LEADER 06184nam 2200637Ia 450 001 9910827551803321 005 20240416233753.0 010 $a0-309-17410-4 010 $a1-280-18692-5 010 $a9786610186921 010 $a0-309-59180-5 010 $a0-585-03947-X 035 $a(CKB)110986584752278 035 $a(SSID)ssj0000236561 035 $a(PQKBManifestationID)11191665 035 $a(PQKBTitleCode)TC0000236561 035 $a(PQKBWorkID)10173400 035 $a(PQKB)11678566 035 $a(MiAaPQ)EBC3376320 035 $a(Au-PeEL)EBL3376320 035 $a(CaPaEBR)ebr10055434 035 $a(OCoLC)923262873 035 $a(EXLCZ)99110986584752278 100 $a19980528d1998 uy 0 101 0 $aeng 135 $aurcn||||||||| 181 $ctxt 182 $cc 183 $acr 200 00$aResearch reactor aluminum spent fuel $etreatment options for disposal /$fMilton Levenson, principal investigator ; Kevin D. Crowley, study director ; Board on Radioactive Waste Management, Commission on Geosciences, Environment, and Resources, National Research Council 205 $a1st ed. 210 $aWashington, D.C. $cNational Academy Press$d1998 215 $axii, 227 p. $cill 300 $aBibliographic Level Mode of Issuance: Monograph 311 $a0-309-06049-4 320 $aIncludes bibliographical references. 327 $aResearch 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. 327 $aCriticality -- 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. 327 $aSummary 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. 606 $aAluminum$xIsotopes 606 $aRadioactive waste disposal 606 $aSpent reactor fuels 615 0$aAluminum$xIsotopes. 615 0$aRadioactive waste disposal. 615 0$aSpent reactor fuels. 676 $a621.48/38 701 $aLevenson$b Milton$01616143 701 $aCrowley$b Kevin D$01615366 712 02$aNational Research Council (U.S.).$bBoard on Radioactive Waste Management. 801 0$bMiAaPQ 801 1$bMiAaPQ 801 2$bMiAaPQ 906 $aBOOK 912 $a9910827551803321 996 $aResearch reactor aluminum spent fuel$93946703 997 $aUNINA