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Note: This page contains sample records for the topic "waste technical review" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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1

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington are pleased to transmit a technical report prepared by the Nuclear Waste Technical Review Board (Board. Based on its review of data gathered by the DOE and the Center for Nuclear Waste Regulatory Analyses

2

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington Dear Speaker Pelosi, Senator Byrd, and Secretary Bodman: The Nuclear Waste Technical Review Board, and transporting high-level radioactive waste and spent nuclear fuel. The Board is required to report its findings

3

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

con202vf UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300, the Nuclear Waste Technical Review Board (Board) submits its second report of 2003 in accordance with provisions of the Nuclear Waste Policy Amendments Act of 1987, Public Law 100-203. The Act requires the Board

4

United States Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

United States Nuclear Waste Technical Review Board Experience Gained From Programs to Manage High-Level Radioactive Waste and Spent Nuclear Fuel in the United States and Other Countries A Report to Congress and the Secretary of Energy April 2011 #12;#12;U.S. Nuclear Waste Technical Review Board Experience Gained From

5

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to The U.S. Congress And The Secretary of Energy January 1, 2003, to December 31, 2003 #12;U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to The U.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE TECHNICAL REVIEW BOARD 2003 Dr. Michael L. Corradini

6

U.S. Nuclear Waste Technical Review Board Performance Evaluation  

E-Print Network [OSTI]

Addendum A Addendum A U.S. Nuclear Waste Technical Review Board Performance Evaluation Fiscal Year 2005 The U.S. Nuclear Waste Technical Review Board The Nuclear Waste Policy Amendments Act nuclear fuel and defense high-level radioactive waste. The Act also estab lished the U.S. Nuclear Waste

7

Appendix A U.S. Nuclear Waste Technical Review  

E-Print Network [OSTI]

Appendices Appendices 37 #12;#12;Appendix A Appendix A U.S. Nuclear Waste Technical Review Board as chair, on the U.S. Nuclear Regulatory Commission's Advisory Commit tee on Nuclear Waste. His areas to the Nuclear Waste Technical Review Board on June 26, 2002, by President George W. Bush. Dr. Abkowitz

8

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to January 1, 2001, to January 31, 2002 The U All NWTRB reports are available at www.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 Appendices Appendix A U.S. Nuclear Waste Technical Review Board Members

9

Appendix A U.S. Nuclear Waste Technical Review  

E-Print Network [OSTI]

Appendices Appendices 31 #12;#12;Appendix A Appendix A U.S. Nuclear Waste Technical Review Board.S. Nuclear Waste Technical Review Board as Chairman on September 10, 2004, by President George W. Bush. Dr­2004), 4 years as chair, on the U.S. Nuclear Regulatory Commission's Advisory Committee on Nuclear Waste

10

Nuclear Waste Technical Review Board Members Appendix A 53  

E-Print Network [OSTI]

51 Appendix A Nuclear Waste Technical Review Board Members #12;#12;Appendix A 53 B. John Garrick, Ph.D., P.E. Chairman Dr. B. John Garrick was appointed to the U.S. Nuclear Waste Technical Review, on the U.S. Nuclear Regula- tory Commission's Advisory Committee on Nuclear Waste. His areas of expertise

11

U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

U.S. Nuclear Waste Technical Review Board Report to The U.S. Congressand The Secretary of Energy March 1, 2006­December 31, 2007 #12;#12;U.S. Nuclear Waste Technical Review Board Report to The U in this report. #12;#12;#12;U.S. Nuclear Waste Technical Review Board B. John Garrick, Ph.D., P.E., Chairman

12

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD The U.S. Congress And The Secretary of Energy Report.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE TECHNICAL REVIEW BOARD Dr. Jared L. Cohon, Chairman Carnegie, California Dr. Debra S. Knopman Progressive Policy Institute Washington, D.C. Dr. Priscilla P. Nelson

13

The U.S. Nuclear Waste Technical Review Board Status Update ...  

Office of Environmental Management (EM)

The U.S. Nuclear Waste Technical Review Board Status Update The U.S. Nuclear Waste Technical Review Board Status Update The U.S. Nuclear Waste Technical Review Board Status Update...

14

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

the Board will focus include the technical implications of very long-term dry storage of commercial spent, facility operation and design, and waste storage and disposal. con266vf #12;con266vf 2 The Board to have responsibility under existing law for the long-term management and disposition of DOE-owned spent

15

Nuclear Waste Technical Review Board Strategic Plan FY 20082013  

E-Print Network [OSTI]

on compliance activities, in conduct- ing its evaluation, the Board will encourage DOE through its science its review of DOE activities into three technical areas: preclosure operations, including surface-facility design and operations and the transport of spent nuclear fuel and high-level radioactive waste from

16

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

) characterization of a potential repository site at Yucca Mountain in Nevada. In a December 11, 2001, letter to the Secretary and Congress on the DOE's technical and scientific work related to a decision on a Yucca Mountain's Yucca Mountain technical and scientific investigations since the Board's inception; (2) an evaluation

17

Savannah River Site - Salt Waste Processing Facility Independent Technical Review  

Broader source: Energy.gov (indexed) [DOE]

SALT WASTE PROCESSING FACILITY SALT WASTE PROCESSING FACILITY INDEPENDENT TECHNICAL REVIEW November 22, 2006 Conducted by: Harry Harmon, Team Lead Civil/Structural Sub Team Facility Safety Sub Team Engineering Sub Team Peter Lowry, Lead James Langsted, Lead George Krauter, Lead Robert Kennedy Chuck Negin Art Etchells Les Youd Jerry Evatt Oliver Block Loring Wyllie Richard Stark Tim Adams Tom Anderson Todd LaPointe Stephen Gosselin Carl Costantino Norman Moreau Patrick Corcoran John Christian Ken Cooper Kari McDaniel _____________________________ Harry D. Harmon ITR Team Leader SPD-SWPF-217 SPD-SWPF-217: Salt Waste Processing Facility Independent Technical Review 11/22/2006 ACKNOWLEDGEMENT The ITR Team wishes to thank Shari Clifford of Pacific Northwest National Laboratory for

18

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

to develop a proposed repository for the permanent disposal of such waste at Yucca Mountain in Nevada the DOE's methods of scientific and engineering analysis of the Yucca Mountain site. Those meetings This has been an eventful year for the Yucca Mountain program, during which important changes have been

19

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

) activities related to evaluating the suitability of the Yucca Mountain site and takes a long-term view the DOE's viability assessment (VA) of the Yucca Mountain site, design of the repository and waste package considerable progress in characterizing the Yucca Mountain site. We also appreciate recent efforts by OCRWM

20

Communication Between the U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

Appendix F Appendix F Communication Between the U.S. Nuclear Waste Technical Review Board on Energy and Air Quality on March 25, 2004 143 #12;#12;Appendix F UNITED STATES NUCLEAR WASTE TECHNICAL much for your written questions related to my testimony on behalf of the Nuclear Waste Technical Review

Note: This page contains sample records for the topic "waste technical review" 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

U.S. Nuclear Waste Technical Review Board Strategic Plan: Fiscal Years 20042009  

E-Print Network [OSTI]

Appendix G Appendix G U.S. Nuclear Waste Technical Review Board Strategic Plan: Fiscal Years 2004­2009 (Revised March 2004) Statement of the Board The Nuclear Waste Policy Amendments Act of 1987 directed the U-level radioactive waste. The Act also established the U.S. Nuclear Waste Technical Review Board as an indepen dent

22

U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

Board Review of OCRWM's Technical and Scientific Investigations. . . . . . . .9 Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .33 Idaho National Laboratory

23

The U.S. Nuclear Waste Technical Review Board Status Update  

Broader source: Energy.gov (indexed) [DOE]

NWTRB NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board The U S Nuclear Waste Technical Review Board The U.S. Nuclear Waste Technical Review Board Status Update Presented to: National Transportation Stakeholders Forum Presented By: National Transportation Stakeholders Forum Mark Abkowitz May 11, 2011 The Board's Statutory Mandate * The 1987 amendments to the Nuclear Waste Policy Act (NWPA) established the U S Nuclear Waste Technical Review Board established the U.S. Nuclear Waste Technical Review Board. * The Board evaluates the technical and scientific validity of DOE activities related to: - transportation, packaging and storage of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) - site characterization, design, development, and operations of facilities for

24

Nuclear Waste Technical Review Board Correspondence with the Department of Energy  

E-Print Network [OSTI]

85 Appendix E Nuclear Waste Technical Review Board Correspondence with the Department of Energy #12;#12;Appendix E 87 Nuclear Waste Technical Review Board Correspondence with the Department of Energy I n of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The letters typically provide

25

U.S. Nuclear Waste Technical Review Board Fiscal Year 2002-2007 Strategic Plan  

E-Print Network [OSTI]

Appendix G Appendix G U.S. Nuclear Waste Technical Review Board Fiscal Year 2002-2007 Strategic Plan Statement of the Chairman The U.S. Nuclear Waste Technical Review Board was established of Energy Mission The Board's mission, established in the Nuclear Waste Policy Amendments Act (NWPAA

26

Nuclear Waste Technical Review Board Thermal-Response Evaluation of Yucca Mountain  

E-Print Network [OSTI]

Nuclear Waste Technical Review Board Thermal-Response Evaluation of Yucca Mountain During the Preclosure and Postclosure Phases July 2008 #12;Thermal Response Evaluation of Yucca Mountain July 2008 Page of the thermal response of the proposed Yucca Mountain repository for various thermal loadings. The U. S. Nuclear

27

Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review  

Broader source: Energy.gov (indexed) [DOE]

Salt Waste Processing Facility Independent Technical Review Harry Harmon January 9, 2007 2 U.S. Department of Energy Outline * SWPF Process Overview * Major Risks * Approach for Conducting Review * Discussion of Findings * Conclusions 3 U.S. Department of Energy Salt Waste Processing Facility 4 U.S. Department of Energy SWPF Process Overview Alpha Finishing Process CSSX Alpha Strike Process MST/ Sludge Cs Strip Effluent DSS 5 U.S. Department of Energy BOTTOM LINE The SWPF Project is ready to move into final design. 6 U.S. Department of Energy Major Risks * Final geotechnical data potentially could result in redesign of the PC-3 CPA base mat and structure. * Cost and schedule impacts arising from the change from ISO-9001 to NQA-1 quality assurance requirements. * The "de-inventory, flush, and then hands-on

28

Greater-than-Class C low-level waste characterization technical review process  

SciTech Connect (OSTI)

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs.

Hutchison, D.; Magleby, M.

1990-01-01T23:59:59.000Z

29

Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report  

Broader source: Energy.gov (indexed) [DOE]

Comprehensive Review of the Hanford Tank Waste Treatment and Immobilization Plant Estimate at Completion Assessment Conducted by an Independent Team of External Experts March 2006 Comprehensive Review of the Hanford Waste Treatment Plant Estimate at Completion Page i of vi Executive Summary Following an August 2005 corporate commitment to the Secretary of Energy, Bechtel National, Inc. chartered a team of industry experts to review the technical, cost, and schedule aspects of the Waste Treatment and Immobilization Plant (WTP) project. This summary reflects the observations and recommendations of the EAC Review Team (ERT), comprised of six senior industry consultants, six retired Bechtel employees, one current Bechtel employee, three employees of Bechtel's competitors, and

30

External Technical Reviews | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Services » Waste Management » Tank Waste and Waste Processing » Services » Waste Management » Tank Waste and Waste Processing » External Technical Reviews External Technical Reviews Documents Available for Download March 17, 2006 Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Full Document and Summary Versions are available for download previous 1 2 next Miscellaneous Supporting Information January 9, 2007 Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review August 10, 2006 Savannah River Site - Tank 48 Briefing on SRS Tank 48 Independent Technical Review August 10, 2006 Savannah River Site - Tank 48 Transmittal Letter of SRS Tank 48 Review

31

External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process  

Broader source: Energy.gov (indexed) [DOE]

Hanford Site Liquid Waste Process Hanford Site Liquid Waste Process September 2009 Monica C. Regalbuto Office of Waste Processing DOE/EM Kevin G. Brown Vanderbilt University and CRESP David W. DePaoli Oak Ridge National Laboratory Candido Pereira Argonne National Laboratory John R. Shultz Office of Waste Processing DOE/EM External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process September 2009 Acknowledgements The Review Team thanks Mr. Glyn Trenchard, Team Lead for Planning and Coordination Waste Disposition Project, U.S. Department of Energy--Office of River Protection, Mr. Paul Rutland, RPP System Planning Manager for Washington River Protection Solutions, and Mr. Ernie Lee,

32

Savannah River Site- Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review  

Broader source: Energy.gov [DOE]

This is a presentation outlining the Salt Waste Processing Facility process, major risks, approach for conducting reviews, discussion of the findings, and conclusions.

33

External Technical Reviews | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Waste Management » Tank Waste and Waste Processing » Waste Management » Tank Waste and Waste Processing » External Technical Reviews External Technical Reviews Documents Available for Download September 1, 2011 Peer Review of the ASCEM Program 2010 Full Document and Summary Versions are available for download September 1, 2011 Compilation of ETR Summaries ETR Summaries from 2011 February 15, 2011 External Technical Review Report for Small Column Ion Exchange Technology at Savannah River Site Full Document and Summary Versions are available for download September 30, 2009 External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process Full Document and Summary Versions are available for download June 30, 2009 Evaluation of System Level Modeling and Simulation Tools in Support of

34

Low-level liquid radioactive waste treatment at Murmansk, Russia: Technical design and review of facility upgrade and expansion  

SciTech Connect (OSTI)

The governments of Norway and the US have committed their mutual cooperation and support the Murmansk Shipping Company (MSCo) to expand and upgrade the Low-Level Liquid Radioactive Waste (LLRW) treatment system located at the facilities of the Russian company RTP Atomflot, in Murmansk, Russia. RTP Atomflot provides support services to the Russian icebreaker fleet operated by the MSCo. The objective is to enable Russia to permanently cease disposing of this waste in Arctic waters. The proposed modifications will increase the facility`s capacity from 1,200 m{sup 3} per year to 5,000 m{sup 3} per year, will permit the facility to process high-salt wastes from the Russian Navy`s Northern fleet, and will improve the stabilization and interim storage of the processed wastes. The three countries set up a cooperative review of the evolving design information, conducted by a joint US and Norwegian technical team from April through December, 1995. To ensure that US and Norwegian funds produce a final facility which will meet the objectives, this report documents the design as described by Atomflot and the Russian business organization, ASPECT, both in design documents and orally. During the detailed review process, many questions were generated, and many design details developed which are outlined here. The design is based on the adsorption of radionuclides on selected inorganic resins, and desalination and concentration using electromembranes. The US/Norwegian technical team reviewed the available information and recommended that the construction commence; they also recommended that a monitoring program for facility performance be instituted.

Dyer, R.S.; Diamante, J.M. [Environmental Protection Agency, Washington, DC (United States). Office of International Activities; Duffey, R.B. [Brookhaven National Lab., Upton, NY (United States)] [and others

1996-07-01T23:59:59.000Z

35

Nuclear Waste Assessment System for Technical Evaluation (NUWASTE)  

Broader source: Energy.gov (indexed) [DOE]

NWTRB NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board U.S. Nuclear Waste Technical Review Board: Roles and Priorities Presented by: Nigel Mote, Executive Director, U.S. Nuclear Waste Technical Review Board May 14, 2013 Hyatt Regency Buffalo, Buffalo, NY. Presented to: National Transportation Stakeholders' Forum NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board The Board's Statutory Mandate * The 1987 amendments to the Nuclear Waste Policy Act (NWPA) established the U.S. Nuclear Waste Technical Review Board. * The Board evaluates the technical and scientific validity of DOE activities related to implementing the NWPA, including: - transportation, packaging, and storage of spent nuclear fuel (SNF) and high-level radioactive waste (HLW)

36

Technical Review Panel Report  

Broader source: Energy.gov (indexed) [DOE]

TRP Report v7, 12 Aug 2012 TRP Report Final December 2012 TRP Report v7, 12 Aug 2012 TRP Report Final December 2012 Advanced Reactor Concepts Technical Review Panel Report Evaluation and Identification of future R&D on eight Advanced Reactor Concepts, conducted April - September 2012 December 2012 Public release version 2 Public release version 3 Table of Contents Summary ................................................................................................................................... 4 1. Overview of the Technical Review Panel Process ............................................................... 5 2. Technical Review Panel Criteria ......................................................................................... 6 3. Concept Summaries ........................................................................................................... 8

37

External Technical Review Report  

Broader source: Energy.gov (indexed) [DOE]

External Technical Review Report External Technical Review Report March 2010 U U . . S S . . D D e e p p a a r r t t m m e e n n t t o o f f E E n n e e r r g g y y O O f f f f i i c c e e o o f f E E n n v v i i r r o o n n m m e e n n t t a a l l M M a a n n a a g g e e m m e e n n t t External Technical Review (ETR) Process Guide September 2008 U.S. DOE Office of Environmental Management September 2008 External Technical Review Process Guide Page 2 of 37 TABLE OF CONTENTS 1.0 INTRODUCTION ....................................................................................................................... 3 1.1 Purpose of Process ............................................................................................................ 3 1.2 Background .........................................................................................................................

38

U.S. Nuclear Waste Technical Review Board Strategic Plan: Fiscal Years 20042009  

E-Print Network [OSTI]

.S. Department of Energy (DOE) to characterize one site, at Yucca Mountain in Nevada, to determine its behavior of a Yucca Mountain repository, (b) developing a reposi tory design, (c) reducing technical understanding of the potential behavior of a repository at Yucca Mountain, (b) developing a repository design

39

TECHNICAL PEER REVIEW REPORT - YUCCA MOUNTAIN: WASTE PACKAGE CLOSURE CONTROL SYSTEM  

SciTech Connect (OSTI)

The objective of the Waste Package Closure System (WPCS) project is to assist in the disposal of spent nuclear fuel (SNF) and associated high-level wastes (HLW) at the Yucca Mountain site in Nevada. Materials will be transferred from the casks into a waste package (WP), sealed, and placed into the underground facility. The SNF/HLW transfer and closure operations will be performed in an aboveground facility. The objective of the Control System is to bring together major components of the entire WPCS ensuring that unit operations correctly receive, and respond to, commands and requests for data. Integrated control systems will be provided to ensure that all operations can be performed remotely. Maintenance on equipment may be done using hands-on or remote methods, depending on complexity, exposure, and ease of access. Operating parameters and nondestructive examination results will be collected and stored as permanent electronic records. Minor weld repairs must be performed within the closure cell if the welds do not meet the inspection acceptance requirements. Any WP with extensive weld defects that require lids to be removed will be moved to the remediation facility for repair.

NA

2005-10-25T23:59:59.000Z

40

Technical requirements specification for tank waste retrieval  

SciTech Connect (OSTI)

This document provides the technical requirements specification for the retrieval of waste from the underground storage tanks at the Hanford Site. All activities covered by this scope are conducted in support of the Tank Waste Remediation System (TWRS) mission.

Lamberd, D.L.

1996-09-26T23:59:59.000Z

Note: This page contains sample records for the topic "waste technical review" 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

External Technical Review for Evaluation of System Level Modeling and  

Broader source: Energy.gov (indexed) [DOE]

for Evaluation of System Level Modeling for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process Full Document and Summary Versions are available for download External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process Summary - System Level Modeling and Simulation Tools for Hanford More Documents & Publications Hanford Site C Tank Farm Meeting Summary - May 2009 System Planning for Low-Activity Waste at Hanford Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External

42

The U.S. Congress and The Secretary of Energy U.S. NUCLEAR WASTE TECHNICAL  

E-Print Network [OSTI]

Report t The U.S. Congress and The Secretary of Energy U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Web site. #12;NUCLEAR WASTE TECHNICAL REVIEW BOARD Dr. Jared L. Cohon, Chairman Carnegie Mellon. Debra S. Knopman Progressive Policy Institute Washington, D.C. Dr. Priscilla P. Nelson National Science

43

Mechanical Engineering Department Technical Review  

SciTech Connect (OSTI)

The Mechanical Engineering Department Technical Review is published to inform readers of various technical activities within the Department, promote exchange of ideas, and give credit to personnel who are achieving the results. The report is presented in two parts: technical achievements and publication abstracts. The first is divided into seven sections, each of which reports on an engineering division and its specific activities related to nuclear tests, nuclear explosives, weapons, energy systems, engineering sciences, magnetic fusion, and materials fabrication.

Carr, R.B.; Denney, R.M. (eds.)

1981-07-01T23:59:59.000Z

44

Radioactive Waste Management Complex Wide Review | Department...  

Office of Environmental Management (EM)

Radioactive Waste Management Complex Wide Review Radioactive Waste Management Complex Wide Review The main goal of this complex-wide review was to obtain feedback from DOE sites...

45

Waste Package Materials Performance Peer Review | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Waste Package Materials Performance Peer Review Waste Package Materials Performance Peer Review Waste Package Materials Performance Peer Review A consensus peer review of the current technical basis and the planned experimental and modeling program for the prediction of the long-term performance of waste package materials being considered for use in a proposed repository at Yucca Mountain, Nevada. Waste Package Materials Performance Peer Review A Compilation of Special Topic Reports Wastepackagematerials_PPRP_final.pdf Evaluation of the Final Report: Waste Package Materials Performance Peer Review Panel Multi-Purpose_Canister_System_Evaluation.pdf More Documents & Publications Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) A Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water

46

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Review, Waste Treatment and Immobilization Plant - March 2012 March 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality This...

47

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Review, Waste Treatment and Immobilization Plant - March 2013 March 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S....

48

Independent Oversight Review, Sodium Bearing Waste Treatment...  

Energy Savers [EERE]

Federal - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Federal - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project -...

49

Independent Oversight Review, Sodium Bearing Waste Treatment...  

Energy Savers [EERE]

Contractor - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Contractor - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project...

50

Independent Oversight Review, Waste Treatment and Immobilization...  

Energy Savers [EERE]

January 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - January 2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant...

51

Waste management project technical baseline description  

SciTech Connect (OSTI)

A systems engineering approach has been taken to describe the technical baseline under which the Waste Management Project is currently operating. The document contains a mission analysis, function analysis, requirement analysis, interface definitions, alternative analysis, system definition, documentation requirements, implementation definitions, and discussion of uncertainties facing the Project.

Sederburg, J.P.

1997-08-13T23:59:59.000Z

52

Technical area status report for low-level mixed waste final waste forms. Volume 1  

SciTech Connect (OSTI)

The Final Waste Forms (FWF) Technical Area Status Report (TASR) Working Group, the Vitrification Working Group (WG), and the Performance Standards Working Group were established as subgroups to the FWF Technical Support Group (TSG). The FWF TASR WG is comprised of technical representatives from most of the major DOE sites, the Nuclear Regulatory Commission (NRC), the EPA Office of Solid Waste, and the EPA`s Risk Reduction Engineering Laboratory (RREL). The primary activity of the FWF TASR Working Group was to investigate and report on the current status of FWFs for LLNM in this TASR. The FWF TASR Working Group determined the current status of the development of various waste forms described above by reviewing selected articles and technical reports, summarizing data, and establishing an initial set of FWF characteristics to be used in evaluating candidate FWFS; these characteristics are summarized in Section 2. After an initial review of available information, the FWF TASR Working Group chose to study the following groups of final waste forms: hydraulic cement, sulfur polymer cement, glass, ceramic, and organic binders. The organic binders included polyethylene, bitumen, vinyl ester styrene, epoxy, and urea formaldehyde. Section 3 provides a description of each final waste form. Based on the literature review, the gaps and deficiencies in information were summarized, and conclusions and recommendations were established. The information and data presented in this TASR are intended to assist the FWF Production and Assessment TSG in evaluating the Technical Task Plans (TTPs) submitted to DOE EM-50, and thus provide DOE with the necessary information for their FWF decision-making process. This FWF TASR will also assist the DOE and the MWIP in establishing the most acceptable final waste forms for the various LLMW streams stored at DOE facilities.

Mayberry, J.L.; DeWitt, L.M. [Science Applications International Corp., Idaho Falls, ID (United States); Darnell, R. [EG and G Idaho, Inc., Idaho Falls, ID (United States)] [and others

1993-08-01T23:59:59.000Z

53

Technical considerations for evaluating substantially complete containment of high-level waste within the waste package  

SciTech Connect (OSTI)

This report deals with technical information that is considered essential for demonstrating the ability of the high-level radioactive waste package to provide substantially complete containment'' of its contents (vitrified waste form or spent light-water reactor fuel) for a period of 300 to 1000 years in a geological repository environment. The discussion is centered around technical considerations of the repository environment, materials and fabrication processes for the waste package components, various degradation modes of the materials of construction of the waste packages, and inspection and monitoring of the waste package during the preclosure and retrievability period, which could begin up to 50 years after initiation of waste emplacement. The emphasis in this report is on metallic materials. However, brief references have been made to other materials such as ceramics, graphite, bonded ceramic-metal systems, and other types of composites. The content of this report was presented to an external peer review panel of nine members at a workshop held at the Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, San Antonio, Texas, April 2--4, 1990. The recommendations of the peer review panel have been incorporated in this report. There are two companion reports; the second report in the series provides state-of-the-art techniques for uncertainty evaluations. 97 refs., 1 fig.

Manaktala, H.K. (Southwest Research Inst., San Antonio, TX (USA). Center for Nuclear Waste Regulatory Analyses); Interrante, C.G. (Nuclear Regulatory Commission, Washington, DC (USA). Div. of High-Level Waste Management)

1990-12-01T23:59:59.000Z

54

Office of Waste Processing Technical Exchange  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

EM Waste Processing Technical Exchange 2010 Agenda EM Waste Processing Technical Exchange 2010 Agenda (Sponsored by EM Office of Waste Processing) November 16 - 18, 2010; Loews Hotel, Atlanta, GA 11/2/2010 Monday, November 15, 2010 5:00 - 7:00 pm Early Registration and Speaker Check-in *Light Refreshments Tuesday Morning, November 16, 2010 Session 1: Technical Exchange Opening (Chair: W. Wilmarth); Salon D Live Webcast Click the video icon to view Session 1 Live Webcast Submit Question Click the Question icon to submit a question. Time Topic Speaker 7:00 am Registration and Check-in 8:00 am S01-01 Welcome T. Michalske, SRNL 8:05 am S01-02 Opening Comments Y. Collazo, DOE-EM 8:15 am S01-03 Introductions G. Flowers, SRNS 8:20 am S01-04 Opening Remarks I. Triay, DOE-EM 8:45 am S01-05 Status of Waste Processing Technology Development

55

Hanford Waste Vitrification Plant technical manual  

SciTech Connect (OSTI)

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01T23:59:59.000Z

56

Office of Waste Processing Technical Exchange  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Event Media Links Event Media Links Session 1: Technical Exchange Opening Topic Speaker PDF Podcast S01-01 Welcome T. Michalske, SRNL N/A Podcast S01-03 Introductions G. Flowers, SRNS N/A Podcast S01-04 Opening Remarks I. Triay, DOE-EM Presentation PDF Podcast S01-05 Status of Waste Processing Technology Development S. Schneider, DOE-EM Presentation PDF Podcast S01-06 Hanford/SRS Tank Waste Path Forward K. Subramanian/ T. Sams, SRR/WRPS Presentation PDF Podcast S01-07 Fluidized Bed Steam Reformer Overview B. Mason, TTT Presentation PDF Podcast S01-08 Next Generation Cesium Solvent B.Moyer/S. Fink/M. Geeting, ORNL/SRNL/SRR Presentation PDF Podcast S01-09 Rotary Microfilter Development/Small Column Ion Exchange D. Herman/ R. Edwards, SRNL/SRR Presentation PDF Podcast Session 2: Increased Waste Loading - Improved Current Processing

57

Independent Oversight Review, Savannah River Site Salt Waste Processing  

Broader source: Energy.gov (indexed) [DOE]

Savannah River Site Salt Waste Savannah River Site Salt Waste Processing Facility - August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development. This report documents the results of an independent oversight review of the safety basis and design development for the Salt Waste Processing Facility (SWPF) at the U.S. Department of Energy (DOE) Savannah River Site. The review was performed February 12-14, 2013 by DOE's Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The purpose of the review was to evaluate the safety basis, design, and the associated technical documents developed for

58

Independent Oversight Review, Savannah River Site Salt Waste Processing  

Broader source: Energy.gov (indexed) [DOE]

Savannah River Site Salt Waste Savannah River Site Salt Waste Processing Facility - August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development. This report documents the results of an independent oversight review of the safety basis and design development for the Salt Waste Processing Facility (SWPF) at the U.S. Department of Energy (DOE) Savannah River Site. The review was performed February 12-14, 2013 by DOE's Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The purpose of the review was to evaluate the safety basis, design, and the associated technical documents developed for

59

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Waste Treatment and Immobilization Plant - October 2012 October 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report...

60

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Waste Treatment and Immobilization Plant - August 2012 August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report...

Note: This page contains sample records for the topic "waste technical review" 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

Independent Oversight Review, Waste Treatment and Immobilization...  

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

Waste Treatment and Immobilization Plant - November 2011 November 2011 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality This...

62

Voluntary Protection Program Onsite Review, Transuranic Waste...  

Energy Savers [EERE]

Transuranic Waste Processing Center - September 2012 Voluntary Protection Program Onsite Review, Transuranic Waste Processing Center - September 2012 September 2012 Evaluation to...

63

Independent Oversight Review, Waste Treatment and Immobilization...  

Office of Environmental Management (EM)

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

64

Office of Waste Processing Technical Exchange  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Agenda Hotel Register Contacts Event Media Speaker Information Home Agenda Hotel Register Contacts Event Media Speaker Information Home Environmental Management Waste Processing Technical Exchange 2010 in Atlanta, GA, November 16 - 18. Over the past eight years, personnel from the three sites, Savannah River/Hanford/Idaho along with others receiving funding from the Environmental Management Office of Waste Processing have met to exchange recent results of on-going field operations and technology development. The purpose of this exchange is to provide a forum for discussion of each Site's efforts to accelerate cleanup operations. Keys to success and lessons learned are openly exchanged in a manner to allow for open discussion between operations, engineering and scientists to accelerate transition of technologies from concepts to field implementation.

65

3116 WASTE DETERMINATIONS PUBLIC MEETINGS AND GENERIC TECHNICAL ISSUES  

Broader source: Energy.gov (indexed) [DOE]

3116 WASTE DETERMINATIONS PUBLIC MEETINGS AND GENERIC TECHNICAL 3116 WASTE DETERMINATIONS PUBLIC MEETINGS AND GENERIC TECHNICAL ISSUES SUMMARIES 3116 WASTE DETERMINATIONS PUBLIC MEETINGS AND GENERIC TECHNICAL ISSUES SUMMARIES Below are public meeting summaries and general technical issue summaries relating to 3116 waste determinations. The 3116 Public Meeting Summaries cover public meetings that the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) periodically host to provide the status of activities associated with waste determinations under Section 3116 (a) of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005. 3116 Public Meeting Summaries - July 2007 3116 Public Meeting Summaries - November 2006 The Generic Technical Issues Summaries cover the informal technical discussions between representatives of the Department of Energy (DOE),

66

Two stage fluid bed-plasma gasification process for solid waste valorisation: Technical review and preliminary thermodynamic modelling of sulphur emissions  

SciTech Connect (OSTI)

Highlights: Black-Right-Pointing-Pointer We investigate sulphur during MSW gasification within a fluid bed-plasma process. Black-Right-Pointing-Pointer We review the literature on the feed, sulphur and process principles therein. Black-Right-Pointing-Pointer The need for research in this area was identified. Black-Right-Pointing-Pointer We perform thermodynamic modelling of the fluid bed stage. Black-Right-Pointing-Pointer Initial findings indicate the prominence of solid phase sulphur. - Abstract: Gasification of solid waste for energy has significant potential given an abundant feed supply and strong policy drivers. Nonetheless, significant ambiguities in the knowledge base are apparent. Consequently this study investigates sulphur mechanisms within a novel two stage fluid bed-plasma gasification process. This paper includes a detailed review of gasification and plasma fundamentals in relation to the specific process, along with insight on MSW based feedstock properties and sulphur pollutant therein. As a first step to understanding sulphur partitioning and speciation within the process, thermodynamic modelling of the fluid bed stage has been performed. Preliminary findings, supported by plant experience, indicate the prominence of solid phase sulphur species (as opposed to H{sub 2}S) - Na and K based species in particular. Work is underway to further investigate and validate this.

Morrin, Shane, E-mail: shane.morrin@ucl.ac.uk [Department of Chemical Engineering, University College London, London, WC1E 7JE (United Kingdom); Advanced Plasma Power, South Marston Business park, Swindon, SN3 4DE (United Kingdom); Lettieri, Paola, E-mail: p.lettieri@ucl.ac.uk [Department of Chemical Engineering, University College London, London, WC1E 7JE (United Kingdom); Chapman, Chris, E-mail: chris.chapman@app-uk.com [Advanced Plasma Power, South Marston Business park, Swindon, SN3 4DE (United Kingdom); Mazzei, Luca, E-mail: l.mazzei@ucl.ac.uk [Department of Chemical Engineering, University College London, London, WC1E 7JE (United Kingdom)

2012-04-15T23:59:59.000Z

67

Review Of Rheology Models For Hanford Waste Blending  

SciTech Connect (OSTI)

The area of rheological property prediction was identified as a technology need in the Hanford Tank Waste - waste feed acceptance initiative area during a series of technical meetings among the national laboratories, Department of Energy-Office of River Protection, and Hanford site contractors. Meacham et al. delivered a technical report in June 2012, RPP-RPT-51652 ''One System Evaluation of Waste Transferred to the Waste Treatment Plant'' that included estimating of single shell tank waste Bingham plastic rheological model constants along with a discussion of the issues inherent in predicting the rheological properties of blended wastes. This report was selected as the basis for moving forward during the technical meetings. The report does not provide an equation for predicting rheological properties of blended waste slurries. The attached technical report gives an independent review of the provided Hanford rheological data, Hanford rheological models for single tank wastes, and Hanford rheology after blending provided in the Meacham report. The attached report also compares Hanford to SRS waste rheology and discusses some SRS rheological model equations for single tank wastes, as well as discussing SRS experience with the blending of waste sludges with aqueous material, other waste sludges, and frit slurries. Some observations of note: Savannah River Site (SRS) waste samples from slurried tanks typically have yield stress >1 Pa at 10 wt.% undissolved solids (UDS), while core samples largely have little or no yield stress at 10 wt.% UDS. This could be due to how the waste has been processed, stored, retrieved, and sampled or simply in the differences in the speciation of the wastes. The equations described in Meacham's report are not recommended for extrapolation to wt.% UDS beyond the available data for several reasons; weak technical basis, insufficient data, and large data scatter. When limited data are available, for example two to three points, the equations are not necessarily satisfactory (justified) for interpolations, due to the number of unknown variables equal the number of known data points, resulting in a coefficient of determination of one. SRS has had some success predicting the rheology of waste blends for similar waste types using rheological properties of the individual wastes and empirical blending viscosity equations. Both the Kendall-Monroe and Olney-Carlson equations were used. High accuracy was not obtained, but predictions were reasonable compared to measured flow curves. Blending SRS processed waste with frit slurry (much larger particles and the source of SRS glass formers) is a different sort of problem than that of two similar slurries of precipitated waste particles. A different approach to rheology prediction has had some success describing the incorporation of large frit particles into waste than the one used for blending two wastes. In this case, the Guth-Simha equation was used. If Hanford waste is found to have significant particles in the >100 ?m diameter range, then it might be necessary to handle those particles differently from broadly distributed waste particles that are primarily <30 ?m in diameter. The following are recommendations for the Hanford tank farms: Investigate the impact of large-scale mixing operations on yield stress for one or more Hanford tanks to see if Hanford waste rheological properties change to become more like SRS waste during both tank retrieval and tank qualification operations; Determine rheological properties of mobilized waste slurries by direct measurement rather than by prediction; Collect and characterize samples during the waste feed qualification process for each campaign; o From single source tanks that feed the qualification tanks; o Blends from the qualification tanks; Predictive rheological models must be used with caution, due to the lack of data to support such models and the utilization of the results that come from these models in making process decisions (e.g. the lack of actual operation experience). As experience is ga

Koopman, D. C.; Stone, M.

2013-09-26T23:59:59.000Z

68

Nuclear waste peer review 'needs more transparency'  

Science Journals Connector (OSTI)

... [LONDON] Scientists advising the UK government on radioactive waste disposal have called on the ... disposal have called on the waste management agency Nirex to open up its peer-review arrangements to independent scrutiny if it ...

Ehsan Masood

1997-01-23T23:59:59.000Z

69

Energy Department Announces New Technical Review to Assess Black Cells at  

Broader source: Energy.gov (indexed) [DOE]

Energy Department Announces New Technical Review to Assess Black Energy Department Announces New Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant Energy Department Announces New Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant August 2, 2012 - 12:00pm Addthis Media Contact 202-586-4940 WASHINGTON, D.C. - The U.S. Department of Energy announced today that Secretary of Energy Steven Chu has assembled a group of independent technical experts to assess the Hanford Site's Waste Treatment Plant (WTP), specifically as it relates to the facility's "black cells." The review involves the plant's capability, as designed, to detect equipment failure and to repair failed equipment inside the WTP's black cells. Black cells are enclosed concrete rooms within the WTP Pretreatment

70

Energy Department Announces New Technical Review to Assess Black Cells at  

Broader source: Energy.gov (indexed) [DOE]

Announces New Technical Review to Assess Black Announces New Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant Energy Department Announces New Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant August 2, 2012 - 12:15pm Addthis News Media Contact (202) 586-4940 WASHINGTON -- The U.S. Department of Energy announced today that Secretary of Energy Steven Chu has assembled a group of independent technical experts to assess the Hanford Site's Waste Treatment Plant (WTP), specifically as it relates to the facility's "black cells." The review involves the plant's capability, as designed, to detect equipment failure and to repair failed equipment inside the WTP's black cells. Black cells are enclosed concrete rooms within the WTP Pretreatment facility that contain tanks and piping. Due to high levels of

71

Energy Department Announces New Technical Review to Assess Black Cells at  

Broader source: Energy.gov (indexed) [DOE]

Energy Department Announces New Technical Review to Assess Black Energy Department Announces New Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant Energy Department Announces New Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant August 2, 2012 - 12:00pm Addthis Media Contact 202-586-4940 WASHINGTON, D.C. - The U.S. Department of Energy announced today that Secretary of Energy Steven Chu has assembled a group of independent technical experts to assess the Hanford Site's Waste Treatment Plant (WTP), specifically as it relates to the facility's "black cells." The review involves the plant's capability, as designed, to detect equipment failure and to repair failed equipment inside the WTP's black cells. Black cells are enclosed concrete rooms within the WTP Pretreatment

72

Energy Department Announces New Technical Review to Assess Black Cells at  

Broader source: Energy.gov (indexed) [DOE]

Technical Review to Assess Black Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant Energy Department Announces New Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant August 2, 2012 - 12:15pm Addthis News Media Contact (202) 586-4940 WASHINGTON -- The U.S. Department of Energy announced today that Secretary of Energy Steven Chu has assembled a group of independent technical experts to assess the Hanford Site's Waste Treatment Plant (WTP), specifically as it relates to the facility's "black cells." The review involves the plant's capability, as designed, to detect equipment failure and to repair failed equipment inside the WTP's black cells. Black cells are enclosed concrete rooms within the WTP Pretreatment facility that contain tanks and piping. Due to high levels of

73

Independent Oversight Review, Waste Treatment and Immobilization...  

Energy Savers [EERE]

May 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of Energy (DOE) Office of Enforcement and Oversight...

74

Enterprise Assessments Review, Waste Isolation Pilot Plant -...  

Energy Savers [EERE]

December 2014 Review of the Waste Isolation Pilot Plant Recovery Plan for Operating Diesel Equipment with Available Underground Airflows. The Office of Nuclear Safety and...

75

Enterprise Assessments Review, Waste Isolation Pilot Plant -...  

Energy Savers [EERE]

December, 2014 Review of the Waste Isolation Pilot Plant Conduct of Maintenance Recovery Plan The Office of Nuclear Safety and Environmental Assessments, within the U.S. Department...

76

Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank  

Broader source: Energy.gov (indexed) [DOE]

ETR Tank Waste Treatment and Immobilization Plant - Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Full Document and Summary Versions are available for download Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Summary - Flowsheet for the Hanford Waste Treatment Plant More Documents & Publications Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

77

Enterprise Assessments Review, Hanford Site Waste Treatment and...  

Office of Environmental Management (EM)

Enterprise Assessments Review, Hanford Site Waste Treatment and Immobilization Plant - September 2014 Enterprise Assessments Review, Hanford Site Waste Treatment and Immobilization...

78

Independent Oversight Review, Hanford Waste Treatment and Immobilizati...  

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

December 2013 Independent Oversight Review, Hanford Waste Treatment and Immobilization Plant - December 2013 December 2013 Review of the Hanford Site Waste Treatment and...

79

Independent Oversight Review, Hanford Waste Treatment and Immobilizati...  

Office of Environmental Management (EM)

March 2014 Independent Oversight Review, Hanford Waste Treatment and Immobilization Plant - March 2014 March 2014 Review of the Hanford Site Waste Treatment and Immobilization...

80

Independent Oversight Review, Hanford Site Waste Treatment and...  

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

Hanford Site Waste Treatment and Immobilization Plant - June 2014 Independent Oversight Review, Hanford Site Waste Treatment and Immobilization Plant - June 2014 June 2014 Review...

Note: This page contains sample records for the topic "waste technical review" 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

Independent Oversight Review, Oak Ridge Transuranic Waste Processing...  

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

Transuranic Waste Processing Center, September 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013 September 2013 Review of Management...

82

Identification of technical problems encountered in the shallow land burial of low-level radioactive wastes  

SciTech Connect (OSTI)

A review of problems encountered in the shallow land burial of low-level radioactive wastes has been made in support of the technical aspects of the National Low-Level Waste (LLW) Management Research and Development Program being administered by the Low-Level Waste Management Program Office, Oak Ridge National Laboratory. The operating histories of burial sites at six major DOE and five commercial facilities in the US have been examined and several major problems identified. The problems experienced st the sites have been grouped into general categories dealing with site development, waste characterization, operation, and performance evaluation. Based on this grouping of the problem, a number of major technical issues have been identified which should be incorporated into program plans for further research and development. For each technical issue a discussion is presented relating the issue to a particular problem, identifying some recent or current related research, and suggesting further work necessary for resolving the issue. Major technical issues which have been identified include the need for improved water management, further understanding of the effect of chemical and physical parameters on radionuclide migration, more comprehensive waste records, improved programs for performance monitoring and evaluation, development of better predictive capabilities, evaluation of space utilization, and improved management control.

Jacobs, D.G.; Epler, J.S.; Rose, R.R.

1980-03-01T23:59:59.000Z

83

Evaluation of the Technical Basis for Extended Dry Storage and  

E-Print Network [OSTI]

-- Executive Summary U.S. Nuclear Waste Technical Review Board December 2010 #12;U.S.U.S. Nuclear Waste Technical Review Board Authors This report was prepared for the U.S. Nuclear Waste Technical Review Board.NWTRB.GOV ii #12;Extended Dry Storage and Transportation of Used Nuclear Fuel U.S. Nuclear Waste Technical

84

Review of Used Nuclear Fuel Storage and Transportation Technical Gap  

Broader source: Energy.gov (indexed) [DOE]

Analyses Analyses Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analyses The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development activities related to storage, transportation, and disposal of used nuclear fuel and high-level radioactive waste. The mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. The Storage and Transportation activities within the UFDC are being developed to address issues regarding the extended storage of UNF and its subsequent

85

Independent Technical Review of In-Tank Precipitation (ITP) at the Savannah River Site  

SciTech Connect (OSTI)

An Independent Technical Review of In-Tank Precipitation (ITP) and Extended Sludge Processing (ESP) at the Savannah River Site (SRS) was carried out in March, 1993. The review focused on ITP/ESP equipment and chemical processes, integration of ITP/ESP within the High Level Waste (HLW) and Defense Waste Processing Facility (DWPF) systems, and management and regulatory concerns. Following the ITR executive summary, this report includes: Chapter I--summary assessment; Chapter II--recommendations; and Chapter III--technical evaluations.

Not Available

1993-06-01T23:59:59.000Z

86

Low-Level Waste Disposal Facility Federal Review Group Manual...  

Office of Environmental Management (EM)

Low-Level Waste Disposal Facility Federal Review Group Manual Low-Level Waste Disposal Facility Federal Review Group Manual This Revision 3 of the Low-Level Waste Disposal Facility...

87

Risk-assessment-methodology development for waste isolation in geologic media. Technical review of documents NUREG/CR-0394, NUREG/CR-0424, NUREG/CR-0458  

SciTech Connect (OSTI)

A review of five documents that were prepared for the USNRC by Sandia Laboratories is presented in this report. The documents covered in the present review include: NUREG/CR-1262, NUREG/CR-1376, NUREG/CR-1377, NUREG/CR-1397 and NUREG/CR-1608. This constitutes the second phase of the review; the first phase was reported in Volume 1 of NUREG/CR-1672, November 1980. Two of the documents concern simplified computational methods illustrative of the calculations necessary to produce a response surface. Three of the reports pertain to statistical methods, including the application of Latin hypercube Sampling (LHS). The following observations have been made relative to the above reports: (1) the reports are, in general, difficult to read, due, in part, to unnecessarily complicated notation and lack of adequate explanation and examples, (2) the relationship of the work to similar work in the US and abroad is not discussed, and (3) limitations of the LHS method are not discussed in sufficient depth. The Sandia's response to this review is published as NUREG/CR-2428. Volume 1 is scheduled for completion in June 1982.

Stevens, C.A.; Fullwood, R.R.; Basin, S.L.

1980-11-01T23:59:59.000Z

88

DOE Office of Waste Processing Technical Exchange - Agenda  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

June 1, 2009 June 1, 2009 Agenda Hotel Information Registration Presentation Guidelines Poster Guidelines Webcast Waiver Contacts Home Waste Processing Technical Exchange Agenda (Version 1.1) Pre-Registration: Monday, May 18, 5:00p - 7:00p Organizer/Session Chair: Blocker (early registration & speaker check-in) Day 1: Tuesday, May 19 Registration - 7:00a - 8:00a Session One - Opening Session Two - Waste Retrieval and Closure 1 Session Three - Waste Form Development Day 2: Wednesday, May 20 Session Four - Pretreatment 1 Session Five - Facility Readiness and Start-up Session Six - Pretreatment 2 Session Seven - Waste Retrieval and Closure 2 Session Eight - Poster Presentations Day 3: Thursday, May 21 Session Nine - Regulatory Activity and Performance Assessment Session Ten - Waste Storage and Tank Farm Operational Improvements

89

Hanford Waste Treatment Plant Construction Quality Review  

Broader source: Energy.gov (indexed) [DOE]

ARPT-WTP-2011-002 ARPT-WTP-2011-002 Site: DOE Hanford Waste Treatment Plant Subject: Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the Hanford Waste Treatment Plant Construction Quality Review Dates of Activity 02/14/2011 - 02/17/2011 Report Preparer Joseph Lenahan Activity Description/Purpose: The purpose of the visit was to perform a review of construction quality assurance at the Waste Treatment Plant (WTP) site activities concurrently with the Department of Energy (DOE) WTP staff. One focus area for this visit was piping and pipe support installations. The Office of Health, Safety and Security (HSS) attended several Bechtel National Incorporated (BNI) project meetings, reviewed the WTP project quality assurance program, reviewed DOE-WTP inspection reports completed by the DOE-WTP

90

INDEPENDENT TECHNICAL REVIEW OF THE FOCUSED FEASIBILITY STUDY AND PROPOSED PLAN FOR DESIGNATED SOLID WASTE MANAGEMENT UNITS CONTRIBUTING TO THE SOUTHWEST GROUNDWATER PLUME AT THE PADUCAH GASEOUS DIFFUSION PLANT  

SciTech Connect (OSTI)

The U. S. Department of Energy (DOE) is currently developing a Proposed Plan (PP) for remediation of designated sources of chlorinated solvents that contribute contamination to the Southwest (SW) Groundwater Plume at the Paducah Gaseous Diffusion Plant (PGDP), in Paducah, KY. The principal contaminants in the SW Plume are trichloroethene (TCE) and other volatile organic compounds (VOCs); these industrial solvents were used and disposed in various facilities and locations at PGDP. In the SW plume area, residual TCE sources are primarily in the fine-grained sediments of the Upper Continental Recharge System (UCRS), a partially saturated zone that delivers contaminants downward into the coarse-grained Regional Gravel Aquifer (RGA). The RGA serves as the significant lateral groundwater transport pathway for the plume. In the SW Plume area, the four main contributing TCE source units are: (1) Solid Waste Management Unit (SWMU) 1 / Oil Landfarm; (2) C-720 Building TCE Northeast Spill Site (SWMU 211A); (3) C-720 Building TCE Southeast Spill Site (SWMU 211B); and (4) C-747 Contaminated Burial Yard (SWMU 4). The PP presents the Preferred Alternatives for remediation of VOCs in the UCRS at the Oil Landfarm and the C-720 Building spill sites. The basis for the PP is documented in a Focused Feasibility Study (FFS) (DOE, 2011) and a Site Investigation Report (SI) (DOE, 2007). The SW plume is currently within the boundaries of PGDP (i.e., does not extend off-site). Nonetheless, reasonable mitigation of the multiple contaminant sources contributing to the SW plume is one of the necessary components identified in the PGDP End State Vision (DOE, 2005). Because of the importance of the proposed actions DOE assembled an Independent Technical Review (ITR) team to provide input and assistance in finalizing the PP.

Looney, B.; Eddy-Dilek, C.; Amidon, M.; Rossabi, J.; Stewart, L.

2011-05-31T23:59:59.000Z

91

2013 Geothermal Technologies Office Peer Review Technical Report  

Broader source: Energy.gov [DOE]

The 2013 Geothermal Technologies Office Peer Review Report is now available for download. The report provides a summary and compilation of expert, independent technical feedback on GTO-funded projects, as well as feedback from the Peer Review reviewers.

92

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect (OSTI)

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6.

Laycak, D T

2008-06-16T23:59:59.000Z

93

Independent Oversight Review, Savannah River Site Salt Waste...  

Energy Savers [EERE]

Waste Treatment and Immobilization Plant - May 2013 Voluntary Protection Program Onsite Review, Salt Waste Processing Facility Construction Project - February 2013 CRAD,...

94

Technical specifications for mechanical recycling of agricultural plastic waste  

SciTech Connect (OSTI)

Highlights: Technical specifications for agricultural plastic wastes (APWs) recycling proposed. Specifications are the base for best economical and environmental APW valorisation. Analysis of APW reveals inherent characteristics and constraints of APW streams. Thorough survey on mechanical recycling processes and industry as it applies to APW. Specifications for APW recycling tested, adjusted and verified through pilot trials. - Abstract: Technical specifications appropriate for the recycling of agricultural plastic wastes (APWs), widely accepted by the recycling industry were developed. The specifications establish quality standards to be met by the agricultural plastics producers, users and the agricultural plastic waste management chain. They constitute the base for the best economical and environmental valorisation of the APW. The analysis of the APW streams conducted across Europe in the framework of the European project LabelAgriWaste revealed the inherent characteristics of the APW streams and the inherent constraints (technical or economical) of the APW. The APW stream properties related to its recycling potential and measured during pilot trials are presented and a subsequent universally accepted simplified and expanded list of APW recycling technical specifications is proposed and justified. The list includes two sets of specifications, applied to two different quality categories of recyclable APW: one for pellet production process (Quality I) and another one for plastic profile production process (Quality II). Parameters that are taken into consideration in the specifications include the APW physical characteristics, contamination, composition and degradation. The proposed specifications are focused on polyethylene based APW that represents the vast majority of the APW stream. However, the specifications can be adjusted to cover also APW of different materials (e.g. PP or PVC) that are found in very small quantities in protected cultivations in Europe. The adoption of the proposed specifications could transform this waste stream into a labelled commodity traded freely in the market and will constitute the base for the best economical and environmental valorisation of the APW.

Briassoulis, D., E-mail: briassou@aua.gr; Hiskakis, M.; Babou, E.

2013-06-15T23:59:59.000Z

95

Regulatory Review of the Safety Case for Siting Licensing of Saligny Low and Intermediate Waste Repository  

SciTech Connect (OSTI)

The paper contains the regulatory review comments produced following submission of siting license application of Saligny repository. The regulatory review was conducted in order to verify the compliance with Romanian regulatory criteria and requirements. After assessment of completeness of safety case and availability of supporting documents the review the main technical areas started. The review process was focused on the site characteristics, waste characteristics, safety considerations as scenarios development, mathematical models, identification and treatment of uncertainties, availability of parameters. (authors)

Dogaru, D.M. [National Commission for Nuclear Activities Control, 5 Bucharest (Romania)

2008-07-01T23:59:59.000Z

96

Review Of Rheology Modifiers For Hanford Waste  

SciTech Connect (OSTI)

As part of Savannah River National Laboratory (SRNL)'s strategic development scope for the Department of Energy - Office of River Protection (DOE-ORP) Hanford Tank Waste Treatment and Immobilization Plant (WTP) waste feed acceptance and product qualification scope, the SRNL has been requested to recommend candidate rheology modifiers to be evaluated to adjust slurry properties in the Hanford Tank Farm. SRNL has performed extensive testing of rheology modifiers for use with Defense Waste Processing Facility (DWPF) simulated melter feed - a high undissolved solids (UDS) mixture of simulated Savannah River Site (SRS) Tank Farm sludge, nitric and formic acids, and glass frit. A much smaller set of evaluations with Hanford simulated waste have also been completed. This report summarizes past work and recommends modifiers for further evaluation with Hanford simulated wastes followed by verification with actual waste samples. Based on the review of available data, a few compounds/systems appear to hold the most promise. For all types of evaluated simulated wastes (caustic Handford tank waste and DWPF processing samples with pH ranging from slightly acidic to slightly caustic), polyacrylic acid had positive impacts on rheology. Citric acid also showed improvement in yield stress on a wide variety of samples. It is recommended that both polyacrylic acid and citric acid be further evaluated as rheology modifiers for Hanford waste. These materials are weak organic acids with the following potential issues: The acidic nature of the modifiers may impact waste pH, if added in very large doses. If pH is significantly reduced by the modifier addition, dissolution of UDS and increased corrosion of tanks, piping, pumps, and other process equipment could occur. Smaller shifts in pH could reduce aluminum solubility, which would be expected to increase the yield stress of the sludge. Therefore, it is expected that use of an acidic modifier would be limited to concentrations that do not appreciably change the pH of the waste; Organics are typically reductants and could impact glass REDOX if not accounted for in the reductant addition calculations; Stability of the modifiers in a caustic, radioactive environment is not known, but some of the modifiers tested were specifically designed to withstand caustic conditions; These acids will add to the total organic carbon content of the wastes. Radiolytic decomposition of the acids could result in organic and hydrogen gas generation. These potential impacts must be addressed in future studies with simulants representative of real waste and finally with tests using actual waste based on the rheology differences seen between SRS simulants and actual waste. The only non-organic modifier evaluated was sodium metasilicate. Further evaluation of this modifier is recommended if a reducing modifier is a concern.

Pareizs, J. M.

2013-09-30T23:59:59.000Z

97

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

of Energy in characterizing a site at Yucca Mountain, Nevada, as a possible location for a permanent to a decision by the Secretary of Energycurrently scheduled for 2001on whether to recommend the Yucca Mountain a clear description of how a Yucca Mountain repository would perform over thousands of years and how

98

Nuclear Waste Technical Review Board Performance Plan  

E-Print Network [OSTI]

, Yucca Mountain in Nevada. The NWPAA also established the Board and charged it with evaluating the NWPA. The activities include characterizing the Yucca Mountain site and packaging and transporting of the repository block (ECRB) at Yucca Mountain. 1.3.2. Evaluate data from the drift-scale heater test. 1

99

Advanced Reactor Concepts Technical Review Panel Report | Department of  

Broader source: Energy.gov (indexed) [DOE]

Advanced Reactor Concepts Technical Review Panel Report Advanced Reactor Concepts Technical Review Panel Report Advanced Reactor Concepts Technical Review Panel Report This report documents the establishment of a technical review process and the findings of the Advanced Reactor Concepts (ARC) Technical Review Panel (TRP).1 The intent of the process is to identify R&D needs for viable advanced reactor concepts in order to inform DOE-NE R&D investment decisions. A goal of the process is to facilitate greater engagement between DOE and industry. The process involved establishing evaluation criteria, conducting a pilot review, soliciting concept inputs from industry entities, reviewing the concepts by TRP members and compiling the results. The eight concepts received from industry spanned a range of reactor types

100

FINAL REPORT WASTE PACKAGE MATERIALS PERFORMANCE PEER REVIEW PANEL  

Broader source: Energy.gov (indexed) [DOE]

REPORT REPORT WASTE PACKAGE MATERIALS PERFORMANCE PEER REVIEW PANEL FEBRUARY 28, 2002 This document is not an official copy and is for informational purposes only. Signature Page Preface Executive Summary TABLE OF CONTENTS 1. INTRODUCTION 1.1 Organization of the Peer Review 1.2 Objectives of the Review 1.3 Content of the Final Report 2. MAIN FINDINGS 2.1 Perspective 2.2 Overall Findings 2.3 Corrosion Degradation Modes 2.4 Higher or Lower Temperature Operating Modes 2.5 Long-Term Uniform Corrosion of Passive Metal 2.6 Alloy Specification and Comparison 2.7 Technical Issues to be Resolved 2.8 Organizational-Managerial Issues 3. SUMMARY OF DEGRADATION MODES AND CONTRIBUTING FACTORS 3.1 Introduction 3.2 Repository Conditions: Overview of Time, Temperature, Environment

Note: This page contains sample records for the topic "waste technical review" 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

Enterprise Assessments Review, Waste Isolation Pilot Plant December 2014  

Broader source: Energy.gov [DOE]

Review of the Waste Isolation Pilot Plant Recovery Plan for Operating Diesel Equipment with Available Underground Airflows

102

Independent Oversight Review, Advanced Mixed Waste Treatment Project- April 2013  

Broader source: Energy.gov [DOE]

Review of Radiation Protection Program Implementation at the Advanced Mixed Waste Treatment Project of the Idaho Site

103

Independent Oversight Review, Oak Ridge Transuranic Waste Processing...  

Broader source: Energy.gov (indexed) [DOE]

Facility - December 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Facility - December 2013 December 2013 Review of the Fire Protection Program and Fire...

104

Independent Oversight Review of the Hanford Site Waste Treatment...  

Office of Environmental Management (EM)

Oversight's November 2013 review included observation of a pneumatic pressure test, structural steel bolting in the High-Level Waste Facility (HLW), and review of the...

105

Analysis of waste treatment requirements for DOE mixed wastes: Technical basis  

SciTech Connect (OSTI)

The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation`s allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered.

NONE

1995-02-01T23:59:59.000Z

106

Independent Oversight Review, Sodium Bearing Waste Treatment Project -  

Broader source: Energy.gov (indexed) [DOE]

Sodium Bearing Waste Treatment Sodium Bearing Waste Treatment Project - Contractor - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Contractor - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Contractor Operational Readiness Review This report documents the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit (SBWTP-IWTU) contractor Operational Readiness Review (C-ORR). The review was conducted at the Idaho Site from February 27 to March 6, 2012. This report discusses the background, scope, results, and conclusions of the review, as well as

107

Review of DOE Waste Package Program. Semiannual report, October 1984-March 1985. Volume 8  

SciTech Connect (OSTI)

A large number of technical reports on waste package component performance were reviewed over the last year in support of the NRC`s review of the Department of Energy`s (DOE`s) Environmental Assessment reports. The intent was to assess in some detail the quantity and quality of the DOE data and their relevance to the high-level waste repository site selection process. A representative selection of the reviews is presented for the salt, basalt, and tuff repository projects. Areas for future research have been outlined. 141 refs.

Davis, M.S. (ed.)

1985-12-01T23:59:59.000Z

108

Technical Evaluations of Proposed Remote-Handled Transuranic Waste Characterization Requirements at WIPP  

SciTech Connect (OSTI)

Characterization, packaging, transport, handling and disposal of remotely handled transuranic (RH TRU) waste at WIPP will be different than similar operations with contact handled transuranic (CH TRU) waste. This paper presents results of technical evaluations associated with the planned disposal of remotely handled transuranic waste at the Waste Isolation Pilot Plant (WIPP).

Anastas, G.; Channell, J. K.

2002-02-26T23:59:59.000Z

109

EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review |  

Broader source: Energy.gov (indexed) [DOE]

Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review Environmental Management Advisory Board EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review Report Number TWS #003 EMAB EM-TWS SRS / Hanford Tank Waste June 23, 2011 This is the second report of the Environmental Management Tank Waste Subcommittee (EMTWS) of the Environmental Management Advisory Board (EMAB). The first report was submitted and accepted by the Assistant Secretary for Environmental Management (EM-1) in September 2010. The EM-TWS responded to three charges from EM-1 regarding the Waste Treatment and Immobilization Plant at Hanford (WTP) under construction in Richland, Washington. EM's responses were timely, and efforts have been

110

Independent Oversight Review, Sodium Bearing Waste Treatment Project -  

Broader source: Energy.gov (indexed) [DOE]

Sodium Bearing Waste Treatment Sodium Bearing Waste Treatment Project - Federal - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Federal - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Federal Operational Readiness Review This report documents the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit (SBWTP-IWTU) DOE (Federal) Operational Readiness Review (D-ORR). The review was performed by the HSS Office of Safety and Emergency Management Evaluations and was intended to assess the effectiveness of the CORR process as implemented for

111

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

Treatment and Immobilization Treatment and Immobilization Plant - November 2011 Independent Oversight Review, Waste Treatment and Immobilization Plant - November 2011 November 2011 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality The Office of Enforcement and Oversight (Independent Oversight) within the Office of Health, Safety and Security conducted an independent review of selected aspects of construction quality at the Hanford Waste Treatment and Immobilization Plant Project (WTP). The independent oversight review, which was performed September 12-15, 2011, was the latest in a series of ongoing quarterly assessments of construction quality at the WTP construction site. Independent Oversight Review, Waste Treatment and Immobilization Plant -

112

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

October 2012 October 2012 Independent Oversight Review, Waste Treatment and Immobilization Plant - October 2012 October 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U. S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted an independent review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed August 6-10, 2012, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. Independent Oversight Review, Waste Treatment and Immobilization Plant -

113

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

March 2013 March 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - March 2013 March 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted an independent review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed November 26-30, 2012, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. Independent Oversight Review, Waste Treatment and Immobilization Plant - March 2013

114

Technical Review of Retrieval and Closure Plans for the INEEL INTEC Tank Farm Facility  

SciTech Connect (OSTI)

The purpose of this report is to document the conclusions of a technical review of retrieval and closure plans for the Idaho National Energy and Environmental Laboratory (INEEL) Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility. In addition to reviewing retrieval and closure plans for these tanks, the review process served as an information exchange mechanism so that staff in the INEEL High Level Waste (HLW) Program could become more familiar with retrieval and closure approaches that have been completed or are planned for underground storage tanks at the Oak Ridge National Laboratory (ORNL) and Hanford sites. This review focused not only on evaluation of the technical feasibility and appropriateness of the approach selected by INEEL but also on technology gaps that could be addressed through utilization of technologies or performance data available at other DOE sites and in the private sector. The reviewers, Judith Bamberger of Pacific Northwest National Laboratory (PNNL) and Dr. Barry Burks of The Providence Group Applied Technology, have extensive experience in the development and application of tank waste retrieval technologies for nuclear waste remediation.

Bamberger, Judith A; Burks, Barry L; Quigley, Keith D; Falter, Diedre D

2001-09-28T23:59:59.000Z

115

The crucial role of Waste-to-Energy technologies in enhanced landfill mining: a technology review  

Science Journals Connector (OSTI)

The novel concepts Enhanced Waste Management (EWM) and Enhanced Landfill Mining (ELFM) intend to place landfilling of waste in a sustainable context. The state of the technology is an important factor in determining the most suitable moment to valorize either as materials (Waste-to-Product, WtP) or as energy (Waste-to-Energy, WtE) certain landfill waste streams. The present paper reviews thermochemical technologies (incineration, gasification, pyrolysis, plasma technologies, combinations) for energetic valorization of calorific waste streams, with focus on municipal solid waste (MSW), possibly processed into refuse derived fuel (RDF). The potential and suitability of these thermochemical technologies for ELFM applications are discussed. From this review it is clear that process and waste have to be closely matched, and that some thermochemical processes succeed in recovering both materials and energy from waste. Plasma gasification/vitrification is a viable candidate for combined energy and material valorization, its technical feasibility for MSW/RDF applications (including excavated waste) has been proven on installations ranging from pilot to full scale. The continued advances that are being made in process control and process efficiency are expected to improve the commercial viability of these advanced thermochemical conversion technologies in the near future.

A. Bosmans; I. Vanderreydt; D. Geysen; L. Helsen

2013-01-01T23:59:59.000Z

116

Pyrolysis of waste tyres: A review  

SciTech Connect (OSTI)

Graphical abstract: - Highlights: Pyrolysis of waste tyres produces oil, gas and char, and recovered steel. Batch, screw kiln, rotary kiln, vacuum and fluidised-bed are main reactor types. Product yields are influenced by reactor type, temperature and heating rate. Pyrolysis oils are complex and can be used as chemical feedstock or fuel. Research into higher value products from the tyre pyrolysis process is reviewed. - Abstract: Approximately 1.5 billion tyres are produced each year which will eventually enter the waste stream representing a major potential waste and environmental problem. However, there is growing interest in pyrolysis as a technology to treat tyres to produce valuable oil, char and gas products. The most common reactors used are fixed-bed (batch), screw kiln, rotary kiln, vacuum and fluidised-bed. The key influence on the product yield, and gas and oil composition, is the type of reactor used which in turn determines the temperature and heating rate. Tyre pyrolysis oil is chemically very complex containing aliphatic, aromatic, hetero-atom and polar fractions. The fuel characteristics of the tyre oil shows that it is similar to a gas oil or light fuel oil and has been successfully combusted in test furnaces and engines. The main gases produced from the pyrolysis of waste tyres are H{sub 2}, C{sub 1}C{sub 4} hydrocarbons, CO{sub 2}, CO and H{sub 2}S. Upgrading tyre pyrolysis products to high value products has concentrated on char upgrading to higher quality carbon black and to activated carbon. The use of catalysts to upgrade the oil to a aromatic-rich chemical feedstock or the production of hydrogen from waste tyres has also been reported. Examples of commercial and semi-commercial scale tyre pyrolysis systems show that small scale batch reactors and continuous rotary kiln reactors have been developed to commercial scale.

Williams, Paul T., E-mail: p.t.williams@leeds.ac.uk

2013-08-15T23:59:59.000Z

117

Lester to lead ORISE's scientific and technical peer review program  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Lester to lead ORISE's scientific and technical peer review program FOR IMMEDIATE RELEASE June 14, 2010 FY10-42 OAK RIDGE, Tenn.-Oak Ridge Associated Universities has appointed...

118

Enterprise Assessments Review, Hanford Waste Treatment and Immobilizat...  

Office of Environmental Management (EM)

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality January 2015 Office of Nuclear Safety and Environmental Assessments Office of Environment,...

119

Independent Oversight Review, Waste Isolation Pilot Plant - November...  

Energy Savers [EERE]

Safety and Security (HSS), conducted an independent review of the U.S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) preparedness for severe natural phenomena...

120

Geological Problems in Radioactive Waste Isolation: Second Worldwide Review  

E-Print Network [OSTI]

Bernard Neerdael SCK-CEN , HADES Project, Waste and Disposalunderground labora- tory (HADES) was constructed in the claydisposal: Historical Review of Hades Program Early studies

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste technical review" 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

Independent Oversight Review, Advanced Mixed Waste Treatment Project -  

Broader source: Energy.gov (indexed) [DOE]

Review, Advanced Mixed Waste Treatment Review, Advanced Mixed Waste Treatment Project - April 2013 Independent Oversight Review, Advanced Mixed Waste Treatment Project - April 2013 April 2013 Review of Radiation Protection Program Implementation at the Advanced Mixed Waste Treatment Project of the Idaho Site This report documents an independent review of activity-level radiation protection program (RPP) implementation at the Advanced Mixed Waste Treatment Project (AMWTP) of the Idaho Site, as conducted by the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight) within the Office of Health, Safety and Security (HSS). The review was performed by the HSS Office of Safety and Emergency Management Evaluations. The purpose of this Independent Oversight targeted review

122

Independent Oversight Review, Sodium Bearing Waste Treatment Project -  

Broader source: Energy.gov (indexed) [DOE]

Contractor - June 2012 Contractor - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Contractor - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Contractor Operational Readiness Review This report documents the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit (SBWTP-IWTU) contractor Operational Readiness Review (C-ORR). The review was conducted at the Idaho Site from February 27 to March 6, 2012. This report discusses the background, scope, results, and conclusions of the review, as well as opportunities for improvement (OFIs) and items identified for further

123

Independent Oversight Review, Sodium Bearing Waste Treatment Project -  

Broader source: Energy.gov (indexed) [DOE]

Federal - June 2012 Federal - June 2012 Independent Oversight Review, Sodium Bearing Waste Treatment Project - Federal - June 2012 June 2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Federal Operational Readiness Review This report documents the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), independent review of the Sodium Bearing Waste Treatment Project-Integrated Waste Treatment Unit (SBWTP-IWTU) DOE (Federal) Operational Readiness Review (D-ORR). The review was performed by the HSS Office of Safety and Emergency Management Evaluations and was intended to assess the effectiveness of the CORR process as implemented for the SBWTP-IWTU. This review also provides additional data regarding

124

Lester to lead ORISE's scientific and technical peer review program  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Lester to lead ORISE's scientific and technical peer review program Lester to lead ORISE's scientific and technical peer review program FOR IMMEDIATE RELEASE June 14, 2010 FY10-42 OAK RIDGE, Tenn.-Oak Ridge Associated Universities has appointed Tony Lester as director of the Oak Ridge Institute for Science and Education's program focused on scientific peer review. Lester has been serving in this role in an acting capacity since September 2009. Tony Lester Tony Lester In his role, Lester manages a research peer review capability that coordinates the use of independent, expert reviewers to determine the scientific technical feasibility of proposals submitted in response to government agency research needs. His team works closely with the federal government to provide liaison, consultation and operations support during the planning and execution of customers' grant management cycles. The

125

AISI waste oxide recycling program. Final technical report  

SciTech Connect (OSTI)

In March 1995 AISI completed a five-year, $60 million collaborative development program on Direct Steelmaking cost-shared by DOE under the Metals Initiative. This program defined an energy-efficient and environmentally-friendly technology to produce hot metal for steelmaking directly from coal and iron ore pellets without incurring the high capital costs and environmental problems associated with traditional coke oven and blast furnace technology. As it becomes necessary to replace present capacity, this new technology will be favored because of reduced capital costs, higher energy efficiency, and lower operating costs. In April 1994, having failed to move forward with a demonstration plant for direct ironmaking, despite substantial efforts by both Stelco and Geneva Steel, an alternative opportunity was sought to commercialize this new technology without waiting until existing ironmaking capacity needed to be replaced. Recycling and resource recovery of steel plant waste oxides was considered an attractive possibility. This led to approval of a ten-month, $8.3 million joint program with DOE on recycling steel plant waste oxides utilizing this new smelting technology. This highly successful trial program was completed in December 1994. The results of the pilot plant work and a feasibility study for a recycling demonstration plant are presented in this final technical report.

Aukrust, E.; Downing, K.B.; Sarma, B.

1995-08-01T23:59:59.000Z

126

Independent Oversight Review, Waste Isolation Pilot Plant - August 2000 |  

Broader source: Energy.gov (indexed) [DOE]

Review, Waste Isolation Pilot Plant - August Review, Waste Isolation Pilot Plant - August 2000 Independent Oversight Review, Waste Isolation Pilot Plant - August 2000 August 2000 Emergency Management Program Review at the Waste Isolation Pilot Plant The U.S. Department of Energy (DOE) Office of Emergency Management Oversight, within the Secretary of Energy's Office of Independent Oversight and Performance Assurance, conducted a review of the emergency management program at the Waste Isolation Pilot Plant (WIPP) in May 2000. The primary purpose of this review was twofold: to assess selected emergency management system elements that focus on WIPP's readiness to protect site personnel and the public from the consequences of onsite events that may result in the release of hazardous materials; and to evaluate the site's ability to provide appropriate information or

127

Advance Reactor Concepts Technical Review Panel Public Report  

Broader source: Energy.gov [DOE]

The Office of Nuclear Energy supports research and development for advanced reactor technologies. This report documents the results of the 2014 Technical Review Panel (TRP) review of seven advanced reactor concepts. The intent of the process was to identify R&D needs for advanced reactor concepts in order to inform Department of Energy (DOE) Office of Nuclear Energy R&D investment decisions.

128

Establishing the Technical Basis for Disposal of Heat-generating Waste in  

Broader source: Energy.gov (indexed) [DOE]

Establishing the Technical Basis for Disposal of Heat-generating Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis. Though the basis for a salt safety case is strong and has been made by the German repository program, RD&D programs continue in order to help reduce uncertainty, to improve understanding of certain complex processes, to demonstrate operational concepts, to confirm performance expectations, and to improve modeling capabilities utilizing the latest software platforms.

129

Waste Management Program. Technical progress report, Aporil-June 1983  

SciTech Connect (OSTI)

This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

None

1984-02-01T23:59:59.000Z

130

Independent Oversight Review, Hanford Waste Treatment and Immobilization  

Broader source: Energy.gov (indexed) [DOE]

Waste Treatment and Waste Treatment and Immobilization Plant - December 2013 Independent Oversight Review, Hanford Waste Treatment and Immobilization Plant - December 2013 December 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the results of an independent oversight review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed September 9-13, 2013, was the latest in a series of ongoing quarterly assessments of construction quality performed by the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS). The scope of this quarterly assessment of construction quality review included observations

131

Independent Oversight Review, Hanford Site Waste Treatment and  

Broader source: Energy.gov (indexed) [DOE]

Waste Treatment and Waste Treatment and Immobilization Plant, August 2013 Independent Oversight Review, Hanford Site Waste Treatment and Immobilization Plant, August 2013 August 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight) within the Office of Health, Safety and Security (HSS) conducted an independent review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed June 10-14, 2013, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. The scope of this quarterly assessment of construction quality review

132

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

Broader source: Energy.gov (indexed) [DOE]

Oak Ridge Transuranic Waste Oak Ridge Transuranic Waste Processing Center, September 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013 September 2013 Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes. This report documents the results of an independent oversight review of the management of safety significant structures, systems, and components at the Oak Ridge Transuranic Waste Processing Center (TWPC). The review was performed April 2-5, April 15-19, and May 19-23, 2013, by the Department of Energy's (DOE) Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The review was carried out within the broader context of an ongoing program of

133

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

Oversight Review, Waste Treatment and Immobilization Oversight Review, Waste Treatment and Immobilization Plant - August 2011 Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2011 August 2011 Hanford Waste Treatment and Immobilization Plant Construction Quality The Office of Safety and Emergency Management Evaluations (Independent Oversight) within the Office of Health, Safety and Security (HSS) conducted an independent review of selected aspects of construction quality at the Hanford Waste Treatment and Immobilization Project (WTP). The review, which was performed May 9-12, 2011, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. HSS determined that construction quality at WTP was adequate in the areas

134

Independent Oversight Review, Advanced Mixed Waste Treatment Project -  

Broader source: Energy.gov (indexed) [DOE]

Advanced Mixed Waste Treatment Advanced Mixed Waste Treatment Project - April 2013 Independent Oversight Review, Advanced Mixed Waste Treatment Project - April 2013 April 2013 Review of Radiation Protection Program Implementation at the Advanced Mixed Waste Treatment Project of the Idaho Site This report documents an independent review of activity-level radiation protection program (RPP) implementation at the Advanced Mixed Waste Treatment Project (AMWTP) of the Idaho Site, as conducted by the U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight) within the Office of Health, Safety and Security (HSS). The review was performed by the HSS Office of Safety and Emergency Management Evaluations. The purpose of this Independent Oversight targeted review

135

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

Broader source: Energy.gov (indexed) [DOE]

Oak Ridge Transuranic Waste Oak Ridge Transuranic Waste Processing Facility - December 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Facility - December 2013 December 2013 Review of the Fire Protection Program and Fire Protection Systems at the Transuranic Waste Processing Center This report documents the results of an independent oversight review of the fire protection programs and systems at the Oak Ridge Transuranic Waste Processing Center. The review was performed during May 20-23, 2013, and July 15-19, 2013, by the U.S. Department of Energy's (DOE) Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The review was one part of a targeted assessment of fire protection at nuclear facilities across the DOE complex.

136

SFEI Page 1 RMP Technical Review Committee  

E-Print Network [OSTI]

Sedlak noted that the draft Triclosan fact sheet was developed in January 2011, and that additional fact Triclosan fact sheet is in the final stages of review, Mike Connor asked that the Steering Committee

137

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

Energy Savers [EERE]

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

138

Independent Oversight Review, Waste Treatment and Immobilization Plant  

Broader source: Energy.gov (indexed) [DOE]

Waste Treatment and Immobilization Waste Treatment and Immobilization Plant Project - October 2010 Independent Oversight Review, Waste Treatment and Immobilization Plant Project - October 2010 October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project The U.S. Department of Energy (DOE) Office of Health, Safety and Security (HSS) conducted an independent review of the nuclear safety culture at the Waste Treatment and Immobilization Plant (WTP) project at the Hanford Site during August and September 2010. The HSS team performed the review in response to a request in a July 30, 2010, memorandum from the Assistant Secretary for the DOE Headquarters Office of Environmental Management (EM), which referred to nuclear safety concerns raised by a contractor employee

139

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

Waste Treatment and Immobilization Waste Treatment and Immobilization Plant - August 2012 Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2012 August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U. S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted independent reviews of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Project (WTP). The reviews for this report were performed on site during February 6-10, 2012 and April 30 - May 4, 2012, and were the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP.

140

Savannah River Site sample and analysis plan for Clemson Technical Center waste  

SciTech Connect (OSTI)

The purpose of this sampling and analysis plan is to determine the chemical, physical and radiological properties of the SRS radioactive Polychlorinated Biphenyl (PCB) liquid waste stream, to verify that it conforms to Waste Acceptance Criteria of the Department of Energy (DOE) East Tennessee Technology Park (ETTP) Toxic Substance Control Act (TSCA) Incineration Facility. Waste being sent to the ETTP TSCA Incinerator for treatment must be sufficiently characterized to ensure that the waste stream meets the waste acceptance criteria to ensure proper handling, classification, and processing of incoming waste to meet the Waste Storage and Treatment Facility`s Operating Permits. This sampling and analysis plan is limited to WSRC container(s) of homogeneous or multiphasic radioactive PCB contaminated liquids generated in association with a treatability study at Clemson Technical Center (CTC) and currently stored at the WSRC Solid Waste Division Mixed Waste Storage Facility (MWSF).

Hagstrom, T.

1998-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste technical review" 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 waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview  

SciTech Connect (OSTI)

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01T23:59:59.000Z

142

Independent Oversight Review, Waste Isolation Pilot Plant - November 2012 |  

Broader source: Energy.gov (indexed) [DOE]

November 2012 Independent Oversight Review, Waste Isolation Pilot Plant - November 2012 November 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant The Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent review of the U.S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) preparedness for severe natural phenomena events (NPEs). The HSS Office of Safety and Emergency Management Evaluations performed this review to evaluate the processes for identifying emergency response capabilities and maintaining them in a state of readiness in case of a severe NPE. Independent Oversight Review, Waste Isolation Pilot Plant - November 2012

143

Technical basis for classification of low-activity waste fraction from Hanford site tanks  

SciTech Connect (OSTI)

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Petersen, C.A.

1996-09-20T23:59:59.000Z

144

THE HYDROGEN ECONOMY A non-technical review  

E-Print Network [OSTI]

, Distribution and Storage 11 Fuel Cells for Mobile and Stationary Uses 14 Carbon Capture and Storage 17-makers, environmental organisations, energy analysts and industry leaders that hydrogen is the fuel of the futureTHE HYDROGEN ECONOMY A non-technical review UNITEDNATIONSENVIRONMENTPROGRAMME #12;Copyright

145

Independent Oversight Review, Waste Isolation Pilot Plant - April 2013 |  

Broader source: Energy.gov (indexed) [DOE]

April April 2013 Independent Oversight Review, Waste Isolation Pilot Plant - April 2013 April 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities The Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted a shadowing oversight activity to review the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) oversight of the Waste Isolation Pilot Plant (WIPP). This Independent Oversight activity was performed by HSS Office of Safety and Emergency Management Evaluations personnel shadowing the CBFO's review of the WIPP operating contractor's Work Control Improvement Plan implementation and effectiveness review, and CBFO's annual review of the contractor's Integrated Safety Management System (ISMS), specifically

146

Emergency Management Program Review at the Waste Isolation Pilot Plant  

Broader source: Energy.gov (indexed) [DOE]

Waste Waste Isolation Pilot Plant Emergency Management Program Review at the May 2000 OVERSIGHT Table of Contents EXECUTIVE SUMMARY ................................................................... 1 1.0 INTRODUCTION ........................................................................... 4 2.0 RESULTS ......................................................................................... 6 Hazards Survey and Hazards Assessments .................................. 6 Program Plans, Procedures, and Responder Performance ........ 9 Training, Drills, and Exercises ..................................................... 13 Emergency Public Information and Offsite Response Interfaces ....................................................................................... 15 Feedback and Continuous Improvement Process

147

Independent Oversight Review, Waste Treatment and Immobilization Plant- January 2013  

Broader source: Energy.gov [DOE]

Review of the Hanford Waste Treatment and Immobilization Plant Black-Cell and Hard-To-Reach Pipe Spools Procurement Process and the Office of River Protection Audit of That Process

148

Independent Oversight Review, Savannah River Site Salt Waste Processing Facility- August 2013  

Broader source: Energy.gov [DOE]

Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development.

149

Independent Oversight Review, Savannah River Site Salt Waste Processing Facility- April 2014  

Broader source: Energy.gov [DOE]

Review of the Savannah River Site Salt Waste Processing Facility Construction Quality and Fire Protection Systems

150

Independent Oversight Review, Waste Treatment and Immobilization Plant Project- October 2010  

Broader source: Energy.gov [DOE]

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

151

Savannah River Site - Tank 48 Briefing on SRS Tank 48 Independent Technical Review  

Broader source: Energy.gov (indexed) [DOE]

Tank 48 Tank 48 Independent Technical Review August 2006 2 SRS Tank 48 ITR SRS Tank 48 ITR Key ITR Observation Two distinct problems: Removing tetraphenylborate (TPB) waste and then cleaning the tank sufficiently to support return to service Processing contents to eliminate TPB hazard August 2006 3 SRS Tank 48 ITR SRS Tank 48 ITR Overarching ITR Conclusions 1. TPB Processing is on the right track - DOE/WSRC have selected the most promising candidates - Fluidized Bed Steam Reforming (FBSR) is the most technically attractive and mature of the candidate processes August 2006 4 SRS Tank 48 ITR SRS Tank 48 ITR Overarching Conclusions (continued) 2. Heel removal and tank cleanout will be a very challenging task. Compounding issues: - Physical difficulties in cleanout (access, congestion, etc.)

152

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

2 2 Independent Oversight Review, Waste Treatment and Immobilization Plant - March 2012 March 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted an independent review of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Plant (WTP). The review, which was performed November 14-17, 2011, was the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP construction site. Independent Oversight determined that construction quality at WTP was adequate in the areas reviewed. BNI Engineering has developed appropriate

153

Low-Level Waste Disposal Facility Federal Review Group Manual  

Broader source: Energy.gov (indexed) [DOE]

LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP MANUAL REVISION 3 JUNE 2008 (This page intentionally left blank) Low-Level JVllsfe Disposal Fllcili~l' Federal Review Group il1allUlli Revision 3, June 200S Concurrence The Low-Level Waste Disposal Facility Federal Review Group Manual, Revision 3, is approved for use as of the most recent date below. Date Chair, Low-Level Waste Disposal Federal Review Group Andrew WalJo, 1II Deputy Director, Otlice of Nuclear Safety, Quality Assurance, and Environment Department of Energy OHlce of Health, Safety, and Security e C. WilJiams Associate Administrator for Infrastructure and Environment National Nuclear Security Administration Low-Level 'Vaste Disposal Facility Federal Review Group J1aJll/ai

154

Review of Used Nuclear Fuel Storage and Transportation Technical Gap  

Broader source: Energy.gov (indexed) [DOE]

Analysis Analysis Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis While both wet and dry storage have been shown to be safe options for storing used nuclear fuel (UNF), the focus of the program is on dry storage of commercial UNF at reactor or centralized locations. This report focuses on the knowledge gaps concerning extended storage identified in numerous domestic and international investigations and provides the Used Fuel Disposition Campaign"s (UFDC) gap description, any alternate gap descriptions, the rankings by the various organizations, evaluation of the priority assignment, and UFDC-recommended action based on the comparison. Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis More Documents & Publications

155

Radioactive Waste Management Complex Wide Review  

Office of Environmental Management (EM)

explain Generation-04.02 Volume, including the waste and any stabilization or absorbent media; No, Yes Generation-04.02.01 If No, please explain Generation-04.03 Weight of the...

156

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

January 2013 January 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - January 2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant Black-Cell and Hard-To-Reach Pipe Spools Procurement Process and the Office of River Protection Audit of That Process The Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted a concurrent independent review with the U.S. Department of Energy (DOE) Office of River Protection (ORP) of selected aspects of the Bechtel National, Inc. (BNI) Hanford Site Waste Treatment and Immobilization Plant (WTP) procurement processes for WTP black-cell (BC) and hard-to-reach (HtR) pipe spools. The Independent Oversight review was performed by the HSS Office of Safety and

157

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

January 2013 January 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - January 2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant Black-Cell and Hard-To-Reach Pipe Spools Procurement Process and the Office of River Protection Audit of That Process The Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted a concurrent independent review with the U.S. Department of Energy (DOE) Office of River Protection (ORP) of selected aspects of the Bechtel National, Inc. (BNI) Hanford Site Waste Treatment and Immobilization Plant (WTP) procurement processes for WTP black-cell (BC) and hard-to-reach (HtR) pipe spools. The Independent Oversight review was performed by the HSS Office of Safety and

158

Independent Oversight Review, Waste Treatment and Immobilization Plant -  

Broader source: Energy.gov (indexed) [DOE]

August 2012 August 2012 Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2012 August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U. S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted independent reviews of selected aspects of construction quality at the Hanford Site Waste Treatment and Immobilization Project (WTP). The reviews for this report were performed on site during February 6-10, 2012 and April 30 - May 4, 2012, and were the latest in a series of ongoing quarterly assessments of construction quality performed by Independent Oversight at the WTP. Independent Oversight determined that construction quality at WTP is

159

Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect (OSTI)

The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report.

Bradley, E.W. [Science Applications International Corp., Oak Ridge, TN (United States); Wu, C.F.; Goff, T.E. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.

1993-12-31T23:59:59.000Z

160

Summary Notes from 28 May 2008 Generic Technical Issue Discussion on Estimating Waste Inventory and Waste Tank Characterization  

Broader source: Energy.gov (indexed) [DOE]

8 Page 1 of 8 8 Page 1 of 8 Summary Notes from 28 May 2008 Generic Technical Issue Discussion on Estimating Waste Inventory and Waste Tank Characterization Attendees: Representatives from Department of Energy-Headquarters (DOE-HQ) and the U.S. Nuclear Regulatory Commission staff (NRC) met at the DOE offices in Germantown, Maryland on 28 May 2008. Representatives from Department of Energy- Savannah River (DOE-SR), Department of Energy-Richland (DOE-RL), and Department of Energy-River Protection (DOE-ORP) participated in the meeting via a teleconference link. Discussion: NRC staff prepared and disseminated agenda topics (listed in the next section) summarizing issues and considerations relative to estimating waste inventory and waste tank characterization. A summary of the discussion regarding each agenda topic is

Note: This page contains sample records for the topic "waste technical review" 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

Technical justifications for the tests and criteria in the waste form technical position appendix on cement stabilization  

SciTech Connect (OSTI)

As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix, Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test, especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guidelines, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes.

Siskind, B.; Cowgill, M.G.

1992-04-01T23:59:59.000Z

162

Technical justifications for the tests and criteria in the waste form technical position appendix on cement stabilization  

SciTech Connect (OSTI)

As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix, Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test, especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guidelines, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes.

Siskind, B.; Cowgill, M.G.

1992-01-01T23:59:59.000Z

163

Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank  

Broader source: Energy.gov (indexed) [DOE]

- Tank Waste Treatment and Immobilization Plant - - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report This is a comprehensive review ofthe Hanford WTP estimate at completion - assessing the project scope, contract requirements, management execution plant, schedule, cost estimates, and risks. Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report More Documents & Publications TBH-0042 - In the Matter of Curtis Hall

164

ANL Technical Support Program for DOE Environmental Restoration and Waste Management; Annual report, October 1992--September 1993  

SciTech Connect (OSTI)

This report is an overview of the progress during FY 1993 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defense Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are anticipated to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: reviewing and evaluating available data on parameters that will be important in establishing the long-term performance of glass in a repository environment; performing tests to further quantify the effects of important variables where there are deficiencies in the available data; and initiating long-term tests to determine glass performance under a range of conditions applicable to repository disposal.

Bates, J.K.; Bourcier, W.L.; Bradley, C.R. [and others

1994-06-01T23:59:59.000Z

165

Waste Heat Reduction and Recovery for Improving Furnace Efficiency, Productivity and Emissions Performance: A BestPractices Process Heating Technical Brief  

SciTech Connect (OSTI)

This technical brief is a guide to help plant operators reduce waste heat losses associated with process heating equipment.

Not Available

2004-11-01T23:59:59.000Z

166

Waste Heat Reduction and Recovery for Improving Furnace Efficiency, Productivity and Emissions Performance: A BestPractices Process Heating Technical Brief  

Broader source: Energy.gov [DOE]

This technical brief is a guide to help plant operators reduce waste heat losses associated with process heating equipment.

167

Mixed Waste Focus Area integrated technical baseline report, Phase 1: Volume 1  

SciTech Connect (OSTI)

The Department of Energy (DOE) established the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet the Department`s commitments for treatment of mixed low-level and transuranic wastes. The mission of the MWFA is to provide acceptable treatment systems, developed in partnership with users and with participation of stakeholders, tribal governments, and regulators, that are capable of treating DOE`s mixed waste. These treatment systems include all necessary steps such as characterization, pretreatment, and disposal. To accomplish this mission, a technical baseline is being established that forms the basis for determining which technology development activities will be supported by the MWFA. The technical baseline is the prioritized list of deficiencies, and the resulting technology development activities needed to overcome these deficiencies. This document presents Phase I of the technical baseline development process, which resulted in the prioritized list of deficiencies that the MWFA will address. A summary of the data and the assumptions upon which this work was based is included, as well as information concerning the DOE Office of Environmental Management (EM) mixed waste technology development needs. The next phase in the technical baseline development process, Phase II, will result in the identification of technology development activities that will be conducted through the MWFA to resolve the identified deficiencies.

NONE

1996-01-16T23:59:59.000Z

168

Review of High Level Waste Tanks Ultrasonic Inspection Data  

SciTech Connect (OSTI)

A review of the data collected during ultrasonic inspection of the Type I high level waste tanks has been completed. The data was analyzed for relevance to the possibility of vapor space corrosion and liquid/air interface corrosion. The review of the Type I tank UT inspection data has confirmed that the vapor space general corrosion is not an unusually aggressive phenomena and correlates well with predicted corrosion rates for steel exposed to bulk solution. The corrosion rates are seen to decrease with time as expected. The review of the temperature data did not reveal any obvious correlations between high temperatures and the occurrences of leaks. The complex nature of temperature-humidity interaction, particularly with respect to vapor corrosion requires further understanding to infer any correlation. The review of the waste level data also did not reveal any obvious correlations.

Wiersma, B

2006-03-09T23:59:59.000Z

169

Review of the Los Alamos National Laboratory Implementation Verification Review at Technical Area-55  

Broader source: Energy.gov (indexed) [DOE]

Los Alamos National Laboratory Implementation Verification Review at Technical Area-55 May 2011 July 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 Introduction ............................................................................................................................................ 1

170

Review of the Los Alamos National Laboratory Implementation Verification Review at Technical Area-55  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Los Alamos National Laboratory Implementation Verification Review at Technical Area-55 May 2011 July 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 Introduction ............................................................................................................................................ 1

171

FFCAct Clearinghouse, directory of abstracts: Radioactive waste technical support program. Revision 2  

SciTech Connect (OSTI)

The Federal Facility Compliance Act (FFCAct) Clearinghouse is a card catalog of information about the FFCAct and its requirements for developing Site Treatment Plans (STP). The information available in the clearinghouse includes abstracts describing computer applications, technical reports, and a list of technical experts. This report contains 61 abstracts from the database relating to radioactive waste management. The clearinghouse includes information on characterization, retrieval, treatment, storage, and disposal elements of waste management as they relate to the FFCAct and the treatment of mixed wastes. Subject areas of information being compiled include: commercial treatment capabilities; listings of technical experts for assistance in selecting and evaluating treatment options and technologies; mixed waste data and treatability groups; guidance on STP development; life-cycle costs planning estimates for facilities; references to documentation on available technologies and technology development activities; Waste Acceptance Criteria (WAC) for treatment facilities; regulatory, health and safety issues associated with treatment facilities and technologies; and computer databases, applications, and models for identifying and evaluating treatment facilities and technologies. Access to the FFCAct clearinghouse is available to the DOE and its DOE contractors involved in STP development and other FFCAct activities.

NONE

1994-10-01T23:59:59.000Z

172

Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013  

Broader source: Energy.gov [DOE]

Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes

173

SRS Waste Solidification Building Project Peer Review, July 2011  

Broader source: Energy.gov (indexed) [DOE]

SRS-2011-07-15 SRS-2011-07-15 Site: Savannah River Site, NA-26 Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Waste Solidification Building Project Peer Review Dates of Activity : 07/12/2011 - 07/15/2011 Report Preparer: James Lockridge Activity Description/Purpose: At the request of the National Nuclear Security Administration (NNSA) Office of Enterprise Project Management (NA- APM-20), the Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), provided an expert to review the Waste Solidification Building (WSB) startup programs and procedures associated with worker safety and health, environment, and security. Criteria for the review was detailed in the Criteria,

174

Independent Oversight Review, Babcock & Wilcox Technical Services Y-12, LLC- July 2012  

Broader source: Energy.gov [DOE]

Review of the Long Lead Procurement Processed Used by Babcock & Wilcox Technical Services Y-12, LLC for the Uranium Processing Facility Project

175

Environmental Management Construction Project Review of the Savannah River Site Salt Waste Processing Facility, July 19-22, 210  

Broader source: Energy.gov (indexed) [DOE]

Office of Independent Oversight's Office of Environment, Safety and Health Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the Shadowing of the Environmental Management Construction Project Review of the Savannah River Site Salt Waste Processing Facility on July 19-22, 2010 A Department of Energy Construction Project Review (CPR) of the Salt Waste Processing Facility (SWPF) project was conducted on July 19-22, 2010, at the request of the Principal Deputy Secretary, Office of Environmental Management (EM-2). The purpose of the review was to assess the cost, schedule, and technical progress against the approved Performance Baseline. Specific review areas were Engineering; Commissioning; Environment, Safety, Health, and Quality Assurance; Cost, Schedule, and Risk; and Management and Acquisition.

176

Spent fuel sabotage test program, characterization of aerosol dispersal : technical review and analysis supplement.  

SciTech Connect (OSTI)

This project seeks to provide vital data required to assess the consequences of a terrorist attack on a spent fuel transportation cask. One such attack scenario involves the use of conical shaped charges (CSC), which are capable of damaging a spent fuel transportation cask. In the event of such an attack, the amount of radioactivity that may be released as respirable aerosols is not known with great certainty. Research to date has focused on measuring the aerosol release from single short surrogate fuel rodlets subjected to attack by a small CSC device in various aerosol chamber designs. The last series of three experiments tested surrogate fuel rodlets made with depleted uranium oxide ceramic pellets in a specially designed double chamber aerosol containment apparatus. This robust testing apparatus was designed to prevent any radioactive release and allow high level radioactive waste disposal of the entire apparatus following testing of actual spent fuel rodlets as proposed. DOE and Sandia reviews of the project to date identified a number of issues. The purpose of this supplemental report is to address and document the DOE review comments and to resolve the issues identified in the Sandia technical review.

Durbin, Samuel G.; Lindgren, Eric Richard

2009-07-01T23:59:59.000Z

177

Communication Between U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

. Russell Dyer, Project Manager, Yucca Mountain Site Characterization Office, to Jared L. Cohon; January 24, 2002. Subject: Fluid inclusions in mineral deposits at Yucca Mountain · Letter from Jared L. Cohon

178

Communication Between U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

Document Manager, Yucca Mountain Site Characterization Office; July 2, 2001. Subject: Board comments on DOE supplement to the draft environmental impact statement for a geologic re- pository at Yucca Mountain, Nevada and Regulatory Compliance, Yucca Mountain Site Characterization Office; July 2, 2001. Subject: Board reaction

179

Other U.S. Nuclear Waste Technical Review Board Correspondence  

E-Print Network [OSTI]

of the Report `Thermochronological Evolution of Calcite Formation at the Potential Yucca Mountain Repository to Michael L. Corradini; November 25, 2003. Subject: Internal criticality risk at Yucca Mountain · Letter Evolution of Calcite Formation at the Potential Yucca Mountain Repository Site, Nevada." We do appreciate

180

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 I. Recommendation and Approval of the Yucca Mountain Site . . . . . . . . . . . . . . . . . . . 3 II. The Board's Input Into the Process for Recommending and Approving the Yucca Mountain Site

Note: This page contains sample records for the topic "waste technical review" 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

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

. . . . . . . . . . . . . . . . . . . . . . . . . . . 1 B. Understanding Fundamental Corrosion Processes . . . . . . . . . . . . . . . . . . . . . . . 2 C of Multiple Lines of Evidence . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 II. DOE Progress

182

U.S. Nuclear Waste Technical Review Board Correspondence with  

E-Print Network [OSTI]

-management system. We look forward to learning more about TSM model components, structure, output metrics, underlying assumptions, and event uncertainties (e.g., weather events that may cause significant delays

183

Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility  

SciTech Connect (OSTI)

This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and mixed waste. Upon approval of the permit modification, B696S rooms 1007, 1008, and 1009 will be able to store hazardous and mixed waste for up to 1 year. Furthermore, an additional drum crusher and a Waste Packaging Unit will be permitted to treat hazardous and mixed waste. RHWM generally processes LLW with no, or extremely low, concentrations of transuranics (i.e., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., {sup 90}Sr, {sup 137}Cs, {sup 3}H. Chapter 5 of the DSA documents the derivation of TSRs and develops the operational limits that protect the safety envelope defined for this facility. The DSA is applicable to the handling of radioactive waste stored and treated in the B695 Segment of the DWTF. Section 5 of the TSR, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the B695 Segment of the DWTF. A basis explanation follows each of the requirements described in Section 5.5, Specific Administrative Controls. The basis explanation does not constitute an additional requirement, but is intended as an expansion of the logic and reasoning behind development of the requirement. Programmatic Administrative Controls are addressed in Section 5.6.

Larson, H L

2007-09-07T23:59:59.000Z

184

Establishment of review groups on US Department of Energy Environmental Restoration and Waste Management Program  

SciTech Connect (OSTI)

A primary purpose of this grant was the establishment of expert research review groups to help facilitate expanded and improved communications and information among states, public, federal agencies, contractors, and DOE, relative to national environmental and waste management issues/problems. The general objectives of this grant were: Research on the further participation avenues of industry and academia and provide appropriate research documentation concerning the implementation of multi-party agreements; Analysis of the impediments that delay the accomplishment of agreements between states and the federal government for environmental compliance, as well as an assessment of the public need for research because of the above agreements; Analysis of the impact of environmental actions on states, industry, academia, public and other federal agencies; Provide research to help facilitate an interactive system that provides the various involved parties the capability and capacity to strengthen their commitment to national environmental and waste management goals and objectives; and Furthering research of public education in the environmental arena and research of needed national education resources in scientific and technical areas related to environmental restoration and waste management.

Eyman, L.D.

1992-12-01T23:59:59.000Z

185

Technical Standards  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Review for Technical Standards of Interest Legend: Red Technical Standards Program Activities and Responsibilities Blue Directives Program Activities and Responsibilities...

186

2013 Geothermal Technologies Office Peer Review Technical Report  

Broader source: Energy.gov [DOE]

Provided in three sections, this comprehensive technical report assesses 100 projects in the GTO portfolio, based on presentations from GTO-funded principal investigators that were evaluated and...

187

E-Print Network 3.0 - activity technical progress Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Ensure that ... Source: U.S. Nuclear Waste Technical Review Board Collection: Fission and Nuclear Technologies ; Environmental Management and Restoration Technologies 30 Pacific...

188

Review of the Waste Isolation Pilot Plant Work Planning and Control...  

Office of Environmental Management (EM)

Independent Oversight Review of the Waste Isolation Pilot Plant Work Planning and Control Activities April 2013 Office of Safety and Emergency Management Evaluations Office of...

189

Technical requirements for the actinide source-term waste test program  

SciTech Connect (OSTI)

This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency`s 40 CFR Part 191B.

Phillips, M.L.F.; Molecke, M.A.

1993-10-01T23:59:59.000Z

190

Estimating Waste Inventory and Waste Tank Characterization |...  

Office of Environmental Management (EM)

Estimating Waste Inventory and Waste Tank Characterization Estimating Waste Inventory and Waste Tank Characterization Summary Notes from 28 May 2008 Generic Technical Issue...

191

L1:PAC.P6.04 Westinghouse Test Stand Technical Readiness Review  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

PAC.P6.04 Westinghouse Test Stand Technical Readiness Review Andrew Godfrey ORNL Completed: June 25, 2013 CASL- -2013-01 -000 Consortium for Advanced Simulation of LWRs Consortium...

192

Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Federal Operational Readiness Review  

Broader source: Energy.gov (indexed) [DOE]

Federal Operational Readiness Review June 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

193

Branch technical position on the use of expert elicitation in the high-level radioactive waste program  

SciTech Connect (OSTI)

Should the site be found suitable, DOE will apply to the US Nuclear Regulatory Commission for permission to construct and then operate a proposed geologic repository for the disposal of spent nuclear fuel and other high-level radioactive waste at Yucca Mountain. In deciding whether to grant or deny DOE`s license application for a geologic repository, NRC will closely examine the facts and expert judgment set forth in any potential DOE license application. NRC expects that subjective judgments of individual experts and, in some cases, groups of experts, will be used by DOE to interpret data obtained during site characterization and to address the many technical issues and inherent uncertainties associated with predicting the performance of a repository system for thousands of years. NRC has traditionally accepted, for review, expert judgment to evaluate and interpret the factual bases of license applications and is expected to give appropriate consideration to the judgments of DOE`s experts regarding the geologic repository. Such consideration, however, envisions DOE using expert judgments to complement and supplement other sources of scientific and technical information, such as data collection, analyses, and experimentation. In this document, the NRC staff has set forth technical positions that: (1) provide general guidelines on those circumstances that may warrant the use of a formal process for obtaining the judgments of more than one expert (i.e., expert elicitation); and (2) describe acceptable procedures for conducting expert elicitation when formally elicited judgments are used to support a demonstration of compliance with NRC`s geologic disposal regulation, currently set forth in 10 CFR Part 60. 76 refs.

Kotra, J.P.; Lee, M.P.; Eisenberg, N.A. [Nuclear Regulatory Commission, Washington, DC (United States); DeWispelare, A.R. [Center for Nuclear Waste Regulatory Analyses, San Antonio, TX (United States)

1996-11-01T23:59:59.000Z

194

Waste Gasification by Thermal Plasma: A Review Frdric Fabry*, Christophe Rehmet, Vandad Rohani, Laurent Fulcheri  

E-Print Network [OSTI]

12 Waste Gasification by Thermal Plasma: A Review Frédéric Fabry*, Christophe Rehmet, Vandad Rohani proposes an overview of waste-to-energy conversion by gasification processes based on thermal plasma, of various waste gasification processes based on thermal plasma (DC or AC plasma torches) at lab scale versus

Paris-Sud XI, Université de

195

Radioactive waste isolation in salt: peer review of Office of Nuclear Waste Isolation's Socioeconomic Program Plan  

SciTech Connect (OSTI)

The following recommendations have been abstracted from the body of this report. The Office of Nuclear Waste Isolation's Socioeconomic Program Plan for the Establishment of Mined Geologic Repositories to Isolate Nuclear Waste should be modified to: (1) encourage active public participation in the decision-making processes leading to repository site selection; (2) clearly define mechanisms for incorporating the concerns of local residents, state and local governments, and other potentially interested parties into the early stages of the site selection process. In addition, the Office of Nuclear Waste Isolation should carefully review the overall role that these persons and groups, including local pressure groups organized in the face of potential repository development, will play in the siting process; (3) place significantly greater emphasis on using primary socioeconomic data during the site selection process, reversing the current overemphasis on secondary data collection, description of socioeconomic conditions at potential locations, and development of analytical methodologies; (4) include additional approaches to solving socioeconomic problems. For example, a reluctance to acknowledge that solutions to socioeconomic problems need to be found jointly with interested parties is evident in the plan; (5) recognize that mitigation mechanisms other than compensation and incentives may be effective; (6) as soon as potential sites are identified, the US Department of Energy (DOE) should begin discussing impact mitigation agreements with local officials and other interested parties; and (7) comply fully with the pertinent provisions of NWPA.

Winter, R.; Fenster, D.; O'Hare, M.; Zillman, D.; Harrison, W.; Tisue, M.

1984-07-01T23:59:59.000Z

196

2008 DOE FCVT Merit Review: BSST Waste Heat Recovery Program...  

Broader source: Energy.gov (indexed) [DOE]

Documents & Publications Automotive Waste Heat Conversion to Power Program Thermoelectric Waste Heat Recovery Program for Passenger Vehicles Development of a 100-Watt High...

197

Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 2, Technical basis  

SciTech Connect (OSTI)

Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume, Volume 2, contains the technical basis for the 1992 PA. Specifically, it describes the conceptual basis for consequence modeling and the PA methodology, including the selection of scenarios for analysis, the determination of scenario probabilities, and the estimation of scenario consequences using a Monte Carlo technique and a linked system of computational models. Additional information about the 1992 PA is provided in other volumes. Volume I contains an overview of WIPP PA and results of a preliminary comparison with the long-term requirements of the EPA`s Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses related to the preliminary comparison with 40 CFR 191B. Volume 5 contains uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance. Finally, guidance derived from the entire 1992 PA is presented in Volume 6.

Not Available

1992-12-01T23:59:59.000Z

198

Historical literature review on waste classification and categorization  

SciTech Connect (OSTI)

The Staff of the Waste Management Document Library (WMDL), in cooperation with Allen Croff have been requested to provide information support for a historical search concerning waste categorization/classification. This bibliography has been compiled under the sponsorship of Oak Ridge National Laboratory`s Chemical Technology Division to help in Allen`s ongoing committee work with the NRC/NRCP. After examining the search, Allen Croff saw the value of the search being published. Permission was sought from the database providers to allow limited publication (i.e. 20--50 copies) of the search for internal distribution at the Oak Ridge National Laboratory and for Allen Croff`s associated committee. Citations from the database providers who did not grant legal permission for their material to be published have been omitted from the literature review. Some of the longer citations have been included in an abbreviated form in the search to allow the format of the published document to be shortened from approximately 1,400 pages. The bibliography contains 372 citations.

Croff, A.G.; Richmond, A.A.; Williams, J.P.

1995-03-01T23:59:59.000Z

199

Geological problems in radioactive waste isolation - A world wide review  

SciTech Connect (OSTI)

The problem of isolating radioactive wastes from the biosphere presents specialists in the earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high-level waste (HLW), which must be isolated in the underground and away from the biosphere for thousands of years. The most widely accepted method of doing this is to seal the radioactive materials in metal canisters that are enclosed by a protective sheath and placed underground in a repository that has been carefully constructed in an appropriate rock formation. Much new technology is being developed to solve the problems that have been raised, and there is a continuing need to publish the results of new developments for the benefit of all concerned. Table 1 presents a summary of the various formations under investigation according to the reports submitted for this world wide review. It can be seen that in those countries that are searching for repository sites, granitic and metamorphic rocks are the prevalent rock type under investigation. Six countries have developed underground research facilities that are currently in use. All of these investigations are in saturated systems below the water table, except the United States project, which is in the unsaturated zone of a fractured tuff.

Witherspoon, P.A. [Lawrence Berkeley Lab., CA (United States)

1991-06-01T23:59:59.000Z

200

Technical, Economical, and Climate-Related Aspects of Biochar Production Technologies: A Literature Review  

Science Journals Connector (OSTI)

Technical, Economical, and Climate-Related Aspects of Biochar Production Technologies: A Literature Review ... Bioenergy Unit, Ecofys, 81243 Mnchen, Germany ... For this reason, this paper summarizes the available peer-reviewed scientific literature (ISI Web of Knowledge) about the technological, economical, and climate-relevant aspects of carbonization technologies. ...

Sebastian Meyer; Bruno Glaser; Peter Quicker

2011-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "waste technical review" 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

Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program. Revision 1  

SciTech Connect (OSTI)

This document provides guidance for the revision of DOE Order 5820.2A, ``Radioactive Waste Management.`` Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee.

Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

1993-04-01T23:59:59.000Z

202

REVIEW OF ALTERNATIVE ENHANCED CHEMICAL CLEANING OPTIONS FOR SRS WASTE TANKS  

SciTech Connect (OSTI)

A literature review was conducted to support the Task Technical and Quality Assurance Plan for Alternative Enhanced Chemical Cleaning (AECC) for sludge heel removal funded as part of the EM-21 Engineering and Technology program. The goal was to identify potential technologies or enhancements to the baseline oxalic acid cleaning process for chemically dissolving or mobilizing Savannah River Site (SRS) sludge heels. The issues with the potentially large volume of oxalate solids generated from the baseline process have driven an effort to find an improved or enhanced chemical cleaning technology for the tank heels. This literature review builds on a previous review conducted in 2003. A team was charged with evaluating the information in these reviews and developing recommendations of alternative technologies to pursue. The new information in this report supports the conclusion of the previous review that oxalic acid remains the chemical cleaning agent of choice for dissolving the metal oxides and hydroxides found in sludge heels in carbon steel tanks. The potential negative impact of large volumes of sodium oxalate on downstream processes indicates that the amount of oxalic acid used for chemical cleaning needs to be minimized as much as possible or the oxalic acid must be destroyed prior to pH adjustment in the receipt tank. The most straightforward way of minimizing the volume of oxalic acid needed for chemical cleaning is through more effective mechanical cleaning. Using a mineral acid to adjust the pH of the sludge prior to adding oxalic acid may also help to minimize the volume of oxalic acid used in chemical cleaning. If minimization of oxalic acid proves insufficient in reducing the volume of oxalate salts, several methods were found that could be used for oxalic acid destruction. For some waste tank heels, another acid or even caustic treatment (or pretreatment) might be more appropriate than the baseline oxalic acid cleaning process. Caustic treatment of high aluminum sludge heels may be appropriate as a means of reducing oxalic acid usage. Reagents other than oxalic acid may also be needed for removing actinide elements from the tank heels. A systems engineering evaluation (SEE) was performed on the various alternative chemical cleaning reagents and organic oxidation technologies discussed in the literature review. The objective of the evaluation was to develop a short list of chemical cleaning reagents and oxalic acid destruction methods that should be the focus of further research and development. The results of the SEE found that eight of the thirteen organic oxidation technologies scored relatively close together. Six of the chemical cleaning reagents were also recommended for further investigation. Based on the results of the SEE and plan set out in the TTQAP the following broad areas are recommended for future study as part of the AECC task: (1) Basic Chemistry of Sludge Dissolution in Oxalic Acid: A better understanding of the variables effecting dissolution of sludge species is needed to efficiently remove sludge heels while minimizing the use of oxalic acid or other chemical reagents. Tests should investigate the effects of pH, acid concentration, phase ratios, temperature, and kinetics of the dissolution reactions of sludge components with oxalic acid, mineral acids, and combinations of oxalic/mineral acids. Real waste sludge samples should be characterized to obtain additional data on the mineral phases present in sludge heels. (2) Simulant Development Program: Current sludge simulants developed by other programs for use in waste processing tests, while compositionally similar to real sludge waste, generally have more hydrated forms of the major metal phases and dissolve more easily in acids. Better simulants containing the mineral phases identified by real waste characterization should be developed to test chemical cleaning methods. (3) Oxalic Acid Oxidation Technologies: The two Mn based oxidation methods that scored highly in the SEE should be studied to evaluate long term potential. One of the AOP's

Hay, M.; Koopman, D.

2009-08-01T23:59:59.000Z

203

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

Broader source: Energy.gov [DOE]

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

204

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results  

SciTech Connect (OSTI)

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site.

Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B. [and others

1996-03-01T23:59:59.000Z

205

Software Sensitivity Review | Scientific and Technical Information Program  

Office of Scientific and Technical Information (OSTI)

Sensitivity Review Sensitivity Review Print page Print page Email page Email page As required by DOE O 241.1B, software submitting sites are to review all software for classified and controlled unclassified information, including Personally Identifiable Information (PII), according to approved local procedures. Prior to announcing and/or submitting software to ESTSC or a SIAC, or disseminating software publicly, the submitting site should conduct reviews to determine the appropriate Intellectual Property or other category of sensitivity. Those categories include: Unlimited Announcement - Software which be made available to all requesters; government, public and foreign (sensitive countries require Headquarters approval). Open Source Software - Computer software that is distributed under a

206

Report of the Review of the Hanford Solid Waste Environmental Impact Statement regarding Data Quality Control and Management Issues  

Broader source: Energy.gov (indexed) [DOE]

Review of the Hanford Review of the Hanford Solid Waste Environmental Impact Statement (EIS) Data Quality, Control and Management Issues January 2006 Hanford Solid Waste Environment Impact Statement (EIS) Data Quality, Control and Management Issues Review Report ii Contents EXECUTIVE SUMMARY .................................................................................. IV 1.0 BACKGROUND ................................................................................................................ 1 2.0 REVIEW APPROACH....................................................................................................... 1 3.0 SUMMARY........................................................................................................................ 2 4.0 REVIEW RESULTS........................................................................................................... 4

207

Low-Level Waste Disposal Facility Federal Review Group (LFRG) | Department  

Broader source: Energy.gov (indexed) [DOE]

Program Management » Compliance » Low-Level Waste Program Management » Compliance » Low-Level Waste Disposal Facility Federal Review Group (LFRG) Low-Level Waste Disposal Facility Federal Review Group (LFRG) The Office of Environmental Management (EM) Low-Level Waste Disposal Facility Federal Review Group (LFRG) was established to fulfill the requirements contained in Section I.2.E(1)(a) of the Department of Energy (DOE) Order 435.1, Radioactive Waste Management, and exercised by the senior managers of EM. The LFRG assists EM senior managers in the review of documentation that supports the approval of performance assessments and composite analyses or appropriate Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA)documents as described in Section II of the LFRG Charter. Through its efforts, the LFRG supports the issuance

208

Radioactive waste isolation in salt: peer review of Office of Nuclear Waste Isolation's Socioeconomic Program Plan  

SciTech Connect (OSTI)

The ONWI Socioeconomic Program Plan spells out DOE's approach to analyzing the socioeconomic impacts from siting, constructing, and operating radioactive waste repositories and discusses mitigation strategies. The peer review indicated the following modifications should be made to the Plan: encourage active public participation in the decision-making processes leading to repository site selection; clearly define mechanisms for incorporating the concerns of local residents, state and local governments, and other potentially interested parties into the early stages of the site selection process; place significantly greater emphasis on using primary socioeconomic data during the site selection process, reversing the current overemphasis on secondary data collection, description of socioeconomic conditions at potential locations, and development of analytical methodologies; recognize that mitigation mechanisms other than compensation and incentives may be effective; as soon as potential sites are identified, the US Department of Energy (DOE) should begin discussing impact mitigation agreements with local officials and other interested parties; and comply fully with the pertinent provisions of NWPA.

Winter, R.; Fenster, D.; O'Hare, M.; Zillman, D.; Harrison, W.; Tisue, M.

1984-02-01T23:59:59.000Z

209

Technical considerations and problems associated with long-term storage of low-level waste  

SciTech Connect (OSTI)

If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

Siskind, B.

1991-01-01T23:59:59.000Z

210

Technical considerations and problems associated with long-term storage of low-level waste  

SciTech Connect (OSTI)

If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

Siskind, B.

1991-12-31T23:59:59.000Z

211

The Mixed Waste Management Facility. Preliminary design review  

SciTech Connect (OSTI)

This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones.

NONE

1995-12-31T23:59:59.000Z

212

Independent Oversight Review, Waste Isolation Pilot Plant - April...  

Broader source: Energy.gov (indexed) [DOE]

shadowing the CBFO's review of the WIPP operating contractor's Work Control Improvement Plan implementation and effectiveness review, and CBFO's annual review of the contractor's...

213

Fuel Gas Production from Organic Wastes by Low Capital Cost Batch Digestion  

Science Journals Connector (OSTI)

The technical background is reviewed on energy recovery from biomass--i.e., all organic wastes, especially municipal solid wastes, but also including agricultural residues and crops grown specifically for ener...

Donald L. Wise; Alfred P. Leuschner

1986-01-01T23:59:59.000Z

214

River Protection Project (RPP) Tank Waste Retrieval and Disposal Mission Technical Baseline Summary Description  

SciTech Connect (OSTI)

This document is one of the several documents prepared by Lockheed Martin Hanford Corp. to support the U. S. Department of Energy's Tank Waste Retrieval and Disposal mission at Hanford. The Tank Waste Retrieval and Disposal mission includes the programs necessary to support tank waste retrieval; waste feed, delivery, storage, and disposal of immobilized waste; and closure of the tank farms.

DOVALLE, O.R.

1999-12-29T23:59:59.000Z

215

Technical issues related to NUREG 0800, Chapter 18: Human Factors Engineering/Standard Review Plan  

SciTech Connect (OSTI)

The revision of Chapter 18 of NUREG 0800, Human Factors Engineering Standard Review Plan (SRP) will be based on SECY 82-111 and guidance contained in NUREG 0700, NUREG 0801 and NUREG 0835, plus other references. In conducting field reviews of control rooms, the NRC has identified technical issues which can be used to enhance the development of the revised version of NUREG 0800, and to establish priorities among the list of possible Branch Technical Positions (BTP) in NUREG 0800, Rev. 0, Table 18.0-2. This report is a compilation of comments and suggestions from the people who used NUREG 0700 in the Control Room field reviews. This information was used to establish possible BTP topic priorities so that the most important BTPs could be issued first. The comments and suggestions are included for HFEB review in conjunction with the table of priorities.

Savage, J.W.

1982-11-05T23:59:59.000Z

216

Report of the Review of the Hanford Solid Waste Environmental Impact  

Broader source: Energy.gov (indexed) [DOE]

of the Review of the Hanford Solid Waste Environmental of the Review of the Hanford Solid Waste Environmental Impact Statement regarding Data Quality Control and Management Issues Report of the Review of the Hanford Solid Waste Environmental Impact Statement regarding Data Quality Control and Management Issues As part of the litigation involving receipt of offsite waste and the HSW EIS, the Court allowed the State of Washington a limited amount of discovery pertaining to iodine-129, technetium-99, and groundwater analyses. While compiling information to respond to the State discovery request, Battelle discovered three data quality issues within the data sets used for the cumulative groundwater impact analysis: As a result of these data quality issues, a team was commissioned to review the HSW EIS for additional data quality issues as well as any programmatic problems which

217

A Technical Review of Interference Testing with Application in the  

E-Print Network [OSTI]

Program under Department of Energy Contract No. DE-AT03-80SF11459 and by the Department of Petroleum.S.I.R., Wellington. Financial support was provided by M.W.D., New Zealand Energy Department, Stanford Geoth- ermal testing and relatdd earth tide arid compressibility effects are reviewed. Hydrological information from

Stanford University

218

Review of research on geological disposal of radioactive waste March 2011 s.haszeldine@ed.ac.uk Page 1 of 13 Review of research on geological disposal of radioactive waste proposed by  

E-Print Network [OSTI]

Review of research on geological disposal of radioactive waste March 2011 s.haszeldine@ed.ac.uk Page 1 of 13 Review of research on geological disposal of radioactive waste proposed by the UK Nuclear, and future research work needed, on the pathway towards choosing sites for a radioactive waste Repository

219

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

220

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

Broader source: Energy.gov (indexed) [DOE]

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

Note: This page contains sample records for the topic "waste technical review" 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

Office of Enterprise Assessments Review of the Waste Isolation...  

Energy Savers [EERE]

and maintains the necessary safety management programs and infrastructure to safely conduct full operations. WIPP, managed and operated by Nuclear Waste Partnership, LLC,...

222

Geological Problems in Radioactive Waste Isolation: Second Worldwide Review  

E-Print Network [OSTI]

waste disposal in underground facilities, Braunschweig (of the present underground facility to perform larger scaleothers i n the underground facility (URF). This research

2010-01-01T23:59:59.000Z

223

Industrial Energy Efficiency Technical Review Guidelines and Best Practices  

E-Print Network [OSTI]

of commercial and other sector programs. The following programs were deemed to represent the best combination of applicability and access to relevant information: ? BC Hydro?s Power Smart Partners - Industrial (Transmission and Distribution...) ? Wisconsin?s Focus on Energy ? Industrial ? California Public Utilities Commission?s (CPUC) Southern California Industrial and Agricultural (SCIA) and Pacific Gas & Electric?s (PG&E) Fabrication, Process and Manufacturing Review of Impact Evaluation...

Dalziel, N.

2013-01-01T23:59:59.000Z

224

Tank Waste Strategy Update  

Broader source: Energy.gov (indexed) [DOE]

Tank Waste Subcommittee www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 Tank Waste Subcommittee Ken Picha Office of Environmental Management December 5, 2011 Background Tank Waste Subcommittee (TWS)originally chartered, in response to Secretary's request to perform a technical review of Waste Treatment and Immobilization Plant (WTP) in May 2010. Three tasks: o Verification of closure of WTP External Flowsheet Review Team (EFRT) issues. o WTP Technical Design Review o WTP potential improvements Report completed and briefed to DOE in September 2010 www.em.doe.gov safety performance cleanup closure E M Environmental Management 2 Report completed and briefed to DOE in September 2010 Follow-on scope for TWS identified immediately after briefing to DOE and

225

Review of CANDU NPP environmental releases and waste production: Current experience and future initiatives  

SciTech Connect (OSTI)

The characterization and sources of nuclear waste effluents arising from CANDU nuclear power plants will be reviewed. The design of the CANDU plant is based on the as low as reasonably achievable (ALARA) principle. Operation has shown that the CANDU plants easily meet regulatory limits and generally operate at the utility set target of one percent of this limit. There is increasing emphasis both within Canada and internationally to reduce environmental releases. Steps are being taken at operating CANDU plants and on future CANDU designs to achieve waste reduction or elimination, to introduce more effective waste handling methods and to improve treatment of radioactive and non-radioactive waste.

Barber, D.; Shalaby, B.A. [AECL CANDU, Mississauga, Ontario (Canada); Buckley, L.P. [AECL Research, Chalk River, Ontario (Canada)

1993-12-31T23:59:59.000Z

226

Record of Technical Change for Corrective Action Plan for Corrective Action Unit 140: Waste Dumps, burn Pits, and Storage Area, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Record of Technical Change for Corrective Action Plan for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada (DOE/NV--963-Rev 2, dated November 2004).

U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office; Bechtel Nevada

2005-01-05T23:59:59.000Z

227

Buried transuranic wastes at ORNL: Review of past estimates and reconciliation with current data  

SciTech Connect (OSTI)

Inventories of buried (generally meaning disposed of) transuranic (TRU) wastes at Oak Ridge National Laboratory (ORNL) have been estimated for site remediation and waste management planning over a period of about two decades. Estimates were required because of inadequate waste characterization and incomplete disposal records. For a variety of reasons, including changing definitions of TRU wastes, differing objectives for the estimates, and poor historical data, the published results have sometimes been in conflict. The purpose of this review was (1) to attempt to explain both the rationale for and differences among the various estimates, and (2) to update the estimates based on more recent information obtained from waste characterization and from evaluations of ORNL waste data bases and historical records. The latter included information obtained from an expert panel`s review and reconciliation of inconsistencies in data identified during preparation of the ORNL input for the third revision of the Baseline Inventory Report for the Waste Isolation Pilot Plant. The results summarize current understanding of the relationship between past estimates of buried TRU wastes and provide the most up-to-date information on recorded burials thereafter. The limitations of available information on the latter and thus the need for improved waste characterization are highlighted.

Trabalka, J.R.

1997-09-01T23:59:59.000Z

228

Reviewing PSA-based analyses to modify technical specifications at nuclear power plants  

SciTech Connect (OSTI)

Changes to Technical Specifications (TSs) at nuclear power plants (NPPs) require review and approval by the United States Nuclear Regulatory Commission (USNRC). Currently, many requests for changes to TSs use analyses that are based on a plant`s probabilistic safety assessment (PSA). This report presents an approach to reviewing such PSA-based submittals for changes to TSs. We discuss the basic objectives of reviewing a PSA-based submittal to modify NPP TSs; the methodology of reviewing a TS submittal, and the differing roles of a PSA review, a PSA Computer Code review, and a review of a TS submittal. To illustrate this approach, we discuss our review of changes to allowed outage time (AOT) and surveillance test interval (STI) in the TS for the South Texas Project Nuclear Generating Station. Based on this experience gained, a check-list of items is given for future reviewers; it can be used to verify that the submittal contains sufficient information, and also that the review has addressed the relevant issues. Finally, recommended steps in the review process and the expected findings of each step are discussed.

Samanta, P.K.; Martinez-Guridi, G. [Brookhaven National Lab., Upton, NY (United States); Vesely, W.E. [Science Applications International Corporation, Dublin, OH (United States)

1995-12-01T23:59:59.000Z

229

Preparation of a technology development roadmap for the Accelerator Transmutation of Waste (ATW) System : report of the ATW separations technologies and waste forms technical working group.  

SciTech Connect (OSTI)

In response to a Congressional mandate to prepare a roadmap for the development of Accelerator Transmutation of Waste (ATW) technology, a Technical Working Group comprised of members from various DOE laboratories was convened in March 1999 for the purpose of preparing that part of the technology development roadmap dealing with the separation of certain radionuclides for transmutation and the disposal of residual radioactive wastes from these partitioning operations. The Technical Working Group for ATW Separations Technologies and Waste Forms completed its work in June 1999, having carefully considered the technology options available. A baseline process flowsheet and backup process were identified for initial emphasis in a future research, development and demonstration program. The baseline process combines aqueous and pyrochemical processes to permit the efficient separation of the uranium, technetium, iodine and transuranic elements from the light water reactor (LWR) fuel in the head-end step. The backup process is an all- pyrochemical system. In conjunction with the aqueous process, the baseline flowsheet includes a pyrochemical process to prepare the transuranic material for fabrication of the ATW fuel assemblies. For the internal ATW fuel cycle the baseline process specifies another pyrochemical process to extract the transuranic elements, Tc and 1 from the ATW fuel. Fission products not separated for transmutation and trace amounts of actinide elements would be directed to two high-level waste forms, one a zirconium-based alloy and the other a glass/sodalite composite. Baseline cost and schedule estimates are provided for a RD&D program that would provide a full-scale demonstration of the complete separations and waste production flowsheet within 20 years.

Collins, E.; Duguid, J.; Henry, R.; Karell, E.; Laidler, J.; McDeavitt, S.; Thompson, M.; Toth, M.; Williamson, M.; Willit, J.

1999-08-12T23:59:59.000Z

230

SUPPLEMENTAL COLUMBIA RIVER PROTECTION ACTIVITIES AT THE DEPARTMENT OF ENERGY HANFORD SITE: 2006 TECHNICAL PEER REVIEW  

SciTech Connect (OSTI)

Prompted by a $10 million Congressional allocation to identify supplemental actions to protect the Columbia River from groundwater contamination beneath the Hanford Reservation, the U. S. Department of Energy (DOE) Environmental Management (EM) Office of Clean-up Technology identified twenty-three potential technical projects and then down-selected ten of these for further evaluation. An independent expert peer review was conducted for the ten down-selected proposals. The review panel consisted of twenty-three recognized subject matter experts that broadly represented academia, industry, and federal laboratories. Of the initial ten proposals reviewed, one was given unconditional support, six were given conditional support, and three were not supported as proposed. Three additional proposals were then submitted by DOE for review--these proposals were structured, in part, to respond to the initial round of technical peer review comments. Peer reviews of these additional proposals provided conditional support. For those proposals that received conditional support, DOE requested specific implementation and work plans and assessed whether the plans adequately addressed the technical conditions identified by the review panel. The final list of technology proposals receiving support, or conditional support, primarily focused on understanding and reducing the potential impacts of uranium, chromium, and strontium from facilities adjacent to the Columbia River, with a secondary focus on understanding and limiting the future Columbia River impacts from the large carbon tetrachloride groundwater plume underlying and downgradient of the Hanford Central Plateau facilities. The results and recommendations of the peer reviews informed the final DOE project selections and supported implementation of the selected projects to protect the Columbia River and address groundwater contamination at Hanford.

Looney, B; Dawn Kaback; Gene Leboeuf; Jason Mulvihill-Kuntz; Lynn Lefkoff

2006-12-20T23:59:59.000Z

231

Microsoft PowerPoint - EM Waste 10-03 Processing Technical Exchange Antifoam 11-17-2010.ppt  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

664, Rev A 664, Rev A Improved Antifoam Agents for SRS Dan Lambert Fellow Engineer, SRNL Dr Darsh T. Wasan, Dr. Alex D. Nikolov, Illinois Institute of Technology EM Waste Processing Technical Exchange Session 10: Advanced Unit Operations and Scaling Print Close 2 SRNL-STI-2010-00698, Rev A Outline Needs/Benefits Background Scope Experimental/Method Results Future work Process Technology Programs Print Close 3 SRNL-STI-2010-00698, Rev A Needs/Benefits Needs: Increase waste processing (melter) throughput Benefits: Maximize Boilup Rate during waste processing at boiling, resulting in an increase in a reduction in overall processing time. Minimize carryover of insoluble solids, resulting in less facility downtime due to foamover into condensate. Process Technology Programs Print Close

232

Establishment of review groups on US Department of Energy Environmental Restoration and Waste Management Program. Final report  

SciTech Connect (OSTI)

A primary purpose of this grant was the establishment of expert research review groups to help facilitate expanded and improved communications and information among states, public, federal agencies, contractors, and DOE, relative to national environmental and waste management issues/problems. The general objectives of this grant were: Research on the further participation avenues of industry and academia and provide appropriate research documentation concerning the implementation of multi-party agreements; Analysis of the impediments that delay the accomplishment of agreements between states and the federal government for environmental compliance, as well as an assessment of the public need for research because of the above agreements; Analysis of the impact of environmental actions on states, industry, academia, public and other federal agencies; Provide research to help facilitate an interactive system that provides the various involved parties the capability and capacity to strengthen their commitment to national environmental and waste management goals and objectives; and Furthering research of public education in the environmental arena and research of needed national education resources in scientific and technical areas related to environmental restoration and waste management.

Eyman, L.D.

1992-12-01T23:59:59.000Z

233

Geological Problems in Radioactive Waste Isolation: Second Worldwide Review  

E-Print Network [OSTI]

number of drums in each cavern associated with each wasteArea F: Maintenance Area T Cavern Entrance Tunnel Ca FigureCross section of L L W cavern. Shotcrete Roof - Crane '

2010-01-01T23:59:59.000Z

234

Office of Enterprise Assessments Review of the Hanford Site Waste...  

Energy Savers [EERE]

of liquid or semi-solid radioactive and chemical waste stored in 177 underground tanks at the Hanford Site. ORP serves as DOE line management for two functions: the Tank...

235

Independent Oversight Review of the Hanford Site Waste Treatment...  

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

of liquid or semi-solid radioactive and chemical waste stored in 177 underground tanks at the Hanford Site. ORP serves as DOE line management for two functions: the Tank...

236

A review of different heat exchangers designs for increasing the diesel exhaust waste heat recovery  

Science Journals Connector (OSTI)

Abstract In this paper, after a short review of waste heat recovery technologies from diesel engines, the heat exchangers (HEXs) used in exhaust of engines is introduced as the most common way. So, a short review of the technologies that increase the heat transfer in \\{HEXs\\} is introduced and the availability of using them in the exhaust of engines is evaluated and finally a complete review of different \\{HEXs\\} which previously were designed for increasing the exhaust waste heat recovery is presented. Also, future view points for next \\{HEXs\\} designs are proposed to increase heat recovery from the exhaust of diesel engines.

M. Hatami; D.D. Ganji; M. Gorji-Bandpy

2014-01-01T23:59:59.000Z

237

Waste to energy status in India: A short review  

Science Journals Connector (OSTI)

Abstract India is one of the most rapidly developing countries in the world. It is witnessing growing industrialization and thus development. Such rapid development needs energy to progress, which further makes India an energy hungry nation. Currently India depends mainly upon fossil fuels and thus has to pay a huge bill at the end of every contractual period. These bills can be shortened and the expenditures brought down by using and exploiting non-conventional sources of energy. India holds a huge potential for such non-conventional sources of energy. The rapid development of India is not just pressing hard upon its resources but forcing expenditures on the same. There are also some neglected side effects of this development process like, generation of waste. A population of 1.2 billion is generating 0.5kg per person every day. This, sums up to a huge pile of waste, which is mostly landfilled in the most unhygienic manner possible. Such unmanaged waste not only eats up resources but demands expenditure as well. This can lead to the downfall of an economy and degradation of the nation. Thus, the paper presents waste to energy as a solution to both the problems stated above, using which not only can we reduce the amount of waste, but also produce energy from the same, thus achieving our goal of waste management as well as energy security. The paper presents the current status, major achievements and future aspects of waste to energy in India which will help decision makers, planners and bodies involved in the management of municipal solid waste understand the current status challenges and barriers of MSWM in India for further better planning and management.

Khanjan Ajaybhai Kalyani; Krishan K. Pandey

2014-01-01T23:59:59.000Z

238

Solid waste integrated forecast technical (SWIFT) report: FY1997 to FY 2070, Revision 1  

SciTech Connect (OSTI)

This web site provides an up-to-date report on the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. It includes: an overview of Hanford-wide solid waste to be managed by the WM Project; program-level and waste class-specific estimates; background information on waste sources; and comparisons with previous forecasts and with other national data sources. This web site does not include: liquid waste (current or future generation); waste to be managed by the Environmental Restoration (EM-40) contractor (i.e., waste that will be disposed of at the Environmental Restoration Disposal Facility (ERDF)); or waste that has been received by the WM Project to date (i.e., inventory waste). The focus of this web site is on low-level mixed waste (LLMW), and transuranic waste (both non-mixed and mixed) (TRU(M)). Some details on low-level waste and hazardous waste are also provided. Currently, this web site is reporting data th at was requested on 10/14/96 and submitted on 10/25/96. The data represent a life cycle forecast covering all reported activities from FY97 through the end of each program's life cycle. Therefore, these data represent revisions from the previous FY97.0 Data Version, due primarily to revised estimates from PNNL. There is some useful information about the structure of this report in the SWIFT Report Web Site Overview.

Valero, O.J.; Templeton, K.J.; Morgan, J.

1997-01-07T23:59:59.000Z

239

Application of Engineering and Technical Requirements for DOE Nuclear Facilities Standard Review Plan (SRP)  

Broader source: Energy.gov [DOE]

This Standard Review Plan (SRP), Application of Engineering and Technical Requirements for DOE Nuclear Facilities, was developed by the Chief of Nuclear Safety (CNS)1, Office of the Under Secretary for Nuclear Security, to help strengthen the technical rigor of line management oversight and federal monitoring of DOE nuclear facilities. This SRP (hereafter refers to as the Engineering SRP) provides consistent review guidance to assure that engineering and technical requirements are appropriately applied for the design, operations and disposition2 of DOE nuclear facilities. It is one of a series of three SRPs developed by the CNS. The other two SRPs address: 1) nuclear safety basis program review; and 2) application of requirements of DOE O 413.3B, Program and Project Management for the Acquisition of Capital Assets, and DOE-STD-1189, Integration of Safety into the Design Process, for DOE Critical Decision (CD) review and approval. These SRPs may be revised in the future to reflect changes in the DOE requirements, lessons learned, and experience/insights from nuclear facility design, operations, and disposition.

240

State-of-the-art review of materials properties of nuclear waste forms.  

SciTech Connect (OSTI)

The Materials Characterization Center (MCC) was established at the Pacific Northwest Laboratory to assemble a standardized nuclear waste materials data base for use in research, systems and facility design, safety analyses, and waste management decisions. This centralized data base will be provided through the means of a Nuclear Waste Materials Handbook. The first issue of the Handbook will be published in the fall of 1981 in looseleaf format so that it can be updated as additional information becomes available. To ensure utmost reliability, all materials data appearing in the Handbook will be obtained by standard procedures defined in the Handbook and approved by an independent Materials Review Board (MRB) comprised of materials experts from Department of Energy laboratories and from universities and industry. In the interim before publication of the Handbook there is need for a report summarizing the existing materials data on nuclear waste forms. This review summarizes materials property data for the nuclear waste forms that are being developed for immobilization of high-level radioactive waste. It is intended to be a good representation of the knowledge concerning the properties of HLW forms as of March 1981. The table of contents lists the following topics: introduction which covers waste-form categories, and important waste-form materials properties; physical properties; mechanical properties; chemical durability; vaporization; radiation effects; and thermal phase stability.

Mendel, J. E.; Nelson, R. D.; Turcotte, R. P.; Gray, W. J.; Merz, M. D.; Roberts, F. P.; Weber, W. J.; Westsik, Jr., J. H.; Clark, D. E.

1981-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste technical review" 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

A Review of Iron Phosphate Glasses and Recommendations for Vitrifying Hanford Waste  

SciTech Connect (OSTI)

This report contains a comprehensive review of the research conducted, world-wide, on iron phosphate glass over the past ~30 years. Special attention is devoted to those iron phosphate glass compositions which have been formulated for the purpose of vitrifying numerous types of nuclear waste, with special emphasis on the wastes stored in the underground tanks at Hanford WA. Data for the structural, chemical, and physical properties of iron phosphate waste forms are reviewed for the purpose of understanding their (a) outstanding chemical durability which meets all current DOE requirements, (b) high waste loadings which can exceed 40 wt% (up to 75 wt%) for several Hanford wastes, (c) low melting temperatures, can be as low as 900C for certain wastes, and (d) high tolerance for problem waste components such as sulfates, halides, and heavy metals (chromium, actinides, noble metals, etc.). Several recommendations are given for actions that are necessary to smoothly integrate iron phosphate glass technology into the present waste treatment plans and vitrification facilities at Hanford.

Delbert E. Ray; Chandra S. Ray

2013-11-01T23:59:59.000Z

242

Life Cycle Assessment of Energy and Energy Carriers from Waste Matter A Review  

Science Journals Connector (OSTI)

Abstract The development of economic growth, population, and rapid urbanization is increasing the pace of energy consumption and waste production. These trends, if left unchecked, will lead to massive environmental degradation. Waste-to-energy (WtE) conversion is one way of alleviating the twin problems of fossil fuel use and solid waste disposal, and their related problems (climate change, pollution etc). Life Cycle Assessment (LCA) is a useful tool for assessing the environmental performances of WtE systems. Over fifty LCA studies on various WtE systems are reviewed, comprising different waste sources, energy products, and including countries from six continents. A variety of waste types, such as agricultural residues, used cooking oil, manure, municipal solid waste, and waste wood were studied. The review found that a large majority of WtE has lower greenhouse gas emissions when compared to fossil fuels. However, some WtE studies showed an increase in environmental impacts such as acidification and eutrophication, compared to fossil fuel extraction and use. This is due to the use of chemicals (fertilizers, pesticides) in agriculture and the allocation of these impacts to the use of the agricultural waste for energy conversion. Other problems with LCA are also highlighted, including allocation issues, definition of reference systems and functional units.

Augustine Quek; Rajasekhar Balasubramanian

2014-01-01T23:59:59.000Z

243

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

Broader source: Energy.gov (indexed) [DOE]

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.

244

State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants  

SciTech Connect (OSTI)

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report.

Not Available

1980-04-01T23:59:59.000Z

245

Geological Problems in Radioactive Waste Isolation: Second Worldwide Review  

E-Print Network [OSTI]

Japan and can be taken as being rep- The Power Reactor and Nuclearand Japan, to possess an overall capacity for manage- ment of low and intermediate level wastes produced by the country's nuclear powerPower Reactor and Nuclear Fuel Development Corporation, 1-9-13 Akasaka, Minato-ku,Tokyo 107 Japan

2010-01-01T23:59:59.000Z

246

Report on the Software Environments Technical Research Review Jerey J. Blevins, E. James Whitehead, Jr., and Harry E. Yessayan  

E-Print Network [OSTI]

, Jr., and Harry E. Yessayan organized by: Leon J. Osterweil and Richard N. Taylor Irvine Research UnitReport on the Software Environments Technical Research Review Jerey J. Blevins, E. James Whitehead

Whitehead, James

247

Geological Problems in Radioactive Waste Isolation: Second Worldwide Review  

E-Print Network [OSTI]

Review comments on that plan from the Nuclear Regulatoryreview by the United States Nuclear Regulatory Commission, of a Site Characterization Plan.

2010-01-01T23:59:59.000Z

248

2008 DOE FCVT Merit Review: BSST Waste Heat Recovery Program  

Broader source: Energy.gov [DOE]

Presentation from the U.S. DOE Office of Vehicle Technologies "Mega" Merit Review 2008 on February 25, 2008 in Bethesda, Maryland.

249

Process and technological aspects of municipal solid waste gasification. A review  

SciTech Connect (OSTI)

Highlights: Black-Right-Pointing-Pointer Critical assessment of the main commercially available MSW gasifiers. Black-Right-Pointing-Pointer Detailed discussion of the basic features of gasification process. Black-Right-Pointing-Pointer Description of configurations of gasification-based waste-to-energy units. Black-Right-Pointing-Pointer Environmental performance analysis, on the basis of independent sources data. - Abstract: The paper proposes a critical assessment of municipal solid waste gasification today, starting from basic aspects of the process (process types and steps, operating and performance parameters) and arriving to a comparative analysis of the reactors (fixed bed, fluidized bed, entrained bed, vertical shaft, moving grate furnace, rotary kiln, plasma reactor) as well as of the possible plant configurations (heat gasifier and power gasifier) and the environmental performances of the main commercially available gasifiers for municipal solid wastes. The analysis indicates that gasification is a technically viable option for the solid waste conversion, including residual waste from separate collection of municipal solid waste. It is able to meet existing emission limits and can have a remarkable effect on reduction of landfill disposal option.

Arena, Umberto, E-mail: umberto.arena@unina2.it [Department of Environmental Sciences, Second University of Naples, Via A. Vivaldi, 43, 81100 Caserta (Italy)

2012-04-15T23:59:59.000Z

250

A literature review of mixed waste components: Sensitivities and effects upon solidification/stabilization in cement-based matrices  

SciTech Connect (OSTI)

The US DOE Oak Ridge Field Office has signed a Federal Facility Compliance Agreement (FFCA) regarding Oak Ridge Reservation (ORR) mixed wastes subject to the land disposal restriction (LDR) provisions of the Resource conservation and Recovery Act. The LDR FFCA establishes an aggressive schedule for conducting treatability studies and developing treatment methods for those ORR mixed (radioactive and hazardous) wastes listed in Appendix B to the Agreement. A development, demonstration, testing, and evaluation program has been initiated to provide those efforts necessary to identify treatment methods for all of the wastes that meet Appendix B criteria. The program has assembled project teams to address treatment development needs in a variety of areas, including that of final waste forms (i.e., stabilization/solidification processes). A literature research has been performed, with the objective of determining waste characterization needs to support cement-based waste-form development. The goal was to determine which waste species are problematic in terms of consistent production of an acceptable cement-based waste form and at what concentrations these species become intolerable. The report discusses the following: hydration mechanisms of Portland cement; mechanisms of retardation and acceleration of cement set-factors affecting the durability of waste forms; regulatory limits as they apply to mixed wastes; review of inorganic species that interfere with the development of cement-based waste forms; review of radioactive species that can be immobilized in cement-based waste forms; and review of organic species that may interfere with various waste-form properties.

Mattus, C.H.; Gilliam, T.M.

1994-03-01T23:59:59.000Z

251

EM Tank Waste Subcommittee Report for SRS and Hanford Tank Waste Review  

Broader source: Energy.gov (indexed) [DOE]

One System Plan. ........................................................................................................ 88 v PREFACE This is the second report of the Environmental Management Tank Waste Subcommittee (EM- TWS) of the Environmental Management Advisory Board (EMAB). The first report was submitted and accepted by the Assistant Secretary for Environmental Management (EM-1) in September 2010. The EM-TWS responded to three charges from EM-1 regarding the Waste Treatment and Immobilization Plant at Hanford (WTP) under construction in Richland, Washington. EM's responses were timely, and efforts have been put in place to address the recommendations that EMAB made. This report addresses eight charges given to the EM-TWS earlier this fiscal year. The current

252

Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013  

Broader source: Energy.gov (indexed) [DOE]

Independent Oversight Review of the Independent Oversight Review of the Waste Isolation Pilot Plant Work Planning and Control Activities April 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background........................................................................................................................................... 1 4.0 Methodology......................................................................................................................................... 2

253

GLASS FABRICATION AND ANALYSIS LITERATURE REVIEW AND METHOD SELECTION FOR WTP WASTE FEED QUALIFICATION  

SciTech Connect (OSTI)

Scope of the Report The objective of this literature review is to identify and review documents to address scaling, design, operations, and experimental setup, including configuration, data collection, and remote handling that would be used during waste feed qualification in support of the glass fabrication unit operation. Items addressed include: ? LAW and HLW glass formulation algorithms; ? Mixing and sampling; ? Rheological measurements; ? Heat of hydration; ? Glass fabrication techniques; ? Glass inspection; ? Composition analysis; ? Use of cooling curves; ? Hydrogen generation rate measurement.

Peeler, D.

2013-06-27T23:59:59.000Z

254

Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports  

SciTech Connect (OSTI)

At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRCs assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978 and 1988. All of the reports reviewed were the regulators assessment of the PSR findings rather than the original PSR report, and all but one were English translations from the original language. In these reviews, it was found that most of the countries base their regulatory guidance to some extent (and often to a large extent) on U.S. design codes and standards, NRC regulatory guidance, and U.S. industry guidance. In addition, many of the observed operational technical issues and OpE events reported for U.S. reactors are also cited in the PSR reports. The PSR reports also identified a number of potential technical material/component performance issues and OpE events that are not commonly reported for U.S. plants.

Chopra, Omesh K. [Argonne National Lab., IL (United States). Environmental Science Division; Diercks, Dwight R. [Argonne National Lab., IL (United States). Nuclear Engineering Division; Ma, David Chia-Chiun [Argonne National Lab., IL (United States). Environmental Science Division; Garud, Yogendra S. [Argonne National Lab., IL (United States). Environmental Science Division

2013-12-17T23:59:59.000Z

255

Phase 5 storage (Project W-112) Central Waste Complex operational readiness review, final report  

SciTech Connect (OSTI)

This document is the final report for the RFSH conducted, Contractor Operational Readiness Review (ORR) for the Central Waste Complex (CWC) Project W-112 and Interim Safety Basis implementation. As appendices, all findings, observations, lines of inquiry and the implementation plan are included.

Wight, R.H.

1997-05-30T23:59:59.000Z

256

Field study of disposed wastes from advanced coal processes. Quarterly technical progress report, May--July 1989  

SciTech Connect (OSTI)

The Department of Energy/Morgantown Energy Technology Center (DOE/METC) has initiated research on the disposal of solid wastes from advanced coal processes. The objective of this research is to develop information to be used by private industry and government agencies for planning waste disposal practices associated with advanced coal processes. To accomplish this objective, DOE has contracted Radian Corporation and the North Dakota Energy & Mineral Research Center (EMRC) to design, construct and monitor a limited number of field disposal tests with advanced coal process wastes. These field tests will be monitored over a three year period with the emphasis on collecting data on the field disposal of these wastes. The specific objectives for the reporting period were as follows: review fourth site candidates; obtain site access for the Freeman United site; select an ash supplier for the Illinois site and initiate subcontracts for on-site work; commence construction of the Freeman United test cell; and obtain waste for the Colorado Ute test site. Accomplishments under each task are discussed.

NONE

1989-12-31T23:59:59.000Z

257

Waste lubricating oil: an annotated review. 1982 revision  

SciTech Connect (OSTI)

Because of renewed interest in waste oil, both in terms of energy conservation and as a threat to the environment, there appears to be a need for a systemic compilation of information on the subject. This is a revision of the 1979 manuscript (BETC/IC-79/4) reflecting publications of the last three years as well as incorporation of papers that were overlooked. The number of citations has jumped from 486 to 1203, with all previous citations also listed here. The bibliography is divided into broad subject areas. The Introduction gives the history and development of the used oil reclamation industry. The General section includes the comprehensive papers that address several subjects and thus, give a capsulated overview of the used oil situation. Sources of Information and Statistical Treatments of Data tell how to obtain additional and future information and data relating to waste oil and could aid those persons interested in keeping their knowledge current. The Other Lubricating Oils section covers many of the lubricants that have the potential for recycling. The Other Oils section is divided into four sub-sections to aid the reader to find the subject of interest. The section on Related Subjects includes those sideline areas that could apply to used oil reclamation.

Cotton, F.O.

1982-10-01T23:59:59.000Z

258

Coolside waste management research. Annual technical progress report, October 1992--September 1993  

SciTech Connect (OSTI)

The composition (major, minor and trace elements) of approximately 400 Coolside waste samples form the Edgewater Coolside demonstration and CONSOL pilot plant tests are summarized and tabulated in this report. The composition changes in the waste samples collected during the Edgewater Coolside demonstration can be correlated with the processing variables and operation conditions. A study was conducted that focused on the formation mechanism of ettringite crystals in FGD waste materials since they were observed to form in Coolside, FBC, and AFBC derived wastes. The degree of swelling in FGD-derived waste can be correlated to the amounts of ettringite crystals present. Reactions controlling the formation, composition and disintegration of ettringite are critical in determining the overall stability and strength of cements and concretes derived from dry-flue gas desulfurization wastes. Since these wastes consist of fly ash, along with, CaSO{sub 3}, and CaSO{sub 4} and unreacted Ca(OH){sub 2}, the sulfites and sulfates react with the Ca(OH){sub 2} along with the glassy aluminosilicates in the fly ash to form calcium sulfo-aluminate minerals. Ettringite, the most important of these, is the main contributor to the compressive strength development of the FGD waste mixtures. However, excessive ettringite formation causes swelling which often leads to destructive crack formation. It has been shown that the quantity of ettringite formed and compressive strength of the FGD waste mixtures reach a maximum until ettringite begins to disintegrate. Because the formation mechanisms of ettringite are not entirely understood, swelling in FGD derived products is difficult to predict.

Not Available

1993-10-01T23:59:59.000Z

259

FINAL ENVIRONMENTAL ASSESSMENT FOR REMOVAL ACTIONS AT THE TECHNICAL AREA III CLASSIFIED WASTE LANDFILL, SANDIA NATIONAL LABORATORIES, NEW MEXICO - DOE/EA-1729  

Broader source: Energy.gov (indexed) [DOE]

FINAL ENVIRONMENTAL ASSESSMENT FOR REMOVAL FINAL ENVIRONMENTAL ASSESSMENT FOR REMOVAL ACTIONS AT THE TECHNICAL AREA III CLASSIFIED WASTE LANDFILL, SANDIA NATIONAL LABORATORIES, NEW MEXICO DOE/EA-1729 August 2010 National Nuclear Security Administration Sandia Site Office P.O. Box 5400 Albuquerque, New Mexico 87185-5400 DOE/EA-1729: Environmental Assessment for Removal Actions at the Technical Area III August 2010 Classified Waste Landfill, Sandia National Laboratories, New Mexico i TABLE OF CONTENTS Section 1.0 PURPOSE AND NEED FOR AGENCY ACTION .................................................................... Page 1 1.1 Background .................................................................................................................................. 1

260

Radioactive Waste Management - It's Role in contributing and achieving Sustainability. R1.13 The French strategy of waste management: technical and political dimensions of sustainability  

SciTech Connect (OSTI)

The sustainability of an energy policy depends on the manner in which it satisfies environmental, economical and social requirements. Nuclear energy is not an exception. The objectives of the future nuclear systems, as defined in the Generation IV International Forum, tend to optimize the ability of nuclear energy to satisfy sustainable development goals. In this regard, they involve strong commitments concerning waste management policy : five designs in six are based on a closed fuel cycle, in order to minimize the volume and radiotoxicity of final waste, and to recycle the fissile materials to save natural resources. Since its beginnings, the French civil nuclear programme has considered a long-term perspective and has developed spent fuel reprocessing. The French current industrial technology has already permitted to recycle 96% of spent fuel materials, to save 30% of natural resources, to reduce by 5 the amount of waste and to reduce by 10 the waste radiotoxicity, all these benefits for less than 6% of the kWh total cost. This strategy has always been criticized by the nuclear opponents, precisely because they saw that it was a sustainable way, and didn't accept to consider nuclear energy as a sustainable source of power. Two arguments were put forward these criticisms. First, the cost of reprocessing versus once-through cycle and second, the risk of proliferation induced by U-Pu partitioning process. These arguments were also invoked in international debates, and they have also been pleaded by the anti-nukes during the National Debate on HLLLW, at the end of 2005, preceding the vote of a new law in 2006 by the French parliament. Fortunately they have not convinced public opinion in France nor political decision-makers. A majority of people with no regard to technical background understand that recycling and saving the natural resources are sustainable principles. And, from a technical point of view, the 6% over cost does not seem significant considering the economics of nuclear power. Lastly, the risk proliferation is more related to the front-end technologies than to the back-end ones. So, the 2006 French Law 'for a sustainable radioactive waste management' has reinforced the closed-cycle strategy and has paved the way for a long-term development of nuclear energy in the 21. century and beyond, towards the third and fourth generations of nuclear systems. It has defined an R and D programme including the continuation of partitioning-transmutation of minor actinides and their recycling in 4. generation fast reactors. In parallel, the French president has committed the French Atomic Energy Commission to implement a 4. generation prototype reactor by 2020, with international cooperation, to guarantee the permanence of technology progress. In this regard, the waste management strategy can't be built without taking into account the perspectives of development of nuclear energy. These perspectives must include the best available technologies and, in the other hand, an adaptation to the political evolutions of societies. (authors)

Bazile, F. [CEA Saclay, French Atomic Energy Commission, Nuclear Energy Div., 91 - Gif-sur-Yvette (France)

2007-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste technical review" 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

A Technical Review on Biomass Processing: Densification, Preprocessing, Modeling and Optimization  

SciTech Connect (OSTI)

It is now a well-acclaimed fact that burning fossil fuels and deforestation are major contributors to climate change. Biomass from plants can serve as an alternative renewable and carbon-neutral raw material for the production of bioenergy. Low densities of 4060 kg/m3 for lignocellulosic and 200400 kg/m3 for woody biomass limits their application for energy purposes. Prior to use in energy applications these materials need to be densified. The densified biomass can have bulk densities over 10 times the raw material helping to significantly reduce technical limitations associated with storage, loading and transportation. Pelleting, briquetting, or extrusion processing are commonly used methods for densification. The aim of the present research is to develop a comprehensive review of biomass processing that includes densification, preprocessing, modeling and optimization. The specific objective include carrying out a technical review on (a) mechanisms of particle bonding during densification; (b) methods of densification including extrusion, briquetting, pelleting, and agglomeration; (c) effects of process and feedstock variables and biomass biochemical composition on the densification (d) effects of preprocessing such as grinding, preheating, steam explosion, and torrefaction on biomass quality and binding characteristics; (e) models for understanding the compression characteristics; and (f) procedures for response surface modeling and optimization.

Jaya Shankar Tumuluru; Christopher T. Wright

2010-06-01T23:59:59.000Z

262

Review of Technical Studies in the United States in Support of Burnup Credit Regulatory Guidance  

SciTech Connect (OSTI)

Taking credit for the reduction in reactivity associated with fuel depletion can enable more cost-effective, higher-density storage, transport, disposal, and reprocessing of spent nuclear fuel (SNF) while maintaining sufficient subcritical margin to establish an adequate safety basis. Consequently, there continues to be considerable interest in the United States (U.S.), as well as internationally, in the increased use of burnup credit in SNF operations, particularly related to storage, transport, and disposal of commercial SNF. This interest has motivated numerous technical studies related to the application of burnup credit, both domestically and internationally, as well as the design of SNF storage, transport and disposal systems that rely on burnup credit for maintaining subcriticality. Responding to industry requests and needs, the U.S. Nuclear Regulatory Commission (NRC) initiated a burnup credit research program in 1999, with support from the Oak Ridge National Laboratory (ORNL), to develop regulatory guidance and the supporting technical bases for allowing and expanding the use of burnup credit in pressurized-water reactor SNF storage and transport applications. Although this NRC research program has not been continuous since its inception, considerable progress has been achieved in many key areas in terms of increased understanding of relevant phenomena and issues, availability of relevant information and data, and subsequently updated regulatory guidance for expanded use of burnup credit. This paper reviews technical studies performed by ORNL for the U.S. NRC burnup credit research program. Examples of topics include reactivity effects associated with reactor operating characteristics, fuel assembly characteristics, burnable absorbers, control rods, spatial burnup distributions, cooling time, and assembly misloading; methods and data for validation of isotopic composition predictions; methods and data for validation of criticality calculations; and operational issues and data related to assembly burnup confirmation. The objective of this paper is to summarize the work and significant accomplishments, with references to the technical reports and publications for complete details, and provide a useful resource to others in the burnup credit community.

Wagner, John C [ORNL] [ORNL; Parks, Cecil V [ORNL] [ORNL; Mueller, Don [ORNL] [ORNL; Gauld, Ian C [ORNL] [ORNL

2010-01-01T23:59:59.000Z

263

Plutonium Equivalent Inventory for Belowground Radioactive Waste at the Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Many aspects of the management of this waste are conducted at Technical Area 54 (TA-54); Area G plays a key role in these management activities as the Laboratory's only disposal facility for low-level radioactive waste (LLW). Furthermore, Area G serves as a staging area for transuranic (TRU) waste that will be shipped to the Waste Isolation Pilot Plant for disposal. A portion of this TRU waste is retrievably stored in pits, trenches, and shafts. The radioactive waste disposed of or stored at Area G poses potential short- and long-term risks to workers at the disposal facility and to members of the public. These risks are directly proportional to the radionuclide inventories in the waste. The Area G performance assessment and composite analysis (LANL, 2008a) project long-term risks to members of the public; short-term risks to workers and members of the public, such as those posed by accidents, are addressed by the Area G Documented Safety Analysis (LANL, 2011a). The Documented Safety Analysis uses an inventory expressed in terms of plutonium-equivalent curies, referred to as the PE-Ci inventory, to estimate these risks. The Technical Safety Requirements for Technical Area 54, Area G (LANL, 2011b) establishes a belowground radioactive material limit that ensures the cumulative projected inventory authorized for the Area G site is not exceeded. The total belowground radioactive waste inventory limit established for Area G is 110,000 PE-Ci. The PE-Ci inventory is updated annually; this report presents the inventory prepared for 2011. The approach used to estimate the inventory is described in Section 2. The results of the analysis are presented in Section 3.

French, Sean B. [Los Alamos National Laboratory; Shuman, Rob [WPS: WASTE PROJECTS AND SERVICES

2012-04-18T23:59:59.000Z

264

Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Uinit Contractor Operational Readiness Review, June 2012  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Contractor Contractor Operational Readiness Review June 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

265

Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Uinit Contractor Operational Readiness Review, June 2012  

Broader source: Energy.gov (indexed) [DOE]

Contractor Contractor Operational Readiness Review June 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

266

Review on potential for waste recycled based bioenergy for marine system  

Science Journals Connector (OSTI)

Human status today can best be defined as an age of knowledge, efficiency and sustainable developments towards fulfilling significant part of human existence in this beautiful planet we all share. Previous time in human history has been dominated with various experimentation, knowledge acquisition which has resulted to new discovery and new philosophy of doing things in efficient, sensitive, cooperative and above all sustainable manner (maintaining quarto bottom balance, i.e. economic, technical, environmental and social, between man technosphere and environsphere world in order to sustain continuous healthy existence of our planet and the right of future generation). New knowledge and technology have emerged, since there is no drain in this planet, the greatest challenge for humanity lies in recycling our waste to the lowest level of usage. This paper will discuss the need to choose waste derived biofuel above all other food sources. This paper also discusses risk and abatement required for choice of best practice sustainable bioenergy generation for marine system.

O.O. Sulaiman; A.S. Abd Kader; A.H. Saharuddin; W.B. Wan Nik; K.B. Samo

2011-01-01T23:59:59.000Z

267

Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis  

SciTech Connect (OSTI)

Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

OHara, J.M.; Higgins, J.C.

2010-01-31T23:59:59.000Z

268

Coolside waste management research. Quarterly technical progress report, April 1, 1993--June 30, 1993  

SciTech Connect (OSTI)

Reactions controlling the formation, composition and disintegration of ettringite are critical in determining the overall stability and strength of cements and concretes derived from dry-flue gas desulfurization wastes. These wastes typically consist primarily of fly ash, along with, CaSO{sub 3}, and CaSO{sub 4} and unreacted Ca(OH){sub 2}. The sulfites and sulfates in these materials react with the portiandite (Ca(OH){sub 2}) along with the glassy aluminosilicate Portion of the fly ash to form calcium sulfo-aluminate minerals. Ettringite, the most important of these, is the main contributor to the compressive strength development of the FGD waste mixtures. Excessive ettringite formation causes first lateral and horizontal swelling of the concrete which often leads to destructive crack formation. It has been shown that the quantity of ettringite formed and compressive strength of the FGD waste mixtures reach a maximum until ettringite begins to disintegrate. Because the formation mechanisms of ettringite are not entirely understood, swelling in FGD derived products is difficult to predict. This study focused on the formation and disintegration mechanism of ettringite in FGD waste mixtures with varying contents of aluminum (hydr)oxides, and calcium (hydr)oxides of the starting materials. Mineralogical transformations were documented in X-ray diffraction and scanning electron microscope (SEM) observations of the materials.

Not Available

1993-12-31T23:59:59.000Z

269

Kaiser Engineers Hanford internal position paper -- Project W-236A, Multi-function Waste Tank Facility -- Peer reviews of selected activities  

SciTech Connect (OSTI)

The purpose of this paper is to develop and document a proposed position on the performance of independent peer reviews on selected design and analysis components of the Title 1 [Preliminary] and Title 2 [Final] design phases of the Multi-Function Waste Tank Facility [MWTF] project. An independent, third-party peer review is defined as a documented critical review of documents, data, designs, design inputs, tests, calculations, or related materials. The peer review should be conducted by persons independent of those who performed the work, but who are technically qualified to perform the original work. The peer review is used to assess the validity of assumptions and functional requirements, to assess the appropriateness and logic of selected methodologies and design inputs, and to verify calculations, analyses and computer software. The peer review can be conducted at the end of the design activity, at specific stages of the design process, or continuously and concurrently with the design activity. This latter method is often referred to as ``Continuous Peer Review.``

Stine, M.D. [Kaiser Engineers Hanford Co., Richland, WA (United States)

1995-01-04T23:59:59.000Z

270

Life cycle assessment of thermal Waste-to-Energy technologies: Review and recommendations  

Science Journals Connector (OSTI)

Abstract Life cycle assessment (LCA) has been used extensively within the recent decade to evaluate the environmental performance of thermal Waste-to-Energy (WtE) technologies: incineration, co-combustion, pyrolysis and gasification. A critical review was carried out involving 250 individual case-studies published in 136 peer-reviewed journal articles within 1995 and 2013. The studies were evaluated with respect to critical aspects such as: (i) goal and scope definitions (e.g. functional units, system boundaries, temporal and geographic scopes), (ii) detailed technology parameters (e.g. related to waste composition, technology, gas cleaning, energy recovery, residue management, and inventory data), and (iii) modeling principles (e.g. energy/mass calculation principles, energy substitution, inclusion of capital goods and uncertainty evaluation). Very few of the published studies provided full and transparent descriptions of all these aspects, in many cases preventing an evaluation of the validity of results, and limiting applicability of data and results in other contexts. The review clearly suggests that the quality of LCA studies of WtE technologies and systems including energy recovery can be significantly improved. Based on the review, a detailed overview of assumptions and modeling choices in existing literature is provided in conjunction with practical recommendations for state-of-the-art LCA of Waste-to-Energy.

Thomas Fruergaard Astrup; Davide Tonini; Roberto Turconi; Alessio Boldrin

2014-01-01T23:59:59.000Z

271

Radioactive waste isolation in salt: peer review of Westinghouse Electric Corporation's report on reference conceptual designs for a repository waste package  

SciTech Connect (OSTI)

This report documents the findings of the peer panel constituted by Argonne National Laboratory to review Region A of Westinghouse Electric Corporation's report entitled Waste Package Reference Conceptual Designs for a Repository in Salt. The panel determined that the reviewed report does not provide reasonable assurance that US Nuclear Regulatory Commission (NRC) requirements for waste packages will be met by the proposed design. It also found that it is premature to call the design a ''reference design,'' or even a ''reference conceptual design.'' This review report provides guidance for the preparation of a more acceptable design document.

Rote, D.M.; Hull, A.B.; Was, G.S.; Macdonald, D.D.; Wilde, B.E.; Russell, J.E.; Kruger, J.; Harrison, W.; Hambley, D.F.

1985-10-01T23:59:59.000Z

272

A Brief Review of Filtration Studies for Waste Treatment at the Hanford Site  

SciTech Connect (OSTI)

This document completes the requirements of Milestone 1-2, PNNL Draft Literature Review, discussed in the scope of work outlined in the EM-31 Support Project task plan WP-2.3.6-2010-1. The focus of task WP 2.3.6 is to improve the U.S. Department of Energys (DOEs) understanding of filtration operations for high-level waste (HLW) to enhance filtration and cleaning efficiencies, thereby increasing process throughput and reducing the sodium demand (through acid neutralization). Developing the processes for fulfilling the cleaning/backpulsing requirements will result in more efficient operations for both the Hanford Tank Waste Treatment and Immobilization Plant (WTP) and the Savannah River Site (SRS), thereby increasing throughput by limiting cleaning cycles. The purpose of this document is to summarize Pacific Northwest National Laboratorys (PNNLs) literature review of historical filtration testing at the laboratory and of testing found in peer-reviewed journals. Eventually, the contents of this document will be merged with a literature review by SRS to produce a summary report for DOE of the results of previous filtration testing at the laboratories and the types of testing that still need to be completed to address the questions about improved filtration performance at WTP and SRS. To this end, this report presents 1) a review of the current state of crossflow filtration knowledge available in the peer-reviewed literature, 2) a detailed review of PNNL-related filtration studies specific to the Hanford site, and 3) an overview of current waste filtration models developed by PNNL and suggested avenues for future model development.

Daniel, Richard C.; Schonewill, Philip P.; Shimskey, Rick W.; Peterson, Reid A.

2010-12-01T23:59:59.000Z

273

SUPPLEMENTAL COLUMBIA RIVER PROTECTION ACTIVITIES AT THE DEPARTMENT OF ENERGY HANFORD SITE 2008 TECHNICAL REVIEW  

SciTech Connect (OSTI)

Beginning in 2006, the US Department of Energy (DOE) supported nine applied research projects to improve the protection of the Columbia River and mitigate the impacts of Hanford Site groundwater. These projects were funded through a supplemental Congressional budget allocation, and are now in various stages of completion in accordance with the research plans. The DOE Office of Environmental Management Groundwater and Soil Cleanup Technologies (EM-22) sponsored a technical peer review meeting for these projects in Richland WA, July 28-31, 2008. The overall objective of the peer review is to provide information to support DOE decisions about the status and potential future application of the various technologies. The charge for the peer review panel was to develop recommendations for each of the nine 'technologies'. Team members for the July 2008 review were Brian Looney, Gene LeBoeuf, Dawn Kaback, Karen Skubal, Joe Rossabi, Paul Deutsch, and David Cocke. Previous project reviews were held in May 2007 and March-May of 2006. The team used the following four rating categories for projects: (a) Incorporate the technology/strategy in ongoing and future EM activities; (b) Finish existing scope of applied research and determine potential for EM activities when research program is finished; (c) Discontinue current development activities and do not incorporate technology/strategy into ongoing and future EM activities unless a significant and compelling change in potential viability is documented; and (d) Supplement original funded work to obtain the data needed to support a DOE decision to incorporate the technology into ongoing and future EM activities. The supplemental funding portfolio included two projects that addressed strontium, five projects that addressed chromium, one project that addressed uranium and one project that addressed carbon tetrachloride. The projects ranged from in situ treatment methods for immobilizing contaminants using chemical-based methods such as phosphate addition, to innovative surface treatment technologies such as electrocoagulation. Total funding for the nine projects was $9,900,000 in fiscal year (FY) 2006 and $2,000,000 in FY 2007. At the Richland meeting, the peer reviewers provided a generally neutral assessment of the projects and overall progress, and a generally positive assessment with regard to the principal investigators meeting their stated research objectives and performing the planned laboratory research and limited field work. Only one project, the Electrocoagulation Treatability Test, received a rating of 'discontinue' from the team because the project goals had not been met. Because this particular project has already ended, no action with respect to funding withdrawal is necessary. All other projects were recommended to be finished and/or incorporated into field efforts at Hanford. Specific technical comments and recommendations were provided by the team for each project.

Looney, B; Dawn S. Kaback, D; Eugene L. LeBoeuf, E; Joe Rossabi, J; Karen L. Skubal, K; David L. Cocke, D; Paul C. Deutsch, P

2008-09-30T23:59:59.000Z

274

Environmental review and regulation for siting a nuclear waste repository at Yucca Mountain, Nevada  

Science Journals Connector (OSTI)

The U.S. Department of Energy (DOE) has proposed that the first geologic repository for high-level nuclear waste in the United States be sited at Yucca Mountain, Nevada. Repository sitting was exempted by the Nuclear Waste Policy Act from the requirements for an environmental impact statement under the National Environmental Policy Act (NEPA) and, additionally, the DOE was prohibited by law from acquiring new empirical information for environmental assessment. Thus, no systematic, interdisciplinary evaluation of impacts based on site-specific data will occur before the Yucca Mountain environment is irreparably altered by site characterization. Exemption of siting activities for the nation's first geologic repository for high-level nuclear wastes from NEPA review is further evidence of the eclipse of NEPA in decision making, a trend that may foretell how controversial, technologically complex projects will be carried out in the future.

Charles R. Malone

1989-01-01T23:59:59.000Z

275

Solid waste projection model: Database version 1. 0 technical reference manual  

SciTech Connect (OSTI)

The Solid Waste Projection Model (SWPM) system is an analytical tool developed by Pacific Northwest Laboratory (PNL) for Westinghouse Hanford Company (WHC). The SWPM system provides a modeling and analysis environment that supports decisions in the process of evaluating various solid waste management alternatives. This document, one of a series describing the SWPM system, contains detailed information regarding the software and data structures utilized in developing the SWPM Version 1.0 Database. This document is intended for use by experienced database specialists and supports database maintenance, utility development, and database enhancement. Those interested in using the SWPM database should refer to the SWPM Database User's Guide. 14 figs., 6 tabs.

Carr, F.; Bowman, A.

1990-11-01T23:59:59.000Z

276

Review of comparative LCAs of food waste management systems - Current status and potential improvements  

SciTech Connect (OSTI)

Highlights: Black-Right-Pointing-Pointer GHG-emissions from different treatment alternatives vary largely in 25 reviewed comparative LCAs of bio-waste management. Black-Right-Pointing-Pointer System-boundary settings often vary largely in reviewed studies. Black-Right-Pointing-Pointer Existing LCA guidelines give varying recommendations in relation to several key issues. - Abstract: Twenty-five comparative cycle assessments (LCAs) addressing food waste treatment were reviewed, including the treatment alternatives landfill, thermal treatment, compost (small and large scale) and anaerobic digestion. The global warming potential related to these treatment alternatives varies largely amongst the studies. Large differences in relation to setting of system boundaries, methodological choices and variations in used input data were seen between the studies. Also, a number of internal contradictions were identified, many times resulting in biased comparisons between alternatives. Thus, noticed differences in global warming potential are not found to be a result of actual differences in the environmental impacts from studied systems, but rather to differences in the performance of the study. A number of key issues with high impact on the overall global warming potential from different treatment alternatives for food waste were identified through the use of one-way sensitivity analyses in relation to a previously performed LCA of food waste management. Assumptions related to characteristics in treated waste, losses and emissions of carbon, nutrients and other compounds during the collection, storage and pretreatment, potential energy recovery through combustion, emissions from composting, emissions from storage and land use of bio-fertilizers and chemical fertilizers and eco-profiles of substituted goods were all identified as highly relevant for the outcomes of this type of comparisons. As the use of LCA in this area is likely to increase in coming years, it is highly relevant to establish more detailed guidelines within this field in order to increase both the general quality in assessments as well as the potentials for cross-study comparisons.

Bernstad, A., E-mail: anna.bernstad@chemeng.lth.se [Water and Environmental Engineering at the Department of Chemical Engineering, Lund University, Chemical Centre, 221 00 Lund (Sweden); Cour Jansen, J. la [Water and Environmental Engineering at the Department of Chemical Engineering, Lund University, Chemical Centre, 221 00 Lund (Sweden)

2012-12-15T23:59:59.000Z

277

SCFA lead lab technical assistance review of the Pit 7 Complex source containment  

SciTech Connect (OSTI)

On January 29-30, 2001 a technical assistance team (TAT) met with the Pit 7 project team at Lawrence Livermore National Laboratory (LLNL) to review technologies being evaluated for remediation in the Site 300 Pit 7 Complex and the process for selecting these technologies. Specifically, the project team presented the TAT with a core need to identify technically and economically practicable technologies and methods to stabilize, contain, or control the tritium and uranium in the source areas at the Pits 3 and 5 landfill area to prevent further releases of these contaminants to groundwater and the migration of tritiated and uranium-contaminated groundwater. The approaches and needs for the systems surrounding the landfills were also presented and discussed. With encouragement from the project team, the TAT expanded its focus to include additional site characterization, a water balance model, and computational models. The TAT was comprised of leading technical and regulatory experts from around the country and was assembled by SCFA's Lead Lab in response to a technical assistance request from John Ziagos, Project Manager for the Pit 7 Area (Technical Assistance Request: LLNL No.1). A list of the TAT members is included below and contact information the TAT members and site participants is in Appendix B. To familiarize the TAT assistance team with Pit 7 Complex issues, the project team gave a presentation outlining the site geology, contaminant hydrogeology, land-use issues, stakeholder concerns, regulatory requirements, groundwater flow and transport modeling efforts, pit source characterization efforts, and remedial options. Time for clarification and questions between the TAT and the site team was integrated into the presentation schedule. On the morning of the second day, the TAT reconvened with the site team and John Evans of the TAT presented information about a helium soil gas survey method that could potentially be used to locate and characterize tritium hot spots in Pits 3 and 5. Following the presentation, the TAT gathered independently to identify issues that are critical to remedy selection and to list questions or information gaps that the site is trying to resolve.

Eaton, D.; Janeday, D.; Woodward, D.; Imrich, J.; Evans, J.; Morris, M.; Reimus, P.; Hazen, T.

2001-01-29T23:59:59.000Z

278

ANL technical support program for DOE environmental restoration and waste management. Annual report, October 1993--September 1994  

SciTech Connect (OSTI)

A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1994 on the following tasks: (1) Critical Reviews of important parameters that affect the reactivity of glass in an unsaturated environment are being prepared. (2) A series of tests is ongoing to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. (3) The effect of radiation upon the durability of waste glasses at a high SA/V ratio and a high gas-to-liquid volume ratio has been assessed. (4) A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SA/V ratios. Such differences in the SA/V ratio may significantly affect glass durability. At long-term periods and high SA/V ratios, acceleration in glass reaction has been observed. (5) Tests were initiated on West Valley Reference 6 (WV6) glass and on the Environmental Assessment (EA) glass. (6) Tests with the actinide-doped West Valley glass ATM-10 have been in progress for over seven years as a part of work for the Yucca Mountain Site Characterization Project (YMP). (7) Analytical electron microscopy (AEM) is being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Also, colloids from the leach solutions are being studied using AEM.

Bates, J.K.; Brown, N.R.; Buck, E.C. [and others

1995-06-01T23:59:59.000Z

279

Microsoft PowerPoint - 7-05 _ Dixion ASCEM Update to Tank Waste technical exchange 111510.pptx  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

ASCEM Program Update ASCEM Program Update ASCEM Multi-Lab Program Manager Paul Dixon Presentation to the EM Waste Processing Technical Exchange November 20, 2010 ascemdoe.org Advanced Simulation Capability for Environmental Management Print Close ascemdoe.org Presentation Outline 1) What is ASCEM?  Motivation  Who We Are  ASCEM Structure and Development Lifecycle 2) FY11 Phase I Demonstration Update  Criteria for Phase 1 Demo  High Level Goals of Phase 1 Demo  Site Selection Evaluation/Savannah River F-Basin  Highlights of Phase 1 Demo 3) Site Application Working Groups for FY11 4) Accomplishments Since Last LFRG Meeting 5) Conclusions and Further Discussion Page 1 Print Close ascemdoe.org What is ASCEM? ascemdoe.org Page 2 ASCEM is a state-of-the-art scientific tool and approach for

280

Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility  

Broader source: Energy.gov (indexed) [DOE]

of5 of5 U.S. Department of Energy Subject: Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility - Inspection Criteria, Approach, and Line:~ HS: Rev: Eff. Date: HSS CRAD 45-57 0 January 31,2013 Office of Safety and Emergency Management Evaluations Acting Direc or, Office of Sifety and Emergency Management Evaluations Date: January 31, 2013 Criteria Review and Approach Document LL.v. ~·M Criteria Lead:ife\riew of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility Page 1 of 5 Date: January 31, 2013 1.0 PURPOSE Within the Office of Health, Safety and Security (HSS), the Office of Enforcement and Oversight, Office of Safety and Emergency Management Evaluations (HS-45) mission is to assess the effectiveness of the

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281

The Second Opening of the Waste Isolation Pilot Plant? Review of Salient Characteristics and Unique Operational Considerations for Remote Handled Transuranic Waste  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) intends to dispose of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) beginning in 2005. (1) Four principle regulatory agencies are involved in the process of approving the RH TRU waste activities. The DOE is responsible for operational activities. The U. S. Nuclear Regulatory Commission (NRC) approves the design and use of shipping containers. The U.S. Environmental Protection Agency (EPA) is responsible for assuring safe and environmentally effective long-term disposal of the radioactive component of the waste and operational environmental monitoring. The New Mexico Environment Department (NMED) is responsible for the handling and the disposal of the non-radioactive hazardous component of the waste. The Environmental Evaluation Group (EEG) is responsible for performing independent technical oversight of all WIPP activities, and will comment on documents and practices for the various regulated RH TRU waste activities. The DOE has already obtained the necessary approvals from the NRC, and has submitted a Class 3 Modification request to the NMED. On December 16, 2002 the DOE Carlsbad Field Office (CBFO) provided the EPA with a notice of proposed change, in accordance with 40 CFR 194.4 (b) (3), to receive and dispose of remote handled transuranic waste. (2) WIPP procedures for the management of RH TRU waste at the site are being developed. While there are no issues with current NRC Certificates of Compliance for the RH TRU waste shipping containers, it is likely that there will be some controversy over other aspects of the currently planned RH TRU waste program. These issues may include: (1) the published RH TRU waste inventory, (2) the characterization of the radionuclide portion of the waste, for which one planned method is to use dose-to-Curie conversions, and (3) the plans to use bounding estimates for the hazardous portion of the WIPP waste, rather than measuring VOCs on a container-by-container basis or by representative sampling as is done for contact handled transuranic (CH TRU) waste. This paper discusses the currently planned process and the possible issues related to the DOE's efforts to dispose RH TRU waste at the WIPP.

Anastas, G.; Walker, B.A.

2003-02-24T23:59:59.000Z

282

Evaluation of a fluidized-bed waste-heat recovery system. A technical case study  

SciTech Connect (OSTI)

The US DOE Office of Industrial Technologies (OIT) sponsors research and development (R&D) to improve the energy efficiency of American industry and to provide for fuel flexibility. Large amounts of heat escape regularly through the waste-gas streams of industrial processes, particularly those processes that use furnaces, kilns, and calciners. Recovering this waste heat will conserve energy; however, the extremely high temperatures and corrosive nature of many flue and exhaust gases make conventional heat recovery difficult. One solution is a waste-heat recovery system that can withstand the high temperatures and rids itself of corrosion-causing particulates. OIT and Aerojet Energy Conversion Company recently completed a joint project to develop just such a system and to evaluate its long-term operation. This technology, called fluidized-bed waste-heat recovery (FBWHR), offers several advantages over conventional heat recovery, including high gas-side heat-transfer coefficients and a self-cleaning capability. The FBWHR system can recover heat from high-temperature, dirty waste-gas streams, such as those found in the metals, glass, cement, chemical, and petroleum-refining industries. In this multiyear R&D project, Aerojet designed and fabricated an FBWHR system that recovers heat from the corrosive flue gases of aluminum melt furnaces to produce process steam for the plant. The system was installed on a 34-million-Btu/h furnace used to melt aluminum scrap at ALCOA`s Massena, New York plant. During a successful one-year field test, the system produced 26 million lb of 175-psig saturated steam, recovering as much as 28% of the fuel energy input to the furnace.

Not Available

1992-04-01T23:59:59.000Z

283

Report of the technical review team on the Catalytic Extraction Process  

SciTech Connect (OSTI)

The TRT was impressed with the quality and volume of laboratory and pilot scale development work that had been conducted over the past year. Many of the doubts and questions raised by the TRP on technical details had been examined, either by theoretical calculations or in the pilot facility. Moreover, a more open and forthcoming attitude was evident among the MMT staff who either presented briefings or responded to the Team`s questions. Of special note to DOE, the TRP recognized a year ago that the pilot facility at Fall River was not designed for radioactive pilot tests. However, from the dialogue surrounding the TRP review, it was evident that not much thought had been given to the hazards, concerns, and special requirements incumbent with radioactive operations -- everything from doing pours of hot radioactive metal from a vessel to remote-handling equipment and operations. This year the TRT noticed a significant improvement in this respect.

NONE

1996-03-01T23:59:59.000Z

284

Technical Review of the CENWP Computational Fluid Dynamics Model of the John Day Dam Forebay  

SciTech Connect (OSTI)

The US Army Corps of Engineers Portland District (CENWP) has developed a computational fluid dynamics (CFD) model of the John Day forebay on the Columbia River to aid in the development and design of alternatives to improve juvenile salmon passage at the John Day Project. At the request of CENWP, Pacific Northwest National Laboratory (PNNL) Hydrology Group has conducted a technical review of CENWP's CFD model run in CFD solver software, STAR-CD. PNNL has extensive experience developing and applying 3D CFD models run in STAR-CD for Columbia River hydroelectric projects. The John Day forebay model developed by CENWP is adequately configured and validated. The model is ready for use simulating forebay hydraulics for structural and operational alternatives. The approach and method are sound, however CENWP has identified some improvements that need to be made for future models and for modifications to this existing model.

Rakowski, Cynthia L.; Serkowski, John A.; Richmond, Marshall C.

2010-12-01T23:59:59.000Z

285

Waste characterization study for the Kemp's Ridley sea turtle. Technical memo  

SciTech Connect (OSTI)

The Kemp's Ridley sea turtle, Lepidochelys kempi, is an endangered species. The National Marine Fisheries Service's Head Start program is part of an international operation to save the turtles from extinction. Under the Head Start program, eggs from the Ridley's only known wild nesting beach at Rancho Nuevo in Mexico are transported to Padre Island on the Texas coast to be hatched. The head start enables the turtles to develop a survival advantage. The principal objective was to develop baseline waste-characterization data required to design a waste-water treatment scheme for the Galveston Head Start facility. As a secondary objective, preliminary testing of some filtration components was undertaken to determine which units were most appropriate for inclusion in a wastewater treatment scheme.

Malone, R.F.; Guarisco, M.

1988-02-01T23:59:59.000Z

286

Review of the WIPP draft application to show compliance with EPA transuranic waste disposal standards  

SciTech Connect (OSTI)

The purpose of the New Mexico Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The EEG was established in 1978 with funds provided by the U.S. Department of Energy (DOE) to the State of New Mexico. Public Law 100-456, the National Defense Authorization Act, Fiscal Year 1989, Section 1433, assigned EEG to the New Mexico Institute of Mining and Technology and continued the original contract DE-AC04-79AL10752 through DOE contract DE-AC04-89AL58309. The National Defense Authorization Act for Fiscal Year 1994, Public Law 103-160, continues the authorization. EEG performs independent technical analyses of the suitability of the proposed site; the design of the repository, its planned operation, and its long-term integrity; suitability and safety of the transportation systems; suitability of the Waste Acceptance Criteria and the generator sites` compliance with them; and related subjects. These analyses include assessments of reports issued by the DOE and its contractors, other federal agencies and organizations, as they relate to the potential health, safety and environmental impacts from WIPP. Another important function of EEG is the independent environmental monitoring of background radioactivity in air, water, and soil, both on-site and off-site.

Neill, R.H.; Chaturvedi, L.; Clemo, T.M. [and others

1996-03-01T23:59:59.000Z

287

Technical cooperation on nuclear security between the United States and China : review of the past and opportunities for the future.  

SciTech Connect (OSTI)

The United States and China are committed to cooperation to address the challenges of the next century. Technical cooperation, building on a long tradition of technical exchange between the two countries, can play an important role. This paper focuses on technical cooperation between the United States and China in the areas of nonproliferation, arms control and other nuclear security topics. It reviews cooperation during the 1990s on nonproliferation and arms control under the U.S.-China Arms Control Exchange, discusses examples of ongoing activities under the Peaceful Uses of Technology Agreement to enhance security of nuclear and radiological material, and suggests opportunities for expanding technical cooperation between the defense nuclear laboratories of both countries to address a broader range of nuclear security topics.

Pregenzer, Arian Leigh

2011-12-01T23:59:59.000Z

288

88 JOURNAL OF WEATHER MODiFiCATiON vOLUME 43 -TECHNICAL NOTES -CORRESPONDENCE -BOOK REVIEW  

E-Print Network [OSTI]

88 JOURNAL OF WEATHER MODiFiCATiON vOLUME 43 - TECHNICAL NOTES - CORRESPONDENCE - BOOK REVIEW much to unravel about the intricacies of aerosol interactions with tropical cyclones. First we need of other factors influencing TC intensity including SST, wind shear, and the moisture content of the lower

Rhode Island, University of

289

110 kW Stationary Combined Heat and Power Systems Status and Technical Potential: Independent Review  

Broader source: Energy.gov [DOE]

This independent review examines the status and technical potential of 1-10 kW stationary combined heat and power fuel cell systems and analyzes the achievability of the DOE cost, efficiency, and durability targets for 2012, 2015, and 2020.

290

Waste Processing Annual Technology Development Report 2007  

Broader source: Energy.gov (indexed) [DOE]

Processing Processing Annual Technology Development Report 2007 SRNS-STI-2008-00040 United States Department of Energy Waste Processing Annual Technology Development Report 2007 Prepared and edited by S. R. Bush EM Technical Integration Office Savannah River National Laboratory Reviewed by Dr. W. R. Wilmarth, Manager EM Technical Integration Office Savannah River National Laboratory Approved by Dr. S. L. Krahn, Director EM-21 Office of Waste Processing U. S. Department of Energy APPROVED for Release for Unlimited (Release to Public) (Signed 08/13/2008) (Signed 08/13/2008) (Signed 08/13/2008) EM-21 Waste Processing Annual Report for Calendar Year 2007 2/74

291

Hanford Waste Vitrification Plant technical background document for best available radionuclide control technology demonstration  

SciTech Connect (OSTI)

This report provides the background documentation to support applications for approval to construct and operate new radionuclide emission sources at the Hanford Waste Vitrification Plant (HWVP) near Richland, Washington. The HWVP is required to obtain permits under federal and state statutes for atmospheric discharges of radionuclides. Since these permits must be issued prior to construction of the facility, draft permit applications are being prepared, as well as documentation to support these permits. This report addresses the applicable requirements and demonstrates that the preferred design meets energy, environmental, and economic criteria for Best Available Radionuclide Control Technology (BARCT) at HWVP. 22 refs., 11 figs., 25 tabs.

Carpenter, A.B.; Skone, S.S.; Rodenhizer, D.G.; Marusich, M.V. (Ebasco Services, Inc., Bellevue, WA (USA))

1990-10-01T23:59:59.000Z

292

End of FY10 report - used fuel disposition technical bases and lessons learned : legal and regulatory framework for high-level waste disposition in the United States.  

SciTech Connect (OSTI)

This report examines the current policy, legal, and regulatory framework pertaining to used nuclear fuel and high level waste management in the United States. The goal is to identify potential changes that if made could add flexibility and possibly improve the chances of successfully implementing technical aspects of a nuclear waste policy. Experience suggests that the regulatory framework should be established prior to initiating future repository development. Concerning specifics of the regulatory framework, reasonable expectation as the standard of proof was successfully implemented and could be retained in the future; yet, the current classification system for radioactive waste, including hazardous constituents, warrants reexamination. Whether or not consideration of multiple sites are considered simultaneously in the future, inclusion of mechanisms such as deliberate use of performance assessment to manage site characterization would be wise. Because of experience gained here and abroad, diversity of geologic media is not particularly necessary as a criterion in site selection guidelines for multiple sites. Stepwise development of the repository program that includes flexibility also warrants serious consideration. Furthermore, integration of the waste management system from storage, transportation, and disposition, should be examined and would be facilitated by integration of the legal and regulatory framework. Finally, in order to enhance acceptability of future repository development, the national policy should be cognizant of those policy and technical attributes that enhance initial acceptance, and those policy and technical attributes that maintain and broaden credibility.

Weiner, Ruth F.; Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Rechard, Robert Paul; Perry, Frank (Los Alamos National Laboratory, Los Alamos, NM); Jenkins-Smith, Hank C. (University of Oklahoma, Norman, OK); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Nutt, Mark (Argonne National Laboratory, Argonne, IL); Cotton, Tom (Complex Systems Group, Washington DC)

2010-09-01T23:59:59.000Z

293

Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility  

Broader source: Energy.gov (indexed) [DOE]

of6 of6 Subject: Review of Safety Basis HS: HSS CRAD 45-59 U.S. Department of Development for the Los Alamos Rev: 0 National Laboratory Transuranic Eff. Date: May 6, 2013 Energy Waste Facility - Criteria and Review Approach Document Office of Safety and ~ Emergency Management Acting Djector, Of~e of Safety and Evaluations Emergency Management Evaluations Date: May 6, 2013 firo,~ Page 1of6 Criteria and Review e;dJatnes 0. Low Approach Document Date: May 6, 2013 1.0 PURPOSE Within the Office of Health, Safety and Security (HSS), the Office of Enforcement and Oversight, Office of Safety and Emergency Management Evaluations (HS-45) mission is to assess the effectiveness of the environment, safety, health, and emergency management systems and practices used by line and

294

Review of private sector treatment, storage, and disposal capacity for radioactive waste. Revision 1  

SciTech Connect (OSTI)

This report is an update of a report that summarized the current and near-term commercial and disposal of radioactive and mixed waste. This report was capacity for the treatment, storage, dating and written for the Idaho National Engineering Laboratory (INEL) with the objective of updating and expanding the report entitled ``Review of Private Sector Treatment, Storage, and Disposal Capacity for Radioactive Waste``, (INEL-95/0020, January 1995). The capacity to process radioactively-contaminated protective clothing and/or respirators was added to the list of private sector capabilities to be assessed. Of the 20 companies surveyed in the previous report, 14 responded to the request for additional information, five did not respond, and one asked to be deleted from the survey. One additional company was identified as being capable of performing LLMW treatability studies and six were identified as providers of laundering services for radioactively-contaminated protective clothing and/or respirators.

Smith, M.; Harris, J.G.; Moore-Mayne, S.; Mayes, R.; Naretto, C.

1995-04-14T23:59:59.000Z

295

Review and Status of Solid Waste Management Practices in Multan, Pakistan  

E-Print Network [OSTI]

of throwing waste in water bodies, burning it as annearby residents. Burning of the waste at landfills and in

Shoaib, Muhammad; Mirza, Umar Karim; Sarwar, Muhammad Avais

2006-01-01T23:59:59.000Z

296

Operational readiness review for the Waste Experimental Reduction Facility. Final report  

SciTech Connect (OSTI)

An Operational Readiness Review (ORR) at the Idaho National Engineering Laboratory`s (INEL`s) Waste Experimental Reduction Facility (WERF) was conducted by EG&G Idaho, Inc., to verify the readiness of WERF to resume operations following a shutdown and modification period of more than two years. It is the conclusion of the ORR Team that, pending satisfactory resolution of all pre-startup findings, WERF has achieved readiness to resume unrestricted operations within the approved safety basis. ORR appraisal forms are included in this report.

Not Available

1993-11-01T23:59:59.000Z

297

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 357: Mud Pits and Waste Dump, Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) plan was prepared as a characterization and closure report for Corrective Action Unit (CAU) 357, Mud Pits and Waste Dump, in accordance with the Federal Facility Agreement and Consent Order. The CAU consists of 14 Corrective Action Sites (CASs) located in Areas 1, 4, 7, 8, 10, and 25 of the Nevada Test Site (NTS). All of the CASs are found within Yucca Flat except CAS 25-15-01 (Waste Dump). Corrective Action Site 25-15-01 is found in Area 25 in Jackass Flat. Of the 14 CASs in CAU 357, 11 are mud pits, suspected mud pits, or mud processing-related sites, which are by-products of drilling activities in support of the underground nuclear weapons testing done on the NTS. Of the remaining CASs, one CAS is a waste dump, one CAS contains scattered lead bricks, and one CAS has a building associated with Project 31.2. All 14 of the CASs are inactive and abandoned. Clean closure with no further action of CAU 357 will be completed if no contaminants are detected above preliminary action levels. A closure report will be prepared and submitted to the Nevada Division of Environmental Protection for review and approval upon completion of the field activities. Record of Technical Change No. 1 is dated 3/2004.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2003-06-25T23:59:59.000Z

298

The U.S. Nuclear Waste Technical Review Board evaluates the technical and scientific validity of ac-  

E-Print Network [OSTI]

and scientific validity of ac- tivities undertaken by the Secretary of Energy to characterize Yucca Mountain) and spent nuclear fuel (SNF). The U.S. Department of Energy (DOE) began studying Yucca Mountain features of Yucca Moun- tain led to its selection as a potential repository site: · Yucca Mountain now

299

Clean energy from municipal solid waste. ERIP technical progress report {number_sign}6  

SciTech Connect (OSTI)

The ground carbonized RDF slurry from the grinding trials at IKA Works at approximately 50 wt.% solids was sealed in drums and shipped to the Energy and Environmental Research Corporation (EER) for the dioxin/furan and trace heavy metal combustion tests. In addition, a fuel characterization and trace component analysis was completed for this final carbonized RDF slurry fuel. This final fuel was a blend of several fuels from the pilot scale slurry carbonization experiments. As can be seen from the data, the final carbonized RDF has an exceptional heating value and volatile matter content. In addition, trace components are significantly lower than the raw RDF pellets. The report summarizes results from combustion tests and air pollution monitoring of these tests. For the upcoming time period 10/96--01/97, it is anticipated that the analysis of the dioxin/furan and trace heavy metal combustion test will be completed. This analysis includes rheology and particle size distribution analysis of the carbonized RDF slurry fuel, carbon content and TCLP of the combustion ash, trace heavy metal balances around combustor, and dioxin/furan emissions. Finally, the slurry carbonization computer model and computer simulations will be completed in the next reporting period (including the waste water treatment subsystem). Based upon this computer model, initial economic estimates and optimizations of the slurry carbonization process will be completed in the next reporting period.

NONE

1996-10-08T23:59:59.000Z

300

A Technical Review of Penning Trap based Investigations in Neutron Decay  

E-Print Network [OSTI]

This review is concerned with a detailed analysis of some of the technical problems which arise in the application of the Penning trap method to the experimental study of neutron $\\beta $ -decay,a technique which was first successfully tested on the low-flux swimming-pool reactor LIDO (capture flux =3$\\cdot 10^6$cm$^(-2)$s$^(-1)$) at AERE Harwell in the 1970's. It does not discuss the scientific merits or demerits of these studies. Of particular importance are the trapping and release of neutron decay protons, and the influence of magnetic mirror effects and radial drifting on the trapped particles. Since these have energies < 1 keV they must be accelerated to energies of order 20-30 keV following release, at which point they are recorded in a silicon surface barrier detector. However serious difficulties were encountered in the post-release acceleration process with vacuum breakdown in the presence of crossed electric and magnetic fields.

Byrne, J

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste technical review" 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

A Technical Review of Penning Trap based Investigations in Neutron Decay  

E-Print Network [OSTI]

This review is concerned with a detailed analysis of some of the technical problems which arise in the application of the Penning trap method to the experimental study of neutron $\\beta $ -decay,a technique which was first successfully tested on the low-flux swimming-pool reactor LIDO (capture flux =3$\\cdot 10^6$cm$^(-2)$s$^(-1)$) at AERE Harwell in the 1970's. It does not discuss the scientific merits or demerits of these studies. Of particular importance are the trapping and release of neutron decay protons, and the influence of magnetic mirror effects and radial drifting on the trapped particles. Since these have energies < 1 keV they must be accelerated to energies of order 20-30 keV following release, at which point they are recorded in a silicon surface barrier detector. However serious difficulties were encountered in the post-release acceleration process with vacuum breakdown in the presence of crossed electric and magnetic fields.

J. Byrne

2014-07-11T23:59:59.000Z

302

Effect of glass composition on waste form durability: A critical review  

SciTech Connect (OSTI)

This report reviews literature concerning the relationship between the composition and durability of silicate glasses, particularly glasses proposed for immobilization of radioactive waste. Standard procedures used to perform durability tests are reviewed. It is shown that tests in which a low-surface area sample is brought into contact with a very large volume of solution provide the most accurate measure of the intrinsic durability of a glass composition, whereas high-surface area/low-solution volume tests are a better measure of the response of a glass to changes in solution chemistry induced by a buildup of glass corrosion products. The structural chemistry of silicate and borosilicate glasses is reviewed to identify those components with the strongest cation-anion bonds. A number of examples are discussed in which two or more cations engage in mutual bonding interactions that result in minima or maxima in the rheologic and thermodynamic properties of the glasses at or near particular optimal compositions. It is shown that in simple glass-forming systems such interactions generally enhance the durability of glasses. Moreover, it is shown that experimental results obtained for simple systems can be used to account for durability rankings of much more complex waste glass compositions. Models that purport to predict the rate of corrosion of glasses in short-term durability tests are evaluated using a database of short-term durability test results for a large set of glass compositions. The predictions of these models correlate with the measured durabilities of the glasses when considered in large groupings, but no model evaluated in this review provides accurate estimates of durability for individual glass compositions. Use of these models in long-term durability models is discussed. 230 refs.

Ellison, A.J.G.; Mazer, J.J.; Ebert, W.L. [Argonne National Lab., IL (United States). Chemical Technology Div.

1994-11-01T23:59:59.000Z

303

Clean energy from municipal solid waste. Technical progress report number 3  

SciTech Connect (OSTI)

Development of the computer models for slurry carbonization have begun and were based upon the collected data (mass balances, yield, temperatures, and pressures) from the previous pilot plant campaigns. All computer models are being developed with Aspen`s SpeedUp{trademark} software. The primary flow sheet with major alternatives has been developed and the majority of equipment descriptions and models, cost algorithms, and baseline parameters have been input to SpeedUp. The remaining modeling parameters will be input in the next reporting period and the initial flow sheet skeleton and model will be completed. The computer models will focus on optimizing capital and operating costs, and evaluating alternative waste water recycling technologies. The weaknesses of the previous pilot plant data and the data required for design of the commercial demonstration facility were identified. The identified weaknesses of the existing data included mass balance precision and accuracy, reactor residence time control (i.e. reactor level control), reactor temperature variations, and air entrainment in the feed RDF slurry. To improve mass balance precision and accuracy, an alternative carbonization gas flow meter will be designed and installed on the pilot plant. EnerTech`s carbonization gas flow meter design has been submitted to the EERC for final approval. In addition, an appropriate number of feed RDF samples will be characterized for moisture content just prior to the next pilot plant run to estimate incoming moisture variation. A pumping test also will be performed with the feed RDF slurry to determine the amount of air entrainment with the feed slurry.

Klosky, M.

1996-01-05T23:59:59.000Z

304

Technical letter report: Submerged bed scrubber sediment resuspension testing for the Hanford Waste Vitrification Plant  

SciTech Connect (OSTI)

During-vitrification operations in the Hanford Waste Vitrification Plant (HWVP), some feed components will be vented from the melter to the melter offgas cleaning equipment. The current HWVP reference process for melter off.-gas treatment includes a submerged bed scrubber (SBS) to provide the first stage of off-gas scrubbing and quenching. During most melter/off-gas test runs at Pacific Northwest Laboratory (PNL) with the Pilot Scale Ceramic Melter (PSCM) and at the West Valley Demonstration Project (WVDP), no significant quantities of sedimentation were accumulated in the SBS scrub tank. However, during test run SF-12, conducted at West Valley, approximately 6 in. of sedimentation accumulated in the scrub tank. This raised concerns that a similar accumulation could occur with the HWVP SBS, If such an accumulation rate occurred during a sustained melter run, the SBS would soon cease to function. To alleviate the potential for sedimentation buildup, the HWVP SBS design includes a sparge ring at the bottom of the scrub tank. The sparge ring will be operated intermittently to prevent buildup of solids which could interfere with circulation with the SBS Scrub tank. This report presents the results of testing conducted to evaluate the effectiveness of the HWVP sparge ring design. Section 2 contains-the conclusions and recommendations; Section 3 summarizes the objectives; Section 4 describes the equipment and materials used; Section 5 gives the experimental approach; and Section 6 discusses the results. The appendices contain procedures for sediment resuspension testing and particle size distribution data for silica and sediment.

Schmidt, A.J.; Herrington, M.G.

1996-03-01T23:59:59.000Z

305

INDEPENDENT TECHNICAL REVIEW OF THE C-400 INTERIM REMEDIAL PROJECT PHASE I RESULTS, PADUCAH, KENTUCKY  

SciTech Connect (OSTI)

The groundwater and soil in the vicinity of the C-400 Building at the Paducah Gaseous Diffusion Plant (PGDP), is contaminated with substantial quantities of industrial solvents, primarily trichoroethene (TCE). This solvent 'source' is recognized as a significant challenge and an important remediation target in the overall environmental cleanup strategy for PGDP. Thus, the cleanup of the C-400 TCE Source is a principal focus for the Department of Energy (DOE) and its contractors, and for PGDP regulators and stakeholders. Using a formal investigation, feasibility study and decision process, Electrical Resistance Heating (ERH) was selected for the treatment of the soil and groundwater in the vicinity of C-400. ERH was selected as an interim action to remove 'a significant portion of the contaminant mass of TCE at the C-400 Cleaning Building area through treatment' with the longer term goal of reducing 'the period the TCE concentration in groundwater remains above its Maximum Contaminant Level (MCL).' ERH is a thermal treatment that enhances the removal of TCE and related solvents from soil and groundwater. The heterogeneous conditions at PGDP, particularly the high permeability regional gravel aquifer (RGA), are challenging to ERH. Thus, a phased approach is being followed to implement this relatively expensive and complex remediation technology. Conceptually, the phased approach encourages safety and efficiency by providing a 'lessons learned' process and allowing appropriate adjustments to be identified and implemented prior to follow-on phase(s) of treatment. More specifically, early deployment targeted portions of the challenging RGA treatment zone with relatively little contamination reducing the risk of adverse collateral impacts from underperformance in terms of heating and capture. Because of the importance and scope of the C-400 TCE source remediation activities, DOE chartered an Independent Technical Review (ITR) in 2007 to assess the C-400 ERH plans prior to deployment and a second ITR to evaluate Phase I performance in September 2010. In this report, these ITR efforts are referenced as the '2007 ITR' and the 'current ITR', respectively. The 2007 ITR document (Looney et al., 2007) provided a detailed technical evaluation that remains relevant and this report builds on that analysis. The primary objective of the current ITR is to provide an expedited assessment of the available Phase I data to assist the PGDP team as they develop the lessons learned from Phase I and prepare plans for Phase II.

Looney, B.; Rossabi, J.; Stewart,L.; Richards, W.

2010-10-29T23:59:59.000Z

306

Summary - Flowsheet for the Hanford Waste Treatment Plant  

Broader source: Energy.gov (indexed) [DOE]

Waste Treatment Plant Waste Treatment Plant ETR Report Date: March 2006 ETR-1 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Flowsheet for the Hanford Waste Treatment Plant (WTP) Why DOE-EM Did This Review The Hanford Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 53 million gallons of radioactive waste, separate it into high- and low-activity fractions, and produce canisters of high-level (HLW) glass (left) and containers of low-activity waste (LAW) glass (right). At the time of this review, the Plant was at approximately 70% design and 30% construction completion. The external review objective was to determine how well the WTP would meet its throughput capacities based on the current design,

307

Nuclear Waste Technical Review Board Strategic Plan for FY 2001-2006  

E-Print Network [OSTI]

undertaken by the Secretary of Energy, including characterizing a site at Yucca Mountain, Nevada, for its credibility of the Secretary of Energy's efforts to characterize the Yucca Mountain site for its suitability--related to the Secretary's efforts to char- acterize the Yucca Mountain site or to package and transport spent nuclear fuel

308

U.S. Nuclear Waste Technical Review Board Strategic Plan: Fiscal Years 20032008  

E-Print Network [OSTI]

of Energy (DOE) to characterize one site, at Yucca Mountain in Nevada, to determine its suitability for constructing a repository at Yucca Mountain. As a result, the DOE plans to prepare and submit an application) gaining a better understanding of the potential behavior of a Yucca Mountain repository; (b) developing

309

Review and Status of Solid Waste Management Practices in Multan, Pakistan  

E-Print Network [OSTI]

waste is also transported to landfill site near Shah Rukn-e-transportation of waste to landfill sites. For direct hauldispose off the waste at landfill site. Trolleys and dumpers

Shoaib, Muhammad; Mirza, Umar Karim; Sarwar, Muhammad Avais

2006-01-01T23:59:59.000Z

310

NOAA Technical Memorandum NMFS-SEFSC-573 A Biological Review of the Tortugas Pink Shrimp Fishery  

E-Print Network [OSTI]

Avenue U Galveston, Texas 77551 October 2008 #12;NOAA Technical Memorandum NMFS-SEFSC-573 A Biological Administration National Marine Fisheries Service Southeast Fisheries Science Center Galveston Laboratory 4700 National Technical Information Center National Marine Fisheries Service 5825 Port Royal Galveston

311

Review Reports | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Safety & Emergency Management Evaluations Safety & Emergency Management Evaluations » Review Reports Review Reports December 31, 2013 Independent Oversight Review, Pantex Plant, December 2013 Targeted Review of the Safety Significant Blast Door and Personnel Door Interlock Systems and Review of Federal Assurance Capability at the Pantex Plant December 30, 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Facility - December 2013 Review of the Fire Protection Program and Fire Protection Systems at the Transuranic Waste Processing Center December 13, 2013 Independent Oversight Review, Los Alamos National Laboratory - December 2013 Review of the Technical Area 55 Safety Class Fire Suppression System at Los Alamos National Laboratory December 13, 2013 Independent Oversight Review, Nevada National Security Site, December 2013

312

Solid Waste Management (North Carolina)  

Broader source: Energy.gov [DOE]

The Solid Waste Program regulates safe management of solid waste through guidance, technical assistance, regulations, permitting, environmental monitoring, compliance evaluation and enforcement....

313

Cesium removal from liquid acidic wastes with the primary focus on ammonium molybdophosphate as an ion exchanger: A literature review  

SciTech Connect (OSTI)

Many articles have been written concerning the selective removal of cesium from both acidic and alkaline defense wastes. The majority of the work performed for cesium removal from defense wastes involves alkaline feed solutions. Several different techniques for cesium removal from acidic solutions have been evaluated such as precipitation, solvent extraction, and ion exchange. The purpose of this paper is to briefly review various techniques for cesium removal from acidic solutions. The main focus of the review will be on ion exchange techniques, particularly those involving ammonium molybdophosphate as the exchanger. The pertinent literature sources are condensed into a single document for quick reference. The information contained in this document was used as an aid in determining techniques to evaluate cesium removal from the acidic Idaho Chemical Processing Plant waste matrices. 47 refs., 2 tabs.

Miller, C.J.

1995-03-01T23:59:59.000Z

314

Review of Catalytic Hydrogen Generation in the Defense Waste Processing Facility (DWPF) Chemical Processing Cell  

SciTech Connect (OSTI)

This report was prepared to fulfill the Phase I deliverable for HLW/DWPF/TTR-98-0018, Rev. 2, ''Hydrogen Generation in the DWPF Chemical Processing Cell'', 6/4/2001. The primary objective for the preliminary phase of the hydrogen generation study was to complete a review of past data on hydrogen generation and to prepare a summary of the findings. The understanding was that the focus should be on catalytic hydrogen generation, not on hydrogen generation by radiolysis. The secondary objective was to develop scope for follow-up experimental and analytical work. The majority of this report provides a summary of past hydrogen generation work with radioactive and simulated Savannah River Site (SRS) waste sludges. The report also includes some work done with Hanford waste sludges and simulants. The review extends to idealized systems containing no sludge, such as solutions of sodium formate and formic acid doped with a noble metal catalyst. This includes general information from the literature, as well as the focused study done by the University of Georgia for the SRS. The various studies had a number of points of universal agreement. For example, noble metals, such as Pd, Rh, and Ru, catalyze hydrogen generation from formic acid and formate ions, and more acid leads to more hydrogen generation. There were also some points of disagreement between different sources on a few topics such as the impact of mercury on the noble metal catalysts and the identity of the most active catalyst species. Finally, there were some issues of potential interest to SRS that apparently have not been systematically studied, e.g. the role of nitrite ion in catalyst activation and reactivity. The review includes studies covering the period from about 1924-2002, or from before the discovery of hydrogen generation during simulant sludge processing in 1988 through the Shielded Cells qualification testing for Sludge Batch 2. The review of prior studies is followed by a discussion of proposed experimental work, additional data analysis, and future modeling programs. These proposals have led to recent investigations into the mercury issue and the effect of co-precipitating noble metals which will be documented in two separate reports. SRS hydrogen generation work since 2002 will also be collected and summarized in a future report on the effect of noble metal-sludge matrix interactions on hydrogen generation. Other potential factors for experimental investigation include sludge composition variations related to both the washing process and to the insoluble species with particular attention given to the role of silver and to improving the understanding of the interaction of nitrite ion with the noble metals.

Koopman, D. C.

2004-12-31T23:59:59.000Z

315

Proceedings of the technical review on advances in geothermal reservoir technology---Research in progress  

SciTech Connect (OSTI)

This proceedings contains 20 technical papers and abstracts describing most of the research activities funded by the Department of Energy (DOE's) Geothermal Reservoir Technology Program, which is under the management of Marshall Reed. The meeting was organized in response to several requests made by geothermal industry representatives who wanted to learn more about technical details of the projects supported by the DOE program. Also, this gives them an opportunity to personally discuss research topics with colleagues in the national laboratories and universities.

Lippmann, M.J. (ed.)

1988-09-01T23:59:59.000Z

316

An integrated analytical framework for quantifying the LCOE of waste-to-energy facilities for a range of greenhouse gas emissions policy and technical factors  

SciTech Connect (OSTI)

This study presents a novel integrated method for considering the economics of waste-to-energy (WTE) facilities with priced greenhouse gas (GHG) emissions based upon technical and economic characteristics of the WTE facility, MSW stream, landfill alternative, and GHG emissions policy. The study demonstrates use of the formulation for six different policy scenarios and explores sensitivity of the results to ranges of certain technical parameters as found in existing literature. The study shows that details of the GHG emissions regulations have large impact on the levelized cost of energy (LCOE) of WTE and that GHG regulations can either increase or decrease the LCOE of WTE depending on policy choices regarding biogenic fractions from combusted waste and emissions from landfills. Important policy considerations are the fraction of the carbon emissions that are priced (i.e. all emissions versus only non-biogenic emissions), whether emissions credits are allowed due to reducing fugitive landfill gas emissions, whether biogenic carbon sequestration in landfills is credited against landfill emissions, and the effectiveness of the landfill gas recovery system where waste would otherwise have been buried. The default landfill gas recovery system effectiveness assumed by much of the industry yields GHG offsets that are very close to the direct non-biogenic GHG emissions from a WTE facility, meaning that small changes in the recovery effectiveness cause relatively larger changes in the emissions factor of the WTE facility. Finally, the economics of WTE are dependent on the MSW stream composition, with paper and wood being advantageous, metal and glass being disadvantageous, and plastics, food, and yard waste being either advantageous or disadvantageous depending upon the avoided tipping fee and the GHG emissions price.

Townsend, Aaron K., E-mail: aarontownsend@utexas.edu [Department of Mechanical Engineering, University of Texas at Austin, 1 University Station C2200, Austin, TX 78712 (United States); Webber, Michael E. [Department of Mechanical Engineering, University of Texas at Austin, 1 University Station C2200, Austin, TX 78712 (United States)

2012-07-15T23:59:59.000Z

317

Possible Applications of the Mssbauer Technique in Waste Management Studies  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

S. L. Ruby

318

Basic Research for Evaluating Nuclear Waste Form Performance  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Don J. Bradley

319

Rock Alteration and Mineral Transformations for Nuclear Waste Management  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Philip A. Helmke

320

Application of Field-Flow Fractionation to Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Marcus N. Myers; Kathy A. Graff; J. Calvin Giddings

Note: This page contains sample records for the topic "waste technical review" 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

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

322

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

Broader source: Energy.gov (indexed) [DOE]

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

323

Radioactive waste isolation in salt: Peer review of the Office of Nuclear Waste Isolation's draft report on an issues hierarchy and data needs for site characterization  

SciTech Connect (OSTI)

At the request of the Salt Repository Project (SRPO), Argonne National Laboratory conducted an independent peer review of a report by the Battelle Office of Nuclear Waste Isolation entitled ''Salt Repository Project Issues Hierarchy and Data Needs for Site Characterization (Draft).'' This report provided a logical structure for evaluating the outstanding questions (issues) related to selection and licensing of a site as a high-level waste repository. It also provided a first estimate of the information and data necessary to answer or resolve those questions. As such, this report is the first step in developing a strategy for site characterization. Microfiche copies of ''Draft Issues Hierarchy, Resolution Strategy, and Information Needs for Site Characterization and Environmental/Socioeconomic Evaluation - July, 1986'' and ''Issues Hierarchy and Data Needs for Site Characterization - February, 1985'' are included in the back pocket of this report.

Harrison, W.; Fenster, D.F.; Ditmars, J.D.; Paddock, R.A.; Rote, D.M.; Hambley, D.F.; Seitz, M.G.; Hull, A.B.

1986-12-01T23:59:59.000Z

324

A Comparative Review of Hydrologic Issues Involved in Geologic Storage of CO2 and Injection Disposal of Liquid Waste  

SciTech Connect (OSTI)

The paper presents a comparison of hydrologic issues and technical approaches used in deep-well injection and disposal of liquid wastes, and those issues and approaches associated with injection and storage of CO{sub 2} in deep brine formations. These comparisons have been discussed in nine areas: (1) Injection well integrity; (2) Abandoned well problems; (3) Buoyancy effects; (4) Multiphase flow effects; (5) Heterogeneity and flow channeling; (6) Multilayer isolation effects; (7) Caprock effectiveness and hydrogeomechanics; (8) Site characterization and monitoring; and (9) Effects of CO{sub 2} storage on groundwater resources There are considerable similarities, as well as significant differences. Scientifically and technically, these two fields can learn much from each other. The discussions presented in this paper should help to focus on the key scientific issues facing deep injection of fluids. A substantial but by no means exhaustive reference list has been provided for further studies into the subject.

Tsang, C.-F.; Birkholzer, J.; Rutqvist, J.

2008-04-15T23:59:59.000Z

325

Agenda for the Derived Liquids to Hydrogen Distributed Reforming Working Group (BILIWG) Hydrogen Production Technical Team Research Review  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

& Hydrogen Production Technical Team Research Review Agenda for Tuesday, November 6, 2007 Location: BCS Incorporated, 8929 Stephens Road, Laurel, MD. 20723 410-997-7778 8:30 - 9:00 Continental Breakfast 9:00 DOE Targets, Tools and Technology o Bio-Derived Liquids to Hydrogen Distributed Reforming Targets DOE, Arlene Anderson o H2A Overview, NREL, Darlene Steward o Bio-Derived Liquids to Hydrogen Distributed Reforming Cost Analysis DTI, Brian James 10:00 Research Review o Low-Cost Hydrogen Distributed Production Systems, H2Gen, Sandy Thomas o Integrated Short Contact Time Hydrogen Generator, GE Global Research, Wei Wei o Distributed Bio-Oil Reforming, NREL, Darlene Steward o High Pressure Steam Ethanol Reforming, ANL, Romesh Kumar

326

Technical Fixes Under Surveillance CCS and Lessons Learned from the Governance of Long-Term Radioactive Waste Management  

Science Journals Connector (OSTI)

Carbon dioxide (CO2) capture and storage (CCS) is a technical option for...2...concentrations in the Earths atmosphere while still using carbon-intensive technologies in power production and other industries. It...

Thomas Fleler

2012-01-01T23:59:59.000Z

327

Field study of disposed solid wastes from advanced coal processes. Annual technical progress report, October 1987--August 1988  

SciTech Connect (OSTI)

Radian Corporation and the North Dakota Mining and Mineral Resources Research Institute (MMRRI) are funded to develop information to be used by private industry and government agencies for managing solid waste produced by advanced coal processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. The first two tasks of this project involve the development of test plans. Through July of 1988 we have developed a generic test design manual, detailed test procedures manual, and test plans for three sites. Task three, field studies, will be initiated as soon as final site access is obtained and the facilities producing the waste are fully operational.

NONE

1988-08-01T23:59:59.000Z

328

Tank farm nuclear criticality review  

SciTech Connect (OSTI)

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

Bratzel, D.R., Westinghouse Hanford

1996-09-11T23:59:59.000Z

329

Summary - Salt Waste Processing Facility Design at the Savannah River Site  

Broader source: Energy.gov (indexed) [DOE]

Salt Waste Processing Facility Salt Waste Processing Facility ETR Report Date: November 2006 ETR-4 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Salt Waste Processing Facility Design at the Savannah River Site (SRS) Why DOE-EM Did This Review The Salt Waste Processing Facility (SWPF) is intended to remove and concentrate the radioactive strontium (Sr), actinides, and cesium (Cs) from the bulk salt waste solutions in the SRS high-level waste tanks. The sludge and strip effluent from the SWPF that contain concentrated Sr, actinide, and Cs wastes will be sent to the SRS Defense Waste Processing Facility (DWPF), where they will be vitrified. The decontaminated salt solution (DSS) that is left after removal of the highly

330

Waste acceptance criteria for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

NONE

1996-04-01T23:59:59.000Z

331

Field study of disposed solid wastes from advanced coal processes. Annual technical progress report, October 1991--September 1992  

SciTech Connect (OSTI)

Radian Corporation and the North Dakota Energy and Environmental Research Center (EERC) are funded to develop information to be used by private industry and government agencies for managing solid wastes produced by advanced coal combustion processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. Three sites were selected for the field studies: Colorado Ute`s fluidized bed combustion (FBC) unit in Nucla, Colorado; Ohio Edison`s limestone injection multistage burner (LIMB) retrofit in Lorain, Ohio; and Freeman United`s mine site in central Illinois with wastes supplied by the nearby Midwest Grain FBC unit. During the past year, field monitoring and sampling of the four landfill test cases constructed in 1989 and 1991 has continued. Option 1 of the contract was approved last year to add financing for the fifth test case at the Freeman United site. The construction of the Test Case 5 cells is scheduled to begin in November, 1992. Work during this past year has focused on obtaining data on the physical and chemical properties of the landfilled wastes, and on developing a conceptual framework for interpreting this information. Results to date indicate that hydration reactions within the landfilled wastes have had a major impact on the physical and chemical properties of the materials but these reactions largely ceased after the first year, and physical properties have changed little since then. Conditions in Colorado remained dry and no porewater samples were collected. In Ohio, hydration reactions and increases in the moisture content of the waste tied up much of the water initially infiltrating the test cells.

Not Available

1992-12-31T23:59:59.000Z

332

A literature review of methods of analysis of organic analytes in radioactive wastes with an emphasis on sources from the United Kingdom  

SciTech Connect (OSTI)

This report, compiled by Pacific Northwest Laboratory (PNL), examines literature originating through the United Kingdom (UK) nuclear industry relating to the analyses of organic constituents of radioactive waste. Additionally, secondary references from the UK and other counties, including the United States, have been reviewed. The purpose of this literature review was to find analytical methods that would apply to the mixed-waste matrices found at Hanford.

Clauss, S.A.; Bean, R.M.

1993-09-01T23:59:59.000Z

333

Evaluation of AFBC co-firing of coal and hospital wastes. Technical report, January 1989--August 1990  

SciTech Connect (OSTI)

The purpose of this program is to expand the use of coal by utilizing CFB (circulating fluidized bed) technology to provide an environmentally safe method for disposing of waste materials. Hospitals are currently experiencing a waste management crisis. In many instances, they are no longer permitted to burn pathological and infectious wastes in incinerators. Older hospital incinerators are not capable of maintaining the stable temperatures and residence times necessary in order to completely destroy toxic substances before release into the atmosphere. In addition, the number of available landfills which can safely handle these substances is decreasing each year. The purpose of this project is to conduct necessary research investigating whether the combustion of the hospital wastes in a coal-fired circulating fluidized bed boiler will effectively destroy dioxins and other hazardous substances before release into the atmosphere. If this is proven feasible, in light of the quantity of hospital wastes generated each year, it would create a new market for coal -- possibly 50 million tons/year.

Not Available

1991-02-01T23:59:59.000Z

334

Voluntary Protection Program Onsite Review, Advanced Mixed Waste Treatment Project- May 2009  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Advanced Mixed Waste Treatment Project is continuing to perform at a level deserving DOE-VPP Star recognition.

335

Voluntary Protection Program Onsite Review, Waste Isolation Pilot Plant- March 2010  

Broader source: Energy.gov [DOE]

Evaluation to determine whether the Waste Isolation Pilot Plant is continuing to perform at a level deserving DOE-VPP Star recognition.

336

Voluntary Protection Program Onsite Review, Waste Isolation Pilot Plant- February 2009  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Waste Isolation Pilot Plant is continuing to perform at a level deserving DOE-VPP Star recognition.

337

Voluntary Protection Program Onsite Review, Waste Treatment Plant Hanford Site- June 2010  

Broader source: Energy.gov [DOE]

Evaluation to determine whether the Waste Treatment Plant Hanford Site is continuing to perform at a level deserving DOE-VPP Star recognition.

338

Voluntary Protection Program Onsite Review, Waste Treatment Plant Construction Project- June 2010  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Waste Treatment Plant Construction Project is continuing to perform at a level deserving DOE-VPP Star recognition.

339

Voluntary Protection Program Onsite Review, Bechtel National Inc., Waste Treatment Plant Construction Site November 2013  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Bechtel National Inc., Waste Treatment Plant Construction Site is performing at a level deserving DOE-VPP Star recognition.

340

Voluntary Protection Program Onsite Review, Transuranic Waste Processing Center- September 2012  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Transuranic Waste Processing Center is continuing to perform at a level deserving DOE-VPP Star recognition.

Note: This page contains sample records for the topic "waste technical review" 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

Voluntary Protection Program Onsite Review, Waste Sampling and Characterization Facility- May 2007  

Broader source: Energy.gov [DOE]

Evaluation of Waste Sampling and Characterization Facility to make the final decision regarding the companys continued participation in DOE-VPP as a Star site.

342

Voluntary Protection Program Onsite Review, Salt Waste Processing Facility Construction Project- February 2013  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Salt Waste Processing Facility Construction Project is continuing to perform at a level deserving DOE-VPP Star recognition.

343

Project Impact Assessments: Building America FY14 Field Test Technical Support- 2014 BTO Peer Review  

Broader source: Energy.gov [DOE]

Presenter: Lieko Earle, National Renewable Energy Laboratory The goal of this project is for the National Renewable Energy Laboratory to provide extensive, hands-on technical support to Building America teams in the areas of experiment design, provision of research-grade measurement hardware, energy modeling, and analysis. Building Americas field testsregularly conducted by both Building America teams and national laboratoriesdemonstrate the programs best house system innovations. The tests enable cost-effective evaluation of real-world performance and help ensure that all Building America field tests result in high-impact findings that push builders and homeowners to higher levels of savings.

344

System Planning for Low-Activity Waste at Hanford  

Broader source: Energy.gov (indexed) [DOE]

Technical Review of System Planning Technical Review of System Planning for Low-Activity Waste Treatment at Hanford November 2008 Dr. David S. Kosson, Vanderbilt University Dr. David R. Gallay, Logistics Management Institute Dr. Ian L. Pegg, The Catholic University of America Dr. Ray G. Wymer, Oak Ridge National Laboratory (ret.) Dr. Steven Krahn, U. S. Department of Energy ii ACKNOWLEDGEMENT The Review Team thanks Mr. Ben Harp, Office of River Protection (ORP), and Mr. James Honeyman, CH2M HILL, for their exceptional support during this review. Mr. Harp was the lead Department of Energy (DOE) representative responsible for organizing reviews held on-site by the Review Team. Mr. Honeyman, and his staff, provided responsive support through technical presentations, telephone conferences, and numerous reference documents.

345

1…10 kW Stationary Combined Heat and Power Systems Status and Technical Potential: Independent Review  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

1-10 kW Stationary Combined Heat 1-10 kW Stationary Combined Heat and Power Systems Status and Technical Potential National Renewable Energy Laboratory 1617 Cole Boulevard * Golden, Colorado 80401 303-275-3000 * www.nrel.gov NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency and Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. Contract No. DE-AC36-08GO28308 Independent Review Published for the U.S. Department of Energy Hydrogen and Fuel Cells Program NREL/BK-6A10-48265 November 2010 NOTICE This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or

346

Quantification of greenhouse gas emissions from waste management processes for municipalities - A comparative review focusing on Africa  

SciTech Connect (OSTI)

The amount of greenhouse gases (GHG) emitted due to waste management in the cities of developing countries is predicted to rise considerably in the near future; however, these countries have a series of problems in accounting and reporting these gases. Some of these problems are related to the status quo of waste management in the developing world and some to the lack of a coherent framework for accounting and reporting of greenhouse gases from waste at municipal level. This review summarizes and compares GHG emissions from individual waste management processes which make up a municipal waste management system, with an emphasis on developing countries and, in particular, Africa. It should be seen as a first step towards developing a more holistic GHG accounting model for municipalities. The comparison between these emissions from developed and developing countries at process level, reveals that there is agreement on the magnitude of the emissions expected from each process (generation of waste, collection and transport, disposal and recycling). The highest GHG savings are achieved through recycling, and these savings would be even higher in developing countries which rely on coal for energy production (e.g. South Africa, India and China) and where non-motorized collection and transport is used. The highest emissions are due to the methane released by dumpsites and landfills, and these emissions are predicted to increase significantly, unless more of the methane is captured and either flared or used for energy generation. The clean development mechanism (CDM) projects implemented in the developing world have made some progress in this field; however, African countries lag behind.

Friedrich, Elena, E-mail: Friedriche@ukzn.ac.za [CRECHE Centre for Research in Environmental, Coastal and Hydrological Engineering, School of Civil Engineering, Surveying and Construction, University of KwaZulu-Natal, Howard College Campus, Durban (South Africa); Trois, Cristina [CRECHE Centre for Research in Environmental, Coastal and Hydrological Engineering, School of Civil Engineering, Surveying and Construction, University of KwaZulu-Natal, Howard College Campus, Durban (South Africa)

2011-07-15T23:59:59.000Z

347

Natural glass analogues to alteration of nuclear waste glass: A review and recommendations for further study  

SciTech Connect (OSTI)

The purpose of this report is to review previous work on the weathering of natural glasses; and to make recommendations for further work with respect to studying the alteration of natural glasses as it relates quantifying rates of dissolution. the first task was greatly simplified by the published papers of Jercinovic and Ewing (1987) and Byers, Jercinovic, and Ewing (1987). The second task is obviously the more difficult of the two and the author makes no claim of completeness in this regard. Glasses weather in the natural environment by reacting with aqueous solutions producing a rind of secondary solid phases. It had been proposed by some workers that the thickness of this rind is a function of the age of the glass and thus could be used to estimate glass dissolution rates. However, Jercinovic and Ewing (1987) point out that in general the rind thickness does not correlate with the age of the glass owing to the differences in time of contact with the solution compared to the actual age of the sample. It should be noted that the rate of glass dissolution is also a function of the composition of both the glass and the solution, and the temperature. Quantification of the effects of these parameters (as well as time of contact with the aqueous phase and flow rates) would thus permit a prediction of the consequences of glass-fluid interactions under varying environmental conditions. Defense high- level nuclear waste (DHLW), consisting primarily of liquid and sludge, will be encapsulated by and dispersed in a borosilicate glass before permanent storage in a HLW repository. This glass containing the DHLW serves to dilute the radionuclides and to retard their dispersion into the environment. 318 refs.

McKenzie, W.F.

1990-01-01T23:59:59.000Z

348

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, August 2012  

Broader source: Energy.gov (indexed) [DOE]

Waste Treatment and Waste Treatment and Immobilization Plant Construction Quality May 2011 August 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 .................................................................................................................................................... 1

349

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, August 2012  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Hanford Site Waste Treatment and Hanford Site Waste Treatment and Immobilization Plant Construction Quality May 2011 August 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 .................................................................................................................................................... 1

350

Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality, November 2011  

Broader source: Energy.gov (indexed) [DOE]

Hanford Site Waste Treatment and Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality May 2011 November 2011 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope .................................................................................................................................................... 1

351

Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality, November 2011  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Hanford Site Waste Treatment and Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality May 2011 November 2011 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope .................................................................................................................................................... 1

352

New Review of Nuclear Waste Disposal Calls for Early Test in New Mexico  

Science Journals Connector (OSTI)

...WIPP spent fuel disposal demonstration...licensing and site selection could...date. Waste disposal will not be inexpen-sive...such as those at Maxey Flats, Kentucky...long-term waste disposal facili-ties...formation at the WIPP site. Satisfying...

WILLIAM D. METZ

1978-03-31T23:59:59.000Z

353

Office of Civilian Radioactive Waste Management | Department...  

Office of Environmental Management (EM)

Civilian Radioactive Waste Management February 2006 Evaluation of technical impact on the Yucca Mountain Project technical basis resulting from issues raised by emails of former...

354

Waste Management | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

August 2, 2012 August 2, 2012 Energy Department Announces New Technical Review to Assess Black Cells at Hanford's Waste Treatment Plant Secretary of Energy Steven Chu has assembled a group of independent technical experts to assess the Hanford Site's Waste Treatment Plant, specifically as it relates to the facility's "black cells." July 9, 2012 Spencer Isom, second year engineering intern for Savannah River Remediation (SRR) and fourth summer at Savannah River Site (SRS), performs a standard equipment check at Saltstone Production Facility. | Photo courtesy of Savannah River Site Savannah River Remediation Intern Sees Nuclear Industry as Job Opportunity College intern Spencer Isom recently began her second summer with Savannah River Remediation (SRR), and her fourth year at Savannah River Site (SRS),

355

A Database for Reviewing and Selecting Radioactive Waste Treatment Technologies and Vendors  

SciTech Connect (OSTI)

Several attempts have been made in past years to collate and present waste management technologies and solutions to waste generators. These efforts have been manifested as reports, buyers' guides, and databases. While this information is helpful at the time it is assembled, the principal weakness is maintaining the timeliness and accuracy of the information over time. In many cases, updates have to be published or developed as soon as the product is disseminated. The recently developed National Low-Level Waste Management Program's Technologies Database is a vendor-updated Internet based database designed to overcome this problem. The National Low-Level Waste Management Program's Technologies Database contains information about waste types, treatment technologies, and vendor information. Information is presented about waste types, typical treatments, and the vendors who provide those treatment methods. The vendors who provide services update their own contact information, their treatment processes, and the types of wastes for which their treatment process is applicable. This information is queriable by a generator of low-level or mixed low-level radioactive waste who is seeking information on waste treatment methods and the vendors who provide them. Timeliness of the information in the database is assured using time clocks and automated messaging to remind featured vendors to keep their information current. Failure to keep the entries current results in a vendor being warned and then ultimately dropped from the database. This assures that the user is dealing with the most current information available and the vendors who are active in reaching and serving their market.

P. C. Marushia; W. E. Schwinkendorf

1999-07-01T23:59:59.000Z

356

A Database for Reviewing and Selecting Radioactive Waste Treatment Technologies and Vendors  

SciTech Connect (OSTI)

Several attempts have been made in past years to collate and present waste management technologies and solutions to waste generators. These efforts have been manifested as reports, buyers guides, and databases. While this information is helpful at the time it is assembled, their principal weakness is maintaining the timeliness and accuracy of the information over time. In many cases, updates have to be published or developed as soon as the product is disseminated. The recently developed National Low-Level Waste Management Programs Technologies Database is a vendor-updated Internet based database designed to overcome this problem. The National Low-Level Waste Management Programs Technologies Database contains information about waste types, treatment technologies, and vendor information. Information is presented about waste types, typical treatments, and the vendors who provide those treatment methods. The vendors who provide services update their own contact information, their treatment processes, and the types of wastes for which their treatment process is applicable. This information is queriable by a generator of low-level or mixed low-level radioactive waste who is seeking information on waste treatment methods and the vendors who provide them. Timeliness of the information in the database is assured using time clocks and automated messaging to remind featured vendors to keep their information current. Failure to keep the entries current results in a vendor being warned and then ultimately dropped from the database. This assures that the user is dealing with the most current information available and the vendors who are active in reaching and serving their market.

Schwinkendorf, William Erich; Marushia, Patrick Charles

1999-07-01T23:59:59.000Z

357

CERTS 2012 Program Review - NASPI Leadership and Task Team Technical Support - Joe Gracia, ORNL  

Broader source: Energy.gov (indexed) [DOE]

ORNL's Support of NASPI ORNL's Support of NASPI Presented at: DOE OE Transmission Reliability Program Review ORNL Team: Jose R. Gracia, P.E. (Presenter) D. Tom Rizy Isabelle Snyder, Ph.D. 12 June 2012 2 Managed by UT-Battelle for the U.S. Department of Energy OE Transmission Reliability Program Review NASPI Goal: To improve the reliable operation of the North American power system by successfully transitioning synchrophasor technologies from research to industry adoption. 2 Project Objective(s) ORNL's activities in support of NASPI include: * Participate in NASPI Leadership Team * Support Operations Implementation Task Team * Participate in Performance and Standards Task Team * Develop needed metrology capabilities in partnership with NIST.

358

Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project, August 2011  

Broader source: Energy.gov (indexed) [DOE]

Review of Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project May 2011 August 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Scope ...................................................................................................................................................... 1 3.0 Background ............................................................................................................................................ 2

359

Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project, July 2011  

Broader source: Energy.gov (indexed) [DOE]

Independent Review of Independent Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project July 2011 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 Scope .........................................................................................................................................1 3.0 Background ...............................................................................................................................2

360

Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project, August 2011  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Review of Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project May 2011 August 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Scope ...................................................................................................................................................... 1 3.0 Background ............................................................................................................................................ 2

Note: This page contains sample records for the topic "waste technical review" 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

Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project, July 2011  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Independent Review of Independent Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project July 2011 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 Scope .........................................................................................................................................1 3.0 Background ...............................................................................................................................2

362

Field study of disposed wastes from advanced coal processes. Quarterly technical progress report, November 1991--January 1992  

SciTech Connect (OSTI)

The objective of this research is to develop information to be used by private industry and government agencies for planning waste disposal practices associated with advanced coal processes. To accomplish this objective, DOE has contracted Radian Corporation and the North Dakota Energy & Environmental Research Center (EERC) to design, construct, and monitor a limited number of field disposal tests with advanced coal process wastes. These field tests will be monitored over a three year period with the emphasis on collecting data on the field disposal of these wastes. Accomplishments for this past quarter are as follows: The 9th quarterly measurements at the Colorado site took place in December, 1991. Permeability and neutron absorption moisture content measurements were made and on site data was collected from the data logger; The 9th quarterly sampling at the Ohio site took place in November 1991. Permeability and moisture content measurements were made, and water samples were collected from the wells and lysimeters; The second quarterly core and water samples from the first Illinois test case were collected in mid November, and field data were collected from the data logger; Chemical analysis of all core and water samples continued; all chemical analyses except for some tests on Illinois second quarter cores are now complete.

Not Available

1992-08-01T23:59:59.000Z

363

Review of technologies for the pretreatment of retrieved single-shell tank waste at Hanford  

SciTech Connect (OSTI)

The purpose of the study reported here was to identify and evaluate innovative processes that could be used to pretreat mixed waste retrieved from the 149 single-shell tanks (SSTs) on the US Department of Energy's (DOE) Hanford site. The information was collected as part of the Single Shell Tank Waste Treatment project at Pacific Northwest Laboratory (PNL). The project is being conducted for Westinghouse Hanford Company under their SST Disposal Program.

Gerber, M.A.

1992-08-01T23:59:59.000Z

364

Review of technologies for the pretreatment of retrieved single-shell tank waste at Hanford  

SciTech Connect (OSTI)

The purpose of the study reported here was to identify and evaluate innovative processes that could be used to pretreat mixed waste retrieved from the 149 single-shell tanks (SSTs) on the US Department of Energy`s (DOE) Hanford site. The information was collected as part of the Single Shell Tank Waste Treatment project at Pacific Northwest Laboratory (PNL). The project is being conducted for Westinghouse Hanford Company under their SST Disposal Program.

Gerber, M.A.

1992-08-01T23:59:59.000Z

365

Past DOE Technical Standards Program Procedures  

Broader source: Energy.gov [DOE]

Review past procedures used to write, revise, or maintain a Department of Energy (DOE) technical standard.

366

Order Module--DOE O 435.1 RADIOACTIVE WASTE MANAGEMENT | Department of  

Broader source: Energy.gov (indexed) [DOE]

35.1 RADIOACTIVE WASTE MANAGEMENT 35.1 RADIOACTIVE WASTE MANAGEMENT Order Module--DOE O 435.1 RADIOACTIVE WASTE MANAGEMENT DOE Order 5820.2A, Radioactive Waste Management, was issued by DOE in September 1988. As early as 1990, DOE began analyzing, assessing, and reviewing the process of implementing the Order. DOE revised the Order on radioactive waste management for several reasons: - After thorough technical reviews and analyses, DOE and the Defense Nuclear Facilities Safety Board concluded that DOE Order 5820.2A did not adequately address the Department's radioactive waste management and disposal practices. -There had been significant advances in radioactive waste management practices and changes in DOE since the Order was issued in 1988. - Risk-based and performance-based requirements were determined to be

367

Report: Findings, Conclusions, and Recommendations Concerning the Waste Treatment and Immobilization Project at Hanford  

Broader source: Energy.gov (indexed) [DOE]

EMAB Tank Waste Subcommittee Summary Report 1 EMAB Tank Waste Subcommittee Summary Report 1 Report of Findings, Conclusions, and Recommendations Concerning the Waste Treatment and Immobilization Project (WTP) at Hanford Submitted by the Environmental Management Advisory Board Tank Waste Subcommittee September 15, 2010 Introduction In May 2010, the Department of Energy established the Environmental Management Tank Waste Subcommittee (EM-TWS). The EM-TWS was charged with conducting an independent technical review of liquid waste capital and operations projects related to the Office of Environmental Management (EM) tank waste cleanup programs at Hanford, Washington; the Savannah River Site in South Carolina; the Idaho National Laboratory; and the West Valley Demonstration Project in New York. The EM-TWS's review focused on the facilities being

368

Order Module--DOE O 435.1 RADIOACTIVE WASTE MANAGEMENT | Department of  

Broader source: Energy.gov (indexed) [DOE]

O 435.1 RADIOACTIVE WASTE MANAGEMENT O 435.1 RADIOACTIVE WASTE MANAGEMENT Order Module--DOE O 435.1 RADIOACTIVE WASTE MANAGEMENT DOE Order 5820.2A, Radioactive Waste Management, was issued by DOE in September 1988. As early as 1990, DOE began analyzing, assessing, and reviewing the process of implementing the Order. DOE revised the Order on radioactive waste management for several reasons: - After thorough technical reviews and analyses, DOE and the Defense Nuclear Facilities Safety Board concluded that DOE Order 5820.2A did not adequately address the Department's radioactive waste management and disposal practices. -There had been significant advances in radioactive waste management practices and changes in DOE since the Order was issued in 1988. - Risk-based and performance-based requirements were determined to be

369

Summary - Environmental Management Waste Management Facility (EMWMF) at Oak Ridge, TN  

Broader source: Energy.gov (indexed) [DOE]

Oak Ridge, TN Oak Ridge, TN EM Project: EM Waste Management Facility ETR Report Date: February 2008 ETR-11 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Environmental Management Waste Management Facility (EMWMF) at Oak Ridge, TN Why DOE-EM Did This Review The Environmental Management Waste Management Facility (EMWMF) is a land disposal facility for wastes generated by environmental restoration activities being conducted at the US Department of Energy's (DOE) Oak Ridge Reservation. Low-level radioactive wastes, hazardous wastes (Subtitle C of the Resource Conservation and Recovery Act), and wastes defined by the Toxic Substances Control Act are approved for disposal in the EMWMF. All of the cells are lined with a

370

Evaluation of System Level Modeling and Simulation Tools in Support of Savannah River Site Liquid Waste Process  

Broader source: Energy.gov (indexed) [DOE]

Savannah River Site Liquid Waste Process Savannah River Site Liquid Waste Process June 2009 Monica C. Regalbuto Office of Waste Processing DOE/EM Kevin G. Brown Vanderbilt University and CRESP David W. DePaoli Oak Ridge National Laboratory Candido Pereira Argonne National Laboratory John R. Shultz Office of Waste Processing DOE/EM Sahid C. Smith Office of Waste Processing DOE/EM External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Savannah River Site Liquid Waste Process June 2009 ACKNOWLEDGEMENTS The Review Team thanks Ms. Sonitza Blanco, Team Lead Planning and Coordination Waste Disposition Project U.S. Department of Energy Savannah River Operations Office and Mr. Pete Hill, Liquid Waste Planning Manager for Washington Savannah River Company, for their

371

CERTS 2012 Program Review - NASPI Leadership and Task Team Technical Support - Jeff Dagle, PNNL  

Broader source: Energy.gov (indexed) [DOE]

PNNL Support for NASPI PNNL Support for NASPI Jeff Dagle Pacific Northwest National Lab jeff.dagle@pnnl.gov 11/12 June 2012 Washington, DC OE Transmission Reliability Program Review 2 Project Objective(s) To improve the reliable operation of the North American power system by successfully transitioning synchrophasor technologies from research to industry adoption PNNL's activities in support of NASPI include:  Facilitate leadership and planning activities for the NASPI leadership team and work group meetings  Support the NASPI website, mailing lists, and task team administrative support (e.g., conference call scheduling and facilitation) PNNL Activities in Support of NASPI in FY12 (cont.)  Special assignments

372

Summary Notes from 28 May 2008 Generic Technical Issue Discussion...  

Office of Environmental Management (EM)

1 of 8 Summary Notes from 28 May 2008 Generic Technical Issue Discussion on Estimating Waste Inventory and Waste Tank Characterization Attendees: Representatives from Department...

373

Methods of chemical analysis for organic waste constituents in radioactive materials: A literature review  

SciTech Connect (OSTI)

Most of the waste generated during the production of defense materials at Hanford is presently stored in 177 underground tanks. Because of the many waste treatment processes used at Hanford, the operations conducted to move and consolidate the waste, and the long-term storage conditions at elevated temperatures and radiolytic conditions, little is known about most of the organic constituents in the tanks. Organics are a factor in the production of hydrogen from storage tank 101-SY and represent an unresolved safety question in the case of tanks containing high organic carbon content. In preparation for activities that will lead to the characterization of organic components in Hanford waste storage tanks, a thorough search of the literature has been conducted to identify those procedures that have been found useful for identifying and quantifying organic components in radioactive matrices. The information is to be used in the planning of method development activities needed to characterize the organics in tank wastes and will prevent duplication of effort in the development of needed methods.

Clauss, S.A.; Bean, R.M.

1993-02-01T23:59:59.000Z

374

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)  

SciTech Connect (OSTI)

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

Cottrell, W.B.; Passiakos, M.

1982-06-01T23:59:59.000Z

375

SRNL PHASE 1 ASSESSMENT OF THE WTP WASTE QUALIFICATION PROGRAM  

SciTech Connect (OSTI)

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the workshop was to share lessons learned and provide a technology exchange to support development of a technically defensible waste qualification program. The objective of this report is to provide a review, from SRNL's perspective, of the WTP waste qualification program as presented during the workshop. In addition to SRNL's perspective on the general approach to the waste qualification program, more detailed insight into the specific unit operations presented by WTP during the workshop is provided. This report also provides a general overview of the SRS qualification program which serves as a basis for a comparison between the two programs. Recommendations regarding specific steps are made based on the review and SRNL's lessons learned from qualification of SRS low-activity waste (LAW) and high-level waste (HLW) to support maturation of the waste qualification program leading to WTP implementation.

Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

2012-03-06T23:59:59.000Z

376

UC Santa Cruz Review / Fall 2005 17 er plants by converting waste  

E-Print Network [OSTI]

, there are some major technical hurdles to overcome, Shakouri says. An efficient thermoelectric material requires Seebeck coefficient (the measure of voltage created by temperature difference within the material as a method of energy filter- ing within a semiconductor material. The basic idea is to structure the material

Zhang, Yi

377

US DRIVE Fuel Cell Technical Team Roadmap | Department of Energy  

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

Fuel Cell Technical Team Roadmap US DRIVE Fuel Cell Technical Team Roadmap The Fuel Cell Technical Team (FCTT) conducts the following activities: (1) Reviews and evaluates...

378

Production of ammonium sulfate fertilizer from FGD waste liquors. Quarterly technical report, October 1, 1994--December 31, 1994  

SciTech Connect (OSTI)

During this quarterly period, an experimental investigation was performed to study the precipitation kinetics and hydrolysis characteristics of calcium imido disulfonate crystals (CaADS). The CaADS crystals were precipitated by a metathetical reaction of lime, supplied by Dravo Lime Co., with flue gas desulfurization (FGD) scrubber waste liquor. Before approaching for the continuous Double Draw-Off (DDO) crystallization studies, the influence of a Dravo lime slurry on the precipitation characteristics of N-S compounds will be established. A series of N-S compound batch crystallization studies were completed in a wide range of pH (7.0--9.0), and the influence of pH on the amount of lime required, as well as the amount of precipitate obtained, was investigated. Although the amount of precipitate increased with increase in solution pH, the safe or optimum pH for the precipitation of CaADS lies in the vicinity of 8.2 to 8.3. For studying the crystallization characteristics of CaADS crystals, a bench scale 7.0 liter DDO crystallizer was built. DDO crystallizer is found to be superior compared to Mixed Suspension Mixed Product Removal (MSMPR) crystallizer. The precipitated crystals were analyzed for elemental composition by chemical analysis. The crystals were also examined under optical microscope for their morphological features. The present studies confirmed our prediction that N-S compounds in the waste liquor can be precipitated by a reaction with lime slurry. The precipitated crystals were mostly calcium imido disulfonate.

Randolph, A.D.; Mukhopadhyay, S.; Unrau, E.

1994-12-31T23:59:59.000Z

379

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, October 2012  

Broader source: Energy.gov (indexed) [DOE]

Site Site Waste Treatment and Immobilization Plant Construction Quality May 2011 October 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope.................................................................................................................................................... 1 4.0 Methodology ........................................................................................................................................

380

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, May 2013  

Broader source: Energy.gov (indexed) [DOE]

Hanford Site Hanford Site Waste Treatment and Immobilization Plant Construction Quality May 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................ 1 2.0 Scope................................................................................................................................................... 1 3.0 Background ......................................................................................................................................... 1 4.0 Methodology ....................................................................................................................................... 2

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


381

Independent Oversight Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, December 2013  

Broader source: Energy.gov (indexed) [DOE]

Waste Treatment and Immobilization Plant Construction Quality December 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope .................................................................................................................................................... 1 3.0 Background .......................................................................................................................................... 1

382

Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, October 2012  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Site Site Waste Treatment and Immobilization Plant Construction Quality May 2011 October 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope.................................................................................................................................................... 1 4.0 Methodology ........................................................................................................................................

383

Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality, March 2012  

Broader source: Energy.gov (indexed) [DOE]

Hanford Site Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality May 2011 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 Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope .................................................................................................................................................... 1

384

Radiological health review of the Final Environmental Impact Statement Waste Isolation Pilot Plant. Volumes 1 and 2. DOE/EIS-0026  

SciTech Connect (OSTI)

Purpose of the Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the potential radiation exposure to people from the proposed Federal radioactive Waste Isolation Pilot Plant (WIPP) near Carlsbad, in order to protect the public health and safety and ensure that there is minimal environmental degradation. Analyses are conducted of reports issued by the US DOE and its contractors, other Federal agencies and other organizations, as they relate to the potential health, safety and environmental impacts from WIPP.

Not Available

1981-01-01T23:59:59.000Z

385

Technical Review Report for the Safety Analysis Report for Packaging Model 9977 S-SARP-G-00001 Revision 2  

SciTech Connect (OSTI)

This Technical Review Report (TRR) summarizes the review findings for the Safety Analysis Report for Packaging (SARP) for the Model 9977 B(M)F-96 shipping container. The content analyzed for this submittal is Content Envelope C.1, Heat Sources, in assemblies of Radioisotope Thermoelectric Generators or food-pack cans. The SARP under review, i.e., S-SARP-G-00001, Revision 2 (August 2007), was originally referred to as the General Purpose Fissile Material Package. The review presented in this TRR was performed using the methods outlined in Revision 3 of the Department of Energy's (DOE's) Packaging Review Guide (PRG) for Reviewing Safety Analysis Reports for Packages. The format of the SARP follows that specified in Revision 2 of the Nuclear Regulatory Commission's, Regulatory Guide 7.9, i.e., Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material. Although the two documents are similar in their content, they are not identical. Formatting differences have been noted in this TRR, where appropriate. The Model 9977 Package is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. The Model 9977 Package design includes a single, 6-inch diameter, stainless steel pressure vessel containment system (i.e., the 6CV) that was designed and fabricated in accordance with Section III, Subsection NB, of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code. The earlier package designs, i.e., the Model 9965, 9966, 9967 and 9968 Packages, were originally designed and certified in the 1980s. In the 1990s, updated package designs that incorporated design features consistent with new safety requirements, based on International Atomic Energy Agency guidelines, were proposed. The updated package designs were the Model 9972, 9973, 9974 and 9975 Packages, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. Differences between the Model 9975 Package and the Model 9977 Package include: (1) The lead shield present in the Model 9975 Package is absent in the Model 9977 Package; (2) The Model 9975 Package has eight allowable contents, while the Model 9977 Package has a single allowable content. (3) The 6CV of the Model 9977 Package is similar in design to the outer Containment Vessel of the Model 9975 Package that also incorporates a 5-inch Containment Vessel as the inner Containment Vessel. (4) The Model 9975 Package uses a Celotex{reg_sign}-based impact limiter while the Model 9977 Package uses Last-A-Foam{reg_sign}, a polyurethane foam, for the impact limiter. (5) The Model 9975 Package has two Containment Vessels, while the Model 9977 Package has a single Containment Vessel.

DiSabatino, A; Hafner, R; West, M

2007-10-04T23:59:59.000Z

386

Columbia River Treaty 2014/2024 Review: Phase 1 Technical Studies  

SciTech Connect (OSTI)

Since 1964, the Columbia River Treaty has provided signi?cant bene?ts to the United States and Canada through coordinated river management by the two countries. It remains the standard against which other international water coordination agreements around the world are compared. When the Treaty was negotiated, its goals were to provide signi?cant ?ood control and power generation bene?ts to both countries. However, the Treaty contains two provisions that may signi?cantly change these bene?ts as early as the year 2024. First, in 2024 the 60 years of purchased ?ood control space in Canadian Treaty projects expires. Instead of a coordinated and managed plan to regulate both Canadian and U.S. projects for ?ood control, the Treaty calls for a shift to a Canadian operation under which the United States can call upon Canada for ?ood control assistance. The United States can request this called upon assistance as needed but only to the extent necessary to meet forecast ?ood control needs in the United States that cannot adequately be met by U.S. projects. When called upon is requested, the United States will then have to pay Canada for its operational costs and any economic losses resulting from the called upon ?ood control operation. Second, while the Treaty has no speci?ed end date, it does allow either Canada or the United States the option to terminate most of the provisions of the Treaty on or after Sept. 16, 2024, with a minimum of 10 years advance written notice. Thus, the year 2024 is the ?rst year a notice of termination would take effect assuming written notice of termination is given by the Canadian or U.S. governments by 2014. Unless the Treaty is terminated or the federal governments elect to modify the Treaty, its provisions continue inde?nitely, except for the changes in ?ood control discussed above. Given the signi?cance of both of these provisions, it is important that the parties to the Treaty understand the implications for post-2024 Treaty planning and Columbia River operations. The U.S. Army Corps of Engineers and the Bonneville Power Administration, the agencies that implement the Treaty in the United States on behalf of the U.S. Entity (see Treaty Governance sidebar), are conducting a multi-year effort to understand these implications. This effort is called the 2014/2024 Columbia River Treaty Review.

none,

2009-04-01T23:59:59.000Z

387

Waste management strategies and disposal design  

Science Journals Connector (OSTI)

A solution to the problem of long-term radioactive waste management (RWM) comprises a technical and social dimension, i. e. it must not only be technically achievable, but also publicly acceptable. The technic...

Christian Streffer; Carl Friedrich Gethmann; Georg Kamp

2012-01-01T23:59:59.000Z

388

Regeneration of FGD waste liquors: Production of ammonium and potassium sulfate mixed fertilizer. Quarterly technical report, July 1993--September 1993  

SciTech Connect (OSTI)

Regeneration of the Fe{sup II}-EDTA scrubbing liquors for simultaneous removal of SO{sub 2} and NO{sub x} in flue gas involves removing the nitrogen-sulfur (N-S) compounds accumulated in the liquor. In this paper, the authors investigated a simple regeneration process which selectively precipitates the N-S compounds as potassium salts and then hydrolyzes them to yield ammonium/potassium sulfate as a marketable byproduct. They believe this is the first report on precipitation and hydrolysis characteristics of the N-S compounds in actual waste scrubbing liquor. Precipitation of the N-S compounds was achieved by adding K{sub 2}SO{sub 4} to the scrubbing liquor. Effects of the amount of added K{sub 2}SO{sub 4} on the amount of removed N-S compounds, precipitated crystals, and the potassium left over in the scrubbing liquor were studied. Hydrolysis of the precipitated N-S compounds to ammonium sulfate was performed in a sulfuric acid environment. Effects of acidity, concentration of N-S compounds, and temperature on the hydrolysis are discussed. Analysis of the observed hydrolysis pattern showed that the reaction proceeded following first order kinetics in terms of N-S compound concentration.

Randolph, A.D.; Kwon, T.M.

1993-12-01T23:59:59.000Z

389

Production of ammonium sulfate fertilizer from FGD waste liquors. First quarterly technical report, [January--March 1995  

SciTech Connect (OSTI)

Hydrolysis of Nitrogen-Sulfur Containing Compounds (N-SCC) derived from desulfurization liquors was carried out at high temperature and pressure with varying sulfuric acid concentration in order to determine the influence of temperature and acid concentration on time required for complete hydrolysis. An ammonia specific electrode (gas sensing) was used to monitor the concentration of ammonium ion in the hydrolyzed liquor. The results indicated a large shortening of time for complete hydrolysis of the Ca salt of N-SCC but varying acid concentration did influence the rate of hydrolysis. Since the physical-chemical analysis of the N-SCC obtained by re-liming the waste scrubbing liquor (containing the Fe-EDTA complex) was found to contain a high quantity of sodium, the N-SCC is believed to be a double salt of calcium and sodium. The final product, (NH{sub 4}){sub 2}SO{sub 4}, was obtained in experimentation using an evaporative crystallizer. The clean hydrolyzed liquor was neutralized with a strong NH{sub 2} solution before the final crystallization of (NH{sub 4}){sub 2}SO{sub 4}.

Randolph, A.D.; Mukhopadhyay, S.; Unrau, E.

1995-08-01T23:59:59.000Z

390

SAM Technical Review Committee Final Report: Summary and Key Recommendations from the Onsite TRC Meeting Held April 22-23, 2013  

SciTech Connect (OSTI)

The System Advisor Model (SAM) is a broad and robust set of models and frameworks for analyzing both system performance and system financing. It does this across a range of technologies dominated by solar technologies including photovoltaics (PV) and concentrated solar power (CSP). The U.S. Department of Energy (DOE) Solar Energy Technology Program requested the SAM development team to review the photovoltaic performance modeling with the development community and specifically, with the independent engineering community. The report summarizes the major effort for this technical review committee (TRC).

Blair, N.; Dobos, S.; Janzou, S.; Gilman, P.; Freeman, J.; Kaffine, L.

2013-08-01T23:59:59.000Z

391

Total energy cycle assessment of electric and conventional vehicles: an energy and environmental analysis. Volume 4: peer review comments on technical report  

SciTech Connect (OSTI)

This report compares the energy use, oil use and emissions of electric vehicles (EVs) with those of conventional, gasoline-powered vehicles (CVs) over the total life cycle of the vehicles. The various stages included in the vehicles` life cycles include vehicle manufacture, fuel production, and vehicle operation. Disposal is not included. An inventory of the air emissions associated with each stage of the life cycle is estimated. Water pollutants and solid wastes are reported for individual processes, but no comprehensive inventory is developed. Volume IV includes copies of all the external peer review comments on the report distributed for review in July 1997.

NONE

1998-01-01T23:59:59.000Z

392

Resouce recovery option in solid-waste management: a review guide for public officials  

SciTech Connect (OSTI)

The purposes of this document are to: serve as a guide for public-works directors and others interested in implementing resource-recovery systems; and (2) provide background material that can be used in presenting information on resource-recovery systems to city managers, mayors, legislative bodies, and citizen advisory groups. It raises some issues of which local communities must be aware before developing resource-recovery systems. Additionally, the document: (1) focuses on possible institutional problems that may arise in planning waste-to-energy systems and presents some solutions and alternatives, and (2) serve public-works officials as a reference for other publications on resource-recovery systems. It will aid public-works officials in the decision-making process concerning the implementation of waste-to-energy systems. Members of the public works profession who are fully aware of all the implementation procedures involved with resource-recovery systems can best decide if this is a feasible solid-waste-management option for their community.

Nemeth, D M

1981-04-01T23:59:59.000Z

393

World first in high level waste vitrification - A review of French vitrification industrial achievements  

SciTech Connect (OSTI)

AREVA has more than 30 years experience in operating industrial HLW (High Level radioactive Waste) vitrification facilities (AVM - Marcoule Vitrification Facility, R7 and T7 facilities). This vitrification technology was based on borosilicate glasses and induction-heating. AVM was the world's first industrial HLW vitrification facility to operate in-line with a reprocessing plant. The glass formulation was adapted to commercial Light Water Reactor fission products solutions, including alkaline liquid waste concentrates as well as platinoid-rich clarification fines. The R7 and T7 facilities were designed on the basis of the industrial experience acquired in the AVM facility. The AVM vitrification process was implemented at a larger scale in order to operate the R7 and T7 facilities in-line with the UP2 and UP3 reprocessing plants. After more than 30 years of operation, outstanding record of operation has been established by the R7 and T7 facilities. The industrial startup of the CCIM (Cold Crucible Induction Melter) technology with enhanced glass formulation was possible thanks to the close cooperation between CEA and AREVA. CCIM is a water-cooled induction melter in which the glass frit and the waste are melted by direct high frequency induction. This technology allows the handling of highly corrosive solutions and high operating temperatures which permits new glass compositions and a higher glass production capacity. The CCIM technology has been implemented successfully at La Hague plant.

Brueziere, J.; Chauvin, E. [AREVA, 1 place Jean Millier, 92084 Paris La Defense (France); Piroux, J.C. [Joint Vitrification Laboratory - LCV, Marcoule, BP171, 30207 Bagnols sur Ceze (France)

2013-07-01T23:59:59.000Z

394

Summary - System Planning for Low-Activity Waste Treatment at Hanford  

Broader source: Energy.gov (indexed) [DOE]

Hanford Hanford EM Project: WTP ETR Report Date: November 2008 ETR-18 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of System Planning for Low-Activity Waste Treatment at Hanford Why DOE-EM Did This Review Construction of the facilities of the Hanford site's Waste Treatment Plant (WTP) are scheduled for completion in 2017, with radioactive waste processing scheduled to begin in 2019. An estimated 23 to 35 years will then be required to complete high-level waste (HLW) vitrification. However, vitrification of low-activity waste (LAW) may extend the WTP mission duration by decades more if supplemental LAW processing beyond the capacity of the present facility is not incorporated. The purpose of this independent review was to

395

Proceedings of the Efficient Separations and Processing Cross-Cutting Program Annual Technical Exchange Meeting  

SciTech Connect (OSTI)

This document contains summaries of technology development presented at the 1995 Efficient Separations and Processing Cross-Cutting Program (ESP) Annual Technical Exchange Meeting. The ESP is sponsored by the US Department of Energy`s Office of Environmental Management (EM), Office of Technology Development. The meeting is held annually to promote a free exchange of ideas among technology developers, potential users (for example, EM focus areas), and other interested parties within EM. During this meeting, developers of ESP-funded technologies describe the problems and needs addressed by their technologies; the technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and evolving potential applications. Presenters are asked to address the following areas: Target waste management problem, waste stream, or data need; scientific background and technical approach; technical accomplishments and resolution of technical issues; schedule and strategy for commercializing and implementing the technology or acquiring needed data; potential alternate applications of the technology or data, including outside of DOE/EM. The meeting is not a program review of the individual tasks or subtasks; but instead focuses on the technical aspects and implementation of ESP-sponsored technology or data. The meeting is also attended by members of the ESP Technical Review Team, who have the opportunity at that time to review the ESP as a whole.

NONE

1995-02-01T23:59:59.000Z

396

Technical Assistance: Increasing Code Compliance - 2014 BTO Peer...  

Broader source: Energy.gov (indexed) [DOE]

Technical Assistance: Increasing Code Compliance - 2014 BTO Peer Review Technical Assistance: Increasing Code Compliance - 2014 BTO Peer Review Presenter: Rosemarie Bartlett,...

397

Independent Oversight Review of the Technical Area 55 Safety Class Fire Suppression System at Los Alamos National Laboratory, December 2013  

Broader source: Energy.gov (indexed) [DOE]

Technical Area 55 Technical Area 55 Safety Class Fire Suppression System at Los Alamos National Laboratory December 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose .................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope ....................................................................................................................................................... 2

398

Environmental Management Waste Management Facility (EMWMF) at Oak Ridge  

Broader source: Energy.gov (indexed) [DOE]

Independent Technical Review Report: Oak Ridge Reservation Independent Technical Review Report: Oak Ridge Reservation Review of the Environmental Management Waste Management Facility (EMWMF) at Oak Ridge By Craig H. Benson, PhD, PE; William H. Albright, PhD; David P. Ray, PE; and John Smegal Sponsored by: The Office of Engineering and Technology (EM-20) 1 February 2008 (v3.0) i TABLE OF CONTENTS 1. INTRODUCTION 1 2. OBJECTIVE AND SCOPE 2 3. LINE OF INQUIRY NO. 1 2 4. LINE OF INQUIRY NO. 2 4 4.1 Compaction Testing of Soil and Debris Mixtures 5 4.2 Final Cover Settlement 6 5. LINE OF INQUIRY NO. 3 7 6. SUMMARY OF RECOMMENDATIONS 8 7. ACKNOWLEDGEMENT 10 8. REFERENCES 10 FIGURES 12 1 1. INTRODUCTION The Environmental Management Waste Management Facility (EMWMF) is a land disposal

399

Los Alamos low-level waste performance assessment status  

SciTech Connect (OSTI)

This report reviews the documented Los Alamos studies done to assess the containment of buried hazardous wastes. Five sections logically present the environmental studies, operational source terms, transport pathways, environmental dosimetry, and computer model development and use. This review gives a general picture of the Los Alamos solid waste disposal and liquid effluent sites and is intended for technical readers with waste management and environmental science backgrounds but without a detailed familiarization with Los Alamos. The review begins with a wide perspective on environmental studies at Los Alamos. Hydrology, geology, and meteorology are described for the site and region. The ongoing Laboratory-wide environmental surveillance and waste management environmental studies are presented. The next section describes the waste disposal sites and summarizes the current source terms for these sites. Hazardous chemical wastes and liquid effluents are also addressed by describing the sites and canyons that are impacted. The review then focuses on the transport pathways addressed mainly in reports by Healy and Formerly Utilized Sites Remedial Action Program. Once the source terms and potential transport pathways are described, the dose assessment methods are addressed. Three major studies, the waste alternatives, Hansen and Rogers, and the Pantex Environmental Impact Statement, contributed to the current Los Alamos dose assessment methodology. Finally, the current Los Alamos groundwater, surface water, and environmental assessment models for these mesa top and canyon sites are described.

Wenzel, W.J.; Purtymun, W.D.; Dewart, J.M.; Rodgers, J.E. (comps.)

1986-06-01T23:59:59.000Z

400

A regulatory approach for e-waste management: a cross-national review of current practice and policy with an assessment and policy recommendation for the Indian perspective  

Science Journals Connector (OSTI)

This paper attempts to make an assessment and policy recommendation for the Indian perspective through a cross-national review of current practice and policy. It also addresses in a transition economy with some reference to policies and practices in other transition economies. It has been shown that existing Hazardous Waste Rules could overturn the necessity of a separate national legislation dealing with e-waste alone after it is being configured to accommodate e-waste for its management in India. The regulatory approach proposed could serve as a model or at least a starting point for other transition countries that may not be so far along as India with respect to management of e-waste.

Amitava Bandyopadhyay

2008-01-01T23:59:59.000Z

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


401

Solid waste integrated forecast technical (SWEFT) report: FY1997 to FY 2070 - Document number changed to HNF-0918 at revision 1 - 1/7/97  

SciTech Connect (OSTI)

This web site provides an up-to-date report on the radioactive solid waste expected to be managed at Hanford`s Solid Waste (SW) Program from onsite and offsite generators. It includes: an overview of Hanford-wide solid waste to be managed by the SW Program; program- level and waste class-specific estimates; background information on waste sources; and Li comparisons with previous forecasts and with other national data sources. The focus of this web site is on low- level mixed waste (LLMW), and transuranic waste (both non-mixed and mixed) (TRU(M)). Some details on low-level waste and hazardous waste are also provided. Currently, this site is reporting data current as of 9/96. The data represent a life cycle forecast covering all reported activities from FY97 through the end of each program`s life cycle.

Valero, O.J.

1996-10-03T23:59:59.000Z

402

Outside Review of the Doctoral Program of the Department of Chemistry and Biochemistry of Texas Technical University (TTU)  

E-Print Network [OSTI]

observed no desire to remain static. There is also a deci- sion-making process in place to support with the internal and external reviewers present and again on February 6 among internal reviewers. The review team

Rock, Chris

403

THERMAL TREATMENT REVIEW . WTE I THERMAL TREATMENT Since the beginning of this century, global waste-to-energy capacity  

E-Print Network [OSTI]

of new waste-to gasification process at an industrial scale The Waste-To-Energy Research and Technology waste-to-energy capacity has increased steadily at the rate of about four million tonnes of MSW per year solid waste (MSW). Three dominant ,technologies _ those developed by The only true A global perspective

Columbia University

404

DOE Comments on Radioactive Waste | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

on Radioactive Waste DOE Comments on Radioactive Waste 1. Summary Comments on Draft Branch Technical Position on a Performance Assessment Methodology for Low-Level Radioactive...

405

Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report. Revision 3  

SciTech Connect (OSTI)

Westinghouse Hanford Company (WHC) is the Integrating Contractor for the Hanford Waste Vitrification Plant (HWVP) Project, and as such is responsible for preparation of the HWVP Preliminary Safety Analysis Report (PSAR). The HWVP PSAR was prepared pursuant to the requirements for safety analyses contained in US Department of Energy (DOE) Orders 4700.1, Project Management System (DOE 1987); 5480.5, Safety of Nuclear Facilities (DOE 1986a); 5481.lB, Safety Analysis and Review System (DOE 1986b) which was superseded by DOE order 5480-23, Nuclear Safety Analysis Reports, for nuclear facilities effective April 30, 1992 (DOE 1992); and 6430.lA, General Design Criteria (DOE 1989). The WHC procedures that, in large part, implement these DOE requirements are contained in WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual. This manual describes the overall WHC safety analysis process in terms of requirements for safety analyses, responsibilities of the various contributing organizations, and required reviews and approvals.

Herborn, D.I.

1993-11-01T23:59:59.000Z

406

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

407

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

Broader source: Energy.gov (indexed) [DOE]

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

408

Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Firre Protection System Design  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

the the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design 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 Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1

409

Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Firre Protection System Design  

Broader source: Energy.gov (indexed) [DOE]

the the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design 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 Review of the Savannah River Site, Waste Solidification Building, Construction Quality of Mechanical Systems Installation and Selected Aspects of Fire Protection System Design Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1

410

Radioactive waste management in the former USSR  

SciTech Connect (OSTI)

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Bradley, D.J.

1992-06-01T23:59:59.000Z

411

Yucca Mountain Climate Technical Support Representative  

SciTech Connect (OSTI)

The primary objective of Project Activity ORD-FY04-012, Yucca Mountain Climate Technical Support Representative, was to provide the Office of Civilian Radioactive Waste Management (OCRWM) with expertise on past, present, and future climate scenarios and to support the technical elements of the Yucca Mountain Project (YMP) climate program. The Climate Technical Support Representative was to explain, defend, and interpret the YMP climate program to the various audiences during Site Recommendation and License Application. This technical support representative was to support DOE management in the preparation and review of documents, and to participate in comment response for the Final Environmental Impact Statement, the Site Recommendation Hearings, the NRC Sufficiency Comments, and other forums as designated by DOE management. Because the activity was terminated 12 months early and experience a 27% reduction in budget, it was not possible to complete all components of the tasks as originally envisioned. Activities not completed include the qualification of climate datasets and the production of a qualified technical report. The following final report is an unqualified summary of the activities that were completed given the reduced time and funding.

Sharpe, Saxon E

2007-10-23T23:59:59.000Z

412

LITERATURE REVIEW ON THE SORPTION OF PLUTONIUM, URANIUM, NEPTUNIUM, AMERICIUM AND TECHNETIUM TO CORROSION PRODUCTS ON WASTE TANK LINERS  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has conducted performance assessment (PA) calculations to determine the risk associated with closing liquid waste tanks. The PA estimates the risk associated with a number of scenarios, making various assumptions. Throughout all of these scenarios, it is assumed that the carbon-steel tank liners holding the liquid waste do not sorb the radionuclides. Tank liners have been shown to form corrosion products, such as Fe-oxyhydroxides (Wiersma and Subramanian 2002). Many corrosion products, including Fe-oxyhydroxides, at the high pH values of tank effluent, take on a very strong negative charge. Given that many radionuclides may have net positive charges, either as free ions or complexed species, it is expected that many radionuclides will sorb to corrosion products associated with tank liners. The objective of this report was to conduct a literature review to investigate whether Pu, U, Np, Am and Tc would sorb to corrosion products on tank liners after they were filled with reducing grout (cementitious material containing slag to promote reducing conditions). The approach was to evaluate radionuclides sorption literature with iron oxyhydroxide phases, such as hematite ({alpha}-Fe{sub 2}O{sub 3}), magnetite (Fe{sub 3}O{sub 4}), goethite ({alpha}-FeOOH) and ferrihydrite (Fe{sub 2}O{sub 3} {center_dot} 0.5H{sub 2}O). The primary interest was the sorption behavior under tank closure conditions where the tanks will be filled with reducing cementitious materials. Because there were no laboratory studies conducted using site specific experimental conditions, (e.g., high pH and HLW tank aqueous and solid phase chemical conditions), it was necessary to extend the literature review to lower pH studies and noncementitious conditions. Consequently, this report relied on existing lower pH trends, existing geochemical modeling, and experimental spectroscopic evidence conducted at lower pH levels. The scope did not include evaluating the appropriateness of K{sub d} values for the Fe-oxyhydroxides, but instead to evaluate whether it is a conservative assumption to exclude this sorption process of radionuclides onto tank liner corrosion products in the PA model. This may identify another source for PA conservatism since the modeling did not consider any sorption by the tank liner.

Li, D.; Kaplan, D.

2012-02-29T23:59:59.000Z

413

Response ¬タモ Tank Waste Subcommittee (1/24/11)  

Broader source: Energy.gov (indexed) [DOE]

1 1 MEMORANDUM FOR JAMES AJELLO CHAIRMAN ENVIRONMENTAL MANAGEMENT ADVISORY BOARD FROM: INES R. TRIAY w sw ASSISTANT SECRETARY FOR V ENVIRONMENTAL MANAGEMENT . SUBJECT: Office of Eilvironmental Management Response to the September 201 0 Report submitted by the Tank Waste Subcommittee of the Environmental Management Advisory Board on the Waste Treatment and Immobilization Plant On September 15,201 0, the Tank Waste Subcommittee (TWS) of the Office of Environmental Management Advisory Board (EMAB) briefed both the full EMAB as well as EM management on the results of its review of several technical aspects of the Waste Treatment and Immobilization Plant (WTP). The EMAB accepted the results of the review and on September 30,2010 you forwarded the full report, Environmental Management Advisory Board EM Tank Waste Subcommittee Report for

414

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity, December 2012  

Broader source: Energy.gov (indexed) [DOE]

the Hanford Site the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background.......................................................................................................................................... 1 3.0 Scope and Methodology... ................................................................................................................... 1

415

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity, December 2012  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

the Hanford Site the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background.......................................................................................................................................... 1 3.0 Scope and Methodology... ................................................................................................................... 1

416

REVIEWS  

Science Journals Connector (OSTI)

......December 1950 book-review REVIEWS REVIEWS R. E. BEARD Statistics...Price 20s. [453 ] REVIEWS Statistics, Volume I...regard to the mathematical standard required by the Institute...distributions.' The general plan of the book is first......

R. E. BEARD

1950-12-01T23:59:59.000Z

417

Analysis of the technical capabilities of DOE sites for disposal of residuals from the treatment of mixed low-level waste  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has stored or expects to generate over the next five years more than 130,000 m{sup 3} of mixed low-level waste (MLLW). Before disposal, MLLW is usually treated to comply with the land disposal restrictions of the Resource Conservation and Recovery Act. Depending on the type of treatment, the original volume of MLLW and the radionuclide concentrations in the waste streams may change. These changes must be taken into account in determining the necessary disposal capacity at a site. Treatment may remove the characteristic in some waste that caused it to be classified as mixed. Treatment of some waste may, by reduction of the mass, increase the concentrations of some transuranic radionuclides sufficiently so that it becomes transuranic waste. In this report, the DOE MLLW streams were analyzed to determine after-treatment volumes and radionuclide concentrations. The waste streams were reclassified as residual MLLW or low-level or transuranic waste resulting from treatment. The volume analysis indicated that about 89,000 m{sup 3} of waste will require disposal as residual MLLW. Fifteen DOE sites were then evaluated to determine their capabilities for hosting disposal facilities for some or all of the residual MLLW. Waste streams associated with about 90% of the total residual MLLW volume are likely to present no significant issues for disposal and require little additional analysis. Future studies should focus on the remaining waste streams that are potentially problematic by examining site-specific waste acceptance criteria, alternative treatment processes, alternative waste forms for disposal, and pending changes in regulatory requirements.

Waters, R.D.; Gruebel, M.M.; Langkopf, B.S.; Kuehne, P.B.

1997-04-01T23:59:59.000Z

418

Summary: Workshop RecommendationsArgonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management

A. M. Friedman; D. J. Lam; M. G. Seitz

419

Lessons Learned from Characterization, Performance Assessment, and EPA Regulatory Review of the 1996 Actinide Source Term for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) facility for the permanent disposal of transuranic waste from defense activities. In 1996, the DOE submitted the Title 40 CFR Part 191 Compliance Certification Application for the Waste Isolation Pilot Plant (CCA) to the US Environmental Protection Agency (EPA). The CCA included a probabilistic performance assessment (PA) conducted by Sandia National Laboratories to establish compliance with the quantitative release limits defined in 40 CFR 191.13. An experimental program to collect data relevant to the actinide source term began around 1989, which eventually supported the 1996 CCA PA actinide source term model. The actinide source term provided an estimate of mobile dissolved and colloidal Pu, Am, U, Th, and Np concentrations in their stable oxidation states, and accounted for effects of uncertainty in the chemistry of brines in waste disposal areas. The experimental program and the actinide source term included in the CCA PA underwent EPA review lasting more than 1 year. Experiments were initially conducted to develop data relevant to the wide range of potential future conditions in waste disposal areas. Interim, preliminary performance assessments and actinide source term models provided insight allowing refinement of experiments and models. Expert peer review provided additional feedback and confidence in the evolving experimental program. By 1995, the chemical database and PA predictions of WIPP performance were considered reliable enough to support the decision to add an MgO backfill to waste rooms to control chemical conditions and reduce uncertainty in actinide concentrations, especially for Pu and Am. Important lessons learned through the characterization, PA modeling, and regulatory review of the actinide source term are (1) experimental characterization and PA should evolve together, with neither activity completely dominating the other, (2) the understanding of physical processes required to develop conceptual models is greater than can be represented in PA models, (3) experimentalists should be directly involved in model and parameter abstraction and simplification for PA, and (4) external expert review should be incorporated early in a project to increase confidence long before regulatory reviews begin.

Larson, K.W.; Moore, R.C.; Nowak, E.J.; Papenguth, H.W.; Jow, H.

1999-03-22T23:59:59.000Z

420

SCFA lead lab technical assistance at Oak Ridge Y-12 nationalsecurity complex: Evaluation of treatment and characterizationalternatives of mixed waste soil and debris at disposal area remedialaction DARA solids storage facility (SSF)  

SciTech Connect (OSTI)

On July 17-18, 2002, a technical assistance team from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with the Bechtel Jacobs Company Disposal Area Remedial Action (DARA) environmental project leader to review treatment and characterization options for the baseline for the DARA Solids Storage Facility (SSF). The technical assistance request sought suggestions from SCFA's team of technical experts with experience and expertise in soil treatment and characterization to identify and evaluate (1) alternative treatment technologies for DARA soils and debris, and (2) options for analysis of organic constituents in soil with matrix interference. Based on the recommendations, the site may also require assistance in identifying and evaluating appropriate commercial vendors.

Hazen, Terry

2002-08-26T23:59:59.000Z

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


421

Sealed source peer review plan  

SciTech Connect (OSTI)

Sealed sources are known quantities of radioactive materials that have been encapsulated in quantities that produce known radiation fields. Sealed sources have multiple uses ranging from instrument calibration sources to sources that produce radiation fields for experimental applications. The Off-Site Source Recovery (OSR) Project at Los Alamos National Laboratory (LANL), created in 1999, under the direction of the Waste Management Division of the U.S. Department of Energy (DOE) Albuquerque has been assigned the responsibility to recover and manage excess and unwanted radioactive sealed sources from the public and private sector. LANL intends to ship drums containing qualified sealed sources to the Waste Isolation Pilot Plant (WIPP) for disposal. Prior to shipping, these drums must be characterized with respect to radiological content and other parameters. The U. S. Environmental Protection Agency (EPA) requires that ten radionulcides be quantified and reported for every container of waste to be disposed in the WIPP. The methods traditionally approved by the EPA include non-destructive assay (NDA) in accordance with Appendix A of the Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (DOE, 2002) (CH WAC). However, because of the nature and pedigree of historical records for sealed sources and the technical infeasibility of performing NDA on these sources, LANL proposes to characterize the content of these waste drums using qualified existing radiological data in lieu of direct measurement. This plan describes the process and documentation requirements for the use of the peer review process to qualify existing data for sealed radiological sources in lieu of perfonning radioassay. The peer review process will be performed in accordance with criteria provided in 40 CFR {section} 194.22 which specifies the use of the NUREG 1297 guidelines. The plan defines the management approach, resources, schedule, and technical requirements for the subject peer review.

Feldman, Alexander [Los Alamos National Laboratory; Leonard, Lee [RETIRED; Burns, Ron [CONTRACTOR

2009-01-01T23:59:59.000Z

422

Technical Report Confirms Reliability of Yucca Mountain Technical Work |  

Broader source: Energy.gov (indexed) [DOE]

Technical Report Confirms Reliability of Yucca Mountain Technical Technical Report Confirms Reliability of Yucca Mountain Technical Work Technical Report Confirms Reliability of Yucca Mountain Technical Work February 17, 2006 - 11:59am Addthis WASHINGTON, DC - The Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM) today released a report confirming the technical soundness of infiltration modeling work performed by U.S. Geological Survey (USGS) employees. "The report makes clear that the technical basis developed by the USGS has a strong conceptual foundation and is corroborated by independently-derived scientific conclusions, and provides a solid underpinning for the 2002 site recommendation," said OCRWM's Acting Director Paul Golan. "We are committed to opening Yucca Mountain based only on sound science. The work

423

Waste-to-Energy Workshop  

Broader source: Energy.gov [DOE]

The Waste to Energy Roadmapping Workshop was held on November 5, 2014, in Arlington, Virginia. This workshop gathered waste-to-energy experts to identify the key technical barriers to the commercial deployment of liquid transportation fuels from wet waste feedstocks.

424

May 15, 2012, Federal Technical Capability Program Face to Face Meeting … Speech: Safety Culture And Training and Competency  

Broader source: Energy.gov (indexed) [DOE]

Safety Safety Culture Safety Culture And Training and Competency Joseph F. Bader Board Member Board Member Defense Nuclear Facilities Safety Board Thanks to Tim Hunt and Doug Minnema Objectives * Discuss the Board's approach to staff training * Review the Board's concerns about safety culture at the Waste Treatment and Immobilization Plant (WTP) Waste Treatment and Immobilization Plant (WTP) * Understand what group culture is and why it is an g p y important part of nuclear operations * Explore the linkage between safety culture and training and competency June 2012 DOE FTCP Meeting 2 The Board's Technical Staff * Currently about 85 Technical Staff members. * Essentially all of the Technical Staff members have at least one technical master's degree, ~20% have a PhD. * Extensive experience in nuclear, mechanical, electrical,

425

Independent Oversight Activity Report, Hanford Waste Treatment...  

Office of Environmental Management (EM)

of River Protection review of the High Level Waste Facility heating, ventilation, and air conditioning systems. Independent Oversight Activity Report, Hanford Waste Treatment...

426

Technical evaluation of WIPP by the New Mexico environmental evaluation group  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is a repository under construction in southeastern New Mexico for the disposal of 14.1 million curies of defense transuranic (TRU) waste. The US Department of Energy (DOE) plans to start storing waste in the underground facility in October 1988 for a 5-yr research and demonstration period. Since the State of New Mexico had a number of concerns in 1978 regarding the impact on health and safety of the proposed WIPP facility for disposal of radioactive waste, the DOE agreed to fund an independent technical review and evaluation of the planned repository, resulting in the creation of the Environmental Evaluation Group (EEG). This full-time multidisciplinary group has published 39 major reports to date, testified before the New Mexico Legislature and the US Congress, and has disseminated the results of analyses to DOE, the governor, the legislature, the Congress, the scientific community, and the general public. While the disposal of radioactive defense mill tailings and defense high-level wastes are both subject to US Nuclear Regulatory Commission (NRC) licensing, Congress specifically chose not to have defense TRU waste disposal licensed by the NRC. This has placed a heavy burden on EEG as the only full-time technical review agency on WIPP, but without regulatory authority.

Neill, R.

1988-01-01T23:59:59.000Z

427

Technical Information Officers | Scientific and Technical Information  

Office of Scientific and Technical Information (OSTI)

Technical Information Officers Technical Information Officers Print page Print page Email page Email page Technical Information Officers: Serve as the DOE element representatives to STIP and ensure that STI objectives and requirements are incorporated into strategic planning, management information plans, life-cycle procedures from project initiation to close-out, and contract language as appropriate. Coordinate with contractor STI managers and have adequate familiarity with STI activities to discern contractor compliance with the CRD portion of this directive. Coordinate the implementation of appropriate review and release procedures by DOE elements, DOE contractors, and financial assistance recipients as appropriate. Serve as Releasing Officials or coordinate designation and official

428

Safety and Technical Services  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Safety and Technical Services Safety and Technical Services Minimize The Safety and Technical Services (STS) organization is a component of the Office of Science's (SC's) Oak Ridge Integrated Support Center. The mission of STS is to provide excellent environmental, safety, health, quality, and engineering support to SC laboratories and other U.S. Department of Energy program offices. STS maintains a full range of technically qualified Subject Matter Experts, all of whom are associated with the Technical Qualifications Program. Examples of the services that we provide include: Integrated Safety Management Quality Assurance Planning and Metrics Document Review Tracking and trending analysis and reporting Assessments, Reviews, Surveillances and Inspections Safety Basis Support SharePoint/Dashboard Development for Safety Programs

429

TECHNICAL RISK RATING OF DOE ENVIRONMENTAL PROJECTS - 9153  

SciTech Connect (OSTI)

The U.S. Department of Energy's Office of Environmental Management (DOE-EM) was established to achieve the safe and compliant disposition of legacy wastes and facilities from defense nuclear applications. The scope of work is diverse, with projects ranging from single acquisitions to collections of projects and operations that span several decades and costs from hundreds of millions to billions US$. The need to be able to manage and understand the technical risks from the project to senior management level has been recognized as an enabler to successfully completing the mission. In 2008, DOE-EM developed the Technical Risk Rating as a new method to assist in managing technical risk based on specific criteria. The Technical Risk Rating, and the criteria used to determine the rating, provides a mechanism to foster open, meaningful communication between the Federal Project Directors and DOE-EM management concerning project technical risks. Four indicators (technical maturity, risk urgency, handling difficulty and resolution path) are used to focus attention on the issues and key aspects related to the risks. Pressing risk issues are brought to the forefront, keeping DOE-EM management informed and engaged such that they fully understand risk impact. Use of the Technical Risk Rating and criteria during reviews provides the Federal Project Directors the opportunity to openly discuss the most significant risks and assists in the management of technical risks across the portfolio of DOE-EM projects. Technical Risk Ratings can be applied to all projects in government and private industry. This paper will present the methodology and criteria for Technical Risk Ratings, and provide specific examples from DOE-EM projects.

Cercy, M; Ronald Fayfich, R; Steven P Schneider, S

2008-12-12T23:59:59.000Z

430

Safety Evaluation Report of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis  

SciTech Connect (OSTI)

This Safety Evaluation Report (SER) documents the Department of Energys (DOE's) review of Revision 9 of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis, DOE/WIPP-95-2065 (WIPP CH DSA), and provides the DOE Approval Authority with the basis for approving the document. It concludes that the safety basis documented in the WIPP CH DSA is comprehensive, correct, and commensurate with hazards associated with CH waste disposal operations. The WIPP CH DSA and associated technical safety requirements (TSRs) were developed in accordance with 10 CFR 830, Nuclear Safety Management, and DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports.

Washington TRU Solutions LLC

2005-09-01T23:59:59.000Z

431

Los Alamos National Laboratory Environmental Restoration Project quarterly technical report, April--June 1994  

SciTech Connect (OSTI)

This quarterly report describes the technical status of activities in the Los Alamos National Laboratory Environmental Restoration (ER) Project. Each activity is identified by an activity data sheet number, a brief title describing the activity or the technical area where the activity is located, and the name of the project leader. The Hazardous and Solid Waste Amendments (HSWA) portion of the facility operating permit requires the submission of a technical progress report on a quarterly basis. This report, submitted to fulfill the permit`s requirement, summarizes the work performed and the results of sampling and analysis in the ER Project. Suspect waste found include: Radionuclides, high explosives, metals, solvents and organics. The data provided in this report have not been validated. These data are considered ``reviewed data.``

Not Available

1994-08-18T23:59:59.000Z

432

Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012  

Broader source: Energy.gov (indexed) [DOE]

Waste Isolation Pilot Plant Waste Isolation Pilot Plant May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose............................................................................................................................................. 1 2.0 Scope................................................................................................................................................ 1 3.0 Background...................................................................................................................................... 2 4.0 Methodology....................................................................................................................................

433

Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Waste Isolation Pilot Plant Waste Isolation Pilot Plant May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose............................................................................................................................................. 1 2.0 Scope................................................................................................................................................ 1 3.0 Background...................................................................................................................................... 2 4.0 Methodology....................................................................................................................................

434

Review of the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility Fire Suppression System, January 2012  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Waste Waste Characterization, Reduction, and Repackaging Facility Fire Suppression System January 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 ...................................................................................................................................................... 1

435

Review of the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility Fire Suppression System, January 2012  

Broader source: Energy.gov (indexed) [DOE]

Waste Waste Characterization, Reduction, and Repackaging Facility Fire Suppression System January 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 ...................................................................................................................................................... 1

436

Review of the Savannah River Site, Salt Waste Processing Facility, Construction Quality of Piping and Pipe Supports, September 2012  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Savannah River Site, Salt Waste Processing Savannah River Site, Salt Waste Processing Facility, Construction Quality of Piping & Pipe Supports September 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background .......................................................................................................................................... 1

437

Review of the Savannah River Site, Salt Waste Processing Facility, Construction Quality of Piping and Pipe Supports, September 2012  

Broader source: Energy.gov (indexed) [DOE]

Savannah River Site, Salt Waste Processing Savannah River Site, Salt Waste Processing Facility, Construction Quality of Piping & Pipe Supports September 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background .......................................................................................................................................... 1

438

Review of U.K. Publication (by Prof. Nickolas J. Themelis, WTERT Chair): A Changing Climate for Energy from Waste?  

E-Print Network [OSTI]

, the U.S. WTEs generate, according to DOE, 13.55 billion kWh of net electricity plus 0.165 billion k chlorinated compounds that have been tabulated by Tchobanoglous et al in the Handbook of Integrated Waste also does not mention the emissions of Waste Transfer Stations and diesel trucks that are needed

Columbia University

439

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

SciTech Connect (OSTI)

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

Rathbun, R.

1994-03-02T23:59:59.000Z

440

A technical look at the WTI incinerator  

SciTech Connect (OSTI)

EPA has granted Waste Technologies Industries (WTI) temporary authorization to burn hazardous waste in its new incinerator in East Liverpool, Ohio. The approval is based on preliminary data showing that the incinerator was able to meet EPA`s emission standards for dioxins and furans in tests run this summer. WTI is allowed to continue burning waste pending final evaluation of its March 1993 performance tests. The action marks yet another hurdle cleared by WTI in its 11-year effort to construct and operate a commercial hazardous waste incinerator. The facility`s long-standing predicament as a target for environmental and public interest groups has made it the subject of numerous lawsuits and many legal reviews. In this article, however, we focus on the technical aspects of the system. The WTI incinerator is described in {open_quotes}Performance Testing of a Rotary Kiln Incinerator,{close_quotes} a paper by Alfred Sigg of Von Roll, Incorporated (Norcross, Georgia). The paper was presented at the 1993 Incineration Conference, which was held in Knoxville, Tennessee on May 3-7, 1993. 1 fig., 2 tabs.

NONE

1993-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste technical review" 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.


441

REVIEWS  

Science Journals Connector (OSTI)

......December 1959 book-review REVIEWS REVIEWS E. S. PEARSON The Advanced...433 . 84s. [491 ] REVIEWS The Advanced Theory of...the same comprehensive standard, three volumes will...inserted in the original plan at this half-way stage......

E. S. PEARSON

1959-12-01T23:59:59.000Z

442

Reviews  

Science Journals Connector (OSTI)

......book-review Reviews Reviews Factors for One-sided...for Variables Sampling Plans. By D. B. OWEN. Sandia...Pp. 412 . 5.00. Reviews 293 Handbook of Nonparametric...for Variables Sampling Plans. By D. B. OWEN. Sandia...expected value ft and standard deviation cr/^/n......

Reviews

1964-06-01T23:59:59.000Z

443

Technical Assistance | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Technical Assistance Technical Assistance Technical Assistance The Technical Assistance program is managed through the Center for Sustainable Soil and Groundwater Solutions at SRNL. The Technical Assistance program provides teams of nationally recognized experts from across the complex to support both DOE's smaller sites, such as Paducah, Portsmouth, Pinellas, Ashtabula, Fernald, Mound and Kansas City Plant, and larger sites such as Oak Ridge, Los Alamos, Lawrence Livermore and Savannah River. Solutions that reduce technical risk and uncertainty Focus on science and engineering issues and strategic implementation of remedial systems Independent reviews facilitate regulatory and stakeholder acceptance of solutions. Contacts Karen Skubal karen.skubal@em.doe.gov (301) 903-6524 Justin Marble

444

Technical summary of groundwater quality protection program at the Savannah River Site, 1952--1986. Volume 1, Site geohydrology and waste sites  

SciTech Connect (OSTI)

This report provides information regarding the status of and groundwater quality at the waste sites at the Department of Energy`s (DOE) Savannah River Site (SRS). Specific information provided for each waste site at SRS includes its location, size, inventory (when known), and history. Many waste sites at SRS are considered to be of little environmental concern because they contain nontoxic or inert material such as construction rubble and debris. Other waste sites, however, either are known to have had an effect on groundwater quality or are suspected of having the potential to affect groundwater. Monitoring wells have been installed at most of these sites; monitoring wells are scheduled for installation at the remaining sites. Results of the groundwater analyses from these monitoring wells, presented in the appendices, are used in the report to help identify potential contaminants of concern, if any, at each waste site. The list of actions proposed for each waste site in Christensen and Gordon`s 1983 report are summarized, and an update is provided for each site. Planned actions for the future are also outlined.

Heffner, J.D. [ed.] [Exploration Resources, Inc., Athens, GA (United States)

1991-11-01T23:59:59.000Z

445

Review of Documented Safety Analysis Development for the Hanford Site Waste Treatment and Immobilization Plant (LBL Facilities), April 23, 2013 (HSS CRAD 45-58, Rev. 0)  

Broader source: Energy.gov (indexed) [DOE]

U.S. Department of U.S. Department of Energy Subject: Review of Documented Safety Analysis Development for the Hanford Site Waste Treatment and Immob ilization Plant (LBL Facilities) - C riteria and Review Approach D oc um~ HS: HSS CRAD 45-58 Rev: 0 Eff. Date: April 23, 2013 Office of Safety and Emergency Management Evaluations Acting Di rec or, Office of Safety and Emergency Nltanagement Evaluations Date: Apri l 23 , 20 13 Criteria and Review Approach Document ~~ trd,James Low Date: April 23 , 20 13 1.0 PURPOSE Within the Office of H.ealth, Safety and Security (HSS), the Office of Enforcement and Overs ight, Office of Safety and Emergency Management Evaluations (HS-45) miss io n is to assess the effectiveness of the environment, safety, health, and emergency management systems and practices used by line and

446

Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2b: Earth-mounded concrete bunkers  

SciTech Connect (OSTI)

The US Army Engineers Waterways Experiment Station (WES) and US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste (LLW) disposal. An EMCB is generally described as a reinforced concrete vault placed below grade, underneath a tumulus, surrounded by filter-blanket and drainage zones. The tumulus is covered over with a low permeability cover layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the EMCB structure through material quality and durability considerations. Specific design review criteria have been developed in detail for each of the eight major categories. 63 refs., 13 figs., 2 tabs.

Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

1988-01-01T23:59:59.000Z

447

Radioactive Waste Radioactive Waste  

E-Print Network [OSTI]

#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to;Radioactive Waste · Program requires · Generator support · Proper segregation · Packaging · labeling #12;Radioactive Waste · What is radioactive waste? · Anything that · Contains · or is contaminated

Slatton, Clint

448

CERTS 2012 Program Review - NASPI Technical Support for OITT & Operations of NERC-TVA NASPI Synchrophasor Network & RTDMS Installation - Jim Dyer, EPG  

Broader source: Energy.gov (indexed) [DOE]

SynchroPhasor Initiative SynchroPhasor Initiative (NASPI) Event Analysis Reports Jim Dyer dyer@ElectricPowerGroup.com June 12, 2012 Washington, DC DOE - CERTS Transmission Reliability R&D Internal Program Review Agenda  Technical Support for Operations of Real Time Dynamics Monitoring System (RTDMS) for NASPI  Support of the RTDMS Users' Group  Support of NASPI Operations Implementation Task Team (OITT) Page 1  Built upon GRID-3P Platform, U.S. Patent 7,233,843, and U.S. Patent 8,060259. All rights reserved. NASPI-RTDMS Support Page 2  Objective - Enhance, maintain and support the RTDMS application, server, data base and client. Support users needs and provide an application that converts phasor date into useful information

449

Waste Isolation Pilot Plant - Reports  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Reports Reports Waste Isolation Pilot Plant Review Report 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013 Review Report 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012 Activity Reports 2011 Orientation Visit to the Waste Isolation Pilot Plant, September 2011 Review Reports 2007 Independent Oversight Inspection of Emergency Management at the Carlsbad Field Office and Waste Isolation Pilot Plant, December 2007 Review Reports 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant - Summary Report, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002

450

Underground engineering at the Basalt Waste Isolation Project  

SciTech Connect (OSTI)

A special task group was organized by the US National Committee for Rock Mechanics and the Board on Radioactive Waste Management of the National Research Council to address issues relating to the geotechnical site characterization program for an underground facility to house high-level radioactive waste of the Basalt Waste Isolation Project (BWIP). Intended to provide an overview of the geotechnical program, the study was carried out by a task group consisting of ten members with expertise in the many disciplines required to successfully complete such a project. The task group recognized from the outset that the short time frame of this study would limit its ability to address all geotechnical issues in detail. Geotechnical issues were considered to range from specific technical aspects such as in-situ testing for rock mass permeability; rock hardness testing in the laboratory; or geologic characterizations and quantification of joints, to broader aspects of design philosophy, data collection, and treatment of uncertainty. The task group chose to focus on the broader aspects of underground design and construction, recognizing that the BWIP program utilizes a peer review group on a regular basis which reviews the specific technical questions related to geotechnical engineering. In this way, it was hoped that the review provided by the task group would complement those prepared by the BWIP peer review group.

Not Available

1987-01-01T23:59:59.000Z

451

Summary - Demonstration Bulk Vitrification System (DBVS) for Low-Actvity Waste at Hanford  

Broader source: Energy.gov (indexed) [DOE]

DBVS DBVS ETR Report Date: September 2006 ETR-3 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Demonstration Bulk Vitrification System (DBVS) for Low Activity Waste (LAW) at Hanford Why DOE-EM Did This Review The Department of Energy (DOE) is charged with the safe retrieval, treatment and disposal of 53 million gallons of Hanford radioactive waste. The Waste Treatment Plant (WTP) is being designed to treat and vitrify the High Level Waste (HLW) fraction in 20-25 years. The WTP is undersized for vitrifying the LAW fraction over the same time frame. The DOE is evaluating Bulk Vitrification as an alternative to increasing the size of the WTP LAW treatment process. Bulk vitrification is an in-container melting