Research reactor aluminum spent fuel :: treatment options for disposal /
Of Findings -- TOPIC: METALLURGY AND CORROSION CONSULTANT: PAUL SHEWMON -- Introduction -- Processing -- Answers to Assigned Questions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: RICHARD I. SMITH -- General Comments -- Specific Comments -- Other Comments -- References -- Appendix E Biograp...
Gespeichert in:
Körperschaft: | |
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Weitere Verfasser: | , |
Format: | Elektronisch E-Book |
Sprache: | English |
Veröffentlicht: |
Washington, D.C. :
National Academy Press,
1998.
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Schlagworte: | |
Online-Zugang: | Volltext |
Zusammenfassung: | Of Findings -- TOPIC: METALLURGY AND CORROSION CONSULTANT: PAUL SHEWMON -- Introduction -- Processing -- Answers to Assigned Questions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: RICHARD I. SMITH -- General Comments -- Specific Comments -- Other Comments -- References -- Appendix E Biographical Sketches of Consultants -- Appendix F Documents Received in This Study. |
Beschreibung: | 1 online resource (xii, 227 pages) : illustrations |
Format: | Master and use copy. Digital master created according to Benchmark for Faithful Digital Reproductions of Monographs and Serials, Version 1. Digital Library Federation, December 2002. |
Bibliographie: | Includes bibliographical references. |
ISBN: | 058503947X 9780585039473 1280186925 9781280186929 9786610186921 6610186928 0309591805 9780309591805 0309174104 9780309174107 |
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245 | 0 | 0 | |a Research reactor aluminum spent fuel : |b treatment options for disposal / |c Milton Levenson, principal investigator ; Kevin D. Crowley, study director ; Board on Radioactive Waste Management, Commission on Geosciences, Environment, and Resources, National Research Council. |
260 | |a Washington, D.C. : |b National Academy Press, |c 1998. | ||
300 | |a 1 online resource (xii, 227 pages) : |b illustrations | ||
336 | |a text |b txt |2 rdacontent | ||
337 | |a computer |b c |2 rdamedia | ||
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504 | |a Includes bibliographical references. | ||
588 | 0 | |a Print version record. | |
506 | |3 Use copy |f Restrictions unspecified |2 star |5 MiAaHDL | ||
533 | |a Electronic reproduction. |b [S.l.] : |c HathiTrust Digital Library, |d 2010. |5 MiAaHDL | ||
538 | |a Master and use copy. Digital master created according to Benchmark for Faithful Digital Reproductions of Monographs and Serials, Version 1. Digital Library Federation, December 2002. |u http://purl.oclc.org/DLF/benchrepro0212 |5 MiAaHDL | ||
583 | 1 | |a digitized |c 2010 |h HathiTrust Digital Library |l committed to preserve |2 pda |5 MiAaHDL | |
546 | |a English. | ||
505 | 0 | |a Research Reactor Aluminum Spent Fuel -- Copyright -- Foreword -- Preface -- Contents -- Summary -- FINDINGS RELATED TO THE SELECTION OF ALUMINUM SPENT FUEL TREATMENT OPTIONS -- FINDINGS RELATED TO WASTE-PACKAGE PERFORMANCE CRITERIA -- FINDINGS RELATED TO COSTS AND TIMING OF ALUMINUM SPENT FUEL TREATMENT OPTIONS -- CONCLUDING OBSERVATIONS -- 1 Background and Task -- TASK STATEMENT AND STUDY PROCESS -- ORGANIZATION OF THIS REPORT -- 2 Treatment Options for Aluminum Spent Nuclear Fuel -- BACKGROUND -- TREATMENT TECHNOLOGIES FOR ALUMINUM SPENT FUEL -- Direct Disposal Technologies -- HEU Dilution Technologies -- Advanced Treatment Technologies -- EVALUATING THE TREATMENT ALTERNATIVES -- TASK TEAM RECOMMENDATIONS -- RESPONSE TO FIRST CHARGE IN STATEMENT OF TASK -- 3 Waste-Package Performance Criteria -- BACKGROUND -- WASTE ACCEPTANCE CRITERIA -- OTHER REQUIREMENTS -- RESPONSE TO SECOND CHARGE IN STATEMENT OF TASK -- 2.3.20.2: Limits on Radionuclide Inventories in Multi-Element Canisters -- 2.3.21: Limits on Total Fissile Material in a Disposable Canister -- 2.3.22: Limits on Disposable Canister Criticality Potential -- CONCLUSIONS -- 4 Cost and Schedule -- TASK TEAM REPORT COST AND SCHEDULE ESTIMATES -- ALTERNATIVE COST STUDY -- COMPARISON OF TASK TEAM AND ALTERNATIVE COST STUDY ESTIMATES -- RESPONSE TO THIRD CHARGE IN STATEMENT OF TASK -- 5 Concluding Observations -- PHASED DECISION AND IMPLEMENTATION STRATEGY FOR TREATMENT OPTION SELECTION -- Spent Fuel Generation -- Spent Fuel Receipt and Storage -- Treatment and Interim Storage -- Transport and Repository Disposal -- Decontamination and Decommissioning -- Post-2015 Aluminum Spent Fuel Inventory -- PATH FORWARD -- References -- Appendix A Study Request Letter from DOE-Savannah River -- Appendix B Meeting Agendas and Participants -- Appendix C Charge to Consultants -- QUESTIONS TO EXPERTS. | |
505 | 8 | |a Criticality -- Proliferation -- Cost and Schedule -- Corrosion and Metallurgy -- Processing and Remote Handling -- Regulatory Waste Acceptance -- Appendix D Consultant Reports -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: JOHN AHEARNE -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: FRANCIS M. ALCORN -- TOPIC: COST AND SCHEDULE CONSULTANT: M.W. ANGVALL -- TOPIC: REGULATORY AND WASTE ACCEPTANCE CONSULTANT: ROBERT M. BERNERO -- Introduction -- Background -- Regulatory Approach for Yucca Mountain -- Evaluation of DOE Aluminum-Based Spent Fuel Alternatives -- Summary -- TOPIC: PROCESSING AND REMOTE HANDLING CONSIDERATIONS CONSULTANT: JOSEPH BYRD -- Introduction and Background -- Processing/Remote Handling Issues -- General Issues -- Conclusions and Recommendations -- References -- TOPIC: METALLURGY AND CORROSION CONSULTANT: R.L. DILLON -- Introduction -- Conclusions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: G. BRIAN ESTES -- References -- TOPIC: PROCESSING AND REMOTE SYSTEMS CONSULTANT: HARRY HARMON -- Introduction -- Responses -- References -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: VALERIE L. PUTMAN -- Introduction -- Conclusion -- Discussion -- Criticality Safety at Savannah River Site (SRS) -- Criticality Safety on Public Roads, Transport to Final Repository -- Criticality Safety at Final Repository -- Intact Canisters and Al-SNF, Initial Repository Conditions -- Degraded Canisters and/or Al-SNF, Long Term Repository Conditions -- Summary -- References -- Other Documents Reviewed -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: DAVID ROSSIN -- Proliferation Assessment -- Identification of Separated Fissile Material as a Proliferation Risk -- Container -- Repository -- Self-Protection Criterion -- Use of Processing for Waste Management. | |
520 | |a Of Findings -- TOPIC: METALLURGY AND CORROSION CONSULTANT: PAUL SHEWMON -- Introduction -- Processing -- Answers to Assigned Questions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: RICHARD I. SMITH -- General Comments -- Specific Comments -- Other Comments -- References -- Appendix E Biographical Sketches of Consultants -- Appendix F Documents Received in This Study. | ||
650 | 0 | |a Radioactive waste disposal |x Management. | |
650 | 0 | |a Spent reactor fuels. |0 http://id.loc.gov/authorities/subjects/sh85126529 | |
650 | 0 | |a Aluminum |x Isotopes. |0 http://id.loc.gov/authorities/subjects/sh85003963 | |
650 | 6 | |a Combustibles nucléaires irradiés. | |
650 | 7 | |a TECHNOLOGY & ENGINEERING |x Power Resources |x Nuclear. |2 bisacsh | |
650 | 7 | |a Aluminum |x Isotopes |2 fast | |
650 | 7 | |a Radioactive waste disposal |x Management |2 fast | |
650 | 7 | |a Spent reactor fuels |2 fast | |
700 | 1 | |a Levenson, Milton. | |
700 | 1 | |a Crowley, Kevin D. | |
710 | 2 | |a National Research Council (U.S.). |b Board on Radioactive Waste Management. |0 http://id.loc.gov/authorities/names/n83053793 | |
776 | 0 | 8 | |i Print version: |t Research reactor aluminum spent fuel. |d Washington, D.C. : National Academy Press, 1998 |z 0309060494 |w (DLC) 98084670 |w (OCoLC)39192820 |
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Datensatz im Suchindex
DE-BY-FWS_katkey | ZDB-4-EBA-ocm42417408 |
---|---|
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adam_text | |
any_adam_object | |
author2 | Levenson, Milton Crowley, Kevin D. |
author2_role | |
author2_variant | m l ml k d c kd kdc |
author_corporate | National Research Council (U.S.). Board on Radioactive Waste Management |
author_corporate_role | |
author_facet | Levenson, Milton Crowley, Kevin D. National Research Council (U.S.). Board on Radioactive Waste Management |
author_sort | Levenson, Milton |
building | Verbundindex |
bvnumber | localFWS |
callnumber-first | T - Technology |
callnumber-label | TD898 |
callnumber-raw | TD898.14.M35 R47 1998eb |
callnumber-search | TD898.14.M35 R47 1998eb |
callnumber-sort | TD 3898.14 M35 R47 41998EB |
callnumber-subject | TD - Environmental Technology |
classification_rvk | UN 5240 |
collection | ZDB-4-EBA |
contents | Research Reactor Aluminum Spent Fuel -- Copyright -- Foreword -- Preface -- Contents -- Summary -- FINDINGS RELATED TO THE SELECTION OF ALUMINUM SPENT FUEL TREATMENT OPTIONS -- FINDINGS RELATED TO WASTE-PACKAGE PERFORMANCE CRITERIA -- FINDINGS RELATED TO COSTS AND TIMING OF ALUMINUM SPENT FUEL TREATMENT OPTIONS -- CONCLUDING OBSERVATIONS -- 1 Background and Task -- TASK STATEMENT AND STUDY PROCESS -- ORGANIZATION OF THIS REPORT -- 2 Treatment Options for Aluminum Spent Nuclear Fuel -- BACKGROUND -- TREATMENT TECHNOLOGIES FOR ALUMINUM SPENT FUEL -- Direct Disposal Technologies -- HEU Dilution Technologies -- Advanced Treatment Technologies -- EVALUATING THE TREATMENT ALTERNATIVES -- TASK TEAM RECOMMENDATIONS -- RESPONSE TO FIRST CHARGE IN STATEMENT OF TASK -- 3 Waste-Package Performance Criteria -- BACKGROUND -- WASTE ACCEPTANCE CRITERIA -- OTHER REQUIREMENTS -- RESPONSE TO SECOND CHARGE IN STATEMENT OF TASK -- 2.3.20.2: Limits on Radionuclide Inventories in Multi-Element Canisters -- 2.3.21: Limits on Total Fissile Material in a Disposable Canister -- 2.3.22: Limits on Disposable Canister Criticality Potential -- CONCLUSIONS -- 4 Cost and Schedule -- TASK TEAM REPORT COST AND SCHEDULE ESTIMATES -- ALTERNATIVE COST STUDY -- COMPARISON OF TASK TEAM AND ALTERNATIVE COST STUDY ESTIMATES -- RESPONSE TO THIRD CHARGE IN STATEMENT OF TASK -- 5 Concluding Observations -- PHASED DECISION AND IMPLEMENTATION STRATEGY FOR TREATMENT OPTION SELECTION -- Spent Fuel Generation -- Spent Fuel Receipt and Storage -- Treatment and Interim Storage -- Transport and Repository Disposal -- Decontamination and Decommissioning -- Post-2015 Aluminum Spent Fuel Inventory -- PATH FORWARD -- References -- Appendix A Study Request Letter from DOE-Savannah River -- Appendix B Meeting Agendas and Participants -- Appendix C Charge to Consultants -- QUESTIONS TO EXPERTS. Criticality -- Proliferation -- Cost and Schedule -- Corrosion and Metallurgy -- Processing and Remote Handling -- Regulatory Waste Acceptance -- Appendix D Consultant Reports -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: JOHN AHEARNE -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: FRANCIS M. ALCORN -- TOPIC: COST AND SCHEDULE CONSULTANT: M.W. ANGVALL -- TOPIC: REGULATORY AND WASTE ACCEPTANCE CONSULTANT: ROBERT M. BERNERO -- Introduction -- Background -- Regulatory Approach for Yucca Mountain -- Evaluation of DOE Aluminum-Based Spent Fuel Alternatives -- Summary -- TOPIC: PROCESSING AND REMOTE HANDLING CONSIDERATIONS CONSULTANT: JOSEPH BYRD -- Introduction and Background -- Processing/Remote Handling Issues -- General Issues -- Conclusions and Recommendations -- References -- TOPIC: METALLURGY AND CORROSION CONSULTANT: R.L. DILLON -- Introduction -- Conclusions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: G. BRIAN ESTES -- References -- TOPIC: PROCESSING AND REMOTE SYSTEMS CONSULTANT: HARRY HARMON -- Introduction -- Responses -- References -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: VALERIE L. PUTMAN -- Introduction -- Conclusion -- Discussion -- Criticality Safety at Savannah River Site (SRS) -- Criticality Safety on Public Roads, Transport to Final Repository -- Criticality Safety at Final Repository -- Intact Canisters and Al-SNF, Initial Repository Conditions -- Degraded Canisters and/or Al-SNF, Long Term Repository Conditions -- Summary -- References -- Other Documents Reviewed -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: DAVID ROSSIN -- Proliferation Assessment -- Identification of Separated Fissile Material as a Proliferation Risk -- Container -- Repository -- Self-Protection Criterion -- Use of Processing for Waste Management. |
ctrlnum | (OCoLC)42417408 |
dewey-full | 621.48/38 |
dewey-hundreds | 600 - Technology (Applied sciences) |
dewey-ones | 621 - Applied physics |
dewey-raw | 621.48/38 |
dewey-search | 621.48/38 |
dewey-sort | 3621.48 238 |
dewey-tens | 620 - Engineering and allied operations |
discipline | Physik Energietechnik |
format | Electronic eBook |
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ALCORN -- TOPIC: COST AND SCHEDULE CONSULTANT: M.W. ANGVALL -- TOPIC: REGULATORY AND WASTE ACCEPTANCE CONSULTANT: ROBERT M. BERNERO -- Introduction -- Background -- Regulatory Approach for Yucca Mountain -- Evaluation of DOE Aluminum-Based Spent Fuel Alternatives -- Summary -- TOPIC: PROCESSING AND REMOTE HANDLING CONSIDERATIONS CONSULTANT: JOSEPH BYRD -- Introduction and Background -- Processing/Remote Handling Issues -- General Issues -- Conclusions and Recommendations -- References -- TOPIC: METALLURGY AND CORROSION CONSULTANT: R.L. DILLON -- Introduction -- Conclusions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: G. BRIAN ESTES -- References -- TOPIC: PROCESSING AND REMOTE SYSTEMS CONSULTANT: HARRY HARMON -- Introduction -- Responses -- References -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: VALERIE L. PUTMAN -- Introduction -- Conclusion -- Discussion -- Criticality Safety at Savannah River Site (SRS) -- Criticality Safety on Public Roads, Transport to Final Repository -- Criticality Safety at Final Repository -- Intact Canisters and Al-SNF, Initial Repository Conditions -- Degraded Canisters and/or Al-SNF, Long Term Repository Conditions -- Summary -- References -- Other Documents Reviewed -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: DAVID ROSSIN -- Proliferation Assessment -- Identification of Separated Fissile Material as a Proliferation Risk -- Container -- Repository -- Self-Protection Criterion -- Use of Processing for Waste Management.</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">Of Findings -- TOPIC: METALLURGY AND CORROSION CONSULTANT: PAUL SHEWMON -- Introduction -- Processing -- Answers to Assigned Questions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: RICHARD I. 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id | ZDB-4-EBA-ocm42417408 |
illustrated | Illustrated |
indexdate | 2024-11-27T13:14:54Z |
institution | BVB |
institution_GND | http://id.loc.gov/authorities/names/n83053793 |
isbn | 058503947X 9780585039473 1280186925 9781280186929 9786610186921 6610186928 0309591805 9780309591805 0309174104 9780309174107 |
language | English |
lccn | 98084670 |
oclc_num | 42417408 |
open_access_boolean | |
owner | MAIN DE-863 DE-BY-FWS |
owner_facet | MAIN DE-863 DE-BY-FWS |
physical | 1 online resource (xii, 227 pages) : illustrations |
psigel | ZDB-4-EBA |
publishDate | 1998 |
publishDateSearch | 1998 |
publishDateSort | 1998 |
publisher | National Academy Press, |
record_format | marc |
spelling | Research reactor aluminum spent fuel : treatment options for disposal / Milton Levenson, principal investigator ; Kevin D. Crowley, study director ; Board on Radioactive Waste Management, Commission on Geosciences, Environment, and Resources, National Research Council. Washington, D.C. : National Academy Press, 1998. 1 online resource (xii, 227 pages) : illustrations text txt rdacontent computer c rdamedia online resource cr rdacarrier data file rda Includes bibliographical references. Print version record. Use copy Restrictions unspecified star MiAaHDL Electronic reproduction. [S.l.] : HathiTrust Digital Library, 2010. MiAaHDL Master and use copy. Digital master created according to Benchmark for Faithful Digital Reproductions of Monographs and Serials, Version 1. Digital Library Federation, December 2002. http://purl.oclc.org/DLF/benchrepro0212 MiAaHDL digitized 2010 HathiTrust Digital Library committed to preserve pda MiAaHDL English. Research Reactor Aluminum Spent Fuel -- Copyright -- Foreword -- Preface -- Contents -- Summary -- FINDINGS RELATED TO THE SELECTION OF ALUMINUM SPENT FUEL TREATMENT OPTIONS -- FINDINGS RELATED TO WASTE-PACKAGE PERFORMANCE CRITERIA -- FINDINGS RELATED TO COSTS AND TIMING OF ALUMINUM SPENT FUEL TREATMENT OPTIONS -- CONCLUDING OBSERVATIONS -- 1 Background and Task -- TASK STATEMENT AND STUDY PROCESS -- ORGANIZATION OF THIS REPORT -- 2 Treatment Options for Aluminum Spent Nuclear Fuel -- BACKGROUND -- TREATMENT TECHNOLOGIES FOR ALUMINUM SPENT FUEL -- Direct Disposal Technologies -- HEU Dilution Technologies -- Advanced Treatment Technologies -- EVALUATING THE TREATMENT ALTERNATIVES -- TASK TEAM RECOMMENDATIONS -- RESPONSE TO FIRST CHARGE IN STATEMENT OF TASK -- 3 Waste-Package Performance Criteria -- BACKGROUND -- WASTE ACCEPTANCE CRITERIA -- OTHER REQUIREMENTS -- RESPONSE TO SECOND CHARGE IN STATEMENT OF TASK -- 2.3.20.2: Limits on Radionuclide Inventories in Multi-Element Canisters -- 2.3.21: Limits on Total Fissile Material in a Disposable Canister -- 2.3.22: Limits on Disposable Canister Criticality Potential -- CONCLUSIONS -- 4 Cost and Schedule -- TASK TEAM REPORT COST AND SCHEDULE ESTIMATES -- ALTERNATIVE COST STUDY -- COMPARISON OF TASK TEAM AND ALTERNATIVE COST STUDY ESTIMATES -- RESPONSE TO THIRD CHARGE IN STATEMENT OF TASK -- 5 Concluding Observations -- PHASED DECISION AND IMPLEMENTATION STRATEGY FOR TREATMENT OPTION SELECTION -- Spent Fuel Generation -- Spent Fuel Receipt and Storage -- Treatment and Interim Storage -- Transport and Repository Disposal -- Decontamination and Decommissioning -- Post-2015 Aluminum Spent Fuel Inventory -- PATH FORWARD -- References -- Appendix A Study Request Letter from DOE-Savannah River -- Appendix B Meeting Agendas and Participants -- Appendix C Charge to Consultants -- QUESTIONS TO EXPERTS. Criticality -- Proliferation -- Cost and Schedule -- Corrosion and Metallurgy -- Processing and Remote Handling -- Regulatory Waste Acceptance -- Appendix D Consultant Reports -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: JOHN AHEARNE -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: FRANCIS M. ALCORN -- TOPIC: COST AND SCHEDULE CONSULTANT: M.W. ANGVALL -- TOPIC: REGULATORY AND WASTE ACCEPTANCE CONSULTANT: ROBERT M. BERNERO -- Introduction -- Background -- Regulatory Approach for Yucca Mountain -- Evaluation of DOE Aluminum-Based Spent Fuel Alternatives -- Summary -- TOPIC: PROCESSING AND REMOTE HANDLING CONSIDERATIONS CONSULTANT: JOSEPH BYRD -- Introduction and Background -- Processing/Remote Handling Issues -- General Issues -- Conclusions and Recommendations -- References -- TOPIC: METALLURGY AND CORROSION CONSULTANT: R.L. DILLON -- Introduction -- Conclusions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: G. BRIAN ESTES -- References -- TOPIC: PROCESSING AND REMOTE SYSTEMS CONSULTANT: HARRY HARMON -- Introduction -- Responses -- References -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: VALERIE L. PUTMAN -- Introduction -- Conclusion -- Discussion -- Criticality Safety at Savannah River Site (SRS) -- Criticality Safety on Public Roads, Transport to Final Repository -- Criticality Safety at Final Repository -- Intact Canisters and Al-SNF, Initial Repository Conditions -- Degraded Canisters and/or Al-SNF, Long Term Repository Conditions -- Summary -- References -- Other Documents Reviewed -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: DAVID ROSSIN -- Proliferation Assessment -- Identification of Separated Fissile Material as a Proliferation Risk -- Container -- Repository -- Self-Protection Criterion -- Use of Processing for Waste Management. Of Findings -- TOPIC: METALLURGY AND CORROSION CONSULTANT: PAUL SHEWMON -- Introduction -- Processing -- Answers to Assigned Questions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: RICHARD I. SMITH -- General Comments -- Specific Comments -- Other Comments -- References -- Appendix E Biographical Sketches of Consultants -- Appendix F Documents Received in This Study. Radioactive waste disposal Management. Spent reactor fuels. http://id.loc.gov/authorities/subjects/sh85126529 Aluminum Isotopes. http://id.loc.gov/authorities/subjects/sh85003963 Combustibles nucléaires irradiés. TECHNOLOGY & ENGINEERING Power Resources Nuclear. bisacsh Aluminum Isotopes fast Radioactive waste disposal Management fast Spent reactor fuels fast Levenson, Milton. Crowley, Kevin D. National Research Council (U.S.). Board on Radioactive Waste Management. http://id.loc.gov/authorities/names/n83053793 Print version: Research reactor aluminum spent fuel. Washington, D.C. : National Academy Press, 1998 0309060494 (DLC) 98084670 (OCoLC)39192820 FWS01 ZDB-4-EBA FWS_PDA_EBA https://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&AN=2250 Volltext |
spellingShingle | Research reactor aluminum spent fuel : treatment options for disposal / Research Reactor Aluminum Spent Fuel -- Copyright -- Foreword -- Preface -- Contents -- Summary -- FINDINGS RELATED TO THE SELECTION OF ALUMINUM SPENT FUEL TREATMENT OPTIONS -- FINDINGS RELATED TO WASTE-PACKAGE PERFORMANCE CRITERIA -- FINDINGS RELATED TO COSTS AND TIMING OF ALUMINUM SPENT FUEL TREATMENT OPTIONS -- CONCLUDING OBSERVATIONS -- 1 Background and Task -- TASK STATEMENT AND STUDY PROCESS -- ORGANIZATION OF THIS REPORT -- 2 Treatment Options for Aluminum Spent Nuclear Fuel -- BACKGROUND -- TREATMENT TECHNOLOGIES FOR ALUMINUM SPENT FUEL -- Direct Disposal Technologies -- HEU Dilution Technologies -- Advanced Treatment Technologies -- EVALUATING THE TREATMENT ALTERNATIVES -- TASK TEAM RECOMMENDATIONS -- RESPONSE TO FIRST CHARGE IN STATEMENT OF TASK -- 3 Waste-Package Performance Criteria -- BACKGROUND -- WASTE ACCEPTANCE CRITERIA -- OTHER REQUIREMENTS -- RESPONSE TO SECOND CHARGE IN STATEMENT OF TASK -- 2.3.20.2: Limits on Radionuclide Inventories in Multi-Element Canisters -- 2.3.21: Limits on Total Fissile Material in a Disposable Canister -- 2.3.22: Limits on Disposable Canister Criticality Potential -- CONCLUSIONS -- 4 Cost and Schedule -- TASK TEAM REPORT COST AND SCHEDULE ESTIMATES -- ALTERNATIVE COST STUDY -- COMPARISON OF TASK TEAM AND ALTERNATIVE COST STUDY ESTIMATES -- RESPONSE TO THIRD CHARGE IN STATEMENT OF TASK -- 5 Concluding Observations -- PHASED DECISION AND IMPLEMENTATION STRATEGY FOR TREATMENT OPTION SELECTION -- Spent Fuel Generation -- Spent Fuel Receipt and Storage -- Treatment and Interim Storage -- Transport and Repository Disposal -- Decontamination and Decommissioning -- Post-2015 Aluminum Spent Fuel Inventory -- PATH FORWARD -- References -- Appendix A Study Request Letter from DOE-Savannah River -- Appendix B Meeting Agendas and Participants -- Appendix C Charge to Consultants -- QUESTIONS TO EXPERTS. Criticality -- Proliferation -- Cost and Schedule -- Corrosion and Metallurgy -- Processing and Remote Handling -- Regulatory Waste Acceptance -- Appendix D Consultant Reports -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: JOHN AHEARNE -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: FRANCIS M. ALCORN -- TOPIC: COST AND SCHEDULE CONSULTANT: M.W. ANGVALL -- TOPIC: REGULATORY AND WASTE ACCEPTANCE CONSULTANT: ROBERT M. BERNERO -- Introduction -- Background -- Regulatory Approach for Yucca Mountain -- Evaluation of DOE Aluminum-Based Spent Fuel Alternatives -- Summary -- TOPIC: PROCESSING AND REMOTE HANDLING CONSIDERATIONS CONSULTANT: JOSEPH BYRD -- Introduction and Background -- Processing/Remote Handling Issues -- General Issues -- Conclusions and Recommendations -- References -- TOPIC: METALLURGY AND CORROSION CONSULTANT: R.L. DILLON -- Introduction -- Conclusions -- References -- TOPIC: COST AND SCHEDULE CONSULTANT: G. BRIAN ESTES -- References -- TOPIC: PROCESSING AND REMOTE SYSTEMS CONSULTANT: HARRY HARMON -- Introduction -- Responses -- References -- TOPIC: NUCLEAR CRITICALITY SAFETY CONSULTANT: VALERIE L. PUTMAN -- Introduction -- Conclusion -- Discussion -- Criticality Safety at Savannah River Site (SRS) -- Criticality Safety on Public Roads, Transport to Final Repository -- Criticality Safety at Final Repository -- Intact Canisters and Al-SNF, Initial Repository Conditions -- Degraded Canisters and/or Al-SNF, Long Term Repository Conditions -- Summary -- References -- Other Documents Reviewed -- TOPIC: PROLIFERATION ASPECTS OF THE TREATMENT OPTIONS CONSULTANT: DAVID ROSSIN -- Proliferation Assessment -- Identification of Separated Fissile Material as a Proliferation Risk -- Container -- Repository -- Self-Protection Criterion -- Use of Processing for Waste Management. Radioactive waste disposal Management. Spent reactor fuels. http://id.loc.gov/authorities/subjects/sh85126529 Aluminum Isotopes. http://id.loc.gov/authorities/subjects/sh85003963 Combustibles nucléaires irradiés. TECHNOLOGY & ENGINEERING Power Resources Nuclear. bisacsh Aluminum Isotopes fast Radioactive waste disposal Management fast Spent reactor fuels fast |
subject_GND | http://id.loc.gov/authorities/subjects/sh85126529 http://id.loc.gov/authorities/subjects/sh85003963 |
title | Research reactor aluminum spent fuel : treatment options for disposal / |
title_auth | Research reactor aluminum spent fuel : treatment options for disposal / |
title_exact_search | Research reactor aluminum spent fuel : treatment options for disposal / |
title_full | Research reactor aluminum spent fuel : treatment options for disposal / Milton Levenson, principal investigator ; Kevin D. Crowley, study director ; Board on Radioactive Waste Management, Commission on Geosciences, Environment, and Resources, National Research Council. |
title_fullStr | Research reactor aluminum spent fuel : treatment options for disposal / Milton Levenson, principal investigator ; Kevin D. Crowley, study director ; Board on Radioactive Waste Management, Commission on Geosciences, Environment, and Resources, National Research Council. |
title_full_unstemmed | Research reactor aluminum spent fuel : treatment options for disposal / Milton Levenson, principal investigator ; Kevin D. Crowley, study director ; Board on Radioactive Waste Management, Commission on Geosciences, Environment, and Resources, National Research Council. |
title_short | Research reactor aluminum spent fuel : |
title_sort | research reactor aluminum spent fuel treatment options for disposal |
title_sub | treatment options for disposal / |
topic | Radioactive waste disposal Management. Spent reactor fuels. http://id.loc.gov/authorities/subjects/sh85126529 Aluminum Isotopes. http://id.loc.gov/authorities/subjects/sh85003963 Combustibles nucléaires irradiés. TECHNOLOGY & ENGINEERING Power Resources Nuclear. bisacsh Aluminum Isotopes fast Radioactive waste disposal Management fast Spent reactor fuels fast |
topic_facet | Radioactive waste disposal Management. Spent reactor fuels. Aluminum Isotopes. Combustibles nucléaires irradiés. TECHNOLOGY & ENGINEERING Power Resources Nuclear. Aluminum Isotopes Radioactive waste disposal Management Spent reactor fuels |
url | https://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&AN=2250 |
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