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Note: This page contains sample records for the topic "defense nuclear facilities" from the National Library of EnergyBeta (NLEBeta).
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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.


1

The Defense Nuclear Facilities Safety Board - Strategic Plan...  

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

all of its defense nuclear facilities. Message from the Board Peter S. Winokur, Chariman Jessie H. Roberson, Vice Chariman John E. Mansfield Joseph F. Bader DEFENSE NUCLEAR...

2

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

3

NNSA and Defense Nuclear Facilities Safety Board certifications...  

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

allocated funding NNSA and Defense Nuclear Facilities Safety Board certifications free up 47 million in previously allocated funding The DNFSB and NNSA required the CMRR...

4

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

5

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

6

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

7

AGENCY: Defense Nuclear Facilities Safety Board, ACTION: Notice...  

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

upon to accomplish the mission assigned to DOE and NNSA under the Atomic Energy Act of 1954, as amended, at defense nuclear facilities . We will focus on what impact DOE's and...

8

DOE M 140.1-1B, 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 ...

2001-03-30T23:59:59.000Z

9

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

10

Assessment of nuclear safety and nuclear criticality potential in the Defense Waste Processing Facility  

SciTech Connect

A panel of experts in the fields of process engineering, process chemistry, and safety analysis met together on January 26, 1993, and February 19, 1993, to discuss nuclear safety and nuclear criticality potential in the Defense Waste Processing Facility (DWPF) processes. Nuclear safety issues and possibilities of nuclear criticality incidents in the DWPF were examined in depth. The discussion started at the receipt of slurry feeds: The Low Point Pump Pit Precipitate Tank (LPPPPT) and the Low Point Pump Pit Sludge Tank (LPPPST), and went into detail the whole DWPF processes. This report provides discussion of each of the areas and processes of the DWPF in terms of potential nuclear safety issues and nuclear criticality concerns.

Ha, B.C.

1993-05-10T23:59:59.000Z

11

Assessment of nuclear safety and nuclear criticality potential in the Defense Waste Processing Facility. Revision 1  

SciTech Connect

The S-Area Defense Waste Processing Facility (DWPF) will initially process Batch 1 sludge in the sludge-only processing mode, with simulated non-radioactive Precipitate Hydrolysis, Aqueous (PHA) product, without the risk of nuclear criticality. The dilute concentration of fissile material in the sludge combined with excess of neutron absorbers during normal operations make criticality throughout the whole process incredible. Subsequent batches of the DWPF involving radioactive precipitate slurry and PHA will require additional analysis. Any abnormal or upset process operations, which are not considered in this report and could potentially separate fissile material, must be individually evaluated. Scheduled maintenance operation procedures are not considered to be abnormal.

Ha, B.C.

1993-07-20T23:59:59.000Z

12

Defense Nuclear Facilities Safety Board Review at the Nevada...  

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

air filters. The Board members and staff toured CEF, DAF, and the Joint Actinide Shock Physics Experimental Research (JASPER) facility. Additional discussions of subcritical...

13

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:

14

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 -

15

General Technical Base Qualification Standard (DOE Defense Nuclear Facilities Technical Personnel)  

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

DOE-STD-1146-2007 December 2007 DOE STANDARD GENERAL TECHNICAL BASE 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-1146-2007 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-1146-2007 iv INTENTIONALLY BLANK DOE-STD-1146-2007 v TABLE OF CONTENTS ACKNOWLEDGMENT................................................................................................................ vii PURPOSE ....................................................................................................................................9

16

Nuclear criticality safety analysis summary report: The S-area defense waste processing facility  

SciTech Connect

The S-Area Defense Waste Processing Facility (DWPF) can process all of the high level radioactive wastes currently stored at the Savannah River Site with negligible risk of nuclear criticality. The characteristics which make the DWPF critically safe are: (1) abundance of neutron absorbers in the waste feeds; (2) and low concentration of fissionable material. This report documents the criticality safety arguments for the S-Area DWPF process as required by DOE orders to characterize and to justify the low potential for criticality. It documents that the nature of the waste feeds and the nature of the DWPF process chemistry preclude criticality.

Ha, B.C.

1994-10-21T23:59:59.000Z

17

Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 1998  

Science Conference Proceedings (OSTI)

This is the ninth Annual Report to the Congress describing Department of Energy (Department) activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of energy regarding public health and safety issues at the Department`s defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department`s defense nuclear facilities. The locations of the major Department facilities are provided. During 1998, Departmental activities resulted in the proposed closure of one Board recommendation. In addition, the Department has completed all implementation plan milestones associated with four other Board recommendations. Two new Board recommendations were received and accepted by the Department in 1998, and two new implementation plans are being developed to address these recommendations. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, a renewed effort to increase the technical capabilities of the federal workforce, and a revised plan for stabilizing excess nuclear materials to achieve significant risk reduction.

NONE

1999-02-01T23:59:59.000Z

18

Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, Calendar Year 1999  

SciTech Connect

This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted in the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

None

2000-02-01T23:59:59.000Z

19

October 24, 2003, Criteria and Guidelines For the Assessment of Safety System Software and Firmware at Defense Nuclear Facilities  

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

3.1 3.1 Revision 3 October 24, 2003 U. S. Department of Energy Criteria and Guidelines For the Assessment of Safety System Software and Firmware at Defense Nuclear Facilities October 24, 2003 CRAD - 4.2.3.1 Revision 3 October 24, 2003 i TABLE OF CONTENTS ACRONYMS...................................................................................................................................ii GLOSSARY ...................................................................................................................................iii 1.0 INTRODUCTION .....................................................................................................................1 2.0 BACKGROUND .......................................................................................................................2

20

April 27, 2010, Department letter transmitting revised Implementation Plan for Recommendation 2009-1, Risk Assessment Methodologies at Defense Nuclear Facilities  

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

April 27, 20 10 April 27, 20 10 The Honorable Peter S. Winokur Chairman Defense Nuclear Facilities Safety Board 625 Indiana Avenue, NW, Suite 700 Washington, DC 20004-294 1 Dear Mr. Chairman: In a letter to the Defense Nuclear Facilities Safety Board dated February 1, 20 10, I reaffirmed our acceptance of Recommendation 2009- 1, Risk Assessment Methodologies at Defense Nuclear Facilities, and committed to several changes to the Department's Plan for implementing the recommendations therein. Enclosed please find the revised Implementation Plan for Defense Nuclear Facilities Safity Board Recommendation 2009-1 that incorporates those changes. I want to express my thanks for your staffs input on this revision and look forward to similar contributions as we revise the Department's Nuclear Safety Policy and implement

Note: This page contains sample records for the topic "defense nuclear facilities" 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

DOE FTCP Supplemental Competencies - Human Factors Engineering Functional Area Qualification Competency Examples for DOE Defense Nuclear Facilities Technical Personnel  

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

FTCP FTCP SUPPLEMENTAL COMPETENCIES HUMAN FACTORS ENGINEERING FUNCTIONAL AREA QUALIFICATION COMPETENCY EXAMPLES For DOE Defense Nuclear Facilities Technical Personnel 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 qualification standards and competencies for Department-wide application. Approval of this set of competency statements by the Federal Technical Capability Panel is indicated by signature below. ?fuv-~ Karen L. Boardman, Chairperson ~·/Cf I Federal Technical Capability Panel * '2._ 3/19/12 I luman Factors Engineering compc1cncics U.S. DEPARTMENT OF ENERGY

22

Annual report to Congress. Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 2000  

Science Conference Proceedings (OSTI)

This Annual Report to the Congress describes the Department of Energy's activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board. During 2000, the Department completed its implementation and proposed closure of one Board recommendation and completed all implementation plan milestones associated with two additional Board recommendations. Also in 2000, the Department formally accepted two new Board recommendations and developed implementation plans in response to those recommendations. The Department also made significant progress with a number of broad-based safety initiatives. These include initial implementation of integrated safety management at field sites and within headquarters program offices, issuance of a nuclear safety rule, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

None

2001-03-01T23:59:59.000Z

23

Improved Schedule for Remediation in the Defense Nuclear Facilities Complex, and 2000-1,  

E-Print Network (OSTI)

Prioritization for Stabilizing Nuclear Materials, to address the nuclear safety issues related to the remnants ofweapons production. Recommendation 94-1, agreed to by the Secretary of Energy, required that the most hazardous nuclear materials be stabilized within two to three years and that the remaining materials be stabilized by the year 2002, which was considered a reasonable period oftime. Both Recommendations also recognized the unique chemical separations capability ofthe F- and H-Canyon facilities at the Savannah River Site as an important and integral part ofthe Department ofEnergy's (DOE) stabilization mission. As this stabilization has proceeded during the years 1995-2002, a number ofevents affecting the effort have evolved. First, a considerable amount ofthe high risk materials identified at the initiation ofthe stabilization program, has been stabilized and placed in safe storage. However, the initially programmed effort fell behind schedule and in 2001, the schedule was lengthened. Much remains to be done. Second, the inventory ofmaterials requiring treatment and stabilization continued to grow as the weapons program downsized and the clean out of facilities

Joseph J. Dinwuio; John E. Mansfield

2002-01-01T23:59:59.000Z

24

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

25

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

The National Nuclear Security Administration Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Test...

26

DOE-STD-1146-2001; General Technical Base Qualification Standard DOE Defense Nuclear Facilities Technical Personnel  

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

46-2001 46-2001 October 2001 DOE STANDARD GENERAL TECHNICAL BASE 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. 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-1146-2001 iii APPROVAL The Federal Technical Capability Panel consists of senior Department of Energy managers responsible for overseeing the Federal Technical Capability Program. This Panel is responsible

27

November 8, 1983: Defense Waste Processing Facility | Department of Energy  

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

November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983 The Department begins construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Plant in South Carolina. DWPF is designed to make high-level nuclear waste into a glass-like substance, which will then be shipped to a repository. DWPF will mix borosilicate glass with the waste, heat it to 2000 degrees F, and pour the mixture into stainless steel canisters. The mixture will cool into solid glass that can be permanently stored. DWPF will immobilize the more than 34 million gallons of liquid high-level waste that have accumulated from producing defense-related nuclear materials

28

Defense Nuclear Facilitiets Safety Board Visit and Site Lead...  

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

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...

29

Defense and nuclear technologies  

SciTech Connect

Fulfilling our national security and stockpile stewardship responsibilities requires tremendous scientific and technical breadth: from esoteric theoretical physics and computational modeling to materials science and precision engineering. Because there exists no broad industrial or university base from which to draw expertise in nuclear weapon science and technology, we rely heavily on formal peer reviews and informal exchanges with our sister laboratory at Los Alamos. LLNL has an important, long-term role in the nation`s nuclear weapons program. We are responsible for four of the ten weapon systems in the enduring US stockpile (three of nine after 2002), including the only systems that incorporate all modern safety features. For years to come, we will be responsible for these weapons and for the problems that will inevitably arise. Our nuclear expertise will also play a crucial role as the US attempts to deal effectively with the threat of nuclear proliferation. This past year brought the culmination of our response to profound changes in the nation`s defense needs as we restructured and refocused our activities to address the Administration`s goal of reducing global nuclear danger. We made major contributions to important national security issues in spite of severe fiscal constraints.

NONE

1995-01-01T23:59:59.000Z

30

October 24, 2003, Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities  

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

4.1 4.1 Revision 3 October 24, 2003 U. S. Department of Energy Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities October 24, 2003 CRAD - 4.2.4.1 Revision 3 October 24, 2003 ii TABLE OF CONTENTS ACRONYMS ..................................................................................................................................iii GLOSSARY ...................................................................................................................................iv 1.0 INTRODUCTION ...............................................................................................................1 2.0 BACKGROUND .................................................................................................................2

31

.Dear Secretary Bodman: In its response to the Defense Nuclear Facilities Safety Board's (Board)  

E-Print Network (OSTI)

of Energy (DOE) committed to revitalizing Integrated Safety Management (ISM) with "a set of actions the Department will pursue to re-confirm that ISM will be the foundation of the Department's safety management approach and to address identified weaknesses in implementation. " The enclosed technical report, DNFSB/TECH-36, Integrated Safety Management: The Foundation for an Effective Safety Culture, provides an assessment of the strengths and weaknesses of the current state of ISM implementation at the National Nuclear Security Administration's (NNSA) production plants and laboratories. ISM was established 10 years ago as a new approach to integrating work and safety. The concept was adopted by DOE to enhance safety awareness, upgrade formality of operations, and improve safety performance. However, the potential for this practical safety system to achieve operational excellence and instill a sustainable safety culture has not been fully realized. From the broadest perspective, requirements and mechanisms to implement ISM are established, but implementation of safety management systems varies from site to site. This report examines the current status of the effectiveness of ISM systems at the seven NNSA weapons sites, summarizes

Joseph F. Bader; John E Mansfield; The Honorable; Samuel W. Bodman; Oversight Of Complex; High-hazard Organizations; The Department; A J. Eggenberger; Ms Patty Wagner

2006-01-01T23:59:59.000Z

32

Nuclear Facilities Production Facilities  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration under contract DE-AC04-94AL85000. Sand 2011-4582P. ENERGY U.S. DEPARTMENT OF Gamma Irradiation Facility (GIF) The GIF provides test cells for...

33

Protection Programming Defensive Planning for Fixed Facilities  

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

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE STD-1207-2012 December 2012 DOE STANDARD Protection Program Defensive Planning For Fixed Facilities U.S. Department of Energy AREA SANS Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE STD-1207-2012 This Page Intentionally Left Blank ii DOE STD-1207-2012 TABLE OF CONTENTS FOREWORD..................................................................................................................................v PROTECTION PROGRAM DEFENSIVE PLANNING ..........................................................1 1. SCOPE............................................................................................................................ 1 2. PURPOSE. ..................................................................................................................... 1

34

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Office of Defense Science Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Research and...

35

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Office of Defense Science Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Research and Development...

36

Review of the Los Alamos National Laoratory Nuclear Facility...  

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

CM Configuration Management CMR Chemistry and Metallurgy Research CSE Cognizant System Engineer DNFSB Defense Nuclear Facilities Safety Board DOE U.S. Department of Energy...

37

Idaho Site Nuclear Facilities  

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

Site Nuclear Facilities Idaho Idaho National Laboratorys (INL) Idaho Closure Project (ICP) This page was last updated on May 16...

38

Contained Firing Facility | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Contained Firing Facility | National Nuclear Security Administration Contained Firing Facility | 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 Contained Firing Facility Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Research and Development > Facilities > Contained Firing Facility

39

High Explosives Application Facility | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Explosives Application Facility | National Nuclear Security Explosives Application Facility | 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 The National Nuclear Security Administration High Explosives Application Facility Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Research and Development >

40

Defense Programs | National Nuclear Security Administration  

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

Programs | National Nuclear Security Administration Programs | 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 Defense Programs Home > About Us > Our Programs > Defense Programs Defense Programs One of the primary missions of NNSA is to maintain and enhance the safety, security and reliability of the U.S. nuclear weapons stockpile. NNSA,

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Office of Nuclear Facility Basis & Facility Design  

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

Office of Nuclear Safety Basis & Facility Design(HS-31) Reports to the Office of Nuclear Safety About Us The Office of Nuclear Safety Basis & Facility Design establishes safety...

42

Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1  

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

Safety and Security Safety and Security Report to the Secretary on the Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1 February 2011 Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS Table of Contents 1.0 Introduction ......................................................................................................................... 1 2.0 Department-wide Action Plan for the Columbia Accident and Davis-Besse Event ........... 3 3.0 Comprehensive Operating Experience Program ................................................................. 5

43

Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1  

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

Safety and Security Safety and Security Report to the Secretary on the Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1 February 2011 Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS Table of Contents 1.0 Introduction ......................................................................................................................... 1 2.0 Department-wide Action Plan for the Columbia Accident and Davis-Besse Event ........... 3 3.0 Comprehensive Operating Experience Program ................................................................. 5

44

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Test Capabilities and Evaluation > Facilities...

45

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Inertial Confinement Fusion Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Inertial Confinement...

46

Nuclear Facility Design  

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

Design Design FUNCTIONAL AREA GOAL: Headquarters and Field organizations and their contractors ensure that nuclear facilities are designed to assure adequate protection for the public, workers, and the environment from nuclear hazards. REQUIREMENTS:  10 CFR 830.120  10 CFR 830 subpart B  DOE O 413.3  DOE O 420.1B  DOE O 414.1C  DOE O 226.1  DOE M 426.1  DEAR 970-5404-2 Guidance:  DOE G 420.1-1  Project Management Practices, Integrated Quality ( Rev E, June 2003)  DOE Implementation Plan for DNSB Recommendation 2004-2 Performance Objective 1: Contractor Program Documentation Contracts between and the contractors who operate nuclear facilities contain adequate requirements concerning the conduct of nuclear facility safety design for nuclear facility capital projects and major modifications and the

47

2011 Annual Planning Summary for Defense Nuclear Nonproliferation (NA-20)  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within Defense Nuclear Nonproliferation (NA-20).

48

Defense Programs | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Defense Programs Home > About Us > Our Programs > Defense Programs Defense Programs One of the primary...

49

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

50

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Office of Defense Science Office of Defense Science Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Research and Development > Facilities Facilities Office of Research and Development, Facilities The Office of Research and Development manages and oversees the operation of an exceptional suite of science, technology, and engineering facilities that support and further the national stockpile stewardship agenda. Of varying size, scope and capabilities, the facilities work in a concert to accomplish the following activities: Annual assessment of the stockpile in the face of increasing challenges due to aging or remanufacture, Reduced response times for resolving stockpile issues, Timely and certifiable completion of Life Extension Programs,

51

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

52

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Inertial Confinement Fusion Inertial Confinement Fusion Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Inertial Confinement Fusion > Facilities Facilities Office of Inertial Confinement Fusion, Facilities ICF operates a set of world-class experimental facilities to create HEDP conditions and to obtain quantitative data in support of its numerous stockpile stewardship-related activities. To learn about three high energy experimental facilities and two small lasers that provide ICF capabilities, select the links below. National Ignition Facility, Lawrence Livermore National Laboratory OMEGA and OMEGA EP, University of Rochester Laboratory for Laser Energetics Z Machine, Sandia National Laboratories

53

Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific  

National Nuclear Security Administration (NNSA)

Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific Northwest National Laboratory | 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 > About Us > Who We Are > In The Spotlight > Steve Mladineo Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific

54

Statement on Defense Nuclear Nonproliferation and Naval Reactors Activities  

National Nuclear Security Administration (NNSA)

Defense Nuclear Nonproliferation and Naval Reactors Activities Defense Nuclear Nonproliferation and Naval Reactors Activities before the House Committee on Appropriations Subcommittee on Energy & Water Development | 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 > Media Room > Congressional Testimony > Statement on Defense Nuclear

55

Statement on Defense Nuclear Nonproliferation and Naval Reactors Activities  

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

Defense Nuclear Nonproliferation and Naval Reactors Activities Defense Nuclear Nonproliferation and Naval Reactors Activities before the House Committee on Appropriations Subcommittee on Energy & Water Development | 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 > Media Room > Congressional Testimony > Statement on Defense Nuclear

56

Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific  

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

Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific Northwest National Laboratory | 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 > About Us > Who We Are > In The Spotlight > Steve Mladineo Senior Adviser, Defense Nuclear Nonproliferation Programs Sector, Pacific

57

2013 NNSA Defense Programs Science Council | National Nuclear Security  

National Nuclear Security Administration (NNSA)

3 NNSA Defense Programs Science Council | National Nuclear Security 3 NNSA Defense Programs Science Council | 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 > 2013 NNSA Defense Programs Science Council 2013 NNSA Defense Programs Science Council Posted By Office of Public Affairs 2013 NNSA Defense Programs Science Council Members of the 2013 NNSA Defense Programs Science Council include, from

58

Idaho Nuclear Technology and Engineering Center Tank Farm Facility |  

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

Idaho Nuclear Technology and Engineering Center Tank Farm Facility Idaho Nuclear Technology and Engineering Center Tank Farm Facility Idaho Nuclear Technology and Engineering Center Tank Farm Facility The Secretary of Energy signed Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 basis of determination for the disposal of grouted residual waste in the tank systems at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF) on November 19, 2006. Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set

59

Nonreactor Nuclear Facilities Division  

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

role in developing science and technology for nuclear power programs, nuclear propulsion, nuclear medicine, and the nation's nuclear weapon program among others. Many...

60

Second Line of Defense Program | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Line of Defense Program | National Nuclear Security Administration Line of Defense Program | 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 Second Line of Defense Program Home > About Us > Our Programs > Nonproliferation > International Materials Protection and Cooperation > Second Line of Defense Program Second Line of Defense Program In April 2009, President Obama called the danger of a terrorist acquiring

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Second Line of Defense Program | National Nuclear Security Administration  

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

Line of Defense Program | National Nuclear Security Administration Line of Defense Program | 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 Second Line of Defense Program Home > About Us > Our Programs > Nonproliferation > International Materials Protection and Cooperation > Second Line of Defense Program Second Line of Defense Program In April 2009, President Obama called the danger of a terrorist acquiring

62

The Defense Waste Processing Facility: Two Years of Radioactive Operation  

Science Conference Proceedings (OSTI)

The Defense Waste Processing Facility (DWPF) at the Savannah River Site in Aiken, SC is currently immobilizing high level radioactive sludge waste in borosilicate glass. The DWPF began vitrification of radioactive waste in May, 1996. Prior to that time, an extensive startup test program was completed with simulated waste. The DWPF is a first of its kind facility. The experience gained and data collected during the startup program and early years of operation can provide valuable information to other similar facilities. This experience involves many areas such as process enhancements, analytical improvements, glass pouring issues, and documentation/data collection and tracking. A summary of this experience and the results of the first two years of operation will be presented.

Marra, S.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Gee, J.T.; Sproull, J.F.

1998-05-01T23:59:59.000Z

63

Defense Waste Processing Facility -- Radioactive operations -- Part 3 -- Remote operations  

SciTech Connect

The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, South Carolina is the nation`s first and world`s largest vitrification facility. Following a ten year construction period and nearly three years of non-radioactive testing, the DWPF began radioactive operations in March 1996. Radioactive glass is poured from the joule heated melter into the stainless steel canisters. The canisters are then temporarily sealed, decontaminated, resistance welded for final closure, and transported to an interim storage facility. All of these operations are conducted remotely with equipment specially designed for these processes. This paper reviews canister processing during the first nine months of radioactive operations at DWPF. The fundamental design consideration for DWPF remote canister processing and handling equipment are discussed as well as interim canister storage.

Barnes, W.M.; Kerley, W.D.; Hughes, P.D.

1997-06-01T23:59:59.000Z

64

Nuclear Energy Advisory Committee Facility Subcommittee visit to Oak Ridge  

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

Committee Facility Subcommittee visit to Committee Facility Subcommittee visit to Oak Ridge National Laboratory Nuclear Energy Advisory Committee Facility Subcommittee visit to Oak Ridge National Laboratory The NEAC Facilities Subcommittee made a site visit to Oak Ridge National Laboratory (ORNL) on August 26, 2010. Subcommittee members included John Ahearne (Vice Chairman of NEAC and Facilities Subcommittee Chairman), Dana Christensen (ORNL), Thomas B. Cochran (Natural Resources Defense Council), Michael Corradini, (University of Wisconsin-Madison), and Andrew Klein (Oregon State University). Tansel Selekler (Department of Energy Office of Nuclear Energy) accompanied the Subcommittee. NEAC_Facitlity_Subcom Visit_OakRidge.pdf More Documents & Publications Meeting Materials: December 9, 2010

65

Contained Firing Facility | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Research and Development > Facilities >...

66

National Ignition Facility | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Inertial Confinement Fusion > Facilities >...

67

Analysis of personnel error occurrence reports across Defense Program facilities  

Science Conference Proceedings (OSTI)

More than 2,000 reports from the Occurrence Reporting and Processing System (ORPS) database were examined in order to identify weaknesses in the implementation of the guidance for the Conduct of Operations (DOE Order 5480.19) at Defense Program (DP) facilities. The analysis revealed recurrent problems involving procedures, training of employees, the occurrence of accidents, planning and scheduling of daily operations, and communications. Changes to DOE 5480.19 and modifications of the Occurrence Reporting and Processing System are recommended to reduce the frequency of these problems. The primary tool used in this analysis was a coding scheme based on the guidelines in 5480.19, which was used to classify the textual content of occurrence reports. The occurrence reports selected for analysis came from across all DP facilities, and listed personnel error as a cause of the event. A number of additional reports, specifically from the Plutonium Processing and Handling Facility (TA55), and the Chemistry and Metallurgy Research Facility (CMR), at Los Alamos National Laboratory, were analyzed separately as a case study. In total, 2070 occurrence reports were examined for this analysis. A number of core issues were consistently found in all analyses conducted, and all subsets of data examined. When individual DP sites were analyzed, including some sites which have since been transferred, only minor variations were found in the importance of these core issues. The same issues also appeared in different time periods, in different types of reports, and at the two Los Alamos facilities selected for the case study.

Stock, D.A.; Shurberg, D.A.; O`Brien, J.N.

1994-05-01T23:59:59.000Z

68

Nuclear and Facility Safety Policy Rules  

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

Nuclear Safety (HS-30) Office of Nuclear Safety Home Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical Standards Program Search ...

69

WIPP Nuclear Facilities Transparency  

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

Transparency Technologies Other Transparency Activities Sandia National Laboratories Cooperative Monitoring Center (CMC) in conjunction with WIPP is providing this Nuclear...

70

Accident Fault Trees for Defense Waste Processing Facility  

Science Conference Proceedings (OSTI)

The purpose of this report is to document fault tree analyses which have been completed for the Defense Waste Processing Facility (DWPF) safety analysis. Logic models for equipment failures and human error combinations that could lead to flammable gas explosions in various process tanks, or failure of critical support systems were developed for internal initiating events and for earthquakes. These fault trees provide frequency estimates for support systems failures and accidents that could lead to radioactive and hazardous chemical releases both on-site and off-site. Top event frequency results from these fault trees will be used in further APET analyses to calculate accident risk associated with DWPF facility operations. This report lists and explains important underlying assumptions, provides references for failure data sources, and briefly describes the fault tree method used. Specific commitments from DWPF to provide new procedural/administrative controls or system design changes are listed in the ''Facility Commitments'' section. The purpose of the ''Assumptions'' section is to clarify the basis for fault tree modeling, and is not necessarily a list of items required to be protected by Technical Safety Requirements (TSRs).

Sarrack, A.G.

1999-06-22T23:59:59.000Z

71

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

72

Establishing nuclear facility drill programs  

SciTech Connect

The purpose of DOE Handbook, Establishing Nuclear Facility Drill Programs, is to provide DOE contractor organizations with guidance for development or modification of drill programs that both train on and evaluate facility training and procedures dealing with a variety of abnormal and emergency operating situations likely to occur at a facility. The handbook focuses on conducting drills as part of a training and qualification program (typically within a single facility), and is not intended to included responses of personnel beyond the site boundary, e.g. Local or State Emergency Management, Law Enforcement, etc. Each facility is expected to develop its own facility specific scenarios, and should not limit them to equipment failures but should include personnel injuries and other likely events. A well-developed and consistently administered drill program can effectively provide training and evaluation of facility operating personnel in controlling abnormal and emergency operating situations. To ensure the drills are meeting their intended purpose they should have evaluation criteria for evaluating the knowledge and skills of the facility operating personnel. Training and evaluation of staff skills and knowledge such as component and system interrelationship, reasoning and judgment, team interactions, and communications can be accomplished with drills. The appendices to this Handbook contain both models and additional guidance for establishing drill programs at the Department`s nuclear facilities.

NONE

1996-03-01T23:59:59.000Z

73

DOE Defense Nuclear Nonproliferation DNN | Open Energy Information  

Open Energy Info (EERE)

Defense Nuclear Nonproliferation DNN Defense Nuclear Nonproliferation DNN Jump to: navigation, search Name DOE Defense Nuclear Nonproliferation (DNN) Place Washington, Washington, DC Zip 20585 Product String representation "Washington D.C. ... ear operations." is too long. Coordinates 38.89037°, -77.031959° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":38.89037,"lon":-77.031959,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

74

NUCLEAR AND CHEMICAL AND BIOLOGICAL DEFENSE PROGRAMS  

E-Print Network (OSTI)

and establishes requirements and procedures for the implementation of the PRP to select and maintain only the most reliable people to perform duties associated with nuclear weapons. Nuclear weapons require special consideration because of their policy implications and military importance, their destructive power, and the political consequences of an accident, loss of a weapon, or an unauthorized act. The safety, security, control, and effectiveness of nuclear weapons are of paramount importance to the security of the United States.

unknown authors

2006-01-01T23:59:59.000Z

75

Principal Deputy Administrator for Defense Nuclear Nonproliferation...  

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

Enrichment for Research and Test Reactors in Lisbon, Portugal | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering...

76

National Laser Users' Facility Grant Program | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Users' Facility Grant Program | National Nuclear Security Users' Facility Grant Program | 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 NLUF National Laser Users' Facility Grant Program Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > University Partnerships / Academic Alliances > National Laser Users' Facility Grant Program

77

Statement of Anne M. Harrington, Deputy Administrator for Defense Nuclear  

National Nuclear Security Administration (NNSA)

Congressional Testimony > Statement of Anne M. Congressional Testimony > Statement of Anne M. Harrington, Deputy Administrator ... Congressional Testimony Statement of Anne M. Harrington, Deputy Administrator for Defense Nuclear Nonproliferation to the Senate Armed Services Sub Committee On Emerging Threats and Capabilities May 10, 2011 Chairwoman Hagan, Ranking Member Portman, thank you for the opportunity to join you today to discuss the investments the President has requested for the National Nuclear Security Administration's Defense Nuclear Nonproliferation programs. But more importantly, thank you for your continued support of the National Nuclear Security Administration, and the 35,000 men and women working across the enterprise to keep our country safe, protect our allies, and enhance global security. We could not do

78

Statement of Anne M. Harrington, Deputy Administrator for Defense Nuclear  

National Nuclear Security Administration (NNSA)

Speeches > Statement of Anne M. Harrington, Deputy Speeches > Statement of Anne M. Harrington, Deputy Administrator ... Speech Statement of Anne M. Harrington, Deputy Administrator for Defense Nuclear Nonproliferation to the Senate Armed Services Sub Committee On Emerging Threats and Capabilities May 10, 2011 Chairwoman Hagan, Ranking Member Portman, thank you for the opportunity to join you today to discuss the investments the President has requested for the National Nuclear Security Administration's Defense Nuclear Nonproliferation programs. But more importantly, thank you for your continued support of the National Nuclear Security Administration, and the 35,000 men and women working across the enterprise to keep our country safe, protect our allies, and enhance global security. We could not do this work without strong, bipartisan support and engaged leadership from

79

H. R. 1836: A Bill to amend the Atomic Energy Act of 1954, with regard to Department of Energy nuclear facilities, and for other purposes. Introduced in the House of Representatives, One Hundredth First Congress, First Session, April 12, 1989  

SciTech Connect

H.R. 1836: A Bill to amend the Atomic Energy Act of 1954, with regard to Department of Energy nuclear facilities, and for other purposes. The amendments change the title Defense Nuclear facilities to Department of Energy Nuclear facilities used for defense purposes and the related facilities Safety Board.

Not Available

1989-01-01T23:59:59.000Z

80

Non-Destructive Evaluation (NDE) and Testing Facilities - Nuclear  

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

Facilities > Non-Destructive Facilities > Non-Destructive Evaluation (NDE) and Testing Facilities Non-Destructive Evaluation (NDE) and Testing Facilities Overview MTS Table Top Load Frame X-ray Inspection Systems Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Non-Destructive Evaluation (NDE) and Testing Facilities The Non-Destructive Evaluation (NDE) and Testing Facilities contain state-of-the-art NDE laboratories including microwave/millimeter wave, acoustic/ultrasonic, X-ray, thermal imaging, optics, and eddy current for health monitoring of materials and components used in aerospace, defense, and power generation (fossil and nuclear) industries as well as for medical and scientific research. Bookmark and Share

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Chemistry and Metallurgy Research Replacement - Nuclear Facility...  

National Nuclear Security Administration (NNSA)

Chemistry and Metallurgy Research Replacement - Nuclear Facility (CMRR-NF SEIS) | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing...

82

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

83

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

84

PROJECTIZING AN OPERATING NUCLEAR FACILITY  

SciTech Connect

This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully accomplish deactivation. This concept had to allow for continued operations in FB Line until 2005, while providing distinct task-oriented teams for deactivation of the FCC. Facility workers, always the most knowledgeable about any facility, were integral parts of the project team. The team defined the scope, developed a bottoms-up estimate, reorganized personnel to designated project teams, and developed a baseline schedule with about 12,000 activities. Training was implemented to prepare the facility workers to use project management tools and concepts, which were to execute the project, coordinate activities and track progress. The project budget was estimated at $579 million. The team completed F Canyon and FB Line deactivation in August 2006, four months ahead of schedule and under budget.

Adams, N

2007-07-08T23:59:59.000Z

85

Management of Hanford Site non-defense production reactor spent nuclear fuel, Hanford Site, Richland, Washington  

SciTech Connect

The US Department of Energy (DOE) needs to provide radiologically, and industrially safe and cost-effective management of the non-defense production reactor spent nuclear fuel (SNF) at the Hanford Site. The proposed action would place the Hanford Site`s non-defense production reactor SNF in a radiologically- and industrially-safe, and passive storage condition pending final disposition. The proposed action would also reduce operational costs associated with storage of the non-defense production reactor SNF through consolidation of the SNF and through use of passive rather than active storage systems. Environmental, safety and health vulnerabilities associated with existing non-defense production reactor SNF storage facilities have been identified. DOE has determined that additional activities are required to consolidate non-defense production reactor SNF management activities at the Hanford Site, including cost-effective and safe interim storage, prior to final disposition, to enable deactivation of facilities where the SNF is now stored. Cost-effectiveness would be realized: through reduced operational costs associated with passive rather than active storage systems; removal of SNF from areas undergoing deactivation as part of the Hanford Site remediation effort; and eliminating the need to duplicate future transloading facilities at the 200 and 400 Areas. Radiologically- and industrially-safe storage would be enhanced through: (1) removal from aging facilities requiring substantial upgrades to continue safe storage; (2) utilization of passive rather than active storage systems for SNF; and (3) removal of SNF from some storage containers which have a limited remaining design life. No substantial increase in Hanford Site environmental impacts would be expected from the proposed action. Environmental impacts from postulated accident scenarios also were evaluated, and indicated that the risks associated with the proposed action would be small.

1997-03-01T23:59:59.000Z

86

RADIATION FACILITY FOR NUCLEAR REACTORS  

DOE Patents (OSTI)

A radiation facility is designed for irradiating samples in close proximity to the core of a nuclear reactor. The facility comprises essentially a tubular member extending through the biological shield of the reactor and containing a manipulatable rod having the sample carrier at its inner end, the carrier being longitudinally movable from a position in close proximity to the reactor core to a position between the inner and outer faces of the shield. Shield plugs are provided within the tubular member to prevent direct radiation from the core emanating therethrough. In this device, samples may be inserted or removed during normal operation of the reactor without exposing personnel to direct radiation from the reactor core. A storage chamber is also provided within the radiation facility to contain an irradiated sample during the period of time required to reduce the radioactivity enough to permit removal of the sample for external handling. (AEC)

Currier, E.L. Jr.; Nicklas, J.H.

1961-12-12T23:59:59.000Z

87

WIRELESS FOR A NUCLEAR FACILITY  

SciTech Connect

The introduction of wireless technology into a government site where nuclear material is processed and stored brings new meaning to the term ''harsh environment''. At SRNL, we are attempting to address not only the harsh RF and harsh physical environment common to industrial facilities, but also the ''harsh'' regulatory environment necessitated by the nature of the business at our site. We will discuss our concepts, processes, and expected outcomes in our attempts to surmount the roadblocks and reap the benefits of wireless in our ''factory''.

Shull, D; Joe Cordaro, J

2007-03-28T23:59:59.000Z

88

WIRELESS FOR A NUCLEAR FACILITY  

SciTech Connect

The introduction of wireless technology into a government site where nuclear material is processed and stored brings new meaning to the term ''harsh environment''. At SRNL, we are attempting to address not only the harsh RF and harsh physical environment common to industrial facilities, but also the ''harsh'' regulatory environment necessitated by the nature of the business at our site. We will discuss our concepts, processes, and expected outcomes in our attempts to surmount the roadblocks and reap the benefits of wireless in our ''factory''.

Shull, D; Joe Cordaro, J

2007-03-28T23:59:59.000Z

89

Infrastructure and Facilities Management | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Infrastructure and Facilities Management | National Nuclear Security Infrastructure and Facilities Management | 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 Infrastructure and Facilities Management Home > content > Infrastructure and Facilities Management Infrastructure and Facilities Management NNSA restores, rebuilds, and revitalizes the physical infrastructure of the

90

Nuclear Science Research Facilities Nuclear Science User Guide  

E-Print Network (OSTI)

LANSCE User Guide Nuclear Science Research Facilities #12;#12;Nuclear Science User Guide Table of Contents Introduction 3 Nuclear Science Research Facilities 3 The LANSCE Accelerator 4 Time structure techniques 8 Nuclear Science User Program 11 Proposal Process 13 Information for Prospective Users 14

91

INSTALLATION OF BUBBLERS IN THE SAVANNAH RIVER SITED DEFENSE WASTE PROCESSING FACILITY MELTER  

Science Conference Proceedings (OSTI)

Savannah River Remediation (SRR) LLC assumed the liquid waste contract at the Savannah River Site (SRS) in the summer of 2009. The main contractual agreement was to close 22 High Level Waste (HLW) tanks in eight years. To achieve this aggressive commitment, faster waste processing throughout the SRS liquid waste facilities will be required. Part of the approach to achieve faster waste processing is to increase the canister production rate of the Defense Waste Processing Facility (DWPF) from approximately 200 canisters filled with radioactive waste glass per year to 400 canisters per year. To reach this rate for melter throughput, four bubblers were installed in the DWPF Melter in the late summer of 2010. This effort required collaboration between SRR, SRR critical subcontractor EnergySolutions, and Savannah River Nuclear Solutions, including the Savannah River National Laboratory (SRNL). The tasks included design and fabrication of the bubblers and related equipment, testing of the bubblers for various technical issues, the actual installation of the bubblers and related equipment, and the initial successful operation of the bubblers in the DWPF Melter.

Smith, M.; Iverson, D.

2010-12-08T23:59:59.000Z

92

High Explosives Application Facility | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration High Explosives Application Facility Home > About Us > Our...

93

Office of Nuclear Facility Safety Programs  

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

Safety Programs establishes requirements related to safety management programs that are essential to the safety of DOE nuclear facilities. In addition, establishes requirements...

94

Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS).  

Science Conference Proceedings (OSTI)

Sandia National Laboratories was tasked with developing the Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS) with the sponsorship of NA-125.3 and the concurrence of DOE/NNSA field and area offices. The purpose of IIIMS was to modernize nuclear materials management information systems at the enterprise level. Projects over the course of several years attempted to spearhead this modernization. The scope of IIIMS was broken into broad enterprise-oriented materials management and materials forecasting. The IIIMS prototype was developed to allow multiple participating user groups to explore nuclear material requirements and needs in detail. The purpose of material forecasting was to determine nuclear material availability over a 10 to 15 year period in light of the dynamic nature of nuclear materials management. Formal DOE Directives (requirements) were needed to direct IIIMS efforts but were never issued and the project has been halted. When restarted, duplicating or re-engineering the activities from 1999 to 2003 is unnecessary, and in fact future initiatives can build on previous work. IIIMS requirements should be structured to provide high confidence that discrepancies are detected, and classified information is not divulged. Enterprise-wide materials management systems maintained by the military can be used as overall models to base IIIMS implementation concepts upon.

Aas, Christopher A.; Lenhart, James E.; Bray, Olin H.; Witcher, Christina Jenkin

2004-11-01T23:59:59.000Z

95

2012 Annual Planning Summary for NNSA Defense Nuclear NonProliferation  

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

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within the NNSA Defense Nuclear NonProliferation.

96

Facilities & Capabilities | Nuclear Science | ORNL  

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

Irradiated Material Examination and Testing (IMET) Facility was designed and built as a hot cell facility. It is a two-story block and brick structure with a two-story high bay...

97

Public Reading Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Reading Facilities | National Nuclear Security Administration Reading Facilities | 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 Public Reading Facilities Home > About Us > Our Operations > NNSA Office of General Counsel > Freedom of Information Act (FOIA) > Public Reading Facilities Public Reading Facilities The FOIA and E-FOIA require that specific types of records as well as

98

Nuclear Facility Operations | Department of Energy  

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

Facility Operations Facility Operations Nuclear Facility Operations INL is a science-based, applied engineering national laboratory dedicated to meeting the nation's environmental, energy, nuclear technology, and national security needs. INL is a science-based, applied engineering national laboratory dedicated to meeting the nation's environmental, energy, nuclear technology, and national security needs. The Idaho Operations Office oversees these contract activities in accordance with DOE directives. INL is a multi-program laboratory In addition to enabling the Office of Nuclear Energy to develop space power systems and advanced fuel cycle and reactor technologies, INL facilities are used by the National Nuclear Security Administration and other DOE offices, together with other Federal agencies such as the Department of

99

Project Hanford nuclear facilities list and authorization basis information  

SciTech Connect

Rev. 4 documents and updates the Nuclear Facilities list and associated Authorization Basis (AB) information for applicable Project Hanford facilities.

EVANS, C.B.

1999-03-03T23:59:59.000Z

100

Appendix B: Rules and Directives Applicable to Nuclear Facilities...  

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

Appendix B: Rules and Directives Applicable to Nuclear Facilities Line Management Oversight Appendix B: Rules and Directives Applicable to Nuclear Facilities Line Management...

Note: This page contains sample records for the topic "defense nuclear facilities" 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

DOE - Office of Legacy Management -- Hallam Nuclear Power Facility...  

Office of Legacy Management (LM)

Hallam Nuclear Power Facility - NE 01 FUSRAP Considered Sites Site: Hallam Nuclear Power Facility (NE.01 ) Designated Name: Alternate Name: Location: Evaluation Year: Site...

102

DOE - Office of Legacy Management -- Piqua Nuclear Power Facility...  

Office of Legacy Management (LM)

Piqua Nuclear Power Facility - OH 08 FUSRAP Considered Sites Site: Piqua Nuclear Power Facility (OH.08 ) Designated Name: Alternate Name: Location: Evaluation Year: Site...

103

Feasibility of very deep borehole disposal of US nuclear defense wastes  

E-Print Network (OSTI)

This thesis analyzes the feasibility of emplacing DOE-owned defense nuclear waste from weapons production into a permanent borehole repository drilled ~4 km into granite basement rock. Two canister options were analyzed ...

Dozier, Frances Elizabeth

2011-01-01T23:59:59.000Z

104

Defense Nuclear Security Safeguards and Security Evaluation and Performance Assurance Program  

E-Print Network (OSTI)

for Defense Nuclear Security (DNS) is issuing this document to promulgate the DNS Evaluation and Performance Assurance Program of the NNSA safeguards and security functional area. Suggestions for improving this document are welcome and should be sent in writing to:

Bradley A. Peterson

2009-01-01T23:59:59.000Z

105

NPO recognized by Defense Programs | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

vice President for Production. NPO recognized by Defense Programs Posted on October 24, 2013 at 1:00 pm ET Printer-friendly version Printer-friendly version Facebook Twitter...

106

Demonstration of Natural Gas Engine Driven Air Compressor Technology at Department of Defense Industrial Facilities  

E-Print Network (OSTI)

Recent downsizing and consolidation of Department of Defense (DOD) facilities provides an opportunity to upgrade remaining facilities with more efficient and less polluting equipment. Use of air compressors by the DOD is widespread and the variety of tools and machinery that operate on compressed air is increasing. The energy cost of operating a natural gas engine-driven air compressor (NGEDAC) is usually lower than the cost of operating an electric-driven air compressor. Initial capital costs are offset by differences in prevailing utility rates, efficiencies of partial load operation, reductions in peak demand, heat recovery, and avoiding the cost of back-up generators. Natural gas, a clean-burning fuel, is abundant and readily available. In an effort to reduce its over-all environmental impact and energy consumption, the U.S. Army plans to apply NGEDAC technology in support of fixed facilities compressed air systems. Site assessment and demonstration results are presented in this paper.

Lin, M.; Aylor, S. W.; Van Ormer, H.

2002-04-01T23:59:59.000Z

107

Updated Costs for Decommissioning Nuclear Power Facilities  

Science Conference Proceedings (OSTI)

This update of 1978 NRC cost estimates--in 1984 dollars--also estimates the costs of several special manpower and licensing options for decommissioning nuclear power facilities. The fully developed methodology offers utilities a sound basis on which to estimate the costs of decommissioning specific plants.

1985-05-13T23:59:59.000Z

108

Tank 42 sludge-only process development for the Defense Waste Processing Facility (DWPF)  

SciTech Connect

Defense Waste Processing Facility (DWPF) requested the development of a sludge-only process for Tank 42 sludge since at the current processing rate, the Tank 51 sludge has been projected to be depleted as early as August 1998. Testing was completed using a non-radioactive Tank 42 sludge simulant. The testing was completed under a range of operating conditions, including worst case conditions, to develop the processing conditions for radioactive Tank 42 sludge. The existing Tank 51 sludge-only process is adequate with the exception that 10 percent additional acid is recommended during sludge receipt and adjustment tank (SRAT) processing to ensure adequate destruction of nitrite during the SRAT cycle.

Lambert, D.P.

2000-03-22T23:59:59.000Z

109

CRAD, Nuclear Facility Construction - Structural Steel, May 29, 2009 |  

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

Steel, May 29, Steel, May 29, 2009 CRAD, Nuclear Facility Construction - Structural Steel, May 29, 2009 May 29, 2009 Nuclear Facility Construction - Structural Steel (HSS CRAD 64-16, Rev. 0) Nuclear Facility Construction - Structural Steel criteria, review, and approach document, observes construction activities and review records and design documentation to assess the quality of structural steel fabrication and erection and to determine if requirements specified by design basis documents, contracts, and applicable codes and standards have been met. CRAD, Nuclear Facility Construction - Structural Steel, May 29, 2009 More Documents & Publications CRAD, Nuclear Facility Construction - Structural Concrete, May 29, 2009 CRAD, Nuclear Facility Construction - Mechanical Equipment - June 26, 2012

110

Unconventional Nuclear Warfare Defense (UNWD) containment and mitigation subtask.  

SciTech Connect

The objective of this subtask of the Unconventional Nuclear Warfare Design project was to demonstrate mitigation technologies for radiological material dispersal and to assist planners with incorporation of the technologies into a concept of operations. The High Consequence Assessment and Technology department at Sandia National Laboratories (SNL) has studied aqueous foam's ability to mitigate the effects of an explosively disseminated radiological dispersal device (RDD). These benefits include particle capture of respirable radiological particles, attenuation of blast overpressure, and reduction of plume buoyancy. To better convey the aqueous foam attributes, SNL conducted a study using the Explosive Release Atmospheric Dispersion model, comparing the effects of a mitigated and unmitigated explosive RDD release. Results from this study compared health effects and land contamination between the two scenarios in terms of distances of effect, population exposure, and remediation costs. Incorporating aqueous foam technology, SNL created a conceptual design for a stationary containment area to be located at a facility entrance with equipment that could minimize the effects from the detonation of a vehicle transported RDD. The containment design was evaluated against several criteria, including mitigation ability (both respirable and large fragment particle capture as well as blast overpressure suppression), speed of implementation, cost, simplicity, and required space. A mock-up of the conceptual idea was constructed at SNL's 9920 explosive test site to demonstrate the containment design.

Wente, William Baker

2005-06-01T23:59:59.000Z

111

2010 Annual Planning Summary for Defense Nuclear Nonproliferation...  

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

Annual Planning Summary for National Nuclear Security Administration Service Center (NNSA-SC) 2010 Annual Planning Summary for Nuclear Energy (NE) Energy.gov Careers & Internships...

112

Improving the Safeguardability of Nuclear Facilities  

SciTech Connect

The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to reduce security risks and proliferation hazards while improving the synergy of major design features and raising operational efficiency, in a world where significant expansion of nuclear energy use may occur. Correspondingly, the U.S. DOEs Next Generation Safeguards Initiative (NGSI) includes objectives to contribute to international efforts to develop SBD, and to apply SBD in the development of new U.S. nuclear infrastructure. Here, SBD is defined as a structured approach to ensure the timely, efficient and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical protection, and safety objectives into the overall design process for a nuclear facility, from initial planning through design, construction and operation. The SBD process, in its simplest form, may be applied usefully today within most national regulatory environments. Development of a mature approach to implementing SBD requires work in the areas of requirements definition, design processes, technology and methodology, and institutionalization. The U.S. efforts described in this paper are supportive of SBD work for international safeguards that has recently been initiated by the IAEA with the participation of many stakeholders including member States, the IAEA, nuclear technology suppliers, nuclear utilities, and the broader international nonproliferation community.

T. Bjornard; R. Bari; D. Hebditch; P. Peterson; M. Schanfein

2009-07-01T23:59:59.000Z

113

An assessment of testing requirement impacts on nuclear thermal propulsion ground test facility design  

SciTech Connect

Programs to develop solid core nuclear thermal propulsion (NTP) systems have been under way at the Department of Defense (DoD), the National Aeronautics and Space Administration (NASA), and the Department of Energy (DOE). These programs have recognized the need for a new ground test facility to support development of NTP systems. However, the different military and civilian applications have led to different ground test facility requirements. The Department of Energy (DOE) in its role as landlord and operator of the proposed research reactor test facilities has initiated an effort to explore opportunities for a common ground test facility to meet both DoD and NASA needs. The baseline design and operating limits of the proposed DoD NTP ground test facility are described. The NASA ground test facility requirements are reviewed and their potential impact on the DoD facility baseline is discussed.

Shipers, L.R.; Ottinger, C.A.; Sanchez, L.C.

1993-10-25T23:59:59.000Z

114

Nuclear Energy Advisory Committee, Facility Subcommittee visit to Idaho National Laboratory May 19-20, 2010  

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

Committee, Facility Subcommittee visit to Idaho National Committee, Facility Subcommittee visit to Idaho National Laboratory May 19-20, 2010 The Nuclear Energy Advisory Committee, Facility Subcommittee visited the Idaho National Laboratory on 19-20 May 2010 to tour the nuclear infrastructure and to discuss the INL plans for facility modernization as a dimension of the DOE Office of Nuclear Energy's (NE) mission. Team Members: Dr. John Ahearne, Sigma Xi, Research Triangle Park, NC Dr. Dana Christensen, Oak Ridge National Laboratory Dr. Thomas Cochran, Natural Resource Defense Council, Washington DC Dr. Andrew Klein, Oregon State University (second day only) Mr. Paul Murray, AREVA Federal Services Dr. John I. Sackett, Idaho National Laboratory, Retired, Support: Andrew Griffith, DOE/NE

115

Defense Nuclear Facilities Safety Board Public Meeting on the...  

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

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...

116

Defense Nuclear Facilities Safety Board - Performance and Accountablit...  

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

July 9, 2012, the Secretary of Energy issued a memorandum entitled Enterprise Risk Management (ERM) Framework for Directives, announcing a new framework for development,...

117

Defense implications of a nuclear Iran for Turkey .  

E-Print Network (OSTI)

??Iran's possible acquisition of nuclear weapons along with more assertive Iranian foreign policies poses new security challenges for Turkey in the Middle East. A nuclear-weapons-capable (more)

Arslan, Erkan.

2007-01-01T23:59:59.000Z

118

Nuclear facility decommissioning and site remedial actions  

SciTech Connect

The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

1990-09-01T23:59:59.000Z

119

Nuclear facility decommissioning and site remedial actions  

SciTech Connect

The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

1989-09-01T23:59:59.000Z

120

IMPACT OF THE SMALL COLUMN ION EXCHANGE PROCESS ON THE DEFENSE WASTE PROCESSING FACILITY - 12112  

SciTech Connect

The Savannah River Site (SRS) is investigating the deployment of a parallel technology to the Salt Waste Processing Facility (SWPF, presently under construction) to accelerate high activity salt waste processing. The proposed technology combines large waste tank strikes of monosodium titanate (MST) to sorb strontium and actinides with two ion exchange columns packed with crystalline silicotitanate (CST) resin to sorb cesium. The new process was designated Small Column Ion Exchange (SCIX), since the ion exchange columns were sized to fit within a waste storage tank riser. Loaded resins are to be combined with high activity sludge waste and fed to the Defense Waste Processing Facility (DWPF) for incorporation into the current glass waste form. Decontaminated salt solution produced by SCIX will be fed to the SRS Saltstone Facility for on-site immobilization as a grout waste form. Determining the potential impact of SCIX resins on DWPF processing was the basis for this study. Accelerated salt waste treatment is projected to produce a significant savings in the overall life cycle cost of waste treatment at SRS.

Koopman, D.; Lambert, D.; Fox, K.; Stone, M.

2011-11-07T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Nuclear Power Generating Facilities (Maine) | Department of Energy  

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

Nuclear Power Generating Facilities (Maine) Nuclear Power Generating Facilities (Maine) Nuclear Power Generating Facilities (Maine) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Maine Program Type Siting and Permitting Provider Radiation Control Program The first subchapter of the statute concerning Nuclear Power Generating Facilities provides for direct citizen participation in the decision to construct any nuclear power generating facility in Maine. The Legislature

122

Financing Strategies for Nuclear Fuel Cycle Facility  

SciTech Connect

To help meet our nations energy needs, reprocessing of spent nuclear fuel is being considered more and more as a necessary step in a future nuclear fuel cycle, but incorporating this step into the fuel cycle will require considerable investment. This report presents an evaluation of financing scenarios for reprocessing facilities integrated into the nuclear fuel cycle. A range of options, from fully government owned to fully private owned, was evaluated using a DPL (Dynamic Programming Language) 6.0 model, which can systematically optimize outcomes based on user-defined criteria (e.g., lowest life-cycle cost, lowest unit cost). Though all business decisions follow similar logic with regard to financing, reprocessing facilities are an exception due to the range of financing options available. The evaluation concludes that lowest unit costs and lifetime costs follow a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. Other financing arrangements, however, including regulated utility ownership and a hybrid ownership scheme, led to acceptable costs, below the Nuclear Energy Agency published estimates. Overwhelmingly, uncertainty in annual capacity led to the greatest fluctuations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; the annual operating costs dominate the government case. It is concluded that to finance the construction and operation of such a facility without government ownership could be feasible with measures taken to mitigate risk, and that factors besides unit costs should be considered (e.g., legal issues, social effects, proliferation concerns) before making a decision on financing strategy.

David Shropshire; Sharon Chandler

2005-12-01T23:59:59.000Z

123

Elimination Of Catalytic Hydrogen Generation In Defense Waste Processing Facility Slurries  

Science Conference Proceedings (OSTI)

Based on lab-scale simulations of Defense Waste Processing Facility (DWPF) slurry chemistry, the addition of sodium nitrite and sodium hydroxide to waste slurries at concentrations sufficient to take the aqueous phase into the alkaline region (pH > 7) with approximately 500 mg nitrite ion/kg slurry (assuming essential components to catalytic hydrogen generation) than the two primary process vessels. Rhodium certainly, and ruthenium likely, are present as metal-ligand complexes that are favored under certain concentrations of the surrounding species. Therefore, in the SMECT or RCT, where a small volume of SRAT or SME material would be significantly diluted, conditions would be less optimal for forming or sustaining the catalytic ligand species. Such conditions are likely to adversely impact the ability of the transferred mass to produce hydrogen at the same rate (per unit mass SRAT or SME slurry) as in the SRAT or SME vessels.

Koopman, D. C.

2013-01-22T23:59:59.000Z

124

Facility Safety Assessment - Nuclear Engineering Division (Argonne...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

125

Computer Facilities - Nuclear Engineering Division (Argonne)  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

126

Steam Generator Tube Integrity Facilities - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

127

Safety of Decommissioning of Nuclear Facilities  

Science Conference Proceedings (OSTI)

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

128

Counterintelligence and operations security-support program for the Defense Nuclear Agency. Directive  

Science Conference Proceedings (OSTI)

The Directive establishes the counterintelligence (CI) and operations security (OPSEC) support program for the Defense Nuclear Agency which includes activities designed to protect classified and operationally sensitive unclassified information and material. Included are CI investigations, counterespionage and countersabotage operations, OPSEC analyses, technical surveillance countermeasures services, CI security education, and CI security assistance.

Nelson, L.

1983-01-25T23:59:59.000Z

129

Groundbreaking at National Ignition Facility | National Nuclear Security  

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

Groundbreaking at National Ignition Facility | National Nuclear Security Groundbreaking at National Ignition Facility | 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 > About Us > Our History > NNSA Timeline > Groundbreaking at National Ignition Facility Groundbreaking at National Ignition Facility May 29, 1997 Livermore, CA Groundbreaking at National Ignition Facility

130

IMPACTS OF ANTIFOAM ADDITIONS AND ARGON BUBBLING ON DEFENSE WASTE PROCESSING FACILITY REDUCTION/OXIDATION  

Science Conference Proceedings (OSTI)

During melting of HLW glass, the REDOX of the melt pool cannot be measured. Therefore, the Fe{sup +2}/{Sigma}Fe ratio in the glass poured from the melter must be related to melter feed organic and oxidant concentrations to ensure production of a high quality glass without impacting production rate (e.g., foaming) or melter life (e.g., metal formation and accumulation). A production facility such as the Defense Waste Processing Facility (DWPF) cannot wait until the melt or waste glass has been made to assess its acceptability, since by then no further changes to the glass composition and acceptability are possible. therefore, the acceptability decision is made on the upstream process, rather than on the downstream melt or glass product. That is, it is based on 'feed foward' statistical process control (SPC) rather than statistical quality control (SQC). In SPC, the feed composition to the melter is controlled prior to vitrification. Use of the DWPF REDOX model has controlled the balanjce of feed reductants and oxidants in the Sludge Receipt and Adjustment Tank (SRAT). Once the alkali/alkaline earth salts (both reduced and oxidized) are formed during reflux in the SRAT, the REDOX can only change if (1) additional reductants or oxidants are added to the SRAT, the Slurry Mix Evaporator (SME), or the Melter Feed Tank (MFT) or (2) if the melt pool is bubble dwith an oxidizing gas or sparging gas that imposes a different REDOX target than the chemical balance set during reflux in the SRAT.

Jantzen, C.; Johnson, F.

2012-06-05T23:59:59.000Z

131

Basic Data Report -- Defense Waste Processing Facility Sludge Plant, Savannah River Plant 200-S Area  

SciTech Connect

This Basic Data Report for the Defense Waste Processing Facility (DWPF)--Sludge Plant was prepared to supplement the Technical Data Summary. Jointly, the two reports were intended to form the basis for the design and construction of the DWPF. To the extent that conflicting information may appear, the Basic Data Report takes precedence over the Technical Data Summary. It describes project objectives and design requirements. Pertinent data on the geology, hydrology, and climate of the site are included. Functions and requirements of the major structures are described to provide guidance in the design of the facilities. Revision 9 of the Basic Data Report was prepared to eliminate inconsistencies between the Technical Data Summary, Basic Data Report and Scopes of Work which were used to prepare the September, 1982 updated CAB. Concurrently, pertinent data (material balance, curie balance, etc.) have also been placed in the Basic Data Report. It is intended that these balances be used as a basis for the continuing design of the DWPF even though minor revisions may be made in these balances in future revisions to the Technical Data Summary.

Amerine, D.B.

1982-09-01T23:59:59.000Z

132

MISSION AND NEED FOR A FUSION NUCLEAR SCIENCE FACILITY  

E-Print Network (OSTI)

MISSION AND NEED FOR A FUSION NUCLEAR SCIENCE FACILITY Mission Gerald Navratil Need Mohamed Abdou and Symposium 1-2 December 2010 #12;FUSION NUCLEAR SCIENCE FACILITY: COMMENTS ON MISSION Gerald A. Navratil Component Test Facility Theory & Simulation FESAC/Snowmass Report: ITER-Based Development Path #12;FUSION

133

Nuclear fuel cycle facility accident analysis handbook  

Science Conference Proceedings (OSTI)

The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

NONE

1998-03-01T23:59:59.000Z

134

The necessity for permanence : making a nuclear waste storage facility  

E-Print Network (OSTI)

The United States Department of Energy is proposing to build a nuclear waste storage facility in southern Nevada. This facility will be designed to last 10,000 years. It must prevent the waste from contaminating the ...

Stupay, Robert Irving

1991-01-01T23:59:59.000Z

135

"Defense-in-Depth" Laser Safety and the National Ignition Facility  

SciTech Connect

The National Ignition Facility (NIF) is the largest and most energetic laser in the world contained in a complex the size of a football stadium. From the initial laser pulse, provided by telecommunication style infrared nanoJoule pulsed lasers, to the final 192 laser beams (1.8 Mega Joules total energy in the ultraviolet) converging on a target the size of a pencil eraser, laser safety is of paramount concern. In addition to this, there are numerous high-powered (Class 3B and 4) diagnostic lasers in use that can potentially send their laser radiation travelling throughout the facility. With individual beam paths of up to 1500 meters and a workforce of more than one thousand, the potential for exposure is significant. Simple laser safety practices utilized in typical laser labs just don't apply. To mitigate these hazards, NIF incorporates a multi layered approach to laser safety or 'Defense in Depth.' Most typical high-powered laser operations are contained and controlled within a single room using relatively simplistic controls to protect both the worker and the public. Laser workers are trained, use a standard operating procedure, and are required to wear Personal Protective Equipment (PPE) such as Laser Protective Eyewear (LPE) if the system is not fully enclosed. Non-workers are protected by means of posting the room with a warning sign and a flashing light. In the best of cases, a Safety Interlock System (SIS) will be employed which will 'safe' the laser in the case of unauthorized access. This type of laser operation is relatively easy to employ and manage. As the operation becomes more complex, higher levels of control are required to ensure personnel safety. Examples requiring enhanced controls are outdoor and multi-room laser operations. At the NIF there are 192 beam lines and numerous other Class 4 diagnostic lasers that can potentially deliver their hazardous energy to locations far from the laser source. This presents a serious and complex potential hazard to personnel. Because of this, a multilayered approach to safety is taken. This paper presents the philosophy and approach taken at the NIF in the multi-layered 'defense-in-depth' approach to laser safety.

King, J J

2010-12-02T23:59:59.000Z

136

CRAD, Nuclear Facility Construction - Mechanical Equipment - June 26, 2012  

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

Nuclear Facility Construction - Mechanical Equipment - June Nuclear Facility Construction - Mechanical Equipment - June 26, 2012 CRAD, Nuclear Facility Construction - Mechanical Equipment - June 26, 2012 June 26, 2012 Nuclear Facility Construction - Mechanical Equipment Installation, (HSS CRAD 45-53, Rev. 0) The purpose of this criteria review and approach, this CRAD includes mechanical equipment installation, including connections of the equipment to installed piping systems, and attachments of the equipment to structures (concrete, structural steel, or embed plates). Mechanical equipment includes items such as pumps and motors, valves, tanks, glove boxes, heat exchangers, ion exchangers, service air system, fire pumps and tanks, and heating, ventilation, and air condition (HVAC) equipment such as fans, scrubbers and filters.

137

Moratorium on Construction of Nuclear Power Facilities (Connecticut)  

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

No construction shall commence on a fifth nuclear power facility until the Commissioner of Environmental Protection finds that the United States Government, through its authorized agency, has...

138

Some noise control problems peculiar to nuclear generating facilities  

Science Conference Proceedings (OSTI)

The ability to confidently predict the noise environment in a nuclear generating facility presently under construction is complicated by the design constraints of physical layout

Robert A. Putnam

1977-01-01T23:59:59.000Z

139

Approaches used for Clearance of Lands from Nuclear Facilities...  

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

:14 Report number: 2013:14 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries...

140

Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities  

E-Print Network (OSTI)

1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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 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

142

THE DEVELOPMENT OF COAL-BASED TECHNOLOGIES FOR DEPARTMENT OF DEFENSE FACILITIES  

Science Conference Proceedings (OSTI)

The third phase of a three-phase project investigating the development of coal-based technologies for US Department of Defense (DOD) facilities was completed. The objectives of the project were to: decrease DOD's dependence on foreign oil and increase its use of coal; promote public and private sector deployment of technologies for utilizing coal-based fuels in oil-designed combustion equipment; and provide a continuing environment for research and development of coal-based fuel technologies for small-scale applications at a time when market conditions in the US are not favorable for the introduction of coal-fired equipment in the commercial and industrial capacity ranges. The Phase III activities were focused on evaluating deeply-cleaned coals as fuels for industrial boilers and investigating emissions control strategies for providing ultra-low emissions when firing coal-based fuels. This was addressed by performing coal beneficiation and preparation studies, and bench- to demonstration-scale emissions reduction studies. In addition, economic studies were conducted focused on determining cost and market penetration, selection of incentives, and regional economic impacts of coal-based technologies.

Bruce G. Miller; Sharon Falcone Miller; Sarma V. Pisupati; Chunshan Song; Ronald S. Wasco; Ronald T. Wincek; Xiaochun Xu; Alan W. Scaroni; Richard Hogg; Subhash Chander; M. Thaddeus Ityokumbul; Mark S. Klima; Peter T. Luckie; Adam Rose; Richard L. Gordon; Jeffrey Lazo; A. Michael Schaal

2004-01-30T23:59:59.000Z

143

RECOMMENDED FRIT COMPOSITION FOR INITIAL SLUDGE BATCH 5 PROCESSING AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

The Savannah River National Laboratory (SRNL) Frit Development Team recommends that the Defense Waste Processing Facility (DWPF) utilize Frit 418 for initial processing of high level waste (HLW) Sludge Batch 5 (SB5). The extended SB5 preparation time and need for DWPF feed have necessitated the use of a frit that is already included on the DWPF procurement specification. Frit 418 has been used previously in vitrification of Sludge Batches 3 and 4. Paper study assessments predict that Frit 418 will form an acceptable glass when combined with SB5 over a range of waste loadings (WLs), typically 30-41% based on nominal projected SB5 compositions. Frit 418 has a relatively high degree of robustness with regard to variation in the projected SB5 composition, particularly when the Na{sub 2}O concentration is varied. The acceptability (chemical durability) and model applicability of the Frit 418-SB5 system will be verified experimentally through a variability study, to be documented separately. Frit 418 has not been designed to provide an optimal melt rate with SB5, but is recommended for initial processing of SB5 until experimental testing to optimize a frit composition for melt rate can be completed. Melt rate performance can not be predicted at this time and must be determined experimentally. Note that melt rate testing may either identify an improved frit for SB5 processing (one which produces an acceptable glass at a faster rate than Frit 418) or confirm that Frit 418 is the best option.

Fox, K; Tommy Edwards, T; David Peeler, D

2008-06-25T23:59:59.000Z

144

FRIT OPTIMIZATION FOR SLUDGE BATCH PROCESSING AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

The Savannah River National Laboratory (SRNL) Frit Development Team recommends that the Defense Waste Processing Facility (DWPF) utilize Frit 418 for initial processing of high level waste (HLW) Sludge Batch 5 (SB5). The extended SB5 preparation time and need for DWPF feed have necessitated the use of a frit that is already included on the DWPF procurement specification. Frit 418 has been used previously in vitrification of Sludge Batches 3 and 4. Paper study assessments predict that Frit 418 will form an acceptable glass when combined with SB5 over a range of waste loadings (WLs), typically 30-41% based on nominal projected SB5 compositions. Frit 418 has a relatively high degree of robustness with regard to variation in the projected SB5 composition, particularly when the Na{sub 2}O concentration is varied. The acceptability (chemical durability) and model applicability of the Frit 418-SB5 system will be verified experimentally through a variability study, to be documented separately. Frit 418 has not been designed to provide an optimal melt rate with SB5, but is recommended for initial processing of SB5 until experimental testing to optimize a frit composition for melt rate can be completed. Melt rate performance can not be predicted at this time and must be determined experimentally. Note that melt rate testing may either identify an improved frit for SB5 processing (one which produces an acceptable glass at a faster rate than Frit 418) or confirm that Frit 418 is the best option.

Fox, K.

2009-01-28T23:59:59.000Z

145

Nuclear Energy Advisory Committee Facility Subcommittee visit to Oak Ridge National  

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

Facility Subcommittee visit to Oak Ridge National Facility Subcommittee visit to Oak Ridge National Laboratory 26 August 2010 The NEAC Facilities Subcommittee made a site visit to Oak Ridge National Laboratory (ORNL) on August 26, 2010. Subcommittee members included John Ahearne (Vice Chairman of NEAC and Facilities Subcommittee Chairman), Dana Christensen (ORNL), Thomas B. Cochran (Natural Resources Defense Council), Michael Corradini, (University of Wisconsin-Madison), and Andrew Klein (Oregon State University). Tansel Selekler (Department of Energy Office of Nuclear Energy) accompanied the Subcommittee. The visit was well-coordinated by Sherrell Greene, who insured that briefings were on time and that Cochran, Corridini, and Ahearne could get to the airport on time to catch departing flights.

146

Commercial nuclear fuel from U.S. and Russian surplus defense inventories: Materials, policies, and market effects  

SciTech Connect

Nuclear materials declared by the US and Russian governments as surplus to defense programs are being converted into fuel for commercial nuclear reactors. This report presents the results of an analysis estimating the market effects that would likely result from current plans to commercialize surplus defense inventories. The analysis focuses on two key issues: (1) the extent by which traditional sources of supply, such as production from uranium mines and enrichment plants, would be displaced by the commercialization of surplus defense inventories or, conversely, would be required in the event of disruptions to planned commercialization, and (2) the future price of uranium considering the potential availability of surplus defense inventories. Finally, the report provides an estimate of the savings in uranium procurement costs that could be realized by US nuclear power generating companies with access to competitively priced uranium supplied from surplus defense inventories.

1998-05-01T23:59:59.000Z

147

September 10, 2003, Board Public Meeting Presentations - Nuclear...  

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

with Defense Nuclear Facilities Safety Board on NRC's Reactor Oversight Process Presented by Cynthia Carpenter Deputy Director, Division of Inspection Program Management, Nuclear...

148

Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)  

SciTech Connect

In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-4 to improve quality assurance programs, processes, and procedures among its safety contractors. Specifically, guidance entitled, ''Safety Software Guide for use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance, DOE G 414.1-4'', provides information and acceptable methods to comply with safety software quality assurance (SQA) requirements. The guidance provides a roadmap for meeting DOE O 414.1C, ''Quality Assurance'', and the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and software application activities. [1, 2] The order and guide are part of a comprehensive implementation plan that addresses issues and concerns documented in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1. [3] Safety SQA requirements for DOE as well as National Nuclear Security Administration contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE G 414.1-4 was developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. The Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities. While the safety software guidance is considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at all DOE nuclear facilities, new nuclear facilities are well suited to take advantage of the guide to ensure compliant programs and processes are implemented. Attributes such as the facility life-cycle stage and the hazardous nature of each facility operations are considered, along with the category and level of importance of the software. The discussion provided herein illustrates benefits of applying the Safety Software Guide to work activities dependent on software applications and directed toward the design of new nuclear facilities. In particular, the Guide-based systematic approach with software enables design processes to effectively proceed and reduce the likelihood of rework activities. Several application examples are provided for the new facility.

VINCENT, Andrew

2005-07-14T23:59:59.000Z

149

National Laser User Facilities Program | National Nuclear Security  

National Nuclear Security Administration (NNSA)

User Facilities Program | National Nuclear Security User Facilities Program | 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 National Laser User Facilities Program Home > National Laser User Facilities Program National Laser User Facilities Program National Laser Users' Facility Grant Program Overview The Laboratory for Laser Energetics (LLE) at the University of Rochester

150

National Laser User Facilities Program | National Nuclear Security  

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

Laser User Facilities Program | National Nuclear Security Laser User Facilities Program | 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 National Laser User Facilities Program Home > National Laser User Facilities Program National Laser User Facilities Program National Laser Users' Facility Grant Program Overview The Laboratory for Laser Energetics (LLE) at the University of Rochester

151

Independent Oversight Review, DOE/NNSA Nuclear Facilities - April 2013 |  

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

DOE/NNSA Nuclear Facilities - April DOE/NNSA Nuclear Facilities - April 2013 Independent Oversight Review, DOE/NNSA Nuclear Facilities - April 2013 April 2013 Lessons Learned from the 2012 Targeted Reviews of Emergency Preparedness for Severe Natural Phenomena Events at Select DOE/NNSA Nuclear Facilities This report provides lessons learned from the 2012 reviews performed by Independent Oversight. The reviews performed during the fall of 2011 and throughout 2012 were at DOE/NNSA sites with hazard category 1 and 2 nuclear facilities, some of which also have significant quantities of hazardous chemicals on site. The purpose of the Independent Oversight review was to determine the state of emergency preparedness of selected sites by examining the sites' processes for evaluating plausible severe NPEs;

152

Independent Oversight Review, DOE Nuclear Facilities - May 2013 |  

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

Review, DOE Nuclear Facilities - May 2013 Review, DOE Nuclear Facilities - May 2013 Independent Oversight Review, DOE Nuclear Facilities - May 2013 May 2013 Lessons Learned from Targeted Reviews of Implementation Verification Review Processes at Department of Energy Nuclear Facilities This report summarizes and analyzes the results of independent reviews of IVR and associated processes at eight DOE sites conducted by Independent Oversight from August 2011 to September 2012. The purpose of the Independent Oversight review was to evaluate the processes and methods used for verifying the implementation of safety basis hazard controls and periodically re-verifying that the controls remain in place. Independent Oversight Review, DOE Nuclear Facilities - May 2013 More Documents & Publications Independent Oversight Review, Hanford Site CH2M Hill Plateau Remediation

153

Protocol, High Hazard Nuclear Facility Project Oversight - November 2012 |  

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

High Hazard Nuclear Facility Project Oversight - November High Hazard Nuclear Facility Project Oversight - November 2012 Protocol, High Hazard Nuclear Facility Project Oversight - November 2012 November 2012 Protocol for High Hazard Nuclear Facility Project Oversight The purpose of this protocol is to establish the requirements and responsibilities for managing and conducting Office of Health, Safety and Security (HSS) independent oversight of high-hazard nuclear facility projects. As part of the Department of Energy's (DOE) self regulatory framework for safety and security, DOE Order 227.1, Independent Oversight Program, assigns HSS the responsibility for implementing an independent oversight program. It also requires the HSS Office of Enforcement and Oversight to conduct independent evaluations of safety and security. This

154

KRS Chapter 278: Nuclear Power Facilities (Kentucky) | Department of Energy  

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

KRS Chapter 278: Nuclear Power Facilities (Kentucky) KRS Chapter 278: Nuclear Power Facilities (Kentucky) KRS Chapter 278: Nuclear Power Facilities (Kentucky) < Back Eligibility Commercial Construction Developer Investor-Owned Utility Municipal/Public Utility Utility Program Info State Kentucky Program Type Environmental Regulations Safety and Operational Guidelines Provider Kentucky Public Service Commission No construction shall commence on a nuclear power facility in the Commonwealth until the Public Service Commission finds that the United States government, through its authorized agency, has identified and approved a demonstrable technology or means for the disposal of high-level nuclear waste. The provisions of this section shall not be construed as applying to or precluding the following nuclear-based technologies,

155

Qualification of the Nippon Instrumentation for use in Measuring Mercury at the Defense Waste Processing Facility  

SciTech Connect

The Nippon Mercury/RA-3000 system installed in 221-S M-14 has been qualified for use. The qualification was a side-by-side comparison of the Nippon Mercury/RA-3000 system with the currently used Bacharach Mercury Analyzer. The side-by-side testing included standards for instrument calibration verifications, spiked samples and unspiked samples. The standards were traceable back to the National Institute of Standards and Technology (NIST). The side-by-side work included the analysis of Sludge Receipt and Adjustment Tank (SRAT) Receipt, SRAT Product, and Slurry Mix Evaporator (SME) samples. With the qualification of the Nippon Mercury/RA-3000 system in M-14, the DWPF lab will be able to perform a head to head comparison of a second Nippon Mercury/RA-3000 system once the system is installed. The Defense Waste Processing Facility (DWPF) analyzes receipt and product samples from the Sludge Receipt and Adjustment Tank (SRAT) to determine the mercury (Hg) concentration in the sludge slurry. The SRAT receipt is typically sampled and analyzed for the first ten SRAT batches of a new sludge batch to obtain an average Hg concentration. This average Hg concentration is then used to determine the amount of steam stripping required during the concentration/reflux step of the SRAT cycle to achieve a less than 0.6 wt% Hg in the SRAT product solids. After processing is complete, the SRAT product is sampled and analyzed for mercury to ensure that the mercury concentration does not exceed the 0.45 wt% limit in the Slurry Mix Evaporator (SME). The DWPF Laboratory utilizes Bacharach Analyzers to support these Hg analyses at this facility. These analyzers are more than 10 years old, and they are no longer supported by the manufacturer. Due to these difficulties, the Bacharach Analyzers are to be replaced by new Nippon Mercury/RA-3000 systems. DWPF issued a Technical Task Request (TTR) for the Savannah River National Laboratory (SRNL) to assist in the qualification of the new systems. SRNL prepared a task technical and quality assurance (TT&QA) plan that outlined the activities that are necessary and sufficient to meet the objectives of the TTR. In addition, TT&QA plan also included a test plan that provided guidance to the DWPF Lab in collecting the data needed to qualify the new Nippon Mercury/RA-3000 systems.

Edwards, T.; Mahannah, R.

2011-07-05T23:59:59.000Z

156

Application of accident progression event tree technology to the Savannah River Site Defense Waste Processing Facility SAR analysis  

SciTech Connect

The Accident Analysis in the Safety Analysis Report (SAR) for the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) has recently undergone an upgrade. Non-reactor SARs at SRS (and other Department of Energy (DOE) sites) use probabilistic techniques to assess the frequency of accidents at their facilities. This paper describes the application of an extension of the Accident Progression Event Tree (APET) approach to accidents at the SRS DWPF. The APET technique allows an integrated model of the facility risk to be developed, where previous probabilistic accident analyses have been limited to the quantification of the frequency and consequences of individual accident scenarios treated independently. Use of an APET allows a more structured approach, incorporating both the treatment of initiators that are common to more than one accident, and of accident progression at the facility.

Brandyberry, M.D.; Baker, W.H.; Wittman, R.S. [Westinghouse Savannah River Co., Aiken, SC (United States); Amos, C.N. [Science Applications International Corp., Albuquerque, NM (United States)

1993-12-31T23:59:59.000Z

157

The TRansUranium EXtraction (TRUEX) process: A vital tool for disposal of US defense nuclear waste  

SciTech Connect

The TRUEX (TRansUranium EXtraction) process is a generic actinide extraction/recovery process for the removal of all actinides from acidic nitrate and chloride nuclear waste solutions. Because of its high efficiency and flexibility and its compatibility with existing process facilities, TRUEX has now become a vital tool for the disposal of certain US defense nuclear waste. The development of TRUEX is closely coupled to the development of bifunctional extractants belonging to the carbamoylphosphoryl class and CMPO in particular. A brief review of the development of CMPO and its relationship to other bifunctional and monofunctional extractants is presented. The effect of TBP on CMPO, the selectivity of CMPO for actinides extracted from acidic nitrate media, the influence of diluents on CMPO behavior and 3rd phase formation, and the radiolysis/hydrolysis of CMPO and subsequent solvent cleanup will be highlighted. Application of TRUEX in the chemical pretreatment of specific nuclear waste streams and a summary of the current status of development and deployment of TRUEX is presented. 15 refs., 10 figs., 3 tabs.

Horwitz, E.P.; Schulz, W.W.

1990-01-01T23:59:59.000Z

158

Newest LANL Facility Receives LEED Gold Certification | National Nuclear  

National Nuclear Security Administration (NNSA)

Newest LANL Facility Receives LEED Gold Certification | National Nuclear Newest LANL Facility Receives LEED Gold Certification | 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 > Newest LANL Facility Receives LEED Gold Certification Newest LANL Facility Receives LEED Gold Certification Posted By Office of Public Affairs RULOB LANL's newest facility, the Radiological Laboratory Utility Office

159

NNSA Holds Groundbreaking at MOX Facility | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Groundbreaking at MOX Facility | National Nuclear Security Groundbreaking at MOX Facility | 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 > About Us > Our History > NNSA Timeline > NNSA Holds Groundbreaking at MOX Facility NNSA Holds Groundbreaking at MOX Facility October 14, 2005 Aiken, SC NNSA Holds Groundbreaking at MOX Facility

160

Ground test facility for nuclear testing of space reactor subsystems  

SciTech Connect

Two major reactor facilities at the INEL have been identified as easily adaptable for supporting the nuclear testing of the SP-100 reactor subsystem. They are the Engineering Test Reactor (ETR) and the Loss of Fluid Test Reactor (LOFT). In addition, there are machine shops, analytical laboratories, hot cells, and the supporting services (fire protection, safety, security, medical, waste management, etc.) necessary to conducting a nuclear test program. This paper presents the conceptual approach for modifying these reactor facilities for the ground engineering test facility for the SP-100 nuclear subsystem. 4 figs.

Quapp, W.J.; Watts, K.D.

1985-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Elimination Of Catalytic Hydrogen Generation In Defense Waste Processing Facility Slurries  

SciTech Connect

Based on lab-scale simulations of Defense Waste Processing Facility (DWPF) slurry chemistry, the addition of sodium nitrite and sodium hydroxide to waste slurries at concentrations sufficient to take the aqueous phase into the alkaline region (pH > 7) with approximately 500 mg nitrite ion/kg slurry (assuming <25 wt% total solids, or equivalently 2,000 mg nitrite/kg total solids) is sufficient to effectively deactivate the noble metal catalysts at temperatures between room temperature and boiling. This is a potential strategy for eliminating catalytic hydrogen generation from the list of concerns for sludge carried over into the DWPF Slurry Mix Evaporator Condensate Tank (SMECT) or Recycle Collection Tank (RCT). These conclusions are drawn in large part from the various phases of the DWPF catalytic hydrogen generation program conducted between 2005 and 2009. The findings could apply to various situations, including a solids carry-over from either the Sludge Receipt and Adjustment Tank (SRAT) or Slurry Mix Evaporator (SME) into the SMECT with subsequent transfer to the RCT, as well as a spill of formic acid into the sump system and transfer into an RCT that already contains sludge solids. There are other potential mitigating factors for the SMECT and RCT, since these vessels are typically operated at temperatures close to the minimum temperatures that catalytic hydrogen has been observed to occur in either the SRAT or SME (pure slurry case), and these vessels are also likely to be considerably more dilute in both noble metals and formate ion (the two essential components to catalytic hydrogen generation) than the two primary process vessels. Rhodium certainly, and ruthenium likely, are present as metal-ligand complexes that are favored under certain concentrations of the surrounding species. Therefore, in the SMECT or RCT, where a small volume of SRAT or SME material would be significantly diluted, conditions would be less optimal for forming or sustaining the catalytic ligand species. Such conditions are likely to adversely impact the ability of the transferred mass to produce hydrogen at the same rate (per unit mass SRAT or SME slurry) as in the SRAT or SME vessels.

Koopman, D. C.

2013-01-22T23:59:59.000Z

162

Groundbreaking at National Ignition Facility | National Nuclear...  

National Nuclear Security Administration (NNSA)

NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Groundbreaking at National Ignition Facility...

163

Nuclear Science: a survey of funding, facilities, and manpower  

SciTech Connect

In 1973 the Committee on Nuclear Science of the National Research Council initiated a re-examination of aspects (funding, manpower, and facilities) of the organization and operation of nuclear science research in order to evaluate any changes in the preceding four years and implications of such changes. The reports of the three ad hoc panels established for this purpose (funding and level of effort, nuclear facilities, manpower and education) are presented. Although they identify current problems in nuclear science, these reports do not provide simple solutions; rather, they attempt to provide updated information for use as background for continuing decisions. (RWR)

1975-01-01T23:59:59.000Z

164

Sodium Reaction Experimental Test Facility (SRETF) - Nuclear...  

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

Form Modeling Departments Engineering Analysis Nuclear Systems Analysis Research & Test Reactor Nonproliferation and National Security Detection & Diagnostic Systems...

165

Facilities & Projects | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering...

166

Integration of Facility Modeling Capabilities for Nuclear Nonproliferation Analysis  

Science Conference Proceedings (OSTI)

Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

Humberto E. Garcia

2012-01-01T23:59:59.000Z

167

INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS  

SciTech Connect

Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

2011-07-18T23:59:59.000Z

168

Integration of facility modeling capabilities for nuclear nonproliferation analysis  

SciTech Connect

Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

Garcia, Humberto [Idaho National Laboratory (INL); Burr, Tom [Los Alamos National Laboratory (LANL); Coles, Garill A [ORNL; Edmunds, Thomas A. [Lawrence Livermore National Laboratory (LLNL); Garrett, Alfred [Savannah River National Laboratory (SRNL); Gorensek, Maximilian [Savannah River National Laboratory (SRNL); Hamm, Luther [Savannah River National Laboratory (SRNL); Krebs, John [Argonne National Laboratory (ANL); Kress, Reid L [ORNL; Lamberti, Vincent [Y-12 National Security Complex; Schoenwald, David [ORNL; Tzanos, Constantine P [ORNL; Ward, Richard C [ORNL

2012-01-01T23:59:59.000Z

169

Approaches used for Clearance of Lands from Nuclear Facilities among  

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

Approaches used for Clearance of Lands from Nuclear Facilities Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input The study entitled, "Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input," focuses on the issue of showing compliance with given clearance levels for site release (also called derived concentration guideline levels, DCGL:s). The Swedish Radiation Safety Authority (SSM) intends to continue working on establishing such clearance levels in Sweden. As a starting point, SSM foresees that levels applied will depend on the features of the specific site and on the expected future use of the land, for example

170

Hanford, WA Selected as Plutonium Production Facility | National Nuclear  

National Nuclear Security Administration (NNSA)

Hanford, WA Selected as Plutonium Production Facility | National Nuclear Hanford, WA Selected as Plutonium Production Facility | 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 > About Us > Our History > NNSA Timeline > Hanford, WA Selected as Plutonium Production Facility Hanford, WA Selected as Plutonium Production Facility January 16, 1943 Hanford, WA

171

KCP celebrates production milestone at new facility | National Nuclear  

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

celebrates production milestone at new facility | National Nuclear celebrates production milestone at new facility | 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 > KCP celebrates production milestone at new facility KCP celebrates production milestone at new facility Posted By Office of Public Affairs The Kansas City Plant celebrated yet another milestone at the National

172

Massive Cement Pour into Hanford Site Nuclear Facility Underway: Recovery  

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

Massive Cement Pour into Hanford Site Nuclear Facility Underway: Massive Cement Pour into Hanford Site Nuclear Facility Underway: Recovery Act Funding Puts U Canyon in Home Stretch of Demolition Preparations Massive Cement Pour into Hanford Site Nuclear Facility Underway: Recovery Act Funding Puts U Canyon in Home Stretch of Demolition Preparations June 14, 2011 - 12:00pm Addthis Media Contacts Andre Armstrong, CH2M HILL Plateau Remediation Company (509) 376-6773 Andre_L_Armstrong@rl.gov Geoff Tyree, DOE (509) 376-4171 Geoffrey.Tyree@rl.doe.gov RICHLAND, Wash. - Hanford workers are pouring enough cement-like material to fill six Olympic-size wimming pools in one of the U.S. Department of Energy's (DOE) largest nuclear facilities at the Hanford Site in southeast Washington State to prepare the massive building for demolition.

173

Independent Oversight Focus Area Review, DOE Nuclear Facilities - April  

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

Independent Oversight Focus Area Review, DOE Nuclear Facilities - Independent Oversight Focus Area Review, DOE Nuclear Facilities - April 2010 Independent Oversight Focus Area Review, DOE Nuclear Facilities - April 2010 April 2010 Review of Specific Administrative Controls at DOE Nuclear Facilities The U.S. Department of Energy (DOE) Office of Independent Oversight, within the Office of Health Safety and Security occasionally reviews specific focus areas. Focus areas are aspects of safety programs that Independent Oversight determines warrant increased management attention based on reviews of performance data, inspection results, and operating experience across DOE sites. Due, in part, to operating experience and previous inspection results. DOE selected specific administrative controls (SACs) as a focus area. SACs are new or revised technical safety requirements (TSRs)

174

DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility...  

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

DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in Idaho Uranium Enrichment Project to Create Over 1,000 Jobs in Idaho Washington, DC As part of a broad...

175

Massive Cement Pour into Hanford Site Nuclear Facility Underway: Recovery  

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

Massive Cement Pour into Hanford Site Nuclear Facility Underway: Massive Cement Pour into Hanford Site Nuclear Facility Underway: Recovery Act Funding Puts U Canyon in Home Stretch of Demolition Preparations Massive Cement Pour into Hanford Site Nuclear Facility Underway: Recovery Act Funding Puts U Canyon in Home Stretch of Demolition Preparations June 14, 2011 - 12:00pm Addthis Media Contacts Andre Armstrong, CH2M HILL Plateau Remediation Company (509) 376-6773 Andre_L_Armstrong@rl.gov Geoff Tyree, DOE (509) 376-4171 Geoffrey.Tyree@rl.doe.gov RICHLAND, Wash. - Hanford workers are pouring enough cement-like material to fill six Olympic-size wimming pools in one of the U.S. Department of Energy's (DOE) largest nuclear facilities at the Hanford Site in southeast Washington State to prepare the massive building for demolition.

176

Nuclear criticality safety evaluation -- DWPF Late Wash Facility, Salt Process Cell and Chemical Process Cell  

SciTech Connect

The Savannah River Site (SRS) High Level Nuclear Waste will be vitrified in the Defense Waste Processing Facility (DWPF) for long term storage and disposal. This is a nuclear criticality safety evaluation for the Late Wash Facility (LWF), the Salt Processing Cell (SPC) and the Chemical Processing Cell (CPC). of the DWPF. Waste salt solution is processed in the Tank Farm In-Tank Precipitation (ITP) process and is then further washed in the DWPF Late Wash Facility (LWF) before it is fed to the DWPF Salt Processing Cell. In the Salt Processing Cell the precipitate slurry is processed in the Precipitate Reactor (PR) and the resultant Precipitate Hydrolysis Aqueous (PHA) produce is combined with the sludge feed and frit in the DWPF Chemical Process Cell to produce a melter feed. The waste is finally immobilized in the Melt Cell. Material in the Tank Farm and the ITP and Extended Sludge processes have been shown to be safe against a nuclear criticality by others. The precipitate slurry feed from ITP and the first six batches of sludge feed are safe against a nuclear criticality and this evaluation demonstrates that the processes in the LWF, the SPC and the CPC do not alter the characteristics of the materials to compromise safety.

Williamson, T.G.

1994-10-17T23:59:59.000Z

177

Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities  

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

14 14 Strengthening Line Management Oversight and Federal Monitoring of Nuclear Facilities Standard Review Plan Commercial Grade Dedication (CGD) August 2013 2 of 14 OFFICE OF ENVIRONMENTAL MANAGEMENT Standard Review Plan (SRP) Commercial Grade Dedication (CGD) Applicability CD-0 CD-1 CD-2 CD-3 CD-4 Operation Post Operation August 2013 3 of 14 Table of Contents Objective ....................................................................................................................................................... 4 Overview of Commercial Grade Dedication for Nuclear Facilities .............................................................. 4 Requirements ................................................................................................................................................ 5

178

HYDROGEN IGNITION MECHANISM FOR EXPLOSIONS IN NUCLEAR FACILITY PIPE SYSTEMS  

DOE Green Energy (OSTI)

Hydrogen and oxygen generation due to the radiolysis of water is a recognized hazard in pipe systems used in the nuclear industry, where the accumulation of hydrogen and oxygen at high points in the pipe system is expected, and explosive conditions exist. Pipe ruptures at nuclear facilities were attributed to hydrogen explosions inside pipelines, in nuclear facilities, i.e., Hamaoka, Nuclear Power Station in Japan, and Brunsbuettel in Germany. Prior to these accidents an ignition source for hydrogen was questionable, but these accidents, demonstrated that a mechanism was, in fact, available to initiate combustion and explosion. Hydrogen explosions may occur simultaneously with water hammer accidents in nuclear facilities, and a theoretical mechanism to relate water hammer to hydrogen deflagrations and explosions is presented herein.

Leishear, R

2010-05-02T23:59:59.000Z

179

INDUSTRIAL CONTROL SYSTEM CYBER SECURITY: QUESTIONS AND ANSWERS RELEVANT TO NUCLEAR FACILITIES, SAFEGUARDS AND SECURITY  

SciTech Connect

Typical questions surrounding industrial control system (ICS) cyber security always lead back to: What could a cyber attack do to my system(s) and; how much should I worry about it? These two leading questions represent only a fraction of questions asked when discussing cyber security as it applies to any program, company, business, or organization. The intent of this paper is to open a dialog of important pertinent questions and answers that managers of nuclear facilities engaged in nuclear facility security and safeguards should examine, i.e., what questions should be asked; and how do the answers affect an organization's ability to effectively safeguard and secure nuclear material. When a cyber intrusion is reported, what does that mean? Can an intrusion be detected or go un-noticed? Are nuclear security or safeguards systems potentially vulnerable? What about the digital systems employed in process monitoring, and international safeguards? Organizations expend considerable efforts to ensure that their facilities can maintain continuity of operations against physical threats. However, cyber threats particularly on ICSs may not be well known or understood, and often do not receive adequate attention. With the disclosure of the Stuxnet virus that has recently attacked nuclear infrastructure, many organizations have recognized the need for an urgent interest in cyber attacks and defenses against them. Several questions arise including discussions about the insider threat, adequate cyber protections, program readiness, encryption, and many more. These questions, among others, are discussed so as to raise the awareness and shed light on ways to protect nuclear facilities and materials against such attacks.

Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

2011-07-01T23:59:59.000Z

180

Nuclear Facility Operations | Department of Energy  

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

Idaho Operations Office oversees these contract activities in accordance with DOE directives. INL is a multi-program laboratory In addition to enabling the Office of Nuclear...

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Facility Representative Program: Nuclear Safety Basis Fundamentals...  

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

Qualification Information Qualification Standards DOE Order Self-Study Modules DOE Fundamentals Handbooks Nuclear Safety Basis Self-Study Guide Energy Online Courses Available...

182

SUMMARY OF FY11 SULFATE RETENTION STUDIES FOR DEFENSE WASTE PROCESSING FACILITY GLASS  

Science Conference Proceedings (OSTI)

This report describes the results of studies related to the incorporation of sulfate in high level waste (HLW) borosilicate glass produced at the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF). A group of simulated HLW glasses produced for earlier sulfate retention studies was selected for full chemical composition measurements to determine whether there is any clear link between composition and sulfate retention over the compositional region evaluated. In addition, the viscosity of several glasses was measured to support future efforts in modeling sulfate solubility as a function of predicted viscosity. The intent of these studies was to develop a better understanding of sulfate retention in borosilicate HLW glass to allow for higher loadings of sulfate containing waste. Based on the results of these and other studies, the ability to improve sulfate solubility in DWPF borosilicate glasses lies in reducing the connectivity of the glass network structure. This can be achieved, as an example, by increasing the concentration of alkali species in the glass. However, this must be balanced with other effects of reduced network connectivity, such as reduced viscosity, potentially lower chemical durability, and in the case of higher sodium and aluminum concentrations, the propensity for nepheline crystallization. Future DWPF processing is likely to target higher waste loadings and higher sludge sodium concentrations, meaning that alkali concentrations in the glass will already be relatively high. It is therefore unlikely that there will be the ability to target significantly higher total alkali concentrations in the glass solely to support increased sulfate solubility without the increased alkali concentration causing failure of other Product Composition Control System (PCCS) constraints, such as low viscosity and durability. No individual components were found to provide a significant improvement in sulfate retention (i.e., an increase of the magnitude necessary to have a dramatic impact on blending, washing, or waste loading strategies for DWPF) for the glasses studied here. In general, the concentrations of those species that significantly improve sulfate solubility in a borosilicate glass must be added in relatively large concentrations (e.g., 13 to 38 wt % or more of the frit) in order to have a substantial impact. For DWPF, these concentrations would constitute too large of a portion of the frit to be practical. Therefore, it is unlikely that specific additives may be introduced into the DWPF glass via the frit to significantly improve sulfate solubility. The results presented here continue to show that sulfate solubility or retention is a function of individual glass compositions, rather than a property of a broad glass composition region. It would therefore be inappropriate to set a single sulfate concentration limit for a range of DWPF glass compositions. Sulfate concentration limits should continue to be identified and implemented for each sludge batch. The current PCCS limit is 0.4 wt % SO{sub 4}{sup 2-} in glass, although frit development efforts have led to an increased limit of 0.6 wt % for recent sludge batches. Slightly higher limits (perhaps 0.7-0.8 wt %) may be possible for future sludge batches. An opportunity for allowing a higher sulfate concentration limit at DWPF may lay lie in improving the laboratory experiments used to set this limit. That is, there are several differences between the crucible-scale testing currently used to define a limit for DWPF operation and the actual conditions within the DWPF melter. In particular, no allowance is currently made for sulfur partitioning (volatility versus retention) during melter processing as the sulfate limit is set for a specific sludge batch. A better understanding of the partitioning of sulfur in a bubbled melter operating with a cold cap as well as the impacts of sulfur on the off-gas system may allow a higher sulfate concentration limit to be established for the melter feed. This approach would have to be taken carefully to ensure that a

Fox, K.; Edwards, T.

2012-05-08T23:59:59.000Z

183

EVALUATION OF A TURBIDITY METER FOR USE AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

Savannah River Remediations (SRRs) Defense Waste Processing Facility (DWPF) Laboratory currently tests for sludge carry-over into the Recycle Collection Tank (RCT) by evaluating the iron concentration in the Slurry Mix Evaporator Condensate Tank (SMECT) and relating this iron concentration to the amount of sludge solids present. A new method was proposed for detecting the amount of sludge in the SMECT that involves the use of an Optek turbidity sensor. Waste Services Laboratory (WSL) personnel conducted testing on two of these units following a test plan developed by Waste Solidification Engineering (WSE). Both Optek units (SN64217 and SN65164) use sensor model AF16-N and signal converter model series C4000. The sensor body of each unit was modified to hold a standard DWPF 12 cc sample vial, also known as a peanut vial. The purpose of this testing was to evaluate the use of this model of turbidity sensor, or meter, to provide a measurement of the sludge solids present in the SMECT based upon samples from that tank. During discussions of the results from this study by WSE, WSL, and Savannah River National Laboratory (SRNL) personnel, an upper limit on the acceptable level of solids in SMECT samples was set at 0.14 weight percent (wt%). A go/no-go decision criterion was to be developed for the critical turbidity response, which is expressed in concentration units (CUs), for each Optek unit based upon the 0.14 wt% solids value. An acceptable or a go decision for the SMECT should reflect the situation that there is an identified risk (e.g. 5%) for a CU response from the Optek unit to be less than the critical CU value when the solids content of the SMECT is actually 0.14 wt% or greater, while a no-go determination (i.e., an Optek CU response above the critical CU value, a conservative decision relative to risk) would lead to additional evaluations of the SMECT to better quantify the possible solids content of the tank. Subsequent to the issuance of the initial version of this report but under the scope of the original request for technical assistance, WSE asked for this report to be revised to include the go/no-go CU value corresponding to 0.28 wt% solids. It was this request that led to the preparation of Revision 1 of the report. The results for the 0.28 wt% solids value were developed following the same approach as that utilized for the 0.14 wt% solids value. A sludge simulant was used to develop standards for testing both Optek units and to determine the viability of a go/no-go CU response for each of the units. Statistical methods were used by SRNL to develop the critical CU value for the go/no-go decision for these standards for each Optek unit. Since only one sludge simulant was available for this testing, the sensitivity of these results to other simulants and to actual sludge material is not known. However, limited testing with samples from the actual DWPF process (both SRAT product samples and SMECT samples) demonstrated that the use of the go/no-go criteria developed from the sludge simulant testing was conservative for these samples taken from the sludge batch, Sludge Batch 7b, being processed at the time of this testing. While both of the Optek units performed very reliably during this testing, there were statistically significant differences (although small on a practical scale) between the two units. Thus, testing should be conducted on any new unit of this Optek model to qualify it before it is used to support the DWPF operation.

Mahannah, R.; Edwards, T.

2013-06-04T23:59:59.000Z

184

Development of nuclear diagnostics for the National Ignition Facility ,,invited...  

E-Print Network (OSTI)

July 2006; published online 5 October 2006 The National Ignition Facility NIF will provide up to 1.8 MJ of laser energy for imploding inertial confinement fusion ICF targets. Ignited NIF targets are expected of nuclear diagnostics in ICF experiments. In 2005, the suite of nuclear-ignition diagnostics for the NIF

185

Method and means of monitoring the effluent from nuclear facilities  

DOE Patents (OSTI)

Radioactive iodine is detected in the effluent cooling gas from a nuclear reactor or nuclear facility by passing the effluent gas through a continuously moving adsorbent filter material which is then purged of noble gases and conveyed continuously to a detector of radioactivity. The purging operation has little or no effect upon the concentration of radioactive iodine which is adsorbed on the filter material.

Lattin, Kenneth R. (Richland, WA); Erickson, Gerald L. (Richland, WA)

1976-01-01T23:59:59.000Z

186

Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities  

E-Print Network (OSTI)

1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

187

Release of radioisotopes and activated materials from nuclear installations and facilities  

E-Print Network (OSTI)

wastes coming from the decommissioning of nuclear reactors,use of a nuclear facility The decommissioning, refurbishingdisposed of. The decommissioning of a nuclear power station

Manfredi, P.F.; Millaud, J.E.

2001-01-01T23:59:59.000Z

188

Innovative cement helps DOE safeguard nuclear facilities | Argonne National  

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

Innovative cement helps DOE safeguard nuclear facilities Innovative cement helps DOE safeguard nuclear facilities By Jared Sagoff * April 25, 2008 Tweet EmailPrint ARGONNE, Ill. - When Argonne materials scientists Arun Wagh and Dileep Singh initially developed Ceramicrete®, a novel phosphate cement that stabilizes radioactive waste streams, they did not immediately recognize that with one or two extra ingredients, the cement could solve another problem in the nuclear complex. In the course of the development of the Ceramicrete technology, Wagh and Singh formed a multilayered collaboration among Argonne, the Russian Federal Nuclear Center (VNIIEF) in Sarov, Russia, and Ceradyne Boron Products LLC. This international scientific partnership created an unusually efficient nuclear shield that blocks the neutrons and gamma rays

189

Siting of nuclear facilities. Selections from Nuclear Safety  

SciTech Connect

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

Buchanan, J.R.

1976-07-01T23:59:59.000Z

190

CRAD, Nuclear Facility Construction - Piping and Pipe Supports Inspection -  

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

Construction - Piping and Pipe Supports Construction - Piping and Pipe Supports Inspection - March 29, 2012 CRAD, Nuclear Facility Construction - Piping and Pipe Supports Inspection - March 29, 2012 March 29, 2012 Nuclear Facility Construction - Piping and Pipe Supports Inspection Criteria, Approach and Lines of Inquiry (HSS CRAD 45-52, Rev. 0) For the purpose of this criteria review and approach, this Criteria Review and Approach Document (CRAD) includes piping and pipe supports and attachments of the pipe supports to structures (concrete, structural steel, or embed plates). Pipe supports include rigid restraints, welded attachments to piping, struts, snubbers, spring cans, and constant supports. Inspection of pipe whip restraints are also included in this CRAD. Selection of nuclear facility piping systems for inspection should be

191

Criteria for Evaluation of Nuclear Facility Training Programs  

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

STD-1070-94 STD-1070-94 Reaffirmed June 2013 DOE STANDARD CRITERIA FOR EVALUATION OF NUCLEAR FACILITY TRAINING PROGRAMS (Formerly Titled: Guidelines for Evaluation of Nuclear Facility Training Programs) U.S. Department of Energy FSC Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE HDBK-1070-94 Errata June 2013 Table of Changes Page/Section Change Cover Criteria for Evaluation of Nuclear Facility Training Programs Page ii This document is available on the Department of Energy Technical Standards Program Web page at http://www.hss.doe.gov/nuclearsafety/ns/techstds/ Page iii Table of Contents Page iv This DOE Technical Standard is invoked as a requirement by DOE Order 426.2, Personnel Selection, Training, Qualifications and

192

Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 2  

SciTech Connect

Nuclear wastes from the defense production cycle contain many uniquely useful, intrinsically valuable, and strategically important materials. These materials have a wide range of known and potential applications in food technology, agriculture, energy, public health, medicine, industrial technology, and national security. Furthermore, their removal from the nuclear waste stream can facilitate waste management and yield economic, safety, and environmental advantages in the management and disposal of the residual nuclear wastes that have no redemptive value. This document is the program plan for implementing the recovery and beneficial use of these valuable materials. An Executive Summary of this document, DOE/DP-0013, Vol. 1, January 1983, is available. Program policy, goals and strategy are stated in Section 2. Implementation tasks, schedule and funding are detailed in Section 3. The remaining five sections and the appendixes provide necessary background information to support these two sections. Section 4 reviews some of the unique properties of the individual byproduct materials and describes both demonstrated and potential applications. The amounts of byproduct materials that are available now for research and demonstration purposes, and the amounts that could be recovered in the future for expanded applications are detailed in Section 5. Section 6 describes the effects byproduct recovery and utilization have on the management and final disposal of nuclear wastes. The institutional issues that affect the recovery, processing and utilization of nuclear byproducts are discussed in Section 7. Finally, Section 8 presents a generalized mathematical process by which applications can be evaluated and prioritized (rank-ordered) to provide planning data for program management.

1983-08-01T23:59:59.000Z

193

REMOTE IN-CELL SAMPLING IMPROVEMENTS PROGRAM AT THESAVANNAH RIVER SITE (SRS) DEFENSE WASTE PROCESSING FACILITY (DWPF)  

Science Conference Proceedings (OSTI)

Remote Systems Engineering (RSE) of the Savannah River National Lab (SRNL) in combination with the Defense Waste Processing Facility(DWPF) Engineering and Operations has evaluated the existing equipment and processes used in the facility sample cells for 'pulling' samples from the radioactive waste stream and performing equipment in-cell repairs/replacements. RSE has designed and tested equipment for improving remote in-cell sampling evolutions and reducing the time required for in-cell maintenance of existing equipment. The equipment within the present process tank sampling system has been in constant use since the facility start-up over 17 years ago. At present, the method for taking samples within the sample cells produces excessive maintenance and downtime due to frequent failures relative to the sampling station equipment and manipulator. Location and orientation of many sampling stations within the sample cells is not conducive to manipulator operation. The overextension of manipulators required to perform many in-cell operations is a major cause of manipulator failures. To improve sampling operations and reduce downtime due to equipment maintenance, a Portable Sampling Station (PSS), wireless in-cell cameras, and new commercially available sampling technology has been designed, developed and/or adapted and tested. The uniqueness of the design(s), the results of the scoping tests, and the benefits relative to in-cell operation and reduction of waste are presented.

Marzolf, A

2007-11-26T23:59:59.000Z

194

Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation  

Science Conference Proceedings (OSTI)

The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

West, K.A.

1988-11-01T23:59:59.000Z

195

Iraq nuclear facility dismantlement and disposal project (NDs Project).  

SciTech Connect

The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.

Cochran, John Russell

2010-06-01T23:59:59.000Z

196

Heat Transfer Modeling of Dry Spent Nuclear Fuel Storage Facilities  

Science Conference Proceedings (OSTI)

The present work was undertaken to provide heat transfer model that accurately predicts the thermal performance of dry spent nuclear fuel storage facilities. One of the storage configurations being considered for DOE Aluminum-clad Spent Nuclear Fuel (Al-SNF), such as the Material and Testing Reactor (MTR) fuel, is in a dry storage facility. To support design studies of storage options a computational and experimental program has been conducted at the Savannah River Site (SRS). The main objective is to develop heat transfer models including natural convection effects internal to an interim dry storage canister and to geological codisposal Waste Package (WP). Calculated temperatures will be used to demonstrate engineering viability of a dry storage option in enclosed interim storage and geological repository WP and to assess the chemical and physical behaviors of the Al-SNF in the dry storage facilities. The current paper describes the modeling approaches and presents the computational results along with the experimental data.

Lee, S.Y.

1999-01-13T23:59:59.000Z

197

Assessment of Nuclear Safety Culture at the Salt Waste Processing...  

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

BARS Behavioral Anchored Rating Scales DNFSB Defense Nuclear Facilities Safety Board DOE U.S. Department of Energy DPO Differing Professional Opinion ECP Employee Concern...

198

Proposed Use of a Constructed Wetland for the Treatment of Metals in the S-04 Outfall of the Defense Waste Processing Facility at the Savannah River Site  

SciTech Connect

The DWPF is part of an integrated waste treatment system at the SRS to treat wastes containing radioactive contaminants. In the early 1980s the DOE recognized that there would be significant safety and cost advantages associated with immobilizing the radioactive waste in a stable solid form. The Defense Waste Processing Facility was designed and constructed to accomplish this task.

Glover, T.

1999-11-23T23:59:59.000Z

199

Integration of facility modeling capabilities for nuclear nonproliferation analysis  

Science Conference Proceedings (OSTI)

Developing automated methods for data collection and analysis that can facilitate nuclearnonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facilitymodeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facilitymodeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facilitymodelingcapabilities and illustrates how they could be integrated and utilized for nonproliferationanalysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facilitymodeling tools. After considering a representative sampling of key facilitymodelingcapabilities, the proposed integration framework is illustrated with several examples.

Burr, Tom [Los Alamos National Laboratory (LANL); Gorensek, M. B. [Savannah River National Laboratory (SRNL); Krebs, John [Argonne National Laboratory (ANL); Kress, Reid L [ORNL; Lamberti, Vincent [Y-12 National Security Complex; Schoenwald, David [ORNL; Ward, Richard C [ORNL

2012-01-01T23:59:59.000Z

200

Clearance Levels For Redundant Material From Decommissioning Of Nuclear Facilities  

E-Print Network (OSTI)

Currently, a great deal is happening in the regulatory field regarding the release of radiologically contaminated material: . The IAEA is working on the revision of Safety Series 89 (governing the principles of exemption and clearance) and of the TECDOC 855 on clearance levels. . The European Commission Directive on basic safety standards for protection against ionizing radiation in both nuclear and non-nuclear industries will become effective in May 2000. . The U.S. NRC has issued its draft on clearance of material from nuclear facilities (NUREG 1640), as well as an "issues" paper on the release of solid materials. The U.S. State Department has launched an International Radioactive Source Management Initiative, one of the objectives being to "develop international standards and guidelines and `harmonize' U.S. and IAEA radioactive clearance levels." Of great significance to the implementor of clearance regulations in the nuclear industry is the emergence of the NORM issue durin...

Shankar Menon Program; Shankar Menon

2000-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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

A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation  

E-Print Network (OSTI)

With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to the inclusion of highly enriched material and reprocessing ...

Iamsumang, Chonlagarn

2010-01-01T23:59:59.000Z

202

Nuclear Energy Advisory Committee, Facility Subcommittee visit to Idaho National Laboratory  

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

The Nuclear Energy Advisory Committee, Facility Subcommittee visited the Idaho National Laboratory on 19-20 May 2010 to tour the nuclear infrastructure and to discuss the INL plans for facility...

203

Airborne release fractions/rates and respirable fractions for nonreactor nuclear facilities. Volume 2, Appendices  

SciTech Connect

This document contains compiled data from the DOE Handbook on Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear facilities. Source data and example facilities utilized, such as the Plutonium Recovery Facility, are included.

Not Available

1994-12-01T23:59:59.000Z

204

Pyroprocessing of Fast Flux Test Facility Nuclear Fuel  

SciTech Connect

Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electrorefined uranium products exceeded 99%.

B.R. Westphal; G.L. Fredrickson; G.G. Galbreth; D. Vaden; M.D. Elliott; J.C. Price; E.M. Honeyfield; M.N. Patterson; L. A. Wurth

2013-10-01T23:59:59.000Z

205

Benefits of explosive cutting for nuclear-facility applications  

Science Conference Proceedings (OSTI)

The study discussed in this report was a cost/benefit analysis to determine: (1) whether explosive cutting is cost effective in comparison with alternative metal sectioning methods and (2) whether explosive cutting would reduce radiation exposure or provide other benefits. Two separate approaches were pursued. The first was to qualitatively assess cutting methods and factors involved in typical sectioning cases and then compare the results for the cutting methods. The second was to prepare estimates of work schedules and potential radiation exposures for candidate sectioning methods for two hypothetical, but typical, sectioning tasks. The analysis shows that explosive cutting would be cost effective and would also reduce radiation exposure when used for typical nuclear facility sectioning tasks. These results indicate that explosive cutting should be one of the principal cutting methods considered whenever steel or similar metal structures or equipment in a nuclear facility are to be sectioned for repair or decommissioning. 13 figures, 7 tables. (DLC)

Hazelton, R.F.; Lundgren, R.A.; Allen, R.P.

1981-06-01T23:59:59.000Z

206

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

207

Assessment of a hot hydrogen nuclear propulsion fuel test facility  

DOE Green Energy (OSTI)

Subsequent to the announcement of the Space Exploration Initiative (SEI), several studies and review groups have identified nuclear thermal propulsion as a high priority technology for development. To achieve the goals of SEI to place man on Mars, a nuclear rocket will operate at near 2700K and in a hydrogen environment at near 60 atmospheres. Under these conditions, the operational lifetime of the rocket will be limited by the corrosion rate at the hydrogen/fuel interface. Consequently, the Los Alamos National Laboratory has been evaluating requirements and design issues for a test facility. The facility will be able to directly heat fuel samples by electrical resistance, microwave deposition, or radio frequency induction heating to temperatures near 3000K. Hydrogen gas at variable pressure and temperatures will flow through the samples. The thermal gradients, power density, and operating times envisioned for nuclear rockets will be duplicated as close as reasonable. The post-sample flow stream will then be scrubbed and cooled before reprocessing. The baseline design and timetable for the facility will be discussed. 7 refs.

Watanabe, H.H.; Howe, S.D.; Wantuck, P.J.

1991-01-01T23:59:59.000Z

208

DEVELOPMENT OF REMOTE HANFORD CONNECTOR GASKET REPLACEMENT TOOLING FOR THE SAVANNAH RIVER SITE'S DEFENSE WASTE PROCESSING FACILITY  

Science Conference Proceedings (OSTI)

The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) requested development of tooling for remote replacement of gaskets in mechanical Hanford connectors. The facility has compressed air supply, two master-slave manipulators (MSM's) and a lightweight robotic arm for operation of the remote tools. The Savannah River National Laboratory (SRNL) developed and tested multiple tools to perform the gasket replacement tasks. Separate pneumatic snap-ring removal tools that use the connector skirt as a reaction surface were developed for removal of the snap ring and spent gasket on both vertical and horizontal Hanford connectors. A pneumatic tool that clamps and centers on the jumper pipe ID was developed to simultaneously install the new gasket and snap ring. A pneumatic snap-ring-loading tool was developed that compresses the snap ring and places it in a groove in the installation tool. All of the tools are located on a custom work table with a pneumatic valve station that directs compressed air to the desired tool and vents the tools as needed. The entire system has been successfully tested using MSM's to manipulate the various tools. Deployment of the entire system is expected during FY08. The Hanford connector gasket replacement tooling has been successfully tested using MSM's to manipulate the various tools. Nitric acid is used in many of the decontamination processes performed in the REDC, where the tooling will be deployed. Although most of the tool components were fabricated/purchased with nitric acid and radioactive service in mind, some of the prototype parts must be replaced with parts that are more compatible with nitric acid/radioactive service. Several modifications to the various tools are needed to facilitate maintenance and replacement of failed components. Development of installation tools for replacement of 1-inch, 2-inch and multi-hole gaskets is being considered. Deployment of the existing system in the DWPF REDC is expected during FY08.

Krementz, D

2007-11-27T23:59:59.000Z

209

VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY'S (DWPF) PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 7A QUALIFICATION SAMPLE  

Science Conference Proceedings (OSTI)

For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) performs confirmation of the applicability of the digestion method to be used by the DWPF lab for elemental analysis of Sludge Receipt and Adjustment Tank (SRAT) receipt samples and SRAT product process control samples. DWPF SRAT samples are typically dissolved using a room temperature HF-HNO{sub 3} acid dissolution (i.e., DWPF Cold Chem Method, see DWPF Procedure SW4-15.201) and then analyzed by inductively coupled plasma - atomic emission spectroscopy (ICP-AES). This report contains the results and comparison of data generated from performing the Aqua Regia (AR), Sodium peroxide/Hydroxide Fusion (PF) and DWPF Cold Chem (CC) method digestions of Sludge Batch 7a (SB7a) SRAT Receipt and SB7a SRAT Product samples. The SB7a SRAT Receipt and SB7a SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constituates the SB7a Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 6 (SB6), to form the Sb7a Blend composition.

Click, D.; Edwards, T.; Jones, M.; Wiedenman, B.

2011-03-14T23:59:59.000Z

210

The development of coal-based technologies for Department of Defense facilities: Phase 1 final report. Volume 1: Technical report  

SciTech Connect

The first phase of a three-phase project investigating the development of coal-based technologies for Department of Defense facilities has been completed. The objectives of the project are to: decrease DOD`s dependence on foreign oil and increase its use of coal; promote public and private sector deployment of technologies for utilizing coal-based fuels in oil-designed combustion equipment; and provide a continuing environment for research and development of coal-based fuel technologies for small-scale applications at a time when market conditions in the US are not favorable for the introduction of coal-fired equipment in the commercial and industrial capacity ranges. The Phase 1 activities were focused on developing clean, coal-based combustion technologies for the utilization of both micronized coal-water mixtures (MCWMs) and dry, micronized coal (DMC) in fuel oil-designed industrial boilers. The specific objective in Phase 1 was to deliver fully engineered retrofit options for a fuel oil-designed watertube boiler located on a DOD installation to fire either MCWM or DMC. This was achieved through a project consisting of fundamental, pilot-sale, and demonstration-scale activities investigating coal beneficiation and preparation, and MCWM and DMC combustion performance. In addition, detailed engineering designs and an economic analysis were conducted for a boiler located at the Naval Surface Warfare Center, near Crane, Indiana. Results are reported on MCWM and DMC combustion performance evaluation; engineering design; and cost/economic analysis.

Miller, B.G.; Morrison, J.L.; Pisupati, S.V. [Pennsylvania State Univ., University Park, PA (United States). Energy and Fuels Research Center] [and others

1997-01-31T23:59:59.000Z

211

National Laser Users' Facility Grant Program | National Nuclear...  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > University Partnerships Academic Alliances > National...

212

Nuclear facility decommissioning and site remedial actions: a selected bibliography  

SciTech Connect

This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

1982-09-01T23:59:59.000Z

213

Nuclear facility decommissioning and site remedial actions: a selected bibliography  

SciTech Connect

This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

1982-09-01T23:59:59.000Z

214

Financing Strategies For A Nuclear Fuel Cycle Facility  

SciTech Connect

To help meet the nations energy needs, recycling of partially used nuclear fuel is required to close the nuclear fuel cycle, but implementing this step will require considerable investment. This report evaluates financing scenarios for integrating recycling facilities into the nuclear fuel cycle. A range of options from fully government owned to fully private owned were evaluated using DPL (Decision Programming Language 6.0), which can systematically optimize outcomes based on user-defined criteria (e.g., lowest lifecycle cost, lowest unit cost). This evaluation concludes that the lowest unit costs and lifetime costs are found for a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. However, this does not mean that the facilities should necessarily be constructed and operated by the government. The costs for hybrid combinations of public and private (commercial) financed options can compete under some circumstances with the costs of the government option. This analysis shows that commercial operations have potential to be economical, but there is presently no incentive for private industry involvement. The Nuclear Waste Policy Act (NWPA) currently establishes government ownership of partially used commercial nuclear fuel. In addition, the recently announced Global Nuclear Energy Partnership (GNEP) suggests fuels from several countries will be recycled in the United States as part of an international governmental agreement; this also assumes government ownership. Overwhelmingly, uncertainty in annual facility capacity led to the greatest variations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; and the annual operating costs, forgiveness of debt, and overnight costs dominate the costs computed for the government case. The uncertainty in operations, leading to lower than optimal processing rates (or annual plant throughput), is the most detrimental issue to achieving low unit costs. Conversely, lowering debt interest rates and the required return on investments can reduce costs for private industry.

David Shropshire; Sharon Chandler

2006-07-01T23:59:59.000Z

215

DOE O 452.6A, Nuclear Weapon Surety Interface with the Department of Defense  

Directives, Delegations, and Requirements

This Order establishes Department of Energy and National Nuclear Security Administration requirements and responsibilities for addressing joint nuclear weapon ...

2009-05-14T23:59:59.000Z

216

Analyses by the Defense Waste Processing Facility Laboratory of Thorium Glasses from the Sludge Batch 6 Variability Study  

Science Conference Proceedings (OSTI)

The Savannah River Remediation (SRR) Defense Waste Processing Facility (DWPF) is currently processing Sludge Batch 6 (SB6) with Frit 418. At times during the processing of this glass system, thorium is expected to be at concentrations in the final wasteform that make it a reportable element for the first time since startup of radioactive operations at the DWPF. The Savannah River National Laboratory (SRNL) supported the qualification of the processing of this glass system at the DWPF. A recommendation from the SRNL studies was the need for the DWPF Laboratory to establish a method to measure thorium by Inductively Coupled Plasma - Atomic Emission Spectroscopy (ICPAES). This recommendation led to the set of thorium-bearing glasses from the SB6 Variability Study (VS) being submitted to the DWPF Laboratory for chemical composition measurement. The measurements were conducted by the DWPF Laboratory using the sodium peroxide fusion preparation method routinely employed for analysis of samples from the Slurry Mix Evaporator (SME). These measurements are presented and reviewed in this report. The review indicates that the measurements provided by the DWPF Laboratory are comparable to those provided by Analytical Development's laboratory at SRNL for these same glasses. As a result, the authors of this report recommend that the DWPF Laboratory begin using its routine peroxide fusion dissolution method for the measurement of thorium in SME samples of SB6. The purpose of this technical report is to present the measurements generated by the DWPF Laboratory for the SB6 VS glasses and to compare the measurements to the targeted compositions for these VS glasses as well as to SRNL's measurements (both sets, targeted and measured, of compositional values were reported by SRNL in [2]). The goal of these comparisons is to provide information that will lead to the qualification of peroxide fusion dissolution as a method for the measurement by the DWPF Laboratory of thorium in SME glass samples.

Edwards, T.; Click, D.; Feller, M.

2011-02-28T23:59:59.000Z

217

Decommissioning of Ris's nuclear facilities. Descriptions and cost assessment.  

E-Print Network (OSTI)

nuclear facilities at Ris National Laboratory to be decommissioned and gives an assessment of the work to be done and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing for the longer decay periods; some operations still will need to be performed remotely. Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to be transferred to a Danish repository. ISBN 87-550-2844-6; 87-550-2846-2 (Internet)

Edited Kurt Lauridsen

2001-01-01T23:59:59.000Z

218

Facilities  

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

Facilities Facilities Facilities LANL's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. Contact Operator Los Alamos National Laboratory (505) 667-5061 Some LANL facilities are available to researchers at other laboratories, universities, and industry. Unique facilities foster experimental science, support LANL's security mission DARHT accelerator DARHT's electron accelerators use large, circular aluminum structures to create magnetic fields that focus and steer a stream of electrons down the length of the accelerator. Tremendous electrical energy is added along the way. When the stream of high-speed electrons exits the accelerator it is

219

Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)  

SciTech Connect

The compact (R0~1.2-1.3m) Fusion Nuclear Science Facility (FNSF) is aimed at providing a fully integrated, continuously driven fusion nuclear environment of copious fusion neutrons. This facility would be used to test, discover, understand, and innovate scientific and technical solutions for the challenges facing DEMO, by addressing the multi-scale synergistic interactions involving fusion plasma material interactions, tritium fuel cycle, power extraction, and the nuclear effects on materials. Such a facility properly designed would provide, initially at the JET-level plasma pressure (~30%T2) and conditions (e.g., Hot-Ion H-Mode), an outboard fusion neutron flux of 0.25 MW/m2 while requiring a fusion power of 19 MW. If and when this research operation is successful, its performance can be extended to 1 MW/m2 and 76 MW by reaching for twice the JET plasma pressure and Q. High-safety factor q and moderate- plasmas would minimize plasma-induced disruptions, helping to deliver reliably a neutron fluence of 1 MW-yr/m2 and a duty factor of 10% presently anticipated for the FNS research. Success of this research will depend on achieving time-efficient installation and replacement of all components using extensive remote handling (RH). This in turn requires modular designs for all internal components, including the single-turn toroidal field coil center-post with RH-compatible bi-directional sliding joints. Such device goals would further dictate placement of support structures and vacuum seal welds behind the internal and shielding components. If these further goals could be achieved, the FNSF would provide a ready upgrade path to the Component Test Facility (CTF), which would aim to test, at higher neutron fluence and duty cycle, the demanding fusion nuclear engineering and technologies for DEMO. This FNSF-CTF strategy would be complementary to the ITER and the Broader Approach programs, and thereby help mitigate the risks of an aggressive world fusion DEMO R&D Program. The key physics and technology research needed in the next decade to manage the potential risks of this FNSF are identified.

Peng, Yueng Kay Martin [ORNL

2010-01-01T23:59:59.000Z

220

Nuclear Physics User Facilities | U.S. DOE Office of Science (SC)  

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

NP User Facilities NP User Facilities User Facilities ASCR User Facilities BES User Facilities BER User Facilities FES User Facilities HEP User Facilities NP User Facilities User Facilities Frequently Asked Questions User Facility Science Highlights Contact Information Office of Science U.S. Department of Energy 1000 Independence Ave., SW Washington, DC 20585 P: (202) 586-5430 NP User Facilities Print Text Size: A A A RSS Feeds FeedbackShare Page The Nuclear Physics program supports the operation of the following national scientific user facilities: Relativistic Heavy Ion Collider (RHIC): External link RHIC at Brookhaven National Laboratory External link is a world-class scientific research facility that began operation in 2000, following 10 years of development and construction. Hundreds of physicists from around

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Methodology for Final Hazard Categorization for Nuclear Facilities from Category 3 to Radiological  

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

Office of Nuclear and Facility Safety Policy Office of Nuclear and Facility Safety Policy Nuclear Safety Technical Position NSTP 2002-2 Methodology for Final Hazard Categorization for Nuclear Facilities from Category 3 to Radiological Issue: DOE-STD-1027-92 defines a lower threshold criterion for preliminary hazard categorization as a nuclear Hazard Category 3 (HC-3) facility or activity. But it does not provide a method other than inventory reduction or segmentation on how an HC-3 facility or activity can be demonstrated to be below HC-3 (i.e., radiological) in final hazard categorization. Background: 10 CFR 830 Subpart B requires that all DOE nuclear facilities categorized as HC-3 or above have a DOE approved safety basis compliant with the requirements of Subpart B. The rule requires the use of DOE-

222

The Association between Cancers and Low Level Radiation: an evaluation of the epidemiological evidence at the Hanford Nuclear Weapons Facility  

E-Print Network (OSTI)

and Rocky Flats Nuclear Weapons Plant. Rad Res 1989;120:19-Evidence at the Hanford Nuclear Weapons Facility MASTERAT T H E HANFORD NUCLEAR WEAPONS FACILITY JULIE BRITTON

Britton, Julie

2010-01-01T23:59:59.000Z

223

Modeling and analysis of a heat transport transient test facility for space nuclear systems.  

E-Print Network (OSTI)

??The purpose of this thesis is to design a robust test facility for a small space nuclear power system and model its physical behavior under (more)

[No author

2013-01-01T23:59:59.000Z

224

Site selection and assessment for a nuclear storage facility  

SciTech Connect

We investigate the structure and accuracy of the decision making process in finding an optimal location for stored nuclear materials for 25-50 years. Using a well-documented facility design, benefit hierarchy is set up for different sites to rank a given site for different options. Criteria involve safeguards standards, technical viability, environmental effects, economics, political impact, and public acceptance. Problem faced here is multi-criterion decision making. Two approaches are investigated: analytic hierarchy process (AHP) of Saaty, and fuzzy logic approach of Yager. Whereas AHP requires a pairwise comparison of criteria and pairwise comparison of alternatives, in Yager`s approach each alternative is considered independently, allowing one to extend the analysis without performing time-consuming computation.

Rutherford, D.A.; Zardecki, A.

1996-09-01T23:59:59.000Z

225

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

226

Author's personal copy Cost analysis of the US spent nuclear fuel reprocessing facility  

E-Print Network (OSTI)

Types of Nuclear Facilities, from 2001 to 2050 62 Figure 13. Decommissioning Schedule of Power PlantsThe Potential for a Nuclear Renaissance: The Development of Nuclear Power Under Climate Change to the Engineering Systems Division and the Department of Nuclear Science and Engineering in Partial Fulfillment

Deinert, Mark

227

Facilities and Programs, Experimental Resources for Nuclear Data...  

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

Nuclear Laboratory U University of California Davis - Crocker Nuclear Laboratory University of Kentucky Lexington - Low Energy Nuclear Physics University of Maryland -...

228

Mission and Readiness Assessment for Fusion Nuclear Facilities  

SciTech Connect

Magnetic fusion development toward DEMO will most likely require a number of fusion nuclear facilities (FNF), intermediate between ITER and DEMO, to test and validate plasma and nuclear technologies and to advance the level of system integration. The FNF mission space is wide, ranging from basic materials research to net electricity demonstration, so there is correspondingly a choice among machine options, scope, and risk in planning such a step. Readiness requirements to proceed with a DEMO are examined, and two FNF options are assessed in terms of the contributions they would make to closing DEMO readiness gaps, and their readiness to themselves proceed with engineering design about ten years from now. An advanced tokamak (AT) pilot plant with superconducting coils and a mission to demonstrate net electricity generation would go a long way toward DEMO. As a next step, however, a pilot plant would entail greater risk than a copper-coil FNSF-AT with its more focussed mission and technology requirements. The stellarator path to DEMO is briefly discussed. Regardless of the choice of FNF option, an accompanying science and technology development program, also aimed at DEMO readiness, is absolutely essential.

G.H. Neilson, et. al.

2012-12-12T23:59:59.000Z

229

Plan for Defense Nuclear Facilities Safety Board Recommendation 2011-1, Safety Culture at the Waste  

E-Print Network (OSTI)

The purpose ofthis letter is to update you on Action 2-6 in the Department ofEnergy's Implementation

Pantex Plant; G N S. Podonsky

2012-01-01T23:59:59.000Z

230

Notices DEFENSE NUCLEAR FACILITIES SAFETY BOARD Draft Revised Strategic Plan for FY  

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

65979 Federal Register 65979 Federal Register / Vol. 78, No. 213 / Monday, November 4, 2013 / Notices hq.doe.gov, or by facsimile to 202-586- 8008. FOR FURTHER INFORMATION CONTACT: Lamont Jackson (Program Office) at 202-586-0808, or by email to Lamont.Jackson@hq.doe.gov. SUPPLEMENTARY INFORMATION: Exports of electricity from the United States to a foreign country are regulated by the Department of Energy (DOE) pursuant to sections 301(b) and 402(f) of the Department of Energy Organization Act (42 U.S.C. 7151(b), 7172(f)) and require authorization under section 202(e) of the Federal Power Act (16 U.S.C. 824a(e)). On February 19, 2009, DOE issued Order No. EA-145-D, which authorized Powerex to transmit electric energy from the United States to Mexico as a power marketer for a five-year term using

231

Analysis of the formation, expression, and economic impacts of risk perceptions associated with nuclear facilities  

SciTech Connect

This report investigates how communities hosting nuclear facilities form and express perceptions of risk and how these risk perceptions affect local economic development. Information was collected from site visits and interviews with plant personnel, officials of local and state agencies, and community activists in the hosting communities. Six commercial nuclear fuel production facilities and five nuclear facilities operated for the US Department of Energy by private contractors were chosen for analysis. The results presented in the report indicate that the nature of risk perceptions depends on a number of factors. These factors are (1) level of communication by plant officials within the local community, (2) track record of the facility. operator, (3) process through which community and state officials receive information and form opinions, (4) level of economic links each plant has with the local community, and (15) physical characteristics of the facility itself. This report finds that in the communities studied, adverse ask perceptions have not affected business location decisions, employment levels in the local community, tourism, or agricultural development. On the basis of case-study findings, this report recommends that nuclear facility siting programs take the following observations into account when addressing perceptions of risk. First, the quality of a facility`s participation with community activists, interest groups, and state agencies helps to determine the level of perceived risk within a community. Second, the development of strong economic links between nuclear facilities and their host communities will produce a higher level of acceptance of the nuclear facilities.

Allison, T.; Hunter, S.; Calzonetti, F.J.

1992-10-01T23:59:59.000Z

232

Review of the Los Alamos National Laoratory Nuclear Facility Coonfiguration Management Program - March 2012  

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

Nuclear Facility Nuclear Facility Configuration Management Program March 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2 4.0 Results ................................................................................................................................................... 2

233

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

234

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

235

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

236

Review of the Los Alamos National Laoratory Nuclear Facility Coonfiguration Management Program - March 2012  

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

Nuclear Facility Nuclear Facility Configuration Management Program March 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2 4.0 Results ................................................................................................................................................... 2

237

Facility Representative Program: 2001 Facility Representative Workshop  

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

1 Facility Representative Workshop 1 Facility Representative Workshop May 15 - 17, 2001 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Day 1: Tuesday, May 15, 2001 Theme: Program Successes and Challenges 8:00 a.m. - Logistics Announcements & Opening Remarks - Joe Arango, Facility Representative Program Manager 8:15 a.m. - Welcome - Debbie Monette, Assistant Manager for National Security, Nevada Operations Office 8:30 a.m. - Keynote Address - Ralph Erickson, National Nuclear Security Administration 9:00 a.m.- DOE Facility Representative of the Year Presentation - Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board 9:30 a.m. - Break 9:50 a.m. - Program Summary - Joe Arango 10:10 a.m. - Management Panel/Questions and Answers

238

Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program Issues and Strategy for Fusion Nuclear Science Facility (FNSF)  

E-Print Network (OSTI)

Need for Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program ­Issues and Strategy for Fusion Nuclear Science Facility (FNSF) ­Key R&D Areas to begin NOW (modeling 12, 2010 #12;Fusion Nuclear Science and Technology (FNST) FNST is the science engineering technology

Abdou, Mohamed

239

DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in  

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

DOE Offers Conditional Loan Guarantee for Front End Nuclear DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in Idaho DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in Idaho May 20, 2010 - 12:00am Addthis Washington, DC - As part of a broad effort to expand the use of nuclear power in the United States and reduce carbon pollution, U.S. Secretary of Energy Steven Chu announced today the Department's first conditional commitment for a front-end nuclear facility. The $2 billion loan guarantee will support AREVA's Eagle Rock Enrichment Facility near Idaho Falls, Idaho, which will supply uranium enrichment services for the U.S. nuclear power industry. "Increasing uranium enrichment in the United States is critical to the nation's energy and national security," said Secretary Chu. "Existing

240

DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in  

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

DOE Offers Conditional Loan Guarantee for Front End Nuclear DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in Idaho DOE Offers Conditional Loan Guarantee for Front End Nuclear Facility in Idaho May 20, 2010 - 12:00am Addthis Washington, DC - As part of a broad effort to expand the use of nuclear power in the United States and reduce carbon pollution, U.S. Secretary of Energy Steven Chu announced today the Department's first conditional commitment for a front-end nuclear facility. The $2 billion loan guarantee will support AREVA's Eagle Rock Enrichment Facility near Idaho Falls, Idaho, which will supply uranium enrichment services for the U.S. nuclear power industry. "Increasing uranium enrichment in the United States is critical to the nation's energy and national security," said Secretary Chu. "Existing

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 1. Executive summary  

Science Conference Proceedings (OSTI)

Nuclear byproducts are a major national resource that has yet to be incorporated into the economy. The current Defense Byproducts Program is designed to match specific military and commercial needs with the availability of valuable products which are currently treated as waste at considerable expense in waste management costs. This program plan focuses on a few specific areas with the greatest potential for near-term development and application. It also recognizes the need for a continuing effort to develop new applications for byproducts and to continue to assess the impacts on waste management. The entire program has been, and will continue to be structured so as to ensure the safety of the public and maintain the purity of the environment. Social and institutional concerns have been recognized and will be handled appropriately. A significant effort will be undertaken to inform the public of the benefits of byproduct use and of the care being taken to ensure safe, efficient operation.

None

1983-08-01T23:59:59.000Z

242

DOE-STD-1064-94; DOE Standard Guideline to Good Practices For Seasonal Facility Preservation at DOE Nuclear Facilities  

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

64-94 64-94 June 1994 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR SEASONAL FACILITY PRESERVATION AT DOE NUCLEAR FACILITIES U.S. Department of Energy Washington, D.C. 20585 AREA MNTY 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; (615) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield VA 22161; (703) 487-4650. Order No. DE94014954 DOE-STD-1064-94 FOREWORD The Guideline to Good Practices for Seasonal Facility Preservation at DOE Nuclear Facilities provides contractor maintenance organizations with information

243

Heat barrier for use in a nuclear reactor facility  

DOE Patents (OSTI)

A thermal barrier for use in a nuclear reactor facility is disclosed herein. Generally, the thermal barrier comprises a flexible, heat-resistant web mounted over the annular space between the reactor vessel and the guard vessel in order to prevent convection currents generated in the nitrogen atmosphere in this space from entering the relatively cooler atmosphere of the reactor cavity which surrounds these vessels. Preferably, the flexible web includes a blanket of heat-insulating material formed from fibers of a refractory material, such as alumina and silica, sandwiched between a heat-resistant, metallic cloth made from stainless steel wire. In use, the web is mounted between the upper edges of the guard vessel and the flange of a sealing ring which surrounds the reactor vessel with a sufficient enough slack to avoid being pulled taut as a result of thermal differential expansion between the two vessels. The flexible web replaces the rigid and relatively complicated structures employed in the prior art for insulating the reactor cavity from the convection currents generated between the reactor vessel and the guard vessel.

Keegan, Charles P. (South Huntingdon Twp., Westmoreland County, PA)

1988-01-01T23:59:59.000Z

244

A survey of decontamination processes applicable to DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The objective of this survey was to select an appropriate technology for in situ decontamination of equipment interiors as part of the decommissioning of U.S. Department of Energy nuclear facilities. This selection depends on knowledge of existing chemical decontamination methods. This report provides an up-to-date review of chemical decontamination methods. According to available information, aqueous systems are probably the most universally used method for decontaminating and cleaning metal surfaces. We have subdivided the technologies, on the basis of the types of chemical solvents, into acid, alkaline permanganate, highly oxidizing, peroxide, and miscellaneous systems. Two miscellaneous chemical decontamination methods (electrochemical processes and foam and gel systems) are also described. A concise technical description of various processes is given, and the report also outlines technical considerations in the choice of technologies, including decontamination effectiveness, waste handing, fields of application, and the advantages and limitations in application. On the basis of this survey, six processes were identified for further evaluation. 144 refs., 2 tabs.

Chen, L.; Chamberlain, D.B.; Conner, C.; Vandegrift, G.F.

1997-05-01T23:59:59.000Z

245

Incentives for the Department's Facility Representative Program,  

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

Incentives for the Department's Facility Representative Program, Incentives for the Department's Facility Representative Program, 12/17/1998 Incentives for the Department's Facility Representative Program, 12/17/1998 The Department's Revised Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 93-3 has once again underscored the Department's commitment to maintaining the technical capability necessary to safely manage and operate our defense nuclear facilities. Attracting and retaining highly qualified employees and placing them in our critical technical positions is vital to fi.dfilling this commitment. You have identified 95'% of your Facility Representative positions as critical technical positions. The Office of Field Management has noted a 12'?40annual attrition rate of Facility Representatives from the Facility

246

Property exempt from taxation: nuclear generation facility property...  

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

legislation would exempt from state property taxes any property purchased, constructed or installed to expand capacity at an existing nuclear plant or to build a new nuclear plant....

247

Nuclear diagnostics for the National Ignition Facility ,,invited... Thomas J. Murphy,a)  

E-Print Network (OSTI)

Nuclear diagnostics for the National Ignition Facility ,,invited... Thomas J. Murphy,a) Cris W unprecedented opportunities for the use of nuclear diagnostics in inertial confinement fusion experiments to produce up to 1019 DT neutrons. In addition to a basic set of nuclear diagnostics based on previous

248

Preliminary Nuclear Calculations for the Shield Test Facility  

SciTech Connect

To find the critical size of the proposed shield test facility based upon available data and present construction concepts.

Baucom, H.H.

1960-01-11T23:59:59.000Z

249

Facility Representative Program: 2003 Facility Representative Workshop  

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

3 Facility Representative Workshop 3 Facility Representative Workshop May 13 - 15, 2003 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Day 1: Tuesday, May 13, 2003 Theme: Program Successes and Challenges 8:00 a.m. John Evans, Facility Representative Program Manager 8:15 a.m. Welcome Kathleen Carlson Manager, Nevada Site Office 8:30 a.m. Keynote Address Savannah River Site and Facility Reps - A Shared History and Common Future Jeffrey M. Allison Manager, Savannah River Operations Office 9:00 a.m. Videotaped Remarks from the Deputy Secretary Kyle E. McSlarrow, Deputy Secretary of Energy 9:10 a.m. Facility Representative of the Year Presentation Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board

250

EM Issues Amended Decision to Expand Use of Nuclear Facility | Department  

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

Issues Amended Decision to Expand Use of Nuclear Facility Issues Amended Decision to Expand Use of Nuclear Facility EM Issues Amended Decision to Expand Use of Nuclear Facility April 1, 2013 - 12:00pm Addthis H-Canyon at Savannah River Site. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains process vessels. H-Canyon at Savannah River Site. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains process vessels. AIKEN, S.C. - EM issued an amended Record of Decision (ROD) to the Savannah River Site (SRS) Spent Nuclear Fuel Environmental Impact Statement to expand the operations of the H-Canyon Facility at SRS to support a major nuclear non-proliferation goal and save taxpayer dollars. DOE recently signed a contract allowing Atomic Energy of Canada Limited

251

EM Issues Amended Decision to Expand Use of Nuclear Facility | Department  

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

EM Issues Amended Decision to Expand Use of Nuclear Facility EM Issues Amended Decision to Expand Use of Nuclear Facility EM Issues Amended Decision to Expand Use of Nuclear Facility April 1, 2013 - 12:00pm Addthis H-Canyon at Savannah River Site. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains process vessels. H-Canyon at Savannah River Site. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains process vessels. AIKEN, S.C. - EM issued an amended Record of Decision (ROD) to the Savannah River Site (SRS) Spent Nuclear Fuel Environmental Impact Statement to expand the operations of the H-Canyon Facility at SRS to support a major nuclear non-proliferation goal and save taxpayer dollars. DOE recently signed a contract allowing Atomic Energy of Canada Limited

252

Microsoft Word - Defense Science Quarterly Nov 2007 final.doc  

National Nuclear Security Administration (NNSA)

November 2007 November 2007 Dr. Brad Wallin Dr. Robert Hanrahan Defense Science Quarterly Inside This Issue 1 Message from the Director 2 Contributions of the Los Alamos Proton Radiography Program to the Nuclear Weapons Program 4 Contributions of the Los Alamos Weapons Neutron Research Facility Programs to the Nuclear Weapons Program 5 Cross-cutting Science: Materials in Extreme Environments 7 Academic Outreach: The Stewardship Science Academic Alliances Program 10 Z Refurbishment Project Wraps Up 11 Publication Highlights Chris Deeney, Director, Office of Defense Science Thank you for another exciting quarter in the Science Campaign. We recently visited Los Alamos and Sandia National Laboratories to conduct a technical review, and

253

National Nuclear Security Administration Supplemental Listing...  

National Nuclear Security Administration (NNSA)

the Defense Nuclear Facilities Safety Board NA-SH-10 DOE G 151.1-1A Emergency Management Fundamentals and the Operational Emergency Base Program NA-SH-10 DOE G 151.1-2 Technical...

254

DOE Issues Landmark Rule for Risk Insurance for Advanced Nuclear Facilities  

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

Landmark Rule for Risk Insurance for Advanced Nuclear Landmark Rule for Risk Insurance for Advanced Nuclear Facilities DOE Issues Landmark Rule for Risk Insurance for Advanced Nuclear Facilities May 8, 2006 - 10:36am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) issued on Saturday, the interim final rule required by the Energy Policy Act of 2005 (EPACT) for risk insurance to facilitate construction of new advanced nuclear power facilities. The rule establishes the requirements for risk insurance to cover costs associated with certain regulatory or litigation-related delays in the start-up of new nuclear power plants. The resurgence of nuclear power is a key component of President Bush's Advanced Energy Initiative. The Standby Support provisions of EPACT (section 638), also referred to as federal risk insurance, authorize the Secretary of Energy to enter into

255

Adjusting External Doses from the ORNL and Y-12 Facilities for the Oak Ridge Nuclear Facilities Mortality Study  

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

Adjusting External Doses from the ORNL and Y-12 Adjusting External Doses from the ORNL and Y-12 Facilities for the Oak Ridge Nuclear Facilities Mortality Study A Supplemental Report to Data Collection, Validation, and Description for the Oak Ridge Nuclear Facilities Mortality Study J. P. Watkins (1), D. L. Cragle (1), E. L. Frome (2), C. M. West (1), D. J. Crawford- Brown (3), and W. G. Tankersley (1) (1) Oak Ridge Institute for Science and Education, Environmental and Health Sciences Division, Center for Epidemiologic Research, Oak Ridge, TN 37831-0117. (2) Oak Ridge National Laboratory, Oak Ridge, TN 37830. (3) School of Public Health, University of North Carolina, Chapel Hill, NC 27599-7400. This report concerns work undertaken as part of the Health and Mortality Study of Department of

256

Facility Operations and User Support | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Above image: Red Storm supercomputer at Sandia National LaboratoriesNew Mexico. (Sandia National Laboratories) This sub-program provides both necessary physical facility and...

257

Review of the Los Alamos National Laoratory Nuclear Facility...  

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

facility configuration management (CM) program in conjunction with a Los Alamos Site Office (LASO) scheduled assessment. Field activities focused on review of the generation and...

258

Safeguards-by-Design: Early Integration of Physical Protection and Safeguardability into Design of Nuclear Facilities  

Science Conference Proceedings (OSTI)

The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to minimize proliferation and security risks as the use of nuclear energy expands worldwide. This paper defines a generic SBD process and its incorporation from early design phases into existing design / construction processes and develops a framework that can guide its institutionalization. SBD could be a basis for a new international norm and standard process for nuclear facility design. This work is part of the U.S. DOEs Next Generation Safeguards Initiative (NGSI), and is jointly sponsored by the Offices of Non-proliferation and Nuclear Energy.

T. Bjornard; R. Bean; S. DeMuth; P. Durst; M. Ehinger; M. Golay; D. Hebditch; J. Hockert; J. Morgan

2009-09-01T23:59:59.000Z

259

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes  

Science Conference Proceedings (OSTI)

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

260

Omega Laser Facility Completes Record 25,000 Experiments | National Nuclear  

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

Omega Laser Facility Completes Record 25,000 Experiments | National Nuclear Omega Laser Facility Completes Record 25,000 Experiments | 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 > Media Room > Press Releases > Omega Laser Facility Completes Record 25,000 Experiments Press Release Omega Laser Facility Completes Record 25,000 Experiments Nov 5, 2013

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities  

Science Conference Proceedings (OSTI)

This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

MITCHELL, R.M.

2000-09-28T23:59:59.000Z

262

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,

263

Facility Representative Program: 2007 Facility Representative Workshop  

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

7 Facility Representative Workshop 7 Facility Representative Workshop May 15 - 17, 2007 Las Vegas, NV Facility Rep of the Year Award | Attendees list | Summary Report [PDF] WORKSHOP AGENDA Final Day 1: Tuesday, May 15, 2007 8:00 a.m. Opening Remarks Joanne Lorence, Facility Representative Program Manager 8:15 a.m. Welcome from the Nevada Site Office Gerald Talbot, Manager, Nevada Site Office 8:30 a.m. Videotaped Remarks from the Deputy Secretary The Honorable Clay Sell, Deputy Secretary of Energy 8:45 a.m. Keynote Address - Safety Oversight Perspective and Expectations Glenn Podonsky, Chief Health, Safety and Security Officer, Office of Health, Safety and Security 9:10 a.m. Facility Representative of the Year Presentation Mark B. Whitaker, Jr., Departmental Representative to the Defense Nuclear Facilities Safety Board,

264

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - NNSA Statement - November 24, 2009  

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

Defense Nuclear Facilities Safety Board Public Meeting on Defense Nuclear Facilities Safety Board Public Meeting on Oversight of Complex, High Hazard Nuclear Operations Statement of Garrett Harencak, BRIG GEN, USAF Principal Assistant Deputy Administrator for Military Application Office of Defense Programs November 24, 2009 Good Morning, Mr. Vice-Chairman. I appreciate the opportunity to speak to the Board this morning regarding the Defense Programs approach to ensuring the safe management and operation of the nuclear security enterprise. Defense Programs Safety Approach and Safety Philosophy Consistent with the rest of the Department of Energy, the foundation of Defense Program's safety philosophy is Integrated Safety Management (ISM). Defense Programs and its Management and Operating Contractors continue to mature their implementation of ISM.

265

Facilities  

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

Environment Feature Stories Public Reading Room: Environmental Documents, Reports LANL Home Phonebook Calendar Video About Operational Excellence Facilities Facilities...

266

The development of coal-based technologies for Department of Defense facilities. Technical progress report, September 1995 - March 1996  

Science Conference Proceedings (OSTI)

The U.S. Department of Defense (DOD), through an Interagency Agreement with the U.S. Department of Energy (DOE), has initiated a three-phase program with the Consortium for Coal-Water Slurry Fuel Technology, with the aim of decreasing DOD`s reliance on imported oil by increasing its use of coal. The program is being conducted as a cooperative agreement between the Consortium and DOE. Activities this reporting period are summarized by phase. During this reporting period, the Phase I final report was completed. Work in Phase II focused on emissions reductions, coal beneficiation/preparation studies, and economic analyses of coal use. Emissions reductions investigations included completing a study to identify appropriate SO{sub 2} and NO{sub x} control technologies for coal-fired industrial boilers. In addition, work continued on the design of a ceramic filtering device for installation on the demonstration boiler. The ceramic filtering device will be used to demonstrate a smaller and more efficient filtering device for retrofit applications. Work related to coal preparation and utilization, and the economic analysis was primarily focused on preparing the final report. Work in Phase III focused on coal preparation studies and economic analyses of coal use. Coal preparation studies were focused on continuing activities on particle size control, physical separations, surface-based separation processes, and dry processing. The economic study focused on community sensitivity to coal usage, regional economic impacts of new coal utilization technologies, and constructing a national energy portfolio.

Miller, B.G.; Pisupati, S.V.; Scaroni, A.W. [and others

1996-10-01T23:59:59.000Z

267

Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants  

Science Conference Proceedings (OSTI)

This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called Safeguards-by-Design. This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials, published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a legal document. As such, it is written in a legalese that is understood by specialists in international law and treaties, but not by most outside of this field, including designers of nuclear facilities. For this reason, many of the requirements have been simplified and restated. However, in all cases, the relevant source document and passage is noted so that readers may trace the requirement to the source. This is a helpful living guide, since some of these requirements are subject to revision over time. More importantly, the practices by which the requirements are met are continuously modernized by the IAEA and nuclear facility operators to improve not only the effectiveness of international nuclear safeguards, but also the efficiency. As these improvements are made, the following guidelines should be updated and revised accordingly.

Robert Bean; Casey Durst

2009-10-01T23:59:59.000Z

268

Area Students Explore SRS Nuclear Facilities during National ...  

Principal Media Contact: DT Townsend Savannah River Nuclear Solutions, LLC 803.952.7566 dt-lawrence.townsend@srs.gov DOE Media Contact: Bill Taylor

269

Rules and Directives applicable to Nuclear Facilities Oversight  

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

G 231.1-1 DOE G 231.1-2 Occurrence Reporting and Processing of Operations Information ORPS Performance Analysis Guide ORPS Causal Analysis Guide Facility Representatives and line...

270

Spent nuclear fuel project cold vacuum drying facility operations manual  

SciTech Connect

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

1999-05-12T23:59:59.000Z

271

Mission and Readiness Assessment for Fusion Nuclear Facilities  

Science Conference Proceedings (OSTI)

DEMO and Next-Step Facilities / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012

G. H. Neilson et al.

272

Guideline to good practices for types of maintenance activities at DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The purpose of the Guideline to Good Practices for Types of Maintenance at DOE Nuclear Facilities is to provide contractor maintenance organizations with information that may be used for the development and implementation of a properly balanced corrective, preventive and predictive maintenance program at DOE nuclear facilities. This document is intended to be an example guideline for the implementation of DOE Order 4330.4A, Maintenance Management Program, Chapter II, Element 4. DOE contractors should not feel obligated to adopt all parts of this guide. Rather, they should use the information contained herein as a guide for developing maintenance programs that are applicable to their facility.

Not Available

1993-03-01T23:59:59.000Z

273

REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS  

Science Conference Proceedings (OSTI)

Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEAs Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facilitys general character, purpose, capacity, and location; (2) Description of the facilitys layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future. Consequently, the NNSA Office of International Regimes and Agreements (NA-243) sponsored a team of U.S. Department of Energy National Laboratory nuclear safeguards experts and technologists to conduct a workshop on methods and technologies for improving this activity, under the ASA-100 Advanced Safeguards Approaches Project. The workshop focused on reviewing and discussing the fundamental safeguards needs, and presented technology and/or methods that could potentially address those needs more effectively and efficiently. Conclusions and Recommendations for technology to enhance the performance of DIV inspections are presented by the workshop team.

Richard Metcalf; Robert Bean

2009-10-01T23:59:59.000Z

274

Defense waste transportation: cost and logistics studies  

SciTech Connect

Transportation of nuclear wastes from defense programs is expected to significantly increase in the 1980s and 1990s as permanent waste disposal facilities come into operation. This report uses models of the defense waste transportation system to quantify potential transportation requirements for treated and untreated contact-handled transuranic (CH-TRU) wastes and high-level defense wastes (HLDW). Alternative waste management strategies in repository siting, waste retrieval and treatment, treatment facility siting, waste packaging and transportation system configurations were examined to determine their effect on transportation cost and hardware requirements. All cost estimates used 1980 costs. No adjustments were made for future changes in these costs relative to inflation. All costs are reported in 1980 dollars. If a single repository is used for defense wastes, transportation costs for CH-TRU waste currently in surface storage and similar wastes expected to be generated by the year 2000 were estimated to be 109 million dollars. Recovery and transport of the larger buried volumes of CH-TRU waste will increase CH-TRU waste transportation costs by a factor of 70. Emphasis of truck transportation and siting of multiple repositories would reduce CH-TRU transportation costs. Transportation of HLDW to repositories for 25 years beginning in 1997 is estimated to cost $229 M in 1980 costs and dollars. HLDW transportation costs could either increase or decrease with the selection of a final canister configuration. HLDW transportation costs are reduced when multiple repositories exist and emphasis is placed on truck transport.

Andrews, W.B.; Cole, B.M.; Engel, R.L.; Oylear, J.M.

1982-08-01T23:59:59.000Z

275

DOE-STD-1072-94; DOE Standard Guideline to Good Practices for Facility Condition Inspections at DOE Nuclear Facilities  

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

2-94 2-94 June 1994 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR FACILITY CONDITION INSPECTIONS AT DOE NUCLEAR FACILITIES U.S. Department of Energy Washington, D.C. 20585 AREA MNTY 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; (615) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 487-4650. Order No. DE94014948 DOE-STD-1072-94 iii FOREWORD The purpose of the Guideline to Good Practices for Facility Condition Inspections

276

DOE-STD-1067; DOE Standard Guideline to Good Practices for Maintenance Facilities, Equipment, and Tools at DOE Nuclear Facilities  

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

7-94 7-94 June 1994 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR MAINTENANCE FACILITIES, EQUIPMENT, AND TOOLS AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA MNTY 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; (615) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703)487-4650. Order No. DE94014952 DOE-STD-1067-94 FOREW ORD The Guideline to Good Practices for Maintenance Facilities, Equipment, and Tools at

277

U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility  

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

Energy, Oak Ridge Operations Office Nuclear Energy, 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)] U.S. Department of Energy, 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)] "This self-study guide provides an overview of safety basis terminology, requirements, and activities that are applicable to DOE and Oak Ridge Operations Office (ORO) nuclear facilities on the Oak Ridge Reservation. By completing this self-study guide, the reader will fulfill ORO Safety Basis Qualification Standard Competency 1, 2 (Part 1), or 7 (Part 1) and gain a familiarity level of knowledge regarding the following:

278

U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility  

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

U.S. Department of Energy, Oak Ridge Operations Office Nuclear U.S. Department of Energy, 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)] U.S. Department of Energy, 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)] "This self-study guide provides an overview of safety basis terminology, requirements, and activities that are applicable to DOE and Oak Ridge Operations Office (ORO) nuclear facilities on the Oak Ridge Reservation. By completing this self-study guide, the reader will fulfill ORO Safety Basis Qualification Standard Competency 1, 2 (Part 1), or 7 (Part 1) and gain a familiarity level of knowledge regarding the following:

279

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

280

NNS computing facility manual P-17 Neutron and Nuclear Science  

SciTech Connect

This document describes basic policies and provides information and examples on using the computing resources provided by P-17, the Neutron and Nuclear Science (NNS) group. Information on user accounts, getting help, network access, electronic mail, disk drives, tape drives, printers, batch processing software, XSYS hints, PC networking hints, and Mac networking hints is given.

Hoeberling, M.; Nelson, R.O.

1993-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Development of a safety assessment approach for decontamination and decommissioning operations at nuclear facilities  

SciTech Connect

The US Department of Energy (DOE) is responsible for nearly 1000 nuclear facilities which will eventually be decommissioned. In order to ensure that the health and safety of the workers, other personnel on site and the public in general is maintained during decontamination and decommissioning (D&D) operations, a methodology specifically for use in evaluating the nuclear safety of the associated activities is being developed within the Department. This methodology represents not so much a departure from that currently fish in the DOE when conducting safety assessments of operations at nuclear facilities but, rather, a formalization of those methods specifically adapted to the D&D activities. As such, it is intended to provide the safety assessment personnel with a framework on which they can base their technical judgement, to assure a consistent approach to safety assessment of D&D operations and to facilitate the systematic collection of data from facilities in the post-operational part of the life cycle.

Worthington, P.R. [USDOE, Washington, DC (United States); Cowgill, M.G. [Brookhaven National Lab., Upton, NY (United States)

1994-12-31T23:59:59.000Z

282

SUBJECT: Guidance on Retention of Facility Representative Technical Competence during Reductions in Force, 4/21/1998  

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

The Departments Revised Implementation Plan (IP) for Defense Nuclear Facilities Safety Board Recommendation 93-3 renews the Departments commitment to maintaining the technical capability...

283

Explosions and other uncontrolled chemical reactions at non-reactor nuclear facilities of the Savannah River Plant  

Science Conference Proceedings (OSTI)

This paper describes five energetic reactions (explosions) that have occurred at the Savannah River Plant non-reactor nuclear facilities. 1 fig.

Durant, W.S.; Gray, L.W.; Wallace, R.M.; Yau, W.W.F.

1988-01-01T23:59:59.000Z

284

DOE O 425.1D Admin Chg 1, Verification of Readiness to Start Up or Restart Nuclear Facilities  

Directives, Delegations, and Requirements

The order establishes requirements for verifying readiness for startup of new Hazard Category 1, 2, and 3 nuclear facilities, activities, and operations, and ...

2010-04-16T23:59:59.000Z

285

Decommissioning of the Nuclear Licensed Facilities at the Fontenay aux Roses CEA Center  

SciTech Connect

This is a summary of the program for the decommissioning of all the CEA's facilities in Fontenay aux Roses. The particularity of this center is that it is located in a built-up area. Taking into account the particularities of the various buildings and the levels of radioactivity in them, it was possible to devise a coherent, optimized program for the CEA-FAR licensed nuclear facility decommissioning operations.

Jeanjacques, Michel; Piketty, Laurence; Mandard, Lionel; Pedron, Guy; Boissonneau, Jean Francois; Fouquereau, Alain; Pichereau, Eric; Lethuaire, Nathalie; Estivie, David; Binet, Cedric; Meden, Igor [Commissariat a l'Energie Atomique, Direction de l'Energie Nucleaire, Direction deleguee des Activites Nucleaires de Saclay, Departement des Reacteurs et des Services Nucleaires, Service d'Assainissement de Fontenay Aux Roses : 18, route du Panorama, BP6, 92265 Fontenay aux Roses Cedex (France)

2008-01-15T23:59:59.000Z

286

Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices  

Science Conference Proceedings (OSTI)

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

NONE

1995-12-01T23:59:59.000Z

287

Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project  

SciTech Connect

This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts. The model will be used to assess the present-day composite distribution for seismic sources along with their characterization in the CEUS and uncertainty. In addition, this model is in a form suitable for use in PSHA evaluations for regulatory activities, such as Early Site Permit (ESPs) and Combined Operating License Applications (COLAs). Applications, Values, and Use Development of a regional CEUS seismic source model will provide value to those who (1) have submitted an ESP or COLA for Nuclear Regulatory Commission (NRC) review before 2011; (2) will submit an ESP or COLA for NRC review after 2011; (3) must respond to safety issues resulting from NRC Generic Issue 199 (GI-199) for existing plants and (4) will prepare PSHAs to meet design and periodic review requirements for current and future nuclear facilities. This work replaces a previous study performed approximately 25 years ago. Since that study was completed, substantial work has been done to improve the understanding of seismic sources and their characterization in the CEUS. Thus, a new regional SSC model provides a consistent, stable basis for computing PSHA for a future time span. Use of a new SSC model reduces the risk of delays in new plant licensing due to more conservative interpretations in the existing and future literature. Perspective The purpose of this study, jointly sponsored by EPRI, the U.S. Department of Energy (DOE), and the NRC was to develop a new CEUS SSC model. The team assembled to accomplish this purpose was composed of distinguished subject matter experts from industry, government, and academia. The resulting model is unique, and because this project has solicited input from the present-day larger technical community, it is not likely that there will be a need for significant revision for a number of years. See also Sponsors Perspective for more details. The goal of this project was to implement the CEUS SSC work plan for developing a regional CEUS SSC model. The work plan, formulated by the project manager and a

Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia (Tish) P. Tuttle

2012-01-31T23:59:59.000Z

288

Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project  

Science Conference Proceedings (OSTI)

This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts. The model will be used to assess the present-day composite distribution for seismic sources along with their characterization in the CEUS and uncertainty. In addition, this model is in a form suitable for use in PSHA evaluations for regulatory activities, such as Early Site Permit (ESPs) and Combined Operating License Applications (COLAs). Applications, Values, and Use Development of a regional CEUS seismic source model will provide value to those who (1) have submitted an ESP or COLA for Nuclear Regulatory Commission (NRC) review before 2011; (2) will submit an ESP or COLA for NRC review after 2011; (3) must respond to safety issues resulting from NRC Generic Issue 199 (GI-199) for existing plants and (4) will prepare PSHAs to meet design and periodic review requirements for current and future nuclear facilities. This work replaces a previous study performed approximately 25 years ago. Since that study was completed, substantial work has been done to improve the understanding of seismic sources and their characterization in the CEUS. Thus, a new regional SSC model provides a consistent, stable basis for computing PSHA for a future time span. Use of a new SSC model reduces the risk of delays in new plant licensing due to more conservative interpretations in the existing and future literature. Perspective The purpose of this study, jointly sponsored by EPRI, the U.S. Department of Energy (DOE), and the NRC was to develop a new CEUS SSC model. The team assembled to accomplish this purpose was composed of distinguished subject matter experts from industry, government, and academia. The resulting model is unique, and because this project has solicited input from the present-day larger technical community, it is not likely that there will be a need for significant revision for a number of years. See also Sponsors Perspective for more details. The goal of this project was to implement the CEUS SSC work plan for developing a regional CEUS SSC model. The work plan, formulated by the project manager and a

Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia (Tish) P. Tuttle

2012-01-31T23:59:59.000Z

289

Fusion Nuclear Science and Technology (FNST)Fusion Nuclear Science and Technology (FNST) Challenges and Facilities  

E-Print Network (OSTI)

Fusion Nuclear Science and Technology (FNST)Fusion Nuclear Science and Technology (FNST) Challenges these issues. 2 #12;FNST is the science, engineering, technology and materials Fusion Nuclear Science & Technology (FNST) FNST is the science, engineering, technology and materials for the fusion nuclear

Abdou, Mohamed

290

Determination of Solar Energy Transition Potential of Large Organizations| An Application to Department of Defense Facilities and Non-Tactical Vehicles.  

E-Print Network (OSTI)

?? The Department of Defense offers a great opportunity to implement solar energy solutions across its United States bases. It is the single largest energy (more)

Castillo, Ariel S.

2011-01-01T23:59:59.000Z

291

A comparative study of worker and general public risks from nuclear facility operation using MACCS2  

Science Conference Proceedings (OSTI)

Over the last five years, the US Department of Energy (DOE) has attempted to establish quantitative risk indices as minimum acceptance criteria for assurance of safe operation of its nuclear facilities. The risk indices serve as aiming points or targets to include consideration of all aspects of operation including normal conditions as well as abnormal, design basis events, and beyond-design basis events. Although initial focus of the application of these safety targets had been on DOE`s reactors, more recent assessments have also considered non-reactor facilities including those encompassing storage and nuclear processing activities. Regardless of the facility`s primary function, accident progression, event tree/fault tree logic models, and probabilistic (dose) consequence assessment model must be implemented to yield a fully integrated analysis of facility operation. The primary tool for probabilistic consequence assessment in the US is the MELCOR Accident Consequence Code System (MACCS). In this study, two version of MACCS are applied to representative source terms developed in the safety analysis associated with a waste processing facility at the Westinghouse Savannah River Company`s (WSRC`s) Savannah River Site (SRS). The MACCS versions are used to estimate population dose and subsequent health effects to workers and the general public from the SRS referenced facility operation. When combined with the frequency of occurrence evaluation, the margin of compliance with the safety targets may be quantified.

East, J.M.; O`Kula, K.R.

1994-10-01T23:59:59.000Z

292

Evaluation of natural phenomena hazards as part of safety assessments for nuclear facilities  

Science Conference Proceedings (OSTI)

The continued operation of existing US Department of Energy (DOE) nuclear facilities and laboratories requires a safety reassessment based on current criteria and guidelines. This also includes evaluations for the effects of Natural Phenomena Hazards (NPH), for which these facilities may not have been designed. The NPH evaluations follow the requirements of DOE Order 5480.28, Natural Phenomena Hazards Mitigation (1993) which establishes NPH Performance Categories (PCs) for DOE facilities and associated target probabilistic performance goals. These goals are expressed as the mean annual probability of exceedance of acceptable behavior for structures, systems and components (SSCs) subjected to NPH effects. The assignment of an NPH Performance Category is based on the overall hazard categorization (low, moderate, high) of a facility and on the function of an SSC under evaluation (DOE-STD-1021, 1992). Detailed guidance for the NPH analysis and evaluation criteria are also provided (DOE-STD-1020, 1994). These analyses can be very resource intensive, and may not be necessary for the evaluation of all SSCs in existing facilities, in particular for low hazard category facilities. An approach relying heavily on screening inspections, engineering judgment and use of NPH experience data (S. J. Eder et al., 1993), can minimize the analytical effort, give reasonable estimates of the NPH susceptibilities, and yield adequate information for an overall safety evaluation of the facility. In the following sections this approach is described in more detail and is illustrated by an application to a nuclear laboratory complex.

Kot, C.A.; Hsieh, B.J.; Srinivasan, M.G.; Shin, Y.W.

1995-02-01T23:59:59.000Z

293

An Overview of Facilities and Capabilities to Support the Development of Nuclear Thermal Propulsion  

DOE Green Energy (OSTI)

Abstract. The future of American space exploration depends on the ability to rapidly and economically access locations of interest throughout the solar system. There is a large body of work (both in the US and the Former Soviet Union) that show that Nuclear Thermal Propulsion (NTP) is the most technically mature, advanced propulsion system that can enable this rapid and economical access by its ability to provide a step increase above what is a feasible using a traditional chemical rocket system. For an NTP system to be deployed, the earlier measurements and recent predictions of the performance of the fuel and the reactor system need to be confirmed experimentally prior to launch. Major fuel and reactor system issues to be addressed include fuel performance at temperature, hydrogen compatibility, fission product retention, and restart capability. The prime issue to be addressed for reactor system performance testing involves finding an affordable and environmentally acceptable method to test a range of engine sizes using a combination of nuclear and non-nuclear test facilities. This paper provides an assessment of some of the capabilities and facilities that are available or will be needed to develop and test the nuclear fuel, and reactor components. It will also address briefly options to take advantage of the greatly improvement in computation/simulation and materials processing capabilities that would contribute to making the development of an NTP system more affordable. Keywords: Nuclear Thermal Propulsion (NTP), Fuel fabrication, nuclear testing, test facilities.

James Werner; Sam Bhattacharyya; Mike Houts

2011-02-01T23:59:59.000Z

294

RADIOACTIVE MATERIALS LABORATORY SAFETY REPORT, MARTIN NUCLEAR FACILITY, QUEHANNA SITE  

SciTech Connect

A description is given of the safety features and the major alterations to be performed prior to occupancy. The evaluation was made in support of fubrication work on the production of safe isotopic power sources from Cm/sup 242/ and Sr/sup 90/. The chemical, nuclear, and radiobiological properties of Cm/sup 242/ and Sr/sup 90/ are outlined. The projected physical fiow of materials for production of the isotopic power souroes is schematically given. An evaluation of the malfunctions, operational hazards, and remedial health physics procedures is presented. The analysis and evaluation of postulated maximum credible incidents are demonstrated. (B.O.G.)

1960-09-01T23:59:59.000Z

295

Guidelines for job and task analysis for DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The guidelines are intended to be responsive to the need for information on methodology, procedures, content, and use of job and task analysis since the establishment of a requirement for position task analysis for Category A reactors in DOE 5480.1A, Chapter VI. The guide describes the general approach and methods currently being utilized in the nuclear industry and by several DOE contractors for the conduct of job and task analysis and applications to the development of training programs or evaluation of existing programs. In addition other applications for job and task analysis are described including: operating procedures development, personnel management, system design, communications, and human performance predictions.

Not Available

1983-06-01T23:59:59.000Z

296

National Nuclear Security Administration  

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

Wnchington, DC 20585 Wnchington, DC 20585 July 13, 2010 OFFICE O F THE ADMINISTRATOR 'l'he Honorable Peter S. Winokur Chairman Defense Nuclear Facilities Safety Board 625 Indiana Avenue, NW, Suite 700 Washington, D.C. 20004 [>ear Mr. Chairman: By the direction of the Secretary of Energy, the enclosed is the Department's Implementation Plan (Plan) for Defense Nuclear Facilities Safety Board (Board) Recommendation 2009-2, Los Alamos Nutional Luhorutory Plutoniu?lt Fucilitj. Sr i s m ic Sufety. The Plan provides the Department's approach for implementing near-term actions to reduce the consequences of seismically-induced events at the Los Alamos National Laboratory Plutonium Facility, and longer-tcrm actions to ensure continued safe operation of the facility. Mr. James .I. McConnell. Assistant Deputy Administrator for Nuclear Safety and

297

Atmospheric Dispersion and Consequence Analysis at Sandia's TA-V Nuclear Facilities  

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

Atmospheric Dispersion and Atmospheric Dispersion and Consequence Analysis at Sandia's TA-V Nuclear Facilities Jim Dahl Manager, Nuclear Safety Analysis Sandia National Laboratories Office: 505-284-9067 Email: jjdahl@sandia.gov SAND2012-4478P Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. 2 Dispersion and Consequence Analysis at Sandia's TA-V Topics: * Site Characteristics * Dispersion Analysis Inputs - Meteorological Data - Stability Class - Dispersion Coefficients - Deposition Velocity

298

HALLAM NUCLEAR POWER FACILITY PREOPERATIONAL TEST COMPLETION REPORT, HOT SODIUM CIRCULATION TEST  

SciTech Connect

Tests were conducted to verify the adequacy of the design, construction, and components of the main heat transfer system of the Hallam Nuclear Power Facility (HNPF) for elevated-temperature and low-power operation. Tests revealed piping interferences, inoperative hangars, and valve difficulties. These discrepancies were rectified and rechecked. Detailed information concerning test results is included. (J.R.D.)

Shaw, P.F.; Johnson, L.L.

1962-07-01T23:59:59.000Z

299

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.

1993-11-01T23:59:59.000Z

300

Performance of a facility for measuring scintillator non-proportionality  

E-Print Network (OSTI)

Office of Defense Nuclear Nonproliferation, Officeof Nuclear Nonproliferation Research and Engineering (NA-22)

Choong, Woon-Seng

2008-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Guideline to good practices for control of maintenance activities at DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The purpose of the Guideline to Good Practices for Control of Maintenance Activities at DOE Nuclear Facilities is to provide contractor maintenance organizations with information that may be used for the development and implementation of a rigorously controlled maintenance program directed at achieving high quality work performance, personnel safety, radiological protection, operating equipment/system protection, and overall site safety and reliability at DOE nuclear facilities. This document is intended to be an example guideline for the implementation of DOE Order 4330.4A, Maintenance Management Program, Chapter II, Element 7. DOE contractors should not feel obligated to adopt all parts of this guide. Rather, they should use the information contained herein as a guide for developing maintenance programs that are applicable to their facility.

Not Available

1993-03-01T23:59:59.000Z

302

Guideline to good practices for planning, scheduling, and coordination of maintenance at DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The purpose of the Guideline to Good Practices for Planning, Scheduling, and Coordination of Maintenance at DOE Nuclear Facilities is to provide contractor maintenance organizations with information that may be used for the development and implementation of a rigorously controlled maintenance program directed at planning, scheduling, and coordinating work packages for maintenance tasks at DOE nuclear facilities. This document is intended to be an example guideline for the implementation of DOE Order 4330.4A, Maintenance Management Program, Chapter II, Element 6. DOE contractors should not feel obligated to adopt all parts of this guide. Rather, they should use the information contained herein as a guide for developing maintenance programs that are applicable to their facility.

Not Available

1993-03-01T23:59:59.000Z

303

Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall  

SciTech Connect

Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

Michael Kruzic

2007-09-01T23:59:59.000Z

304

MEASUREMENT AND CALCULATION OF RADIONUCLIDE ACTIVITIES IN SAVANNAH RIVER SITE HIGH LEVEL WASTE SLUDGE FOR ACCEPTANCE OF DEFENSE WASTE PROCESSING FACILITY GLASS IN A FEDERAL REPOSITORY  

SciTech Connect

This paper describes the results of the analyses of High Level Waste (HLW) sludge slurry samples and of the calculations necessary to decay the radionuclides to meet the reporting requirement in the Waste Acceptance Product Specifications (WAPS) [1]. The concentrations of 45 radionuclides were measured. The results of these analyses provide input for radioactive decay calculations used to project the radionuclide inventory at the specified index years, 2015 and 3115. This information is necessary to complete the Production Records at Savannah River Site's Defense Waste Processing Facility (DWPF) so that the final glass product resulting from Macrobatch 5 (MB5) can eventually be submitted to a Federal Repository. Five of the necessary input radionuclides for the decay calculations could not be measured directly due to their low concentrations and/or analytical interferences. These isotopes are Nb-93m, Pd-107, Cd-113m, Cs-135, and Cm-248. Methods for calculating these species from concentrations of appropriate other radionuclides will be discussed. Also the average age of the MB5 HLW had to be calculated from decay of Sr-90 in order to predict the initial concentration of Nb-93m. As a result of the measurements and calculations, thirty-one WAPS reportable radioactive isotopes were identified for MB5. The total activity of MB5 sludge solids will decrease from 1.6E+04 {micro}Ci (1 {micro}Ci = 3.7E+04 Bq) per gram of total solids in 2008 to 2.3E+01 {micro}Ci per gram of total solids in 3115, a decrease of approximately 700 fold. Finally, evidence will be given for the low observed concentrations of the radionuclides Tc-99, I-129, and Sm-151 in the HLW sludges. These radionuclides were reduced in the MB5 sludge slurry to a fraction of their expected production levels due to SRS processing conditions.

Bannochie, C; David Diprete, D; Ned Bibler, N

2008-12-31T23:59:59.000Z

305

Style, content and format guide for writing safety analysis documents. Volume 1, Safety analysis reports for DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The purpose of Volume 1 of this 4-volume style guide is to furnish guidelines on writing and publishing Safety Analysis Reports (SARs) for DOE nuclear facilities at Sandia National Laboratories. The scope of Volume 1 encompasses not only the general guidelines for writing and publishing, but also the prescribed topics/appendices contents along with examples from typical SARs for DOE nuclear facilities.

Not Available

1994-06-01T23:59:59.000Z

306

FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I  

SciTech Connect

The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios. (MOW)

Abdou, M.

1984-10-01T23:59:59.000Z

307

Risk Assessment Using The Homeland-Defense Operational Planning System (HOPS)  

DOE Green Energy (OSTI)

For over ten years, the Counterproliferation Analysis and Planning System (CAPS) at Lawrence Livermore National Laboratory (LLNL) has been a planning tool used by U.S. combatant commands for mission support planning against foreign programs engaged in the manufacture of weapons of mass destruction (WMD). CAPS is endorsed by the Secretary of Defense as the preferred counterproliferation tool to be used by the nation's armed services. A sister system, the Homeland-Defense Operational Planning System (HOPS), is a new operational planning tool leveraging CAPS expertise designed to support the defense of the U.S. homeland. HOPS provides planners with a basis to make decisions to protect against acts of terrorism, focusing on the defense of facilities critical to U.S. infrastructure. Criticality of facilities, structures, and systems is evaluated on a composite matrix of specific projected casualty, economic, and sociopolitical impact bins. Based on these criteria, significant unidentified vulnerabilities are identified and secured. To provide insight into potential successes by malevolent actors, HOPS analysts strive to base their efforts mainly on unclassified open-source data. However, more cooperation is needed between HOPS analysts and facility representatives to provide an advantage to those whose task is to defend these facilities. Evaluated facilities include: refineries, major ports, nuclear power plants and other nuclear licensees, dams, government installations, convention centers, sports stadiums, tourist venues, and public and freight transportation systems. A generalized summary of analyses of U.S. infrastructure facilities will be presented.

Durling, R L; Price, D E; Spero, K K

2005-06-06T23:59:59.000Z

308

Vulnerability And Risk Assessment Using The Homeland-Defense Operational Planning System (HOPS)  

DOE Green Energy (OSTI)

For over ten years, the Counterproliferation Analysis and Planning System (CAPS) at Lawrence Livermore National Laboratory (LLNL) has been a planning tool used by U.S. combatant commands for mission support planning against foreign programs engaged in the manufacture of weapons of mass destruction (WMD). CAPS is endorsed by the Secretary of Defense as the preferred counterproliferation tool to be used by the nation's armed services. A sister system, the Homeland-Defense Operational Planning System (HOPS), is a new operational planning tool leveraging CAPS expertise designed to support the defense of the U.S. homeland. HOPS provides planners with a basis to make decisions to protect against acts of terrorism, focusing on the defense of facilities critical to U.S. infrastructure. Criticality of facilities, structures, and systems is evaluated on a composite matrix of specific projected casualty, economic, and sociopolitical impact bins. Based on these criteria, significant unidentified vulnerabilities are identified and secured. To provide insight into potential successes by malevolent actors, HOPS analysts strive to base their efforts mainly on unclassified open-source data. However, more cooperation is needed between HOPS analysts and facility representatives to provide an advantage to those whose task is to defend these facilities. Evaluated facilities include: refineries, major ports, nuclear power plants and other nuclear licensees, dams, government installations, convention centers, sports stadiums, tourist venues, and public and freight transportation systems. A generalized summary of analyses of U.S. infrastructure facilities is presented.

Durling, Jr., R L; Price, D E; Spero, K K

2005-01-03T23:59:59.000Z

309

Project Hanford management contract quality assurance program implementation plan for nuclear facilities  

SciTech Connect

During transition from the Westinghouse Hanford Company (WHC) Management and Operations (M and O) contract to the Fluor Daniel Hanford (FDH) Management and Integration (M and I) contract, existing WHC policies, procedures, and manuals were reviewed to determine which to adopt on an interim basis. Both WHC-SP-1131,Hanford Quality Assurance Program and Implementation Plan, and WHC-CM-4-2, Quality Assurance Manual, were adopted; however, it was recognized that revisions were required to address the functions and responsibilities of the Project Hanford Management Contract (PHMC). This Quality Assurance Program Implementation Plan for Nuclear Facilities (HNF-SP-1228) supersedes the implementation portion of WHC-SP-1 13 1, Rev. 1. The revised Quality Assurance (QA) Program is documented in the Project Hanford Quality Assurance Program Description (QAPD), HNF-MP-599. That document replaces the QA Program in WHC-SP-1131, Rev. 1. The scope of this document is limited to documenting the nuclear facilities managed by FDH and its Major Subcontractors (MSCS) and the status of the implementation of 10 CFR 830.120, Quality Assurance Requirements, at those facilities. Since the QA Program for the nuclear facilities is now documented in the QAPD, future updates of the information provided in this plan will be by letter. The layout of this plan is similar to that of WHC-SP-1 13 1, Rev. 1. Sections 2.0 and 3.0 provide an overview of the Project Hanford QA Program. A list of Project Hanford nuclear facilities is provided in Section 4.0. Section 5.0 provides the status of facility compliance to 10 CFR 830.120. Sections 6.0, 7.0, and 8.0 provide requested exemptions, status of open items, and references, respectively. The four appendices correspond to the four projects that comprise Project Hanford.

Bibb, E.K.

1997-10-15T23:59:59.000Z

310

Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility  

Science Conference Proceedings (OSTI)

A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational time savings, and significantly improved ALARA exposure.

Dippre, M. A.

2003-02-25T23:59:59.000Z

311

Order Module--DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR FACILITY  

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

DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS Order Module--DOE-STD-1104-2009, REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS The familiar level of this module is divided into two sections that are intended to provide only an overview of the material contained in DOE-STD-1104-2009, which should be consulted for complete information. The first section covers the introduction, applicability, and chapters 1 and 2. The second section covers chapters 3, 4, and 5. We have provided examples throughout the module to help familiarize you with the material. The examples will also help prepare you for the practice at the end of this module and for the criterion test.

312

MORTALITY AMONG WORKERS AT THE SAVANNAH RIVER NUCLEAR FUELS PRODUCTION FACILITY  

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

MORTALITY AMONG WORKERS AT THE SAVANNAH RIVER NUCLEAR FUELS MORTALITY AMONG WORKERS AT THE SAVANNAH RIVER NUCLEAR FUELS PRODUCTION FACILITY Donna L. Cragle and Janice P. Watkins, Center for Epidemiologic Research; Kathryn Robertson-DeMers, Bechtel Hanford, Inc. Donna Cragle, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 Key Words: mortality study, radiation exposure, leukemia, occupational cohort, trend test INTRODUCTION Since 1952 the Savannah River Site (SRS), located in Aiken, South Carolina, has operated as a Department of Energy (DOE) production facility for nuclear fuels and other materials. A previous study 1 through 1980 of 9,860 white males employed at least 90 consecutive days at the SRS between 1952 and 1974 found an increased number of leukemia deaths among

313

Introduction to structural failure modes for nuclear power facilities  

SciTech Connect

This introduction provides a background of the evaluation methods for earthquakes larger than design basis. Seismic probabilistic risk assessment (SPRA) and seismic margin assessment (SMA) methods are introduced to the reader. The basic parameters used to define seismic capacity for each method are explained. The objectives of both evaluation methods and how they can be used to evaluate the adequacy of a seismic design are discussed. General issues related to computing seismic capacity are reviewed relative to SPRA and SMA. Four companion papers presented in the journal following this introduction discuss the types of information (i.e., dynamic tests, earthquake experience, and analytical data) that are used to determine the real capacity of structures and equipment in nuclear power plants to resist earthquakes. The motivation for discussing these three types of information is presented as an introduction to these papers that following in this journal edition. The purpose of the present paper is to lay the groundwork and provide motivation for these papers.

Reed, J.W. (Jack R. Benjamin and Associates, Inc., Mountain View, CA (United States)); Gurbuz, O. (Bechtel Corp., Norwalk, CA (United States))

1993-08-01T23:59:59.000Z

314

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual  

SciTech Connect

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

1999-07-02T23:59:59.000Z

315

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual  

Science Conference Proceedings (OSTI)

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

2000-02-03T23:59:59.000Z

316

Nuclear Theory and Science of the Facility for Rare Isotope Beams  

E-Print Network (OSTI)

The Facility for Rare Isotope Beams (FRIB) will be a world-leading laboratory for the study of nuclear structure, reactions and astrophysics. Experiments with intense beams of rare isotopes produced at FRIB will guide us toward a comprehensive description of nuclei, elucidate the origin of the elements in the cosmos, help provide an understanding of matter in neutron stars, and establish the scientific foundation for innovative applications of nuclear science to society. FRIB will be essential for gaining access to key regions of the nuclear chart, where the measured nuclear properties will challenge established concepts, and highlight shortcomings and needed modifications to current theory. Conversely, nuclear theory will play a critical role in providing the intellectual framework for the science at FRIB, and will provide invaluable guidance to FRIB's experimental programs. This article overviews the broad scope of the FRIB theory effort, which reaches beyond the traditional fields of nuclear structure and reactions, and nuclear astrophysics, to explore exciting interdisciplinary boundaries with other areas. \\keywords{Nuclear Structure and Reactions. Nuclear Astrophysics. Fundamental Interactions. High Performance Computing. Rare Isotopes. Radioactive Beams.

A. B Balantekin; J. Carlson; D. J. Dean; G. M. Fuller; R. J. Furnstahl; M. Hjorth-Jensen; R. V. F. Janssens; Bao-An Li; W. Nazarewicz; F. M. Nunes; W. E. Ormand; S. Reddy; B. M. Sherrill

2014-01-24T23:59:59.000Z

317

2012 Annual Workforce Analysis and Staffing Plan Report- Nuclear Energy Oak Ridge Site Office  

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

Managers perform an annual workforce analysis of their organization and develop staffing plans that identify technical capabilities and positions they need to ensure safe operation of defense nuclear facilities.

318

The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities  

SciTech Connect

Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

Kwan-Seong Jeong; Dong-Gyu Lee; Chong-Hun Jung; Kune-Woo Lee [Korea Atomic Energy Research Institute, Deokjin-dong 150, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

2007-07-01T23:59:59.000Z

319

Requirements and Design Envelope for Volumetric Neutron Source Fusion Facilities for Fusion Nuclear Technology Development  

SciTech Connect

The paper shows that timely development of fusion nuclear technology (FNT) components, e.g. blanket, for DEMO requires the construction and operation of a fusion facility parallel to ITER. This facility, called VNS, will be dedicated to testing, developing and qualifying FNT components and material combinations. Without VNS, i.e. with ITER alone, the confidence level in achieving DEMO operating goals has been quantified and is unacceptably low (< 1 %). An attractive design envelope for VNS exists. Tokamak VNS designs with driven plasma (Q ~ 1-3), steady state plasma operation and normal copper toroidal field coils lead to small sized devices with moderate cost.

Abdou, M [University of California, Los Angeles; Peng, Yueng Kay Martin [ORNL

1995-01-01T23:59:59.000Z

320

A HYDROGEN IGNITION MECHANISM FOR EXPLOSIONS IN NUCLEAR FACILITY PIPING SYSTEMS  

SciTech Connect

Hydrogen explosions may occur simultaneously with water hammer accidents in nuclear facilities, and a theoretical mechanism to relate water hammer to hydrogen deflagrations and explosions is presented herein. Hydrogen and oxygen generation due to the radiolysis of water is a recognized hazard in pipe systems used in the nuclear industry, where the accumulation of hydrogen and oxygen at high points in the pipe system is expected, and explosive conditions may occur. Pipe ruptures in nuclear reactor cooling systems were attributed to hydrogen explosions inside pipelines, i.e., Hamaoka, Nuclear Power Station in Japan, and Brunsbuettel in Germany. Prior to these accidents, an ignition source for hydrogen was not clearly demonstrated, but these accidents demonstrated that a mechanism was, in fact, available to initiate combustion and explosion. A new theory to identify an ignition source and explosion cause is presented here, and further research is recommended to fully understand this explosion mechanism.

Leishear, R.

2013-03-28T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel  

SciTech Connect

This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

1994-10-01T23:59:59.000Z

322

Safeguards Guidance for Designers of Commercial Nuclear Facilities International Safeguards Requirements for Uranium Enrichment Plants  

SciTech Connect

For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

Philip Casey Durst; Scott DeMuth; Brent McGinnis; Michael Whitaker; James Morgan

2010-04-01T23:59:59.000Z

323

The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology  

Science Conference Proceedings (OSTI)

To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team projects and faculty/staff exchanges. In June of 2008, the first week-long ATR NSUF Summer Session was attended by 68 students, university faculty and industry representatives. The Summer Session featured presentations by 19 technical experts from across the country and covered topics including irradiation damage mechanisms, degradation of reactor materials, LWR and gas reactor fuels, and non-destructive evaluation. High impact research results from leveraging the entire research infrastructure, including universities, industry, small business, and the national laboratories. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. Current partner facilities include the MIT Reactor, the University of Michigan Irradiated Materials Testing Laboratory, the University of Wisconsin Characterization Laboratory, and the University of Nevada, Las Vegas transmission Electron Microscope User Facility. Needs for irradiation of material specimens at tightly controlled temperatures are being met by dedication of a large in-pile pressurized water loop facility for use by ATR NSUF users. Several environmental mechanical testing systems are under construction to determine crack growth rates and fracture toughness on irradiated test systems.

T. R. Allen; J. B. Benson; J. A. Foster; F. M. Marshall; M. K. Meyer; M. C. Thelen

2009-05-01T23:59:59.000Z

324

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

325

DOE-HDBK-1099-96; Establishing Nuclear Facility Drill Programs  

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

DOE-HDBK-1099-96 March 1996 DOE HANDBOOK ESTABLISHING NUCLEAR FACILITY DRILL PROGRAMS U.S. Department of Energy FSC 6910 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) 487-4650. Order No. DE96008247 DOE-HDBK-1099-96 iii FOREWORD This Department of Energy (DOE) Handbook, DOE-HDBK-1099-95, Establishing Nuclear Facility Drill Programs, is approved

326

Automatic Estimation of the Radiological Inventory for the Dismantling of Nuclear Facilities  

Science Conference Proceedings (OSTI)

The estimation of the radiological inventory of Nuclear Facilities to be dismantled is a process that included information related with the physical inventory of all the plant and radiological survey. Estimation of the radiological inventory for all the components and civil structure of the plant could be obtained with mathematical models with statistical approach. A computer application has been developed in order to obtain the radiological inventory in an automatic way. Results: A computer application that is able to estimate the radiological inventory from the radiological measurements or the characterization program has been developed. In this computer applications has been included the statistical functions needed for the estimation of the central tendency and variability, e.g. mean, median, variance, confidence intervals, variance coefficients, etc. This computer application is a necessary tool in order to be able to estimate the radiological inventory of a nuclear facility and it is a powerful tool for decision taken in future sampling surveys.

Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E. [Iberdrola Ingenieria y Construccion (Spain); Martin, N. [ENRESA (Spain)

2008-01-15T23:59:59.000Z

327

DOE-STD-1070-94; DOE Standard Guidelines for Evalation of Nuclear Facility Training Programs  

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

DOE-STD-1070-94 June 1994 DOE STANDARD GUIDELINES FOR EVALUATION OF NUCLEAR FACILITY TRAINING PROGRAMS U.S. Department of Energy FSC-6910 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; (615)576-8401. Available to the public from the U. S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA. 22161; (703)487-4650. Order No. DE94015536 DOE-STD-1070-94 iii FOREWORD The Department of Energy (DOE) Guidelines for Evaluation of Nuclear Facility Training

328

Defense High Level Waste Disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms [IPWF]) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. US Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as co-disposal. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister inserted in the center and/or one or more DOE SNF canisters displacing a HLW canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents.

N. E. Pettit

2001-07-13T23:59:59.000Z

329

Descriptions of selected accidents that have occurred at nuclear reactor facilities  

SciTech Connect

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

Bertini, H.W.

1980-04-01T23:59:59.000Z

330

Descriptions of selected accidents that have occurred at nuclear reactor facilities  

SciTech Connect

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

Bertini, H.W.

1980-04-01T23:59:59.000Z

331

Nuclear heating in thick iron slabs at the ORR Pool Side Facility  

SciTech Connect

The purpose of this work was to determine experimentally and computationally the nuclear heating rates in iron in the Pool Side Facility (PSF) of the Oak Ridge Research Reactor (ORR). This work was performed in support of the NRC-Pressure Vessel Surveillance Program, the objective of which is to verify and upgrade dosimetry and damage correlations for pressure vessels of Light Water Reactors (LWR).

Siman-Tov, I.I.

1979-01-01T23:59:59.000Z

332

Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information  

SciTech Connect

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses.

NONE

1995-07-14T23:59:59.000Z

333

Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management  

Science Conference Proceedings (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

NONE

1995-07-14T23:59:59.000Z

334

Project Plan: Central and Eastern United States Seismic Source Characterization for Nuclear Facilities  

Science Conference Proceedings (OSTI)

This project plan outlines the Central and Eastern United States Seismic Source Characterization for Nuclear Facilities (CEUS SSC) Project, which will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI report NP-4726, July 1986. The objective of the CEUS SSC project is to develop an up-to-date assessment of probabilistic seismic hazard analysis (PSHA) SSC for CEUS. Input to a PSHA consists of both seismic source and ground motion characterization. These two components ...

2008-06-16T23:59:59.000Z

335

Conceptual design report: Nuclear materials storage facility renovation. Part 6, Alternatives study  

SciTech Connect

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for material and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment 111-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VI - Alternatives Study, presents a study of the different storage/containment options considered for NMSF.

1995-07-14T23:59:59.000Z

336

EVALUATION OF THE IMPACT OF THE DEFENSE WASTE PROCESSING FACILITY (DWPF) LABORATORY GERMANIUM OXIDE USE ON RECYCLE TRANSFERS TO THE H-TANK FARM  

SciTech Connect

When processing High Level Waste (HLW) glass, the Defense Waste Processing Facility (DWPF) cannot wait until the melt or waste glass has been made to assess its acceptability, since by then no further changes to the glass composition and acceptability are possible. Therefore, the acceptability decision is made on the upstream feed stream, rather than on the downstream melt or glass product. This strategy is known as 'feed forward statistical process control.' The DWPF depends on chemical analysis of the feed streams from the Sludge Receipt and Adjustment Tank (SRAT) and the Slurry Mix Evaporator (SME) where the frit plus adjusted sludge from the SRAT are mixed. The SME is the last vessel in which any chemical adjustments or frit additions can be made. Once the analyses of the SME product are deemed acceptable, the SME product is transferred to the Melter Feed Tank (MFT) and onto the melter. The SRAT and SME analyses have been analyzed by the DWPF laboratory using a 'Cold Chemical' method but this dissolution did not adequately dissolve all the elemental components. A new dissolution method which fuses the SRAT or SME product with cesium nitrate (CsNO{sub 3}), germanium (IV) oxide (GeO{sub 2}) and cesium carbonate (Cs{sub 2}CO{sub 3}) into a cesium germanate glass at 1050 C in platinum crucibles has been developed. Once the germanium glass is formed in that fusion, it is readily dissolved by concentrated nitric acid (about 1M) to solubilize all the elements in the SRAT and/or SME product for elemental analysis. When the chemical analyses are completed the acidic cesium-germanate solution is transferred from the DWPF analytic laboratory to the Recycle Collection Tank (RCT) where the pH is increased to {approx}12 M to be released back to the tank farm and the 2H evaporator. Therefore, about 2.5 kg/yr of GeO{sub 2}/year will be diluted into 1.4 million gallons of recycle. This 2.5 kg/yr of GeO{sub 2} may increase to 4 kg/yr when improvements are implemented to attain an annual canister production goal of 400 canisters. Since no Waste Acceptance Criteria (WAC) exists for germanium in the Tank Farm, the Effluent Treatment Project, or the Saltstone Production Facility, DWPF has requested an evaluation of the fate of the germanium in the caustic environment of the RCT, the 2H evaporator, and the tank farm. This report evaluates the effect of the addition of germanium to the tank farm based on: (1) the large dilution of Ge in the RCT and tank farm; (2) the solubility of germanium in caustic solutions (pH 12-13); (3) the potential of germanium to precipitate as germanium sodalites in the 2H Evaporator; and (4) the potential of germanium compounds to precipitate in the evaporator feed tank. This study concludes that the impacts of transferring up to 4 kg/yr germanium to the RCT (and subsequently the 2H evaporator feed tank and the 2H evaporator) results in <2 ppm per year (1.834 mg/L) which is the maximum instantaneous concentration expected from DWPF. This concentration is insignificant as most sodium germanates are soluble at the high pH of the feed tank and evaporator solutions. Even if sodium aluminosilicates form in the 2H evaporator, the Ge will likely substitute for some small amount of the Si in these structures and will be insignificant. It is recommended that the DWPF continue with their strategy to add germanium as a laboratory chemical to Attachment 8.2 of the DWPF Waste Compliance Plan (WCP).

Jantzen, C.; Laurinat, J.

2011-08-15T23:59:59.000Z

337

Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography  

Science Conference Proceedings (OSTI)

This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1985-09-01T23:59:59.000Z

338

Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8  

SciTech Connect

The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1987-09-01T23:59:59.000Z

339

Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography  

SciTech Connect

This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory.

Faust, R.A.; Fore, C.S.; Knox, N.P.

1980-09-01T23:59:59.000Z

340

NNSA's Second Line of Defense Program Receives Capability Award...  

National Nuclear Security Administration (NNSA)

Institute (UNICRI) and the U.S. Defense Threat Reduction Agency (DTRA). SLD's capacity-building work in the area of nuclear nonproliferation and nuclear security was...

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Applicability of base-isolation R D in non-reactor facilities to a nuclear reactor plant  

SciTech Connect

Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. The question, therefore, is to what extent can research and development (R D) for non-nuclear use be used to provide technological data needed for seismic isolation of a nuclear power plant. This question, of course is not unique to seismic isolation. Virtually every structural component, system, or piece of equipment used in nuclear power plants is also used in non- nuclear facilities. Experience shows that considerable effort is needed to adapt conventional technology into a nuclear power plant. Usually, more thorough analysis is required, material and fabrication quality-control requirements are more stringent as are controls on field installation. In addition, increased emphasis on maintainability and inservice inspection throughout the life of the plant is generally required to gain acceptance in nuclear power plant application. This paper reviews the R D programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant. 2 refs.

Seidensticker, R.W.; Chang, Y.W.

1990-01-01T23:59:59.000Z

342

Nuclear-nuclear collision centrality determination by the spectators calorimeter for the MPD setup at the NICA facility  

SciTech Connect

The work conditions of the hadron calorimeter for spectators registration (Zero Degree Calorimeter, ZDC) were studied for the heavy nuclei collisions with the several GeV invariant energy. The ZDC simulations were performed for the MPD (Multi-Purpose Detector) at the NICA (Nuclotron-based Ion Collider fAcility) collider, which are under developement at the Joint Institute for Nuclear Research (JINR, Dubna). Taking into account the spectator nuclear fragments leads to a nonmonotonic dependence of the ZDC response on the impact parameter. The reason for this dependence studied with several event generators is the primary beam hole in the ZDC center. It is shown, that the ZDC signal should be combined with a data from other MPD-NICA detector subsystems to determine centrality.

Golubeva, M. B.; Guber, F. F.; Ivashkin, A. P. [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation)] [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation); Isupov, A. Yu. [Joint Institute for Nuclear Research (Russian Federation)] [Joint Institute for Nuclear Research (Russian Federation); Kurepin, A. B. [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation)] [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation); Litvinenko, A. G., E-mail: litvin@moonhe.jinr.ru; Litvinenko, E. I.; Migulina, I. I.; Peresedov, V. F. [Joint Institute for Nuclear Research (Russian Federation)] [Joint Institute for Nuclear Research (Russian Federation)

2013-01-15T23:59:59.000Z

343

Use of nuclear facilities at Argonne-West to support new environmental missions  

SciTech Connect

At Argonne National Laboratory-West, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used to meet the environmental and waste management need of the US Department of Energy. These needs include waste characterization, waste testing, and waste treatment technology development. Waste characterization and repackaging activities are being performed in the Hot Fuel Examination Facility for the Waste Isolation Pilot Plant (WIPP) Experimental Test Program. Characterization activities include sampling the gas in actual waste containers, categorizing waste contents for their gas generation potential, and extracting solid samples. A new waste testing project will utilize the Zero Powered Physics Reactor facility. In the workroom of these facility, laboratory gas generation experiments will be conducted with contact-handled transuranic waste. Both the characterization and waste testing activities are part of the effort to prepare the WIPP performance assessment. Waste treatment demonstrations have or will be conducted at the Transient Reactor Test facility and involve private sector participants. The demonstrations involve the development of thermal treatment for materials containing residual amounts of plutonium using plasma-arc technology. The success of these new programs is largely due to experience gained from past missions in such areas as radiological control and nuclear safety.

Black, D.B.; Dwight, C.C.; Lineberry, M.J.

1994-08-01T23:59:59.000Z

344

Handbook for the implementation of IAEA inspection activities at Department of Energy nuclear facilities  

SciTech Connect

The Nonproliferation Support Program (NSP) in the United States Department of Energy (DOE) Office of Safeguards and Security (OSS) has responsibility for supporting and aiding implementation of international and multilateral programs, agreements, and treaties at domestic facilities. In late 1995, the {open_quotes}Readiness Planning Guide for Nonproliferation Visits{close_quotes} (DOE 470.1-1) was issued to assist DOE sites prepare for the host foreign delegations visiting DOE facilities. Since then, field and head-quarters programs have expressed a need for a document that addresses domestic safeguards and security activities, specifically planning for and hosting International Atomic Energy Agency (IAEA) technical visits and inspections. As a result, OSS/NSP conducted a workshop to prepare a handbook that would contain guidance on domestic safeguards and security preparation and follow-on activities to ensure that this handbook could be utilized by all facilities to improve operational efficiencies and reduce implementation problems. The handbook has been structured to provide detailed background and guidance concerning the obligation, negotiation, inspection, and reporting processes for IAEH safeguards activities in DOE nuclear facilities as well as the lessons-learned by currently inspected facilities and how-we-do-it implementation examples. This paper will present an overview of the preparation and content of this new Handbook.

Zack, N.R.; Thomas, K.E. [Los Alamos National Lab., NM (United States); Coady, K.J.; Desmond, W.J. [Department of Energy, Washington, DC (United States)

1997-11-01T23:59:59.000Z

345

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program  

Science Conference Proceedings (OSTI)

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

346

Nuclear Security & Safety  

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

The Energy Department is working to enhance nuclear security through defense, nonproliferation, and environmental efforts.

347

Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending June 30, 1993  

Science Conference Proceedings (OSTI)

This is the ninth quarterly report on the progress of activities that address safety issues associated with Hanford Site high-level radioactive waste tanks containing ferrocyanide compounds. Milestones completed this quarter include (1) a report on the credibility of hot spots and a recommendation on infrared scans; (2) a document discussing the strength and limitations of proposed moisture monitoring technologies; (3) limited calibration of the neutron probe in simulant-filled drums; (4) a report interpreting data from auger surface samples of ferrocyanide tank 241-BY-104; (5) a document on the effect of possible catalyst, initiator, and diluents on ferrocyanide reactivity; (6) a report on small scale sensitivity tests of ferrocyanide flowsheet simulants; and (7) preparation and shipment of T Plant simulants for calorimetric and dryout tests.

Cash, R.J.; Dukelow, G.T.; Forbes, C.J.; Meacham, J.E.

1993-10-01T23:59:59.000Z

348

Review of the Implementation Verification Rev iew Processes at the Savannah River Site Environmental Management Nuclear Facilities, September 2011  

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

Implementation Verification Review Implementation Verification Review Processes at the Savannah River Site Environmental Management Nuclear Facilities May 2011 September 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy i Independent Oversight Review of the Implementation Verification Review Processes at the Savannah River Site Environmental Management Nuclear Facilities Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background ........................................................................................................................................... 1

349

Review of the Implementation Verification Rev iew Processes at the Savannah River Site Environmental Management Nuclear Facilities, September 2011  

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

Implementation Verification Review Implementation Verification Review Processes at the Savannah River Site Environmental Management Nuclear Facilities May 2011 September 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy i Independent Oversight Review of the Implementation Verification Review Processes at the Savannah River Site Environmental Management Nuclear Facilities Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background ........................................................................................................................................... 1

350

75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY  

SciTech Connect

For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)

Gronemeyer, F.C.; Merryman, J.W.

1960-01-01T23:59:59.000Z

351

SUBJECT: Guidance on Retention of Facility Representative Technical  

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

SUBJECT: Guidance on Retention of Facility Representative Technical SUBJECT: Guidance on Retention of Facility Representative Technical Competence during Reductions in Force, 4/21/1998 SUBJECT: Guidance on Retention of Facility Representative Technical Competence during Reductions in Force, 4/21/1998 The Department's Revised Implementation Plan (IP) for Defense Nuclear Facilities Safety Board Recommendation 93-3 renews the Department's commitment to maintaining the technical capability necessary to safely manage and operate defense nuclear facilities. Retaining highly qualified employees in critical technical skills areas is vital to the maintenance of these technical capabilities. The Department has therefore committed in the revised R? to the development of a model that offices can use to proactively manage and preserve critical technical capabilities. During the

352

June 21, 1999 Memo, Facility Representative Program Status  

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

June June 21, 1999 MEMORANDUM FOR: Assistant Secretary for Defense Programs Assistant Secretary for Environmental Management Director, Office of Science Director, Office of Nuclear Energy, Science and Technology FROM: John Wilcynski, Director, Office of Field Integration SUBJECT: FACILITY REPRESENTATIVE PROGRAM STATUS Since September, 1993, the Office of Field Management has served as the Department's corporate advocate for the Facility Representative Program. The Facility Representative (FR) is a critical technical position serving as line management's "eyes and ears" for operational safety in our contractor-operated facilities. I recognize the importance of the FR Program, and commit the Office of Field Integration (FI) to its continued crosscutting support. The FI staff continues to work with your staff members and with the Defense Nuclear Facilities

353

Use of the Homeland-Defense Operational Planning System (HOPS) for Emergency Management  

DOE Green Energy (OSTI)

The Homeland-Defense Operational Planning System (HOPS), is a new operational planning tool leveraging Lawrence Livermore National Laboratory's expertise in weapons systems and in sparse information analysis to support the defense of the U.S. homeland. HOPS provides planners with a basis to make decisions to protect against acts of terrorism, focusing on the defense of facilities critical to U.S. infrastructure. Criticality of facilities, structures, and systems is evaluated on a composite matrix of specific projected casualty, economic, and sociopolitical impact bins. Based on these criteria, significant unidentified vulnerabilities are identified and secured. To provide insight into potential successes by malevolent actors, HOPS analysts strive to base their efforts mainly on unclassified open-source data. However, more cooperation is needed between HOPS analysts and facility representatives to provide an advantage to those whose task is to defend these facilities. Evaluated facilities include: refineries, major ports, nuclear power plants and other nuclear licensees, dams, government installations, convention centers, sports stadiums, tourist venues, and public and freight transportation systems. A generalized summary of analyses of U.S. infrastructure facilities will be presented.

Durling, Jr., R L; Price, D E

2005-12-16T23:59:59.000Z

354

Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5  

SciTech Connect

This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

1984-09-01T23:59:59.000Z

355

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program  

SciTech Connect

The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

Not Available

1991-09-01T23:59:59.000Z

356

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities.

Bryant, J.W.; Nenni, J.A.

2003-05-22T23:59:59.000Z

357

Nuclear Desalination Complex with VK-300 Boiling-Type Reactor Facility  

E-Print Network (OSTI)

With regard to the global-scale development of desalination technologies and the stable growth demand for them, Russia also takes an active part in the development of these technologies. Two major aspects play a special role here: they are providing the desalination process with power and introducing new materials capable of making the production of fresh water cheaper and of raising the technical reliability of desalination units. In achieving these tasks, the focus is on the most knowledge-intensive issues, to which Russia is capable of making its contribution based both on the experience of developing national nuclear power and the experience of developing, manufacturing and operating desalination units, including the use of nuclear power (the experience of BN-350 in Aktau (formerly Shevchenko), Kazakhstan). In terms of design, the Nuclear Desalination Complex (NDC) with a VK-300 reactor facility is a modification of a nuclear power unit with a VK-300 reactor developed for application at Russian nuclear cogeneration plants. A power unit

B. A. Gabaraev; Yu. N. Kuznetzov; A. A. Romenkov; Yu. A. Mishanina

2004-01-01T23:59:59.000Z

358

Maximum Reasonable Radioxenon Releases from Medical Isotope Production Facilities and Their Effect on Monitoring Nuclear Explosions  

SciTech Connect

Fission gases such as 133Xe are used extensively for monitoring the world for signs of nuclear testing in systems such as the International Monitoring System (IMS). These gases are also produced by nuclear reactors and by fission production of 99Mo for medical use. Recently, medical isotope production facilities have been identified as the major contributor to the background of radioactive xenon isotopes (radioxenon) in the atmosphere (Saey, et al., 2009). These releases pose a potential future problem for monitoring nuclear explosions if not addressed. As a starting point, a maximum acceptable daily xenon emission rate was calculated, that is both scientifically defendable as not adversely affecting the IMS, but also consistent with what is possible to achieve in an operational environment. This study concludes that an emission of 5109 Bq/day from a medical isotope production facility would be both an acceptable upper limit from the perspective of minimal impact to monitoring stations, but also appears to be an achievable limit for large isotope producers.

Bowyer, Ted W.; Kephart, Rosara F.; Eslinger, Paul W.; Friese, Judah I.; Miley, Harry S.; Saey, Paul R.

2013-01-01T23:59:59.000Z

359

Identifying Potential Areas for Siting Interim Nuclear Waste Facilities Using Map Algebra and Optimization Approaches  

Science Conference Proceedings (OSTI)

The renewed interest in siting new nuclear power plants in the United States has brought to the center stage, the need to site interim facilities for long-term management of spent nuclear fuel (SNF). In this paper, a two-stage approach for identifying potential areas for siting interim SNF facilities is presented. In the first stage, the land area is discretized into grids of uniform size (e.g., 100m x 100m grids). For the continental United States, this process resulted in a data matrix of about 700 million cells. Each cell of the matrix is then characterized as a binary decision variable to indicate whether an exclusion criterion is satisfied or not. A binary data matrix is created for each of the 25 siting criteria considered in this study. Using map algebra approach, cells that satisfy all criteria are clustered and regarded as potential siting areas. In the second stage, an optimization problem is formulated as a p-median problem on a rail network such that the sum of the shortest distance between nuclear power plants with SNF and the potential storage sites from the first stage is minimized. The implications of obtained results for energy policies are presented and discussed.

Omitaomu, Olufemi A [ORNL; Liu, Cheng [ORNL; Cetiner, Mustafa Sacit [ORNL; Belles, Randy [ORNL; Mays, Gary T [ORNL; Tuttle, Mark A [ORNL

2013-01-01T23:59:59.000Z

360

Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities  

E-Print Network (OSTI)

1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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

Low Prevalence of Chronic Beryllium Disease among Workers at a Nuclear Weapons Research and Development Facility  

SciTech Connect

To study the prevalence of beryllium sensitization (BeS) and chronic beryllium disease (CBD) in a cohort of workers from a nuclear weapons research and development facility. We evaluated 50 workers with BeS with medical and occupational histories, physical examination, chest imaging with HRCT (N=49), and pulmonary function testing. Forty of these workers also underwent bronchoscopy for bronchoalveolar lavage (BAL) and transbronchial biopsies. The mean duration of employment at the facility was 18 yrs and the mean latency (from first possible exposure) to time of evaluation was 32 yrs. Five of the workers had CBD at the time of evaluation (based on histology or HRCT); three others had evidence of probable CBD. These workers with BeS, characterized by a long duration of potential Be exposure and a long latency, had a low prevalence of CBD.

Arjomandi, M; Seward, J P; Gotway, M B; Nishimura, S; Fulton, G P; Thundiyil, J; King, T E; Harber, P; Balmes, J R

2010-01-11T23:59:59.000Z

362

Technical Considerations for the Nuclear Regulatory Commission/ National Academy of Sciences Proposed Study: Cancer in Populations L iving Near Nuclear Facilities  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commission (NRC), through the National Academy of Sciences (NAS), is updating the 1990 U.S. National Institutes of Health - National Cancer Institute (NCI) report, Cancer in Populations Living near Nuclear Facilities. The Electric Power Research Institute (EPRI) formed a committee of scientists and professionals in the fields of epidemiology, radiation biology, nuclear plant effluents, and environmental risk assessment to provide study design considerations to the NAS committe...

2011-11-04T23:59:59.000Z

363

A DOE-STD-3009 hazard and accident analysis methodology for non-reactor nuclear facilities  

Science Conference Proceedings (OSTI)

This paper demonstrates the use of appropriate consequence evaluation criteria in conjunction with generic likelihood of occurrence data to produce consistent hazard analysis results for nonreactor nuclear facility Safety Analysis Reports (SAR). An additional objective is to demonstrate the use of generic likelihood of occurrence data as a means for deriving defendable accident sequence frequencies, thereby enabling the screening of potentially incredible events (<10{sup {minus}6} per year) from the design basis accident envelope. Generic likelihood of occurrence data has been used successfully in performing SAR hazard and accident analyses for two nonreactor nuclear facilities at Sandia National Laboratories. DOE-STD-3009-94 addresses and even encourages use of a qualitative binning technique for deriving and ranking nonreactor nuclear facility risks. However, qualitative techniques invariably lead to reviewer requests for more details associated with consequence or likelihood of occurrence bin assignments in the test of the SAR. Hazard analysis data displayed in simple worksheet format generally elicits questions about not only the assumptions behind the data, but also the quantitative bases for the assumptions themselves (engineering judgment may not be considered sufficient by some reviewers). This is especially true where the criteria for qualitative binning of likelihood of occurrence involves numerical ranges. Oftentimes reviewers want to see calculations or at least a discussion of event frequencies or failure probabilities to support likelihood of occurrence bin assignments. This may become a significant point of contention for events that have been binned as incredible. This paper will show how the use of readily available generic data can avoid many of the reviewer questions that will inevitably arise from strictly qualitative analyses, while not significantly increasing the overall burden on the analyst.

MAHN,JEFFREY A.; WALKER,SHARON ANN

2000-03-23T23:59:59.000Z

364

Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9  

SciTech Connect

The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

1988-09-01T23:59:59.000Z

365

Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9  

SciTech Connect

The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

1988-09-01T23:59:59.000Z

366

YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).  

SciTech Connect

The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

2010-04-28T23:59:59.000Z

367

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 ..........................................................................................................................

368

Characterization of thorium and uranium contaminated soil from a nuclear fuel facility  

Science Conference Proceedings (OSTI)

This paper describes the utility of soil characterization using electron microscopy to support decontamination efforts of contaminated soil. Soil contaminated with thorium and uranium from the grounds of a nuclear fuel manufacturing facility was subjected to remediation efforts. A light acid leach was able to remove only 30% of the thorium suggesting that the thorium was present in two or more forms. Analytical electron microscopy determined that all of the thorium was present as ThO{sub 2}, but in a bimodal size distribution and occasionally closely associated with other minerals. Electron microscopy was useful in understanding the remediation data and demonstrates the need for characterization of contaminated soils.

Brown, N.R.; Buck, E.C.; Dietz, N.L.; Bates, J.K. [Argonne National Lab., IL (United States); Carlson, B. [Ecotek, Inc., Erwin, TN (United States)

1994-02-01T23:59:59.000Z

369

Report on emergency electrical power supply systems for nuclear fuel cycle and reactor facilities security systems  

SciTech Connect

The report includes information that will be useful to those responsible for the planning, design and implementation of emergency electric power systems for physical security and special nuclear materials accountability systems. Basic considerations for establishing the system requirements for emergency electric power for security and accountability operations are presented. Methods of supplying emergency power that are available at present and methods predicted to be available in the future are discussed. The characteristics of capacity, cost, safety, reliability and environmental and physical facility considerations of emergency electric power techniques are presented. The report includes basic considerations for the development of a system concept and the preparation of a detailed system design.

1977-01-01T23:59:59.000Z

370

NGNP Nuclear-Industrial Facility and Design Certification Boundaries White Paper  

SciTech Connect

The Next Generation Nuclear Plant (NGNP) Project was initiated at Idaho National Laboratory by the U.S. Department of Energy pursuant to the 2005 Energy Policy Act and based on research and development activities supported by the Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of the high temperature gas-cooled reactor (HTGR) technology. The HTGR is helium cooled and graphite moderated and can operate at reactor outlet temperatures much higher than those of conventional light water reactor (LWR) technologies. Accordingly, it can be applied in many industrial applications as a substitute for burning fossil fuels, such as natural gas, in addition to producing electricity, which is the principal application of current LWRs. These varied industrial applications may involve a standard HTGR modular design using different Energy Conversion Systems. Additionally, some of these process heat applications will require process heat delivery systems to lie partially outside the HTGR operators facility.

Thomas E. Hicks

2011-07-01T23:59:59.000Z

371

Calculational framework for safety analyses of non-reactor nuclear facilities  

DOE Green Energy (OSTI)

A calculational framework for the consequences analysis of non-reactor nuclear facilities is presented. The analysis framework starts with accident scenarios which are developed through a traditional hazard analysis and continues with a probabilistic framework for the consequences analysis. The framework encourages the use of response continua derived from engineering judgment and traditional deterministic engineering analyses. The general approach consists of dividing the overall problem into a series of interrelated analysis cells and then devising Markov chain like probability transition matrices for each of the cells. An advantage of this division of the problem is that intermediate output (as probability state vectors) are generated at each calculational interface. The series of analyses when combined yield risk analysis output. The analysis approach is illustrated through application to two non-reactor nuclear analyses: the Ulysses Space Mission, and a hydrogen burn in the Hanford waste storage tanks.

Coleman, J.R.

1994-06-01T23:59:59.000Z

372

The Use of Staff Augmentation Subcontracts at the National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility, IG-0887  

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

The Use of Staff Augmentation The Use of Staff Augmentation Subcontracts at National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility DOE/IG-0887 May 2013 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 May 15, 2013 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "The Use of Staff Augmentation Subcontracts at the National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility" BACKGROUND Shaw AREVA MOX Services, LLC (MOX Services) is responsible for the design and construction of the National Nuclear Security Administration's (NNSA) nearly $5 billion Mixed

373

Technical Considerations for NRC/National Academy Proposed Study of Cancer Risks in Populations Living near Nuclear Facilities  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commission (NRC), through the National Academy of Sciences (NAS), is updating the 1990 U.S. National Institutes of Health - National Cancer Institute (NCI) report, "Cancer in Populations Living near Nuclear Facilities." The Electric Power Research Institute (EPRI) formed a committee of scientists and professionals in the fields of epidemiology, radiation biology, nuclear plant effluents, and environmental risk assessment to provide study design considerations to the NAS commit...

2011-06-30T23:59:59.000Z

374

Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research  

SciTech Connect

The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue Universitys Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called Users Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. Users week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

John Jackson; Todd Allen; Frances Marshall; Jim Cole

2013-03-01T23:59:59.000Z

375

Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities. Outcomes of the International Conference, 11-15 December 2006, Athens, Greece  

Science Conference Proceedings (OSTI)

Full text of publication follows: decommissioning activities are increasing worldwide covering wide range of facilities - from nuclear power plant, through fuel cycle facilities to small laboratories. The importance of these activities is growing with the recognition of the need for ensuring safe termination of practices and reuse of sites for various purposes, including the development of new nuclear facilities. Decommissioning has been undertaken for more than forty years and significant knowledge has been accumulated and lessons have been learned. However the number of countries encountering decommissioning for the first time is increasing with the end of the lifetime of the facilities around the world, in particular in countries with small nuclear programmes (e.g. one research reactor) and limited human and financial resources. In order to facilitate the exchange of lessons learned and good practices between all Member States and to facilitate and improve safety of the planned, ongoing and future decommissioning projects, the IAEA in cooperation with the Nuclear Energy Agency to OECD, European Commission and World Nuclear Association organised the international conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities, held in Athens, Greece. The conference also highlighted areas where future cooperation at national and international level is required in order to improve decommissioning planning and safety during decommissioning and to facilitate decommissioning by selecting appropriate strategies and technologies for decontamination, dismantling and management of waste. These and other aspects discussed at the conference are presented in this paper, together with the planned IAEA measures for amendment and implementation of the International Action Plan on Decommissioning of Nuclear Facilities and its future programme on decommissioning.

Batandjieva, B.; Laraia, M. [International Atomic Energy Agency, Vienna (Austria)

2008-01-15T23:59:59.000Z

376

NEW MATERIALS DEVELOPED TO MEET REGULATORY AND TECHNICAL REQUIREMENTS ASSOCIATED WITH IN-SITU DECOMMISSIONING OF NUCLEAR REACTORS AND ASSOCIATED FACILITIES  

Science Conference Proceedings (OSTI)

For the 2010 ANS Embedded Topical Meeting on Decommissioning, Decontamination and Reutilization and Technology, Savannah River National Laboratory's Mike Serrato reported initial information on the newly developed specialty grout materials necessary to satisfy all requirements associated with in-situ decommissioning of P-Reactor and R-Reactor at the U.S. Department of Energy's Savannah River Site. Since that report, both projects have been successfully completed and extensive test data on both fresh properties and cured properties has been gathered and analyzed for a total of almost 191,150 m{sup 3} (250,000 yd{sup 3}) of new materials placed. The focus of this paper is to describe the (1) special grout mix for filling the P-Reactor vessel (RV) and (2) the new flowable structural fill materials used to fill the below grade portions of the facilities. With a wealth of data now in hand, this paper also captures the test results and reports on the performance of these new materials. Both reactors were constructed and entered service in the early 1950s, producing weapons grade materials for the nation's defense nuclear program. R-Reactor was shut down in 1964 and the P-Reactor in 1991. In-situ decommissioning (ISD) was selected for both facilities and performed as Comprehensive Environmental Response, Compensations and Liability Act actions (an early action for P-Reactor and a removal action for R-Reactor), beginning in October 2009. The U.S. Department of Energy concept for ISD is to physically stabilize and isolate intact, structurally robust facilities that are no longer needed for their original purpose of producing (reactor facilities), processing (isotope separation facilities), or storing radioactive materials. Funding for accelerated decommissioning was provided under the American Recovery and Reinvestment Act. Decommissioning of both facilities was completed in September 2011. ISD objectives for these CERCLA actions included: (1) Prevent industrial worker exposure to radioactive or hazardous contamination exceeding Principal Threat Source Material levels; (2) Minimize human and ecological exposure to unacceptable risk associated with radiological and hazardous constituents that are or may be present; (3) Prevent to the extent practicable the migration of radioactive or hazardous contaminants from the closed facility to the groundwater so that concentrations in groundwater do not exceed regulatory standards; (4) Eliminate or control all routes of human exposure to radiological and chemical contamination; and (5) Prevent animal intruder exposure to radioactive and hazardous contamination.

Blankenship, J.; Langton, C.; Musall, J.; Griffin, W.

2012-01-18T23:59:59.000Z

377

Nuclear waste form risk assessment for US defense waste at Savannah River Plant. Annual report fiscal year 1980  

SciTech Connect

Waste form dissolution studies and preliminary performance analyses were carried out to contribute a part of the data needed for the selection of a waste form for the disposal of Savannah River Plant defense waste in a deep geologic repository. The first portion of this work provides descriptions of the chemical interactions between the waste form and the geologic environment. We reviewed critically the dissolution/leaching data for borosilicate glass and SYNROC. Both chemical kinetic and thermodynamic models were developed to describe the dissolution process of these candidate waste forms so as to establish a fundamental basis for interpretation of experimental data and to provide directions for future experiments. The complementary second portion of this work is an assessment of the impacts of alternate waste forms upon the consequences of disposal in various proposed geological media. Employing systems analysis methodology, we began to evaluate the performance of a generic waste form for the case of a high risk scenario for a bedded salt repository. Results of sensitivity analysis, uncertainty analyses, and sensitivity to uncertainty analysis are presented.

Cheung, H.; Jackson, D.D.; Revelli, M.A.

1981-07-01T23:59:59.000Z

378

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory  

Science Conference Proceedings (OSTI)

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91 (DOE 1991). The DOE nuclear safety policy states that the general public be protected-such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL. A safety analyst uses the frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy.

Lucas, D.E.; Ikenberry, T.A.

1994-03-01T23:59:59.000Z

379

MODELING THE IMPACT OF ELEVATED MERCURY IN DEFENSE WASTE PROCESSING FACILITY MELTER FEED ON THE MELTER OFF-GAS SYSTEM - PRELIMINARY REPORT  

SciTech Connect

The Defense Waste Processing Facility (DWPF) is currently evaluating an alternative Chemical Process Cell (CPC) flowsheet to increase throughput. It includes removal of the steam-stripping step, which would significantly reduce the CPC processing time and lessen the sampling needs. However, its downside would be to send 100% of the mercury that come in with the sludge straight to the melter. For example, the new mercury content in the Sludge Batch 5 (SB5) melter feed is projected to be 25 times higher than that in the SB4 with nominal steam stripping of mercury. This task was initiated to study the impact of the worst-case scenario of zero-mercury-removal in the CPC on the DWPF melter off-gas system. It is stressed that this study is intended to be scoping in nature, so the results presented in this report are preliminary. In order to study the impact of elevated mercury levels in the feed, it is necessary to be able to predict how mercury would speciate in the melter exhaust under varying melter operating conditions. A homogeneous gas-phase oxidation model of mercury by chloride was developed to do just that. The model contains two critical parameters pertaining to the partitioning of chloride among HCl, Cl, Cl{sub 2}, and chloride salts in the melter vapor space. The values for these parameters were determined at two different melter vapor space temperatures by matching the calculated molar ratio of HgCl (or Hg{sub 2}Cl{sub 2}) to HgCl{sub 2} with those measured during the Experimental-Scale Ceramic Melter (ESCM) tests run at the Pacific Northwest National Laboratory (PNNL). The calibrated model was then applied to the SB5 simulant used in the earlier flowsheet study with an assumed mercury stripping efficiency of zero; the molar ratio of Cl-to-Hg in the resulting melter feed was only 0.4, compared to 12 for the ESCM feeds. The results of the model run at the indicated melter vapor space temperature of 650 C (TI4085D) showed that due to excessive shortage of chloride, only 6% of the mercury fed is expected to get oxidized, mostly as HgCl, while the remaining mercury would exist either as elemental mercury vapor (90%) or HgO (4%). Noting that the measured chloride level in the SB5 qualification sample was an order of magnitude lower than that used in the SB5 simulant, the degree of chloride shortage will be even greater. As a result, the projected level of HgCl in the actual SB5 melter exhaust will be even lower than 6% of the total mercury fed, while that of elemental mercury is likely to be greater than 90%. The homogeneous oxidation of mercury in the off-gas was deemed to be of primary importance based on the postulation that mercury and other volatile salts form submicron sized aerosols upon condensation and thus remain largely in the gas stream downstream of the quencher where they can deposit in the off-gas lines, Steam-Atomized Scrubbers (SAS), and High-Efficiency Mist Eliminator (HEME). Formation of these submicron semi-volatile salts in the condensate liquid is considered to be unlikely, so the liquid phase reactions were considered to be less important. However, subsequent oxidation of mercury in the liquid phase in the off-gas system was examined in a simplified model of the off-gas condensate. It was found that the condensate chemistry was consistent with further oxidation of elemental mercury to Hg{sub 2}Cl{sub 2} and conversion of HgO to chlorides. The results were consistent with the available experimental data. It should also be noted that the model predictions presented in this report do not include any physically entrained solids, which typically account for much of the off-gas carryover on a mass basis. The high elemental mercury vapor content predicted at the DWPF Quencher inlet means that physically entrained solids could provide the necessary surface onto which elemental mercury vapor could condense, thereby coating the solids as well as the internal surfaces of the off-gas system with mercury. Clearly, there are many process benefits to be gained by removing the steam-stripping step from the CPC c

Zamecnik, J.; Choi, A.

2009-03-25T23:59:59.000Z

380

MODELING THE IMPACT OF ELEVATED MERCURY IN DEFENSE WASTE PROCESSING FACILITY MELTER FEED ON THE MELTER OFF-GAS SYSTEM-PRELIMINARY REPORT  

SciTech Connect

The Defense Waste Processing Facility (DWPF) is currently evaluating an alternative Chemical Process Cell (CPC) flowsheet to increase throughput. It includes removal of the steam-stripping step, which would significantly reduce the CPC processing time and lessen the sampling needs. However, its downside would be to send 100% of the mercury that comes in with the sludge straight to the melter. For example, the new mercury content in the Sludge Batch 5 (SB5) melter feed is projected to be 25 times higher than that in the SB4 with nominal steam stripping of mercury. This task was initiated to study the impact of the worst-case scenario of zero-mercury-removal in the CPC on the DWPF melter offgas system. It is stressed that this study is intended to be scoping in nature, so the results presented in this report are preliminary. In order to study the impact of elevated mercury levels in the feed, it is necessary to be able to predict how mercury would speciate in the melter exhaust under varying melter operating conditions. A homogeneous gas-phase oxidation model of mercury by chloride was developed to do just that. The model contains two critical parameters pertaining to the partitioning of chloride among HCl, Cl, Cl{sub 2}, and chloride salts in the melter vapor space. The values for these parameters were determined at two different melter vapor space temperatures by matching the calculated molar ratio of HgCl (or Hg{sub 2}Cl{sub 2}) to HgCl{sub 2} with those measured during the Experimental-Scale Ceramic Melter (ESCM) tests run at the Pacific Northwest National Laboratory (PNNL). The calibrated model was then applied to the SB5 simulant used in the earlier flowsheet study with an assumed mercury stripping efficiency of zero; the molar ratio of Cl-to-Hg in the resulting melter feed was only 0.4, compared to 12 for the ESCM feeds. The results of the model run at the indicated melter vapor space temperature of 650 C (TI4085D) showed that due to excessive shortage of chloride, only 6% of the mercury fed is expected to get oxidized, mostly as HgCl, while the remaining mercury would exist either as elemental mercury vapor (90%) or HgO (4%). Noting that the measured chloride level in the SB5 qualification sample was an order of magnitude lower than that used in the SB5 simulant, the degree of chloride shortage will be even greater. As a result, the projected level of HgCl in the actual SB5 melter exhaust will be even lower than 6% of the total mercury fed, while that of elemental mercury is likely to be greater than 90%. The homogeneous oxidation of mercury in the off-gas was deemed to be of primary importance based on the postulation that mercury and other volatile salts form submicron sized aerosols upon condensation and thus remain largely in the gas stream downstream of the quencher where they can deposit in the off-gas lines, Steam-Atomized Scrubbers (SAS), and High-Efficiency Mist Eliminator (HEME). Formation of these submicron semi-volatile salts in the condensate liquid is considered to be unlikely, so the liquid phase reactions were considered to be less important. However, subsequent oxidation of mercury in the liquid phase in the off-gas system was examined in a simplified model of the off-gas condensate. It was found that the condensate chemistry was consistent with further oxidation of elemental mercury to Hg{sub 2}Cl{sub 2} and conversion of HgO to chlorides. The results were consistent with the available experimental data. It should also be noted that the model predictions presented in this report do not include any physically entrained solids, which typically account for much of the off-gas carryover on a mass basis. The high elemental mercury vapor content predicted at the DWPF Quencher inlet means that physically entrained solids could provide the necessary surface onto which elemental mercury vapor could condense, thereby coating the solids as well as the internal surfaces of the off-gas system with mercury. Clearly, there are many process benefits to be gained by removing the steam-stripping step from the CPC c

Zamecnik, J.; Choi, A.

2010-08-18T23:59:59.000Z

Note: This page contains sample records for the topic "defense nuclear facilities" 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
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381

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

382

Material handling for the Los Alamos National Laboratory Nuclear Material Storage Facility  

SciTech Connect

This paper will present the design and application of material handling and automation systems currently being developed for the Los Alamos National Laboratory (LANL) Nuclear Material Storage Facility (NMSF) renovation project. The NMSF is a long-term storage facility for nuclear material in various forms. The material is stored within tubes in a rack called a basket. The material handling equipment range from simple lift assist devices to more sophisticated fully automated robots, and are split into three basic systems: a Vault Automation System, an NDA automation System, and a Drum handling System. The Vault Automation system provides a mechanism to handle a basket of material cans and to load/unload storage tubes within the material vault. In addition, another robot is provided to load/unload material cans within the baskets. The NDA Automation System provides a mechanism to move material within the small canister NDA laboratory and to load/unload the NDA instruments. The Drum Handling System consists of a series of off the shelf components used to assist in lifting heavy objects such as pallets of material or drums and barrels.

Pittman, P.; Roybal, J.; Durrer, R.; Gordon, D.

1999-04-01T23:59:59.000Z

383

Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.  

SciTech Connect

Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in the report, there was significant teaming between the various participants to best help the GOI. On-the-ground progress is the focus of the Iraq NDs Program and much of the work is a transfer of technical and practical skills and knowledge that Sandia uses day-to-day. On-the-ground progress was achieved in July of 2008 when the GOI began the physical cleanup and dismantlement of the Active Metallurgical Testing Laboratory (LAMA) facility at Al Tuwaitha, near Baghdad.

Cochran, John Russell; Danneels, Jeffrey John

2009-03-01T23:59:59.000Z

384

ASTM STANDARD GUIDE FOR EVALUATING DISPOSAL OPTIONS FOR REUSE OF CONCRETE FROM NUCLEAR FACILITY DECOMMISSIONING  

SciTech Connect

Within the nuclear industry, many contaminated facilities that require decommissioning contain huge volumes of concrete. This concrete is generally disposed of as low-level waste at a high cost. Much of the concrete is lightly contaminated and could be reused as roadbed, fill material, or aggregate for new concrete, thus saving millions of dollars. However, because of the possibility of volumetric contamination and the lack of a method to evaluate the risks and costs of reusing concrete, reuse is rarely considered. To address this problem, Argonne National Laboratory-East (ANL-E) and the Idaho National Engineering and Environmental Laboratory teamed to write a ''concrete protocol'' to help evaluate the ramifications of reusing concrete within the U.S. Department of Energy (DOE). This document, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Site (1) is based on ANL-E's previously developed scrap metal recycle protocols; on the 10-step method outlined in DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material (2); and on DOE Order 4500.5, Radiation Protection of the Public and the Environment (3). The DOE concrete protocol was the basis for the ASTM Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning, which was written to make the information available to a wider audience outside DOE. The resulting ASTM Standard Guide is a more concise version that can be used by the nuclear industry worldwide to evaluate the risks and costs of reusing concrete from nuclear facility decommissioning. The bulk of the ASTM Standard Guide focuses on evaluating the dose and cost for each disposal option. The user calculates these from the detailed formulas and tabulated data provided, then compares the dose and cost for each disposal option to select the best option that meets regulatory requirements. With this information, the reuse of concrete may be possible, thus reducing dose and decontamination and decommissioning costs. This paper outlines ten steps required to release concrete for reuse and discusses the disposal options covered in the ASTM Standard Guide.

Phillips, Ann Marie; Meservey, Richard H.

2003-02-27T23:59:59.000Z

385

Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4  

Science Conference Proceedings (OSTI)

This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.

Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

1983-09-01T23:59:59.000Z

386

The development of coal-based technologies for Department of Defense facilities. Semiannual technical progress report, March 28, 1994--September 27, 1994  

SciTech Connect

The US Department of Defense (DOD), through an Interagency Agreement with the US Department of Energy (DOE), has initiated a three-phase program with the Consortium for Coal Water Slurry Fuel Technology, with the aim of decreasing DOD`s reliance on imported oil by increasing its use of coal. The program is being conducted as a cooperative agreement between the Consortium and DOE and the first two phases of the program are underway. Activities this reporting period included performing coal beneficiation/preparation studies, conducting combustion performance evaluations, preparing retrofit engineering designs, determining retrofit economics, and installing a micronized coal-water mixture (MCWM) circuit.

Miller, B.G.; Bartley, D.A.; Morrison, J.L. [and others

1995-04-14T23:59:59.000Z

387

Evaluation of Suitability of Selected Set of Department of Defense Military Bases and Department of Energy Facilities for Siting a Small Modular Reactor  

SciTech Connect

This report summarizes the approach that ORNL developed for screening a sample set of US Department of Defense (DOD) military base sites and DOE sites for possible powering with an SMR; the methodology employed, including spatial modeling; and initial results for several sample sites. The objective in conducting this type of siting evaluation is demonstrate the capability to characterize specific DOD and DOE sites to identify any particular issues associated with powering the sites with an SMR using OR-SAGE; it is not intended to be a definitive assessment per se as to the absolute suitability of any particular site.

Poore III, Willis P [ORNL; Belles, Randy [ORNL; Mays, Gary T [ORNL; Omitaomu, Olufemi A [ORNL

2013-03-01T23:59:59.000Z

388

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.

389

Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility  

SciTech Connect

The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

Ansley, Shannon L.

2002-02-20T23:59:59.000Z

390

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites  

Science Conference Proceedings (OSTI)

The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.

Zull, Lawrence M.; Yeniscavich, William [Defense Nuclear Facilities Safety Board, 625 Indiana Ave., NW, Suite 700, Washington, DC 20004-2901 (United States)

2008-01-15T23:59:59.000Z

391

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - EM Statement - November 24, 2009  

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

Defense Nuclear Facilities Safety Board Public Meeting on Defense Nuclear Facilities Safety Board Public Meeting on Oversight of Complex High Hazard Nuclear Operations Statement of Dr. Ines Triay Assistant Secretary, DOE Office of Environmental Management November 24, 2009 Good morning Mr. Vice Chairman and Members of the Defense Nuclear Facilities Safety Board. I appreciate the opportunity to be here today to represent the Department of Energy's Office of Environmental Management (EM) and address the actions our office has taken regarding oversight of complex high hazard nuclear operations. My remarks cover the six topics you provided to the Secretary in your letter dated August 25, 2009. Expectations of the senior Department of Energy (DOE) leadership with respect to safety philosophy and safety management approach.

392

DOE Order Self Study Modules - DOE O 425.1D, Verification of Readiness to Startup or Restart Nuclear Facilities  

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

5.1D 5.1D VERIFICATION OF READINESS TO START UP OR RESTART NUCLEAR FACILITIES DOE O 425.1D Familiar Level June 2011 1 DOE O 425.1D VERIFICATION OF READINESS TO START UP OR RESTART NUCLEAR FACILITIES FAMILIAR LEVEL _________________________________________________________________________ OBJECTIVES Given the familiar level of this module and the resources, you will be able to perform the following: 1. What is the purpose of DOE O 425.1D, Verification of Readiness to Startup or Restart Nuclear Facilities? 2. What are the requirements for determining the level of readiness review [operational readiness reviews (ORRs) and readiness assessments (RAs)]? 3. What are the requirements for determining the startup authorization authority? 4. What are the requirements for startup notification reports?

393

DOE Order Self Study Modules - DOE O 433.1B, Maintenance Management Program for DOE Nuclear Facilities  

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

3.1B 3.1B MAINTENANCE MANAGEMENT PROGRAM FOR DOE NUCLEAR FACILITIES DOE O 433.1B Familiar Level August 2011 1 DOE O 433.1B MAINTENANCE MANAGEMENT PROGRAM FOR DOE NUCLEAR FACILITIES FAMILIAR LEVEL OBJECTIVES Given the familiar level of this module and the resources, you will be able to answer the following questions: 1. What is the objective of DOE O 433.1B, Maintenance Management Program for DOE Nuclear Facilities? 2. What is the purpose for quantitative indicators in maintenance management? 3. What are three types of environmental controls included in a maintenance shop? 4. What is the relationship between DOE G 433.1-1 and DOE O 433.1A? 5. What is the purpose for post-maintenance testing? 6. What is the objective of a good equipment maintenance history program?

394

DOE G 420.1-1A, 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 ...

2012-12-04T23:59:59.000Z

395

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

396

Preparation Guide for U. S. Department of Energy Nonreator Nuclear Facility Document Safety Analysis  

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

SENSITIVE DOE-STD-3009-94 July 1994 CHANGE NOTICE NO. 1 January 2000 CHANGE NOTICE NO. 2 April 2002 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. TS TS 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 Administration, National Technical Information Service, Springfield, VA 22161;

397

Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input  

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

:14 :14 Report number: 2013:14 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries Evaluation for Regulatory Input Robert A. Meck Author: SSM perspektiv SSM har nyligen beslutat om föreskrifter om friklassning av material, loka- ler, byggnader och mark vid verksamhet med joniserande strålning (SSMFS 201 1:2). Föreskrifterna innehåller bland annat krav på att tillståndshavare, vid avveckling av verksamhet med joniserande strålning, ska vidta åtgärder som möjliggör friklassning av lokaler, byggnader och mark. Föreskrifterna innehåller nuklidspecifika friklassningsnivåer i becquerel per m2 för lokaler och byggnader men ger ingen upplysning om vilka friklassningsnivåer som

398

Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities, Volume II  

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

TS NOT MEASUREMENT SENSITIVE DOE-HDBK-3010-94 December 1994 Reaffirmed 2013 DOE HANDBOOK AIRBORNE RELEASE FRACTIONS/RATES AND RESPIRABLE FRACTIONS FOR NONREACTOR NUCLEAR FACILITIES Volume II - Appendices 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; (615) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 487-4650. Order No. DE95004711 DOE-HDBK-3010-94

399

Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analysis  

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

DOE-STD-3009-94 July 1994 CHANGE NOTICE NO. 12 January 2000 5 December 24 April 20021 DOE STANDARD PREPARATION GUIDE FOR U.S DEPARTMENT OF ENERGY NONREACTOR NUCLEAR FACILITY DOCUMENTED SAFETY ANALYSISANALYSES REPORTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS 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 Administration, National Technical Information Service, Springfield, VA 22161;

400

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.

Note: This page contains sample records for the topic "defense nuclear facilities" 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.
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to obtain the most current and comprehensive results.


401

FIRST SODIUM REACTOR EXPERIMENT (SRE) TEST OF HALLAM NUCLEAR POWER FACILITY (HNPF) CONTROL MATERIALS  

SciTech Connect

An experiment was conducted in the SRE to measure temperatures and neutron flux levels in and near a boron-containing simulated control rod. The data are being used to check analytical methods developed for prediction of control rod heat generation rates and maximum temperatures in this type of control rod in the Hallam Nuclear Power Facility. The maximum observed temperatures with a reactor power level of 20 Mw were 1363 deg F for a boron-- nickel alloy ring having a 0.105-in. radial clearance with the thimble and 1100 deg F for a boron -nickel alloy ring having a 0.020-in. radial clearance. The maximum temperature difference between the coolant and the control rod was 473 deg F. It is concluded that the expected greater heat generation rates in the Hallam reactor would prohibit the use of boron-containing absorber materials in a combined a him-safety rod. (auth)

Arneson, S.O.

1959-06-01T23:59:59.000Z

402

Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2008  

Science Conference Proceedings (OSTI)

This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 2008 annual reports submitted by five of the seven categories1 of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. The annual reports submitted by these licensees consist of radiation exposure records for each monitored individual. These records are analyzed for trends and presented in this report in terms of collective dose and the distribution of dose among the monitored individuals. Because there are no geologic repositories for high-level waste currently licensed and no low-level waste disposal facilities in operation, only five categories will be considered in this report.

U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research

2009-12-01T23:59:59.000Z

403

Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities, Volume 1  

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

TS NOT MEASUREMENT SENSITIVE DOE-HDBK-3010-94 December 1994 Reaffirmed 2013 DOE HANDBOOK AIRBORNE RELEASE FRACTIONS/RATES AND RESPIRABLE FRACTIONS FOR NONREACTOR NUCLEAR FACILITIES Volume I - Analysis of Experimental Data 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; (615) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 487-4650.

404

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

405

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes  

SciTech Connect

This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

NONE

1997-09-01T23:59:59.000Z

406

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities.

Bryant, J.W.; Nenni, J.A.

2003-05-22T23:59:59.000Z

407

A COMPARISON OF THE NUCLEAR DEFENSE CAPABILITIES ON NUCLEAR AND COAL-FIRED POWER PLANTS. FUEL COST STUDY VARIOUS REACTORS AT 100 AND 300 Mwe  

SciTech Connect

Appendices C and D may further be identified as SL1925 and CF-61-12- 20(Rev.), respectively. A comparative report is presented in which the economics and feasibility of plant protection from nuclear attack by plant hardening, remote siting, and utilization of optional fueling concepts for the coal-fired plant are evaluated. (J.R.D.)

Gift, E.H.

1962-05-29T23:59:59.000Z

408

Thermal and flow analyses of the Nuclear Materials Storage Facility Renovation Title I 60% design  

Science Conference Proceedings (OSTI)

The authors are continuing to use the computational fluid dynamics code CFX-4.2 to evaluate the steady-state thermal-hydraulic conditions in the Nuclear Material Storage Facility Renovation Title 1 60% Design. The analyses build on those performed for the 30% design. They have run an additional 9 cases to investigate both the performance of the passive vault and of an individual drywell. These cases investigated the effect of wind on the inlet tower, the importance of resolving boundary layers in the analyses, and modifications to the porous-medium approach used in the earlier analyses to represent better the temperature fields resulting from the detailed modeling of the boundary layers. The difference between maximum temperatures of the bulk air inside the vault for the two approaches is small. They continued the analyses of the wind effects around the inflector fixture, a canopy and cruciform device, on the inlet tower by running a case with the wind blowing diagonally across the inflector. The earlier analyses had investigated a wind that was blowing parallel to one set of vanes on the inflector. Several subcases for these analyses investigated coupling the analysis to the facility analysis and design changes for the inflector.

Knight, T.D.; Steinke, R.G.; Mueller, C.

1998-08-01T23:59:59.000Z

409

Unclassified Controlled Nuclear Information (UCNI) | Department of Energy  

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

Unclassified Controlled Nuclear Unclassified Controlled Nuclear Information (UCNI) Unclassified Controlled Nuclear Information (UCNI) Welcome to the Unclassified Controlled Nuclear Information (UCNI) webpage. This page is designed to provide information, answer questions, and provide a point of contact for UCNI inquiries. UCNI is certain unclassified information about nuclear facilities and nuclear weapons that must be controlled because its unauthorized release could have a significant adverse effect on the national security or public health and safety. The Director, Office of Classification (OC), decides what specific information is UCNI. For information under the cognizance of the National Nuclear Security Administration (NNSA), the decisions are made in coordination with the Associate Administrator for Defense Nuclear

410

Sampling and analysis plan for the preoperational environmental survey of the spent nuclear fuel project facilities  

Science Conference Proceedings (OSTI)

This sampling and analysis plan will support the preoperational environmental monitoring for construction, development, and operation of the Spent Nuclear Fuel (SNF) Project facilities, which have been designed for the conditioning and storage of spent nuclear fuels; particularly the fuel elements associated with the operation of N-Reactor. The SNF consists principally of irradiated metallic uranium, and therefore includes plutonium and mixed fission products. The primary effort will consist of removing the SNF from the storage basins in K East and K West Areas, placing in multicanister overpacks, vacuum drying, conditioning, and subsequent dry vault storage in the 200 East Area. The primary purpose and need for this action is to reduce the risks to public health and safety and to the environment. Specifically these include prevention of the release of radioactive materials into the air or to the soil surrounding the K Basins, prevention of the potential migration of radionuclides through the soil column to the nearby Columbia River, reduction of occupational radiation exposure, and elimination of the risks to the public and to workers from the deterioration of SNF in the K Basins.

MITCHELL, R.M.

1999-04-01T23:59:59.000Z

411

Analysis of environment, safety, and health (ES{ampersand}H) management systems for Department of Energy (DOE) Defense Programs (DP) facilities  

Science Conference Proceedings (OSTI)

The purpose of this paper is to provide a summary analysis and comparison of various environment, safety, and health (ES&H) management systems required of, or suggested for use by, the Departrnent of Energy Defense Programs` sites. The summary analysis is provided by means of a comparison matrix, a set of Vean diagrams that highlights the focus of the systems, and an `End Gate` filter diagram that integrates the three Vean diagrams. It is intended that this paper will act as a starting point for implementing a particular system or in establishing a comprehensive site-wide integrated ES&H management system. Obviously, the source documents for each system would need to be reviewed to assure proper implementation of a particular system. The matrix compares nine ES&H management systems against a list of elements generated by identifying the unique elements of all the systems. To simplify the matrix, the elements are listed by means of a brief title. An explanation of the matrix elements is provided in Attachment 2 entitled, `Description of System Elements.` The elements are categorized under the Total Quality Management (TQM) `Plan, Do, Check, Act` framework with the added category of `Policy`. (The TQM concept is explained in the `DOE Quality Management implementation Guidelines,` July 1997 (DOE/QM- 0008)). The matrix provides a series of columns and rows to compare the unique elements found in each of the management systems. A `V` is marked if the element is explicitly identified as part of the particular ES&H management system. An `X` is marked if the element is not found in the particular ES&H management system, or if it is considered to be inadequately addressed. A `?` is marked if incorporation of the element is not clear. Attachment I provides additional background information which explains the justification for the marks in the matrix cells. Through the Vean diagrams and the `End Gate` filter in Section 3, the paper attempts to pictorially display the focus of each system with respect to ES&H, the hazard of concern, and any limitations with respect to the TQM categories. A summary evaluation and explanation of each of the systems is provided in Section 4 of the paper. Several other ES&H systems were reviewed in preparation of the paper, but were not specifically included as a system in this matrix. Only those ES&H management systems that are potentially applicable to DOE Defense Program sites were included as part of the matrix comparison. A description of other ES&H management systems that were evaluated, but not specifically incorporated in this matrix comparison, are provided in Attachment 3 entitled, `Other ES&H Management Systems Reviewed.` In the past, it has been difficult integrating ES&H into work planning for several reasons. One barrier to this integration has been the complexity caused by the existence of several `stove pipe` ES&H systems. By analyzing the unique elements of the various ES&H systems, as well as their strengths and limitations, and their similarities and differences, it is envisioned that this paper will aid in facilitating the integration of ES&H into work planning. This paper was developed by the Office of Defense Programs (DP-45) and all questions or comments should be directed to Anthony Neglia of that office at (301) 903-3531 or Anthony.Neglia@dp.doe.gov.

Neglia, A. V., LLNL

1998-03-01T23:59:59.000Z

412

The development of coal-based technologies for Department of Defense facilities. Semiannual technical progress report, September 28, 1992--March 27, 1993  

Science Conference Proceedings (OSTI)

The US Department of Defense (DOD), through an Interagency Agreement with the US Department of Energy (DOE), has initiated a three-phase program with the Consortium for Coal-Water Slurry Fuel Technology, with the aim of decreasing DOD`s reliance on imported oil by increasing its use of coal. The program is being conducted as a cooperative agreement between the Consortium and DOE and the first phase of the program is underway. Phase I activities are focused on developing clean, coal-based combustion technologies for the utilization of both micronized coal-water mixtures (MCWMs) and dry, micronized coal (MC) in fuel oil-designed industrial boilers. Phase II research and development activities will continue to focus on industrial boiler retrofit technologies by addressing emissions control and pre-combustion (i.e., slagging combustion and/or gasification) strategies for the utilization of high ash and high sulfur coals. Phase III activities will examine coal-based fuel combustion systems that cofire wastes. Each phase includes an engineering cost analysis and technology assessment. The activities and status of Phase I are described below. The objective in Phase I is to deliver fully engineered retrofit options for a fuel oil- designed watertube boiler located on a DOD installation to fire either MCWM or MC. This will be achieved through a program consisting of the following five tasks: (1) Coal Beneficiation and Preparation; (2) Combustion Performance Evaluation; (3) Engineering Design; (4) Engineering and Economic Analysis; (5) Final Report/Submission of Design Package.

Miller, B.G.; Scaroni, A.W.; Hogg, R. [and others

1993-05-13T23:59:59.000Z

413

Statement of Anne M. Harrington, Deputy Administrator for Defense...  

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

Speech Statement of Anne M. Harrington, Deputy Administrator for Defense Nuclear Nonproliferation to the Senate Armed Services Sub Committee On Emerging Threats and Capabilities...

414

Statement of Anne M. Harrington, Deputy Administrator for Defense...  

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

Statement of Anne M. Harrington, Deputy Administrator for Defense Nuclear Nonproliferation to the Senate Armed Services Sub Committee On Emerging Threats and Capabilities...

415

Independent Oversight Lessons Learned from Targeted Reviews of Implementation Verification Review Processes at Department of Energy Nuclear Facilities, May 2013  

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

Lessons Learned from Targeted Reviews of Implementation Verification Review Processes at Department of Energy Nuclear Facilities 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 Acronyms ......................................................................................................................................................ii Executive Summaiy .....................................................................................................................................iii 1.0 Introduction ............................................................................................................................................. 1

416

Independent Oversight Lessons Learned from Targeted Reviews of Implementation Verification Review Processes at Department of Energy Nuclear Facilities, May 2013  

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

Lessons Learned from Targeted Reviews of Implementation Verification Review Processes at Department of Energy Nuclear Facilities 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 Acronyms ......................................................................................................................................................ii Executive Summaiy .....................................................................................................................................iii 1.0 Introduction ............................................................................................................................................. 1

417

CFD analysis and experimental investigation associated with the design of the Los Alamos nuclear materials storage facility  

Science Conference Proceedings (OSTI)

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory is being renovated for long-term storage of canisters designed to hold heat-generating nuclear materials, such as powders, ingots, and other components. The continual heat generation within the canisters necessitates a reliable cooling scheme of sufficient magnitude which maintains the stored material temperatures within acceptable limits. The primary goal of this study was to develop both an experimental facility and a computational fluid dynamics (CFD) model of a subsection of the NMSF which could be used to observe general performance trends of a proposed passive cooling scheme and serve as a design tool for canister holding fixtures. Comparisons of numerical temperature and velocity predictions with empirical data indicate that the CFD model provides an accurate representation of the NMSF experimental facility. Minor modifications in the model geometry and boundary conditions are needed to enhance its accuracy, however, the various fluid and thermal models correctly capture the basic physics.

Bernardin, J.D.; Hopkins, S.; Gregory, W.S.; Martin, R.A. [and others

1997-06-01T23:59:59.000Z

418

Guideline to good practices for control and calibration of measuring and test equipment (M TE) at DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The purpose of the Guideline to Good Practices for Control and Calibration of Measuring and Test Equipment (M TE) at DOE Nuclear Facilities is to provide contractor maintenance organizations with information that may be used for the development and implementation of a rigorously controlled maintenance program directed at controlling and calibrating M TE used for maintenance tasks at DOE nuclear facilities. This document is intended to be an example guideline for the implementation of DOE Order 4330.4A, Maintenance Management Program, Chapter II, Element 11. DOE contractors should not feel obligated to adopt all parts of this guide. Rather, they should use the information contained herein as a guide for developing an M TE program applicable to their facility.

Not Available

1993-03-01T23:59:59.000Z

419

December 17, 1998 Memo, Incentives for the Department's Facility Representative Program  

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

mE mE F 1325.8 (a89) EFG (U7-W) United States Government Department of Energy memorandum DATE: December 17, 1998 REPLY TO ATTN OF: FM- 10(J. Hassenfeldt, 202 586-1643) SUBJECT Incentives for the Department's Facility Representative Program TO:Distribution The Department's Revised Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 93-3 has once again underscored the Department's commitment to maintaining the technical capability necessary to safely manage and operate our defense nuclear facilities. Attracting and retaining highly qualified employees and placing them in our critical technical positions is vital to fi.dfilling this commitment. You have identified 95'% of your Facility Representative positions as critical technical positions. The Office of Field Management has noted a 12'?40 annual attrition rate of Facility Representatives

420