the Department of Energy Technical Standards Program Web site at http://tis.eh.doe.gov/techstds/. DOE-STD-3015-2004 iii FOREWORD This Department of Energy (DOE) Technical Standard is approved for use by the Assistant Deputy Administrator for Military Application and Stockpile Operations, National Nuclear Security Administration (NNSA), and is available for use with DOE O 452.1, NUCLEAR EXPLOSIVE AND WEAPON SURETY PROGRAM, and DOE O 452.2, SAFETY OF

436

Technical Data to Justify Full Burnup Credit in Criticality Safety Licensing Analysis  

SciTech Connect

Enercon Services, Inc. (ENERCON) was requested under Task Order No.2 to identify scientific and technical data needed to benchmark and justify Full Burnup Credit, which adds 16 fission products and 4 minor actinides1 to Actinide-Only burnup credit. The historical perspective for Full Burnup Credit is discussed, and interviews of organizations participating in burnup credit activities are summarized as a basis for identifying additional data needs and making recommendation. Input from burnup credit participants representing two segments of the commercial nuclear industry is provided. First, the Electric Power Research Institute (EPRI) has been very active in the development of Full Burnup Credit, representing the interests of nuclear utilities in achieving capacity gains for storage and transport casks. EPRI and its utility customers are interested in a swift resolution of the validation issues that are delaying the implementation of Full Burnup Credit [EPRI 2010b]. Second, used nuclear fuel storage and transportation Cask Vendors favor improving burnup credit beyond Actinide-Only burnup credit, although their discussion of specific burnup credit achievements and data needs was limited citing business sensitive and technical proprietary concerns. While Cask Vendor proprietary items are not specifically identified in this report, the needs of all nuclear industry participants are reflected in the conclusions and recommendations of this report. In addition, Oak Ridge National Laboratory (ORNL) and Sandia National Laboratory (SNL) were interviewed for their input into additional data needs to achieve Full Burnup Credit. ORNL was very open to discussions of Full Burnup Credit, with several telecoms and a visit by ENERCON to ORNL. For many years, ORNL has provided extensive support to the NRC regarding burnup credit in all of its forms. Discussions with ORNL focused on potential resolutions to the validation issues for the use of fission products. SNL was helpful in ENERCON's understanding of the difficult issues related to obtaining and analyzing additional cross section test data to support Full Burnup Credit. A PIRT (Phenomena Identification and Ranking Table) analysis was performed by ENERCON to evaluate the costs and benefits of acquiring different types of nuclear data in support of Full Burnup Credit. A PIRT exercise is a formal expert elicitation process with the final output being the ranking tables. The PIRT analysis (Table 7-4: Results of PIRT Evaluation) showed that the acquisition of additional Actinide-Only experimental data, although beneficial, was associated with high cost and is not necessarily needed. The conclusion was that the existing Radiochemical Assay (RCA) data plus the French Haut Taux de Combustion (HTC)2 and handbook Laboratory Critical Experiment (LCE) data provide adequate benchmark validation for Actinide-Only Burnup Credit. The PIRT analysis indicated that the costs and schedule to obtain sufficient additional experimental data to support the addition of 16 fission products to Actinide-Only Burnup Credit to produce Full Burnup Credit are quite substantial. ENERCON estimates the cost to be $50M to $100M with a schedule of five or more years. The PIRT analysis highlights another option for fission product burnup credit, which is the application of computer-based uncertainty analyses (S/U - Sensitivity/Uncertainty methodologies), confirmed by the limited experimental data that is already available. S/U analyses essentially transform cross section uncertainty information contained in the cross section libraries into a reactivity bias and uncertainty. Recent work by ORNL and EPRI has shown that a methodology to support Full Burnup Credit is possible using a combination of traditional RCA and LCE validation plus S/U validation for fission product isotopics and cross sections. Further, the most recent cross section data (ENDF/B-VII) can be incorporated into the burnup credit codes at a reasonable cost compared to the acquisition of equivalent experimental data. ENERCON concludes that even with the cos

Enercon Services, Inc.

2011-03-14T23:59:59.000Z

437

Defense Nuclear Facilitiets Safety Board Visit and Site Lead Planning Activities at the Los Alamos National Laboratory  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 1 Report Number: HIAR LANL-2012-08-16 Site: Los Alamos National Laboratory (LANL) Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Defense Nuclear Facilities Safety Board Visit and Site Lead Planning Activities at the Los Alamos National Laboratory Dates of Activity : 08/14/2012 - 08/16/2012 Report Preparer: Robert Freeman Activity Description/Purpose: The purpose of this Office of Health, Safety and Security (HSS) activity was to maintain site operational awareness of key nuclear safety performance areas of interest to the Defense Nuclear Facilities Safety Board (DNFSB), monitor ongoing site oversight and planning activities for Los Alamos National Laboratory (LANL) nuclear facilities, and identify and initiate

438

Defense Nuclear Facilitiets Safety Board Visit and Site Lead Planning Activities at the Los Alamos National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 1 Report Number: HIAR LANL-2012-08-16 Site: Los Alamos National Laboratory (LANL) Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Defense Nuclear Facilities Safety Board Visit and Site Lead Planning Activities at the Los Alamos National Laboratory Dates of Activity : 08/14/2012 - 08/16/2012 Report Preparer: Robert Freeman Activity Description/Purpose: The purpose of this Office of Health, Safety and Security (HSS) activity was to maintain site operational awareness of key nuclear safety performance areas of interest to the Defense Nuclear Facilities Safety Board (DNFSB), monitor ongoing site oversight and planning activities for Los Alamos National Laboratory (LANL) nuclear facilities, and identify and initiate

439

Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility, October 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-Y-12-2012-10-02 Site: Y-12 UPF Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Defense Nuclear Facilities Safety Board (DNFSB) Public Meeting on the Status of Integration of Safety into the Design of the Uranium Processing Facility (UPF) Dates of Activity: October 2, 2012 Report Preparer: Timothy Mengers Activity Description/Purpose: The Office of Health, Safety and Security (HSS) observed the public hearing of the DNFSB review of the UPF project status for integrating safety into design. The meeting was broken into three parts: a panel discussion and questioning of National Nuclear Security Administration (NNSA) oversight and execution; a panel discussion and questioning of the B&W Y-12

440

ON THE USE OF SPRAY SYSTEMS: AN EXAMPLE OF R&D WORK IN HYDROGEN SAFETY FOR NUCLEAR APPLICATIONS  

E-Print Network (OSTI)

occurred since the Three Mile Island nuclear accident in 1979 through experimental programs1 ON THE USE OF SPRAY SYSTEMS: AN EXAMPLE OF R&D WORK IN HYDROGEN SAFETY FOR NUCLEAR APPLICATIONS, igniters and spray systems have been designed and installed in modern nuclear power plants. Mitigation

Boyer, Edmond

Note: This page contains sample records for the topic "nuclear criticality safety" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Nuclear Safety Regulatory Assistance Reviews | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

July 22, 2013 July 22, 2013 Enforcement Letter, NEL-2013-03 Issued to Lawrence Livermore National Security, LLC related to Programmatic Deficiencies in the Software Quality Assurance Program at the Lawrence Livermore National Laboratory February 12, 2013 Enforcement Letter, NEL-2013-02 Issued to Los Alamos National Security, LLC related to a Radiological Contamination Event at the Los Alamos Neutron Science Center at Los Alamos National Laboratory January 7, 2013 Enforcement Letter, NEL-2013-01 Issued to B&W Pantex, LLC related to the Conduct of Nuclear Explosive Operations at the Pantex Plant October 23, 2012 Enforcement Letter, Controlled Power Company - WEL-2012-02 Enforcement Letter issued to Controlled Power Company related to an Electrical Shock Near Miss that occurred in the Radiological Laboratory

442

Stakeholder Transportation Scorecard: Reviewing Nevada's Recommendations for Enhancing the Safety and Security of Nuclear Waste Shipments - 13518  

SciTech Connect

As a primary stakeholder in the Yucca Mountain program, the state of Nevada has spent three decades examining and considering national policy regarding spent nuclear fuel and high-level radioactive waste transportation. During this time, Nevada has identified 10 issues it believes are critical to ensuring the safety and security of any spent nuclear fuel transportation program, and achieving public acceptance. These recommendations are: 1) Ship the oldest fuel first; 2) Ship mostly by rail; 3) Use dual-purpose (transportable storage) casks; 4) Use dedicated trains for rail shipments; 5) Implement a full-scale cask testing program; 6) Utilize a National Environmental Policy Act (NEPA) process for the selection of a new rail spur to the proposed repository site; 7) Implement the Western Interstate Energy Board (WIEB) 'straw man' process for route selection; 8) Implement Section 180C assistance to affected States, Tribes and localities through rulemaking; 9) Adopt safety and security regulatory enhancements proposed states; and 10) Address stakeholder concerns about terrorism and sabotage. This paper describes Nevada's proposals in detail and examines their current status. The paper describes the various forums and methods by which Nevada has presented its arguments and sought to influence national policy. As of 2012, most of Nevada's recommendations have been adopted in one form or another, although not yet implemented. If implemented in a future nuclear waste program, the State of Nevada believes these recommendations would form the basis for a successful national transportation plan for shipments to a geologic repository and/or centralized interim storage facility. (authors)

Dilger, Fred C. [Black Mountain Research, Henderson, NV 81012 (United States)] [Black Mountain Research, Henderson, NV 81012 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge, CA 91330 (United States)] [Department of Sociology, California State University, Northridge, CA 91330 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States)] [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States)

2013-07-01T23:59:59.000Z

443

Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel  

SciTech Connect

In conventional criticality evaluations of nuclear powder systems, effects of particulate behavior were not considered. In other words, it is difficult to take into account the particle motion in the criticality evaluations. We have developed a novel criticality evaluation code to resolve this problem. The criticality evaluation code, coupling a discrete element method simulation code with a continuous-energy Monte Carlo transport code, makes it possible to study the effects of the particulate dynamics on criticality. This criticality evaluation code is applied to the mixed-oxide (MOX) fuel powder agitation process. The criticality evaluations are performed while mixing the MOX fuel powder and an additive powder in a stirred vessel to investigate the effects of the powder free surface deformation and the particulate mixture state on the effective multiplication factor. The evaluation results reveal that the effective multiplication factor decreases due to the powder boundary deformation while it increases as the mixture condition of MOX powder and Zn-St powder is close to homogeneous.

Sakai, Mikio; Yamamoto, Toshihiro; Murazaki, Minoru; Miyoshi, Yoshinori [Japan Atomic Energy Research Institute (Japan)

2005-02-15T23:59:59.000Z

444

Summary of Preliminary Criticality Analysis for Peach Bottom Fuel in the DOE Standardized Spent Nuclear Fuel Canister  

SciTech Connect

The Department of Energy's (DOE's) National Spent Nuclear Fuel Program is developing a standardized set of canisters for DOE spent nuclear fuel (SNF). These canisters will be used for DOE SNF handling, interim storage, transportation, and disposal in the national repository. Several fuels are being examined in conjunction with the DOE SNF canisters. This report summarizes the preliminary criticality safety analysis that addresses general fissile loading limits for Peach Bottom graphite fuel in the DOE SNF canister. The canister is considered both alone and inside the 5-HLW/DOE Long Spent Fuel Co-disposal Waste Package, and in intact and degraded conditions. Results are appropriate for a single DOE SNF canister. Specific facilities, equipment, canister internal structures, and scenarios for handling, storage, and transportation have not yet been defined and are not evaluated in this analysis. The analysis assumes that the DOE SNF canister is designed so that it maintains reasonable geometric integrity. Parameters important to the results are the canister outer diameter, inner diameter, and wall thickness. These parameters are assumed to have nominal dimensions of 45.7-cm (18.0-in.), 43.815-cm (17.25-in), and 0.953-cm (0.375-in.), respectively. Based on the analysis results, the recommended fissile loading for the DOE SNF canister is 13 Peach Bottom fuel elements if no internal steel is present, and 15 Peach Bottom fuel elements if credit is taken for internal steel.

Henrikson, D.J.

1999-09-01T23:59:59.000Z

445

Just in Time DSA-The Hanford Nuclear Safety Basis Strategy  

SciTech Connect

The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safety Basis Requirements (the Rule) in January 2001 imposed the requirement that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSA that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: compliance with the Rule; a ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

Olinger, S. J.; Buhl, A. R.

2002-02-26T23:59:59.000Z

446

Criticality Safety Evaluation Report for the Cold Vacuum Drying (CVD) Facilities Process Water Handling System  

SciTech Connect

This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified.

KESSLER, S.F.

2000-08-10T23:59:59.000Z

447

De-alerting of U.S. nuclear forces: a critical appraisal  

SciTech Connect

Since the end of the Cold War, there have been pressures by disarmament advocates to move more quickly to draw down, toward zero, the number of nuclear weapons in U.S. and Russian arsenals. They criticize the process of negotiating arms control agreements as being too slow, and point out that treaty implementation is hampered by the necessity of ratification by the U.S. Senate and Russian Duma. One method of moving more rapidly toward nuclear abolition suggested by some analysts is de-alerting of nuclear-weapon delivery systems. De-alerting is defined as taking steps that increase significantly the time required to launch a given delivery vehicle armed with a nuclear warhead. Although there is little inclination by the U.S. Government to de-alert its nuclear forces at present, some academic literature and press stories continue to advocate such steps. This paper offers a critique of de-alerting proposals together with an assessment of the dangers of accidental, unauthorized, or unintended use of nuclear weapons. It concludes that de-alerting nuclear forces would be extremely de-stabilizing, principally because it would increase the value to an opponent of launching a first strike.

Bailey, K C; Barish, F

1998-08-21T23:59:59.000Z

448

General-purpose heat source project and space nuclear safety fuels program. Progress report, February 1980  

SciTech Connect

This formal monthly report covers the studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are: General-Purpose Heat Source Development and Space Nuclear Safety and Fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work.

Maraman, W.J. (comp.)

1980-05-01T23:59:59.000Z

449

Implementation Evaluation Criteria for January 2001 Amended 10 CFR Part 830 Nuclear Safety Management  

SciTech Connect

This document provides criteria for use in performing gap evaluations of processes and documents relative to the requirements of 10 CFR Part 830, Nuclear Safety Management. The criteria and associated objective evidence statements have been approved by the cognizant interpretative authorities. The criteria have been developed for each section of 10 CFR Part 830. The criteria have been divided into two categories. Criteria and objective evidence have been developed for use in assessing Fluor Hanford (FH) programs and procedures at the company level--programmatic requirements and evidence. Criteria and objective evidence statements have also been developed for FH nuclear facilities and projects.

EVANS, C.B.

2001-02-13T23:59:59.000Z

450

Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3009-94 3009-94 July 1994 CHANGE NOTICE NO.1 January 2000 CHANGE NOTICE NO. 2 April 2002 CHANGE NOTICE NO. 3 March 2006 DOE STANDARD PREPARATION GUIDE FOR U.S DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSES U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-3009-94 Page ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. DOE-STD-3009-94 Page iii Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses Table of Changes

451

A case study on effectiveness of structural reliability analysis in nuclear reactor safety assessment  

Science Journals Connector (OSTI)

Problems on reliability of structural integrity occupy an important position in various aspects of nuclear reactor safety. In the present paper, an effective method for quantitative evaluation of structural reliability based on stress strength model is developed with the objectives of taking a larger number of factors into the evaluation than before and giving useful results within moderate computing time. The method is applied to the reliability analysis of PWR pressure vessels. The results show the relative importance of inspection as well as the parameter uncertainty for assuring the reliability of the structure, although analysis is limited within the scope of linear elastic fracture mechanics (LEFM). This case study also shows that the analysis of structural reliability is effective for safety assessment of nuclear power plants in general and possibly for the improvements of the consistency in the design code.

A. Yamaguchi; S. Kondo; Y. Togo

1983-01-01T23:59:59.000Z

452

Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Operations Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions Name: Organization: Directions: This is an open-book evaluation. Complete the questions, and submit your answers (hand-written or electronically) to the Training Center. Someone will check and grade your answers. If you achieve a score of at least 80%, you will receive a completion certificate. Questions: 1. What is safety basis (SB)? 2. How does SB fit with integrated safety management (ISM)? 3. In what primary DOE documents can requirements and guidance for SB be found? 4. What are the "graded approach" factors that DOE takes into account in ensuring that the level of analysis and documentation and the actions used to comply with the requirements are

453

Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Operations Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions Name: Organization: Directions: This is an open-book evaluation. Complete the questions, and submit your answers (hand-written or electronically) to the Training Center. Someone will check and grade your answers. If you achieve a score of at least 80%, you will receive a completion certificate. Questions: 1. What is safety basis (SB)? 2. How does SB fit with integrated safety management (ISM)? 3. In what primary DOE documents can requirements and guidance for SB be found? 4. What are the "graded approach" factors that DOE takes into account in ensuring that the level of analysis and documentation and the actions used to comply with the requirements are

454

The nucleotide-binding domain of NLRC5 is critical for nuclear import and transactivation activity  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer NLRC5 requires an intact NLS for its function as MHC class I transactivator. Black-Right-Pointing-Pointer Nuclear presence of NLRC5 is required for MHC class I induction. Black-Right-Pointing-Pointer Nucleotide-binding controls nuclear import and transactivation activity of NLRC5. -- Abstract: Major histocompatibility complex (MHC) class I and class II are crucial for the function of the human adaptive immune system. A member of the NLR (nucleotide-binding domain, leucine-rich repeat) protein family, NLRC5, has recently been identified as a transcriptional regulator of MHC class I and related genes. While a 'master regulator' of MHC class II genes, CIITA, has long been known, NLRC5 specifically associates with and transactivates the proximal promoters of MHC class I genes. In this study, we analyzed the molecular requirements of NLRC5 nuclear import and transactivation activity. We show that NLRC5-mediated MHC class I gene induction requires an intact nuclear localization signal and nuclear distribution of NLRC5. In addition, we find that the nucleotide-binding domain (NBD) of NLRC5 is critical not only for nuclear translocation but also for the transactivation of MHC class I genes. Changing the cellular localization of NLRC5 is likely to immediately impact MHC class I expression as well as MHC class I-mediated antigen presentation. NLRC5 may thus provide a promising target for the modulation of MHC class I antigen presentation, especially in the setting of transplant medicine.

Meissner, Torsten B. [Department of Cancer Immunology and AIDS, Dana-Farber Cancer Institute, Boston, MA 02215 (United States) [Department of Cancer Immunology and AIDS, Dana-Farber Cancer Institute, Boston, MA 02215 (United States); Department of Microbiology and Immunobiology, Harvard Medical School, Boston, MA 02215 (United States); Li, Amy; Liu, Yuen-Joyce [Department of Cancer Immunology and AIDS, Dana-Farber Cancer Institute, Boston, MA 02215 (United States)] [Department of Cancer Immunology and AIDS, Dana-Farber Cancer Institute, Boston, MA 02215 (United States); Gagnon, Etienne [Department of Cancer Immunology and AIDS, Dana-Farber Cancer Institute, Boston, MA 02215 (United States) [Department of Cancer Immunology and AIDS, Dana-Farber Cancer Institute, Boston, MA 02215 (United States); Institut de Recherche en Immunologie et Cancerologie, Departement de Microbiologie et Immunologie, Universite de Montreal, Montreal, Canada H3T1J4 (Canada); Kobayashi, Koichi S., E-mail: Koichi_Kobayashi@dfci.harvard.edu [Department of Cancer Immunology and AIDS, Dana-Farber Cancer Institute, Boston, MA 02215 (United States); Department of Microbiology and Immunobiology, Harvard Medical School, Boston, MA 02215 (United States)

2012-02-24T23:59:59.000Z

455

Observation of the critical end point in the phase diagram for hot and dense nuclear matter  

E-Print Network (OSTI)

Excitation functions for the Gaussian emission source radii difference ($R^2_{\\text{out}} - R^2_{\\text{side}}$) obtained from two-pion interferometry measurements in Au+Au ($\\sqrt{s_{NN}}= 7.7 - 200$ GeV) and Pb+Pb ($\\sqrt{s_{NN}}= 2.76$ TeV) collisions, are studied for a broad range of collision centralities. The observed non-monotonic excitation functions validate the finite-size scaling patterns expected for the deconfinement phase transition and the critical end point (CEP), in the temperature vs. baryon chemical potential ($T,\\mu_B$) plane of the nuclear matter phase diagram. A Finite-Size Scaling (FSS) analysis of these data indicate a second order phase transition with the estimates $T^{\\text{cep}} \\sim 165$~MeV and $\\mu_B^{\\text{cep}} \\sim 100$~MeV for the location of the critical end point. The critical exponents ($\

Lacey, Roy A

2014-01-01T23:59:59.000Z

456

The EOP Visualization Module Integrated into the Plasma On-Line Nuclear Power Plant Safety Monitoring and Assessment System  

SciTech Connect

An ambitious project to replace the unit information systems (UISs) at the Hungarian Paks nuclear power plant was started in 1998-99. The basic aim of the reconstruction project is to install a modern, distributed UIS architecture on all four Paks VVER-440 units. The new UIS includes an on-line plant safety monitoring and assessment system (PLASMA), which contains a critical safety functions monitoring module and provides extensive operator support during the execution of the new, symptom-oriented emergency operating procedures (EOPs). PLASMA includes a comprehensive EOP visualization module, based on the COPMA-III procedure-handling software developed by the Organization for Economic Cooperation and Development, Halden Reactor Project. Intranet technology is applied for the presentation of the EOPs with the use of a standard hypertext markup language (HTML) browser as a visualization tool. The basic design characteristics of the system, with a detailed description of its user interface and functions of the new EOP display module, are presented.

Hornaes, Arne [Organization for Economic Cooperation and Development (France); Hulsund, John Einar [Organization for Economic Cooperation and Development (France); Vegh, Janos [KFKI Atomic Energy Research Institute (Hungary); Major, Csaba [KFKI Atomic Energy Research Institute (Hungary); Horvath, Csaba [KFKI Atomic Energy Research Institute (Hungary); Lipcsei, Sandor [KFKI Atomic Energy Research Institute (Hungary); Kapocs, Gyoergy [Paks Nuclear Power Plant Ltd. (Hungary)

2001-08-15T23:59:59.000Z

457

The potential role of new technology for enhanced safety and performance of nuclear power plants through improved service maintenance  

E-Print Network (OSTI)

Refinements in the safety and performance of nuclear power plants must be made to maintain public confidence and ensure competitiveness with other power sources. The aircraft industry, US Navy, and other programs have ...

Achorn, Ted Glen

1991-01-01T23:59:59.000Z

458

Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports  

Directives, Delegations, and Requirements

he purpose of this DOE Standard is to establish guidance for the preparation and review of hazard categorization and accident analyses techniques as required in DOE Order 5480.23, Nuclear Safety Analysis Reports.

1997-12-12T23:59:59.000Z

459

[6450-01-P], DEPARTMENT OF ENERGY, 10 CFR Part 830, Nuclear Safety Management, AGENCY: Department of Energy (DOE).  

Energy.gov (U.S. Department of Energy (DOE))

The Department of Energy (DOE) is issuing a final rule regarding Nuclear SafetyManagement. This Part establishes requirements for the safe management of DOE contractor andsubcontractor work at the...

460

Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project, November 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Idaho Cleanup Project Idaho Cleanup Project Sodium Bearing Waste Treatment Project May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project Table of Contents 1.0 Introduction........................................................................................................................................... 1 2.0 Scope and Methodology ....................................................................................................................... 2

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461

Assessment of Nuclear Safety Culture at the Los Alamos National Laboratory Chemistry and Metallurgy Research Replacement Project, April 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Los Alamos National Laboratory Los Alamos National Laboratory Chemistry and Metallurgy Research Replacement Project May 2011 April 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Los Alamos National Laboratory Chemistry and Metallurgy Research Replacement Project Table of Contents 1. Introduction ........................................................................................................................................... 1 2. Scope and Methodology ....................................................................................................................... 2

462

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

of the health and safety impact of fossil fuel emissions.to public health and safety, of any fossil fuel plant areHEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL

Nero, A.V.

2010-01-01T23:59:59.000Z

463

DOE's Nuclear Weapons Complex: Challenges to Safety, Security, and Taxpayer Stewardship  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oversight and Investigations Oversight and Investigations Committee on Energy and Commerce U.S. House of Representatives "DOE's Nuclear Weapons Complex: Challenges to Safety, Security, and Taxpayer Stewardship" FOR RELEASE ON DELIVERY 10:00 AM September 12, 2012 1 Mr. Chairman and Members of the Subcommittee, I am pleased to be here at your request to testify on matters relating to the Department of Energy's oversight of the nuclear weapons complex. 1 The National Nuclear Security Administration (NNSA) was established under the National Defense Authorization Act of 2000 as a separately organized agency within the Department of Energy. This action was intended to allow NNSA to concentrate on its defense-related mission, free from other Departmental operations. Its creation was, in large measure, a reaction to highly

464

Letter from Nuclear Energy Institute regarding Integrated Safety Analysis: Why it is Appropropriate for Fuel Recycling Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

082 l F: 202.533.0166 l rxm@nei.org l www.nei.org 082 l F: 202.533.0166 l rxm@nei.org l www.nei.org Rod McCullum DIRECTOR FUEL CYCLE PROJECTS NUCLEAR GENERATION DIVISION September 10, 2010 Ms. Catherine Haney Director Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689 Dear Ms. Haney: Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is intended as an information source for the NRC and should serve as a foundation for discussion with industry representatives on the issue.

465

Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities  

Energy.gov (U.S. Department of Energy (DOE))

In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made.

466

Nuclear incident monitor criticality alarm instrument for the Savannah River Site: Technical manual  

SciTech Connect

The Savannah River Site is a Department of Energy facility. The facility stores, processes, and works with fissionable material at a number of locations. Technical standards and US Department of Energy orders, require these locations to be monitored by criticality alarm systems under certain circumstances. The Savannah River Site calls such instruments Nuclear Incident Monitors or NIMs. The Sole purpose of the Nuclear Incident Monitor is to provide an immediate evacuation signal in the case of an accidental criticality in order to minimize personnel exposure to radiation. The new unit is the third generation Nuclear Incident Monitor at the Savannah River Site. The second generation unit was developed in 1979. It was designed to eliminate vacuum-tube circuits, and was the first solid state NIM at SRS. The major design objectives of the second generation NIM were to improve reliability and reduce maintenance costs. Ten prototype units have been built and tested. This report describes the design of the new NIM and the testing that took place to verify its acceptability.

Jenkins, J.B.

1996-05-21T23:59:59.000Z

467

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing  

SciTech Connect

This volume of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power - generating capability and one without.

Not Available

1980-06-01T23:59:59.000Z

468

Techniques to evaluate the importance of common cause degradation on reliability and safety of nuclear weapons.  

SciTech Connect

As the nuclear weapon stockpile ages, there is increased concern about common degradation ultimately leading to common cause failure of multiple weapons that could significantly impact reliability or safety. Current acceptable limits for the reliability and safety of a weapon are based on upper limits on the probability of failure of an individual item, assuming that failures among items are independent. We expanded the current acceptable limits to apply to situations with common cause failure. Then, we developed a simple screening process to quickly assess the importance of observed common degradation for both reliability and safety to determine if further action is necessary. The screening process conservatively assumes that common degradation is common cause failure. For a population with between 100 and 5000 items we applied the screening process and conclude the following. In general, for a reliability requirement specified in the Military Characteristics (MCs) for a specific weapon system, common degradation is of concern if more than 100(1-x)% of the weapons are susceptible to common degradation, where x is the required reliability expressed as a fraction. Common degradation is of concern for the safety of a weapon subsystem if more than 0.1% of the population is susceptible to common degradation. Common degradation is of concern for the safety of a weapon component or overall weapon system if two or more components/weapons in the population are susceptible to degradation. Finally, we developed a technique for detailed evaluation of common degradation leading to common cause failure for situations that are determined to be of concern using the screening process. The detailed evaluation requires that best estimates of common cause and independent failure probabilities be produced. Using these techniques, observed common degradation can be evaluated for effects on reliability and safety.

Darby, John L.

2011-05-01T23:59:59.000Z

469

Development of a Societal-Risk Goal for Nuclear Power Safety  

SciTech Connect

The safety-goal policy of the Nuclear Regulatory Commission (NRC) has never included a true societal-risk goal. The NRC did acknowledge that the original goal for the risk of latent cancer facilities was an individual risk goal not related to the number of people involved, and stated that a true societal risk goal would place a limit on the aggregate number of people affected. However, this limitation was never satisfactorily addressed. Moreover, the safety goal has historically focused primarily on fatalities and latent health effects, while experience with actual nuclear accidents has shown that societal disruption can be significant even in accidents that yield only small to modest numbers of fatalities. Therefore, we have evaluated the social disruption effects from severe reactor accidents as a basis to develop a societal-risk goal for nuclear power plants, considering both health effects and non-health concerns such as property damage and land interdiction. Our initial analysis considered six different nuclear power plant sites in the U.S. for Boiling Water Reactors and Pressurized Water Reactors. The accident sequences considered for these two reactor types were station blackout sequences (both short-term and long-term SBO) as well as an STSBO with RCIC failure for the BWR and a Steam Generator Tube Rupture for the PWR. The source term release was an input in a RASCAL calculation of the off-site consequences using actual site-based weather data for each of the six plant sites randomly selected over a two-year period. The source term release plumes were then compared to Geographical Information System data for each site to determine the population affected and that would need to be evacuated to meet current emergency preparedness regulations. Our results to date suggest that number of people evacuated to meet current protective action guidelines appears to be a good proxy for disruption -- and, unlike other measures of disruption, has the advantage of being relatively straightforward to calculate for a given accident scenario and a given geographical location and plant site. Revised safety goals taking into account the potential for societal disruption could in principle be applied to the current generation of nuclear plants, but could also be used in evaluating and siting new technologies, such as small modular light water reactors, advanced Gen-IV high-temperature reactors, as well as reactor designs with passive safety features such as filtered vented containments.

Vicki Bier; Michael Corradini; Robert Youngblood