LEADER 00934cam0 2200265 450 001 E600200005300 005 20180321110450.0 100 $a20040929d1967 |||||ita|0103 ba 101 $aita 102 $aIT 200 1 $aStoria d'Italia dal 1871 al 1915$fBenedetto Croce 210 $aBari$cLaterza$d1967 215 $aVIII,336 p.$d18 cm 225 2 $aOpere di Benedetto Croce in edizione economica$v9 410 1$1001LAEC00019614$12001 $a*Opere di Benedetto Croce in edizione economica$v9 700 1$aCroce$b, Benedetto <1866-1952>$3AF00003357$4070$09641 801 0$aIT$bUNISOB$c20180321$gRICA 850 $aUNISOB 852 $aUNISOB$j900$m118759 912 $aE600200005300 940 $aM 102 Monografia moderna SBN 941 $aM 957 $a900$b004195$gSi$d118759$hNegro$rdono$1catenacci$2UNISOB$3UNISOB$420040929121031.0$520180321110435.0$6bethb 996 $aStoria d'Italia dal 1871 al 1915$976777 997 $aUNISOB LEADER 00761cas0 2200265 450 001 SOBP300121 005 20181108090933.0 011 $a11210311 100 $a20050505b19762010|||||ita|0103 ba 101 $aita 102 $aIT 110 $aa 200 1 $a<>delfino$ebimestrale del Centro italiano di solidarietà 207 1$a1976-2010 210 $aRoma$cCentro italiano di solidarietà 215 $av.$d28 cm 801 0$aIT$bUNISOB$c20181108$gRICA 850 $aUNISOB 852 $aUNISOB$jIt$m31838 912 $aSOBP300121 940 $aS 120 Periodico SBN 941 $aS 957 $aIt$b000037$gCON$d31838$racquisto$1carrano$2UNISOB$3UNISOB$420061004094411.0$520150805105503.0$6bethb 996 $aDelfino$9892718 997 $aUNISOB LEADER 06597nam 2200745 a 450 001 9910957625203321 005 20251116140752.0 010 $a9786610191765 010 $a9780309174923 010 $a0309174929 010 $a9781280191763 010 $a1280191767 010 $a9780309590105 010 $a0309590108 010 $a9780585085395 010 $a0585085390 035 $a(CKB)110986584751960 035 $a(OCoLC)614743023 035 $a(CaPaEBR)ebrary10055536 035 $a(SSID)ssj0000150858 035 $a(PQKBManifestationID)11162912 035 $a(PQKBTitleCode)TC0000150858 035 $a(PQKBWorkID)10317339 035 $a(PQKB)11293817 035 $a(MiAaPQ)EBC3376368 035 $a(Au-PeEL)EBL3376368 035 $a(CaPaEBR)ebr10055536 035 $a(CaONFJC)MIL19176 035 $a(OCoLC)923263260 035 $a(Perlego)4736338 035 $a(BIP)47377449 035 $a(EXLCZ)99110986584751960 100 $a19961211d1997 uy 0 101 0 $aeng 135 $aurcn||||||||| 181 $ctxt 182 $cc 183 $acr 200 00$aEvaluation of the U.S. Department of Energy's alternatives for the removal and disposition of molten salt reactor experiment fluoride salts /$fMolten Salt Panel of the Committee on Remediation of Buried and Tank Wastes, Board on Radioactive Waste Management, Commission of Geosciences, Environment, and Resources, National Research Council 205 $a1st ed. 210 $aWashington, D.C. $cNational Academy Press$d1997 215 $a1 online resource (147 p.) 300 $aBibliographic Level Mode of Issuance: Monograph 311 08$a9780309056847 311 08$a0309056845 320 $aIncludes bibliographical references. 327 $aEvaluation of the U.S. Department of Energy's -- Copyright -- Acknowledgments -- Preface -- Contents -- Executive Summary -- THE MSRE FACILITY AND CURRENT REMEDIATION PLANS -- PURPOSE OF THIS REPORT -- SUMMARY OF FINDINGS ON THREE MAJOR ISSUES -- MAJOR CONCLUSIONS -- MAJOR RECOMMENDATIONS -- 1-Introduction -- CURRENT STATUS OF THE MSRE -- ROLE OF THE NATIONAL RESEARCH COUNCIL -- SCOPE AND ORGANIZATION OF THIS REPORT -- 2-Radiolysis and Nuclear Reactions -- RADIOACTIVE SOURCE TERMS -- RADIATION EFFECTS AND GENERAL COMMENTS -- Radiation-Induced Liberation of Fluorine and Uranium Hexafluoride Gases -- Radiation Decomposition of Solid Uranium Hexafluoride -- Long-Term Effects of Leaving Plutonium in the Salt After Uranium Removal -- EXCESS OF REDUCING SPECIES IN THE SALT AND HAZARDS OF SIMPLE REMELTING -- 3-Fluoride Salt Chemistry, Partitioning, and System Corrosion -- CHEMISTRY RELEVANT TO THE PRESENT STATUS -- Chemical Consequences of Radiolysis -- PARTITIONING OF URANIUM FROM THE SALT -- PLUTONIUM PARTITIONING BY FLUORINATION -- NONFLUORINATION OPTION FOR PLUTONIUM SEPARATION -- SYSTEM CORROSION ISSUES -- Radiation-Induced Corrosion Questions -- 4-Preferred Technical Approach -- COMMENTS ON PROCESS STEPS -- DEVELOPMENT OF A PREFERRED APPROACH -- 5-Comments on Specific Separation Technologies -- FLUORINATION -- Direct Fluorination -- Hydrofluorination -- Alternative Fluorinating Agents -- ELECTROREFINING -- DISTILLATION OF MOLTEN SALT -- AQUEOUS DISSOLUTION AND SEPARATION -- Criticality Concerns in Aqueous Processing -- Fluoride Removal -- Conclusions on Aqueous Processing -- STABILIZATION TECHNOLOGIES -- 6-Nuclear Criticality Considerations -- CRITICALITY ISSUES IN PROCESSING -- CRITICALITY HAZARD OF REMELTING THE FLUORIDE SALTS IN THE DRAIN TANKS -- RATIONALE FOR TECHNICAL INSIGNIFICANCE OF A CRITICALITY EXCURSION -- CONCLUDING COMMENTS. 327 $a7-Strategic Alternatives -- PERMANENT DISPOSAL IN THE DRAIN TANKS -- DISPOSAL OF ALL KEY CONTAMINANTS IN THE FEDERAL REPOSITORY -- DISPOSAL OF KEY CONTAMINANTS IN THE SALT RESIDUE IN THE WASTE ISOLATION PILOT PLANT (WIPP) -- DISPOSAL OF KEY CONTAMINANTS IN SALT RESIDUE IN THE FEDERAL REPOSITORY -- REUSE OF THE SALT -- INTERIM STORAGE -- RATIONALE FOR REJECTING THE FIRST SIX ALTERNATIVES -- INTERIM VERSUS PERMANENT STORAGE AND DISPOSAL -- 8-Management of MSRE Hazards -- CURRENT HAZARDS -- HAZARD MANAGEMENT ACTIVITIES -- CRUCIAL ROLE OF FURTHER ACTIVITIES FOR CONDITION AND PROCESS ASSESSMENT -- MAJOR RECOMMENDATION CONCERNING HAZARDS -- DETAILED RECOMMENDATIONS REGARDING HAZARDS -- 9-Summary and Responses to Questions in Statement of Task -- TECHNICAL SUMMARY -- STRATEGY FOR REMEDIATION -- Where Is the Uranium? -- How Can a Condition Assessment Affect Remediation Plans? -- The Panel's Preferred Alternative -- Hazards -- RESPONSES TO QUESTIONS IN STATEMENT OF TASK -- Question 1 -- Question 2 -- The Consequences of Failure to Complete According to Plan -- Cost Estimates -- A Possible Strategy -- Question 3 -- PANEL PERSPECTIVE -- OVERALL CONCLUSION -- References -- Appendixes -- Appendix A-List of Materials Reviewed -- Appendix B-Alternative Fluorinating Agents -- Appendix C-Contamination Concerns Relating to Radon Gas Spread -- Appendix D-Use of a Nuclear Poison to Inhibit Nuclear Criticality -- Appendix E-Hazard Scoping of Major Actions for Remediation -- Appendix F-List of Acronyms and Abbreviations -- Appendix G-Glossary -- Appendix H-Biographical Sketches of Molten Salt Panel Members and Consultants -- Consultants. 330 $aThis book discusses the technical alternatives for cleanup of radioactive fluoride salts that were the fuel for the Molten Salt Reactor Experiment, a novel nuclear reactor design that was tested in the 1960s at the Oak Ridge National Laboratory in Tennessee. These fluoride salts pose an unusual cleanup challenge. The book discusses alternatives for processing and removing the salts based on present knowledge of fluoride salt chemistry and nuclear reactions of the radioactive constituents. 517 3 $aAlternatives for the removal and disposition of molten salt reactor experiment fluoride salts 606 $aRadioactive waste disposal$zUnited States 606 $aMolten salt reactors 606 $aFluorides 615 0$aRadioactive waste disposal 615 0$aMolten salt reactors. 615 0$aFluorides. 676 $a363.72/89 712 02$aNational Research Council (U.S.).$bCommittee on Remediation of Buried and Tank Wastes.$bMolten Salt Panel. 801 0$bMiAaPQ 801 1$bMiAaPQ 801 2$bMiAaPQ 906 $aBOOK 912 $a9910957625203321 996 $aEvaluation of the U.S. Department of Energy's alternatives for the removal and disposition of molten salt reactor experiment fluoride salts$94354122 997 $aUNINA