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Criticality Safety Analysis of Nuclear-Cycle Facilities for Weapons-Grade Plutonium PDF

108 Pages·2001·0.72 MB·English
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ORNL/TM-2001/262 Investigations and Recommendations on the Use of Existing Experiments in Criticality Safety Analysis of Nuclear Fuel Cycle Facilities for Weapons-Grade Plutonium B. T. Rearden K. R. Elam DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of Energy (DOE) Information Bridge. Web site http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source. National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900 E-mail [email protected] Web site http://www.ntis.gov/support/ordernowabout.htm Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange (ETDE) representatives, and International Nuclear Information System (INIS) representatives from the following source. Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831 Telephone 865-576-8401 Fax 865-576-5728 E-mail [email protected] Web site http://www.osti.gov/contact.html 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 usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States government or any agency thereof. ORNL/TM-2001/262 Nuclear ScienceandTechnologyDivision(94) Investigations and Recommendations on the Use of Existing Experiments in Criticality Safety Analysis of Nuclear Fuel Cycle Facilities for Weapons-Grade Plutonium B. T. Rearden and K. R. Elam Oak Ridge NationalLaboratory, PO Box2008, Oak Ridge, TN 37831-6370 Date Published: June 2002 Prepared bythe OAKRIDGE NATIONALLABORATORY Oak Ridge, Tennessee 37831 managed and operated by UT-Battelle, LLC for the U.S. DEPARTMENT OFENERGY under contract DE-AC05-00OR22725 CONTENTS Page LIST OFFIGURES......................................................................................................................v LIST OFTABLES.....................................................................................................................vii ACKNOWLEDGMENTS...........................................................................................................ix EXECUTIVE SUMMARY.........................................................................................................xi 1. INTRODUCTION................................................................................................................1 2. SENSITIVITY AND UNCERTAINTY BASED CRITICALITY VALIDATION TECHNIQUES.....................................................................................................................3 2.1. SENSITIVITY THEORY...........................................................................................3 2.2. SENSITIVITY-BASED INTEGRALPARAMETERS...............................................5 2.3. UNCERTAINTY-BASED INTEGRALPARAMETERS............................................7 2.4. AREAOF APPLICABILITY USING INTEGRALPARAMETER TECHNIQUES...9 2.5. SUMMARY OFS/U ANALYSIS TECHNIQUES....................................................10 3. PROTOTYPICALSENSITIVITY AND UNCERTAINTY ANALYSIS CODES FOR CRITICALITY SAFETY WITH THESCALE CODE SYSTEM........................................13 3.1. SEN1 SEQUENCE...................................................................................................13 3.2. SEN3 SEQUENCE...................................................................................................13 3.3. SENSITIVITY TO RESONANCE-SHIELDED MULTIGROUP CROSS SECTIONS..................................................................................................14 3.4. SENSITIVITY DATA..............................................................................................14 3.5. CANDE ..........................................................................................................14 4. SAMPLE DESIGN APPLICATIONS FOR THE MIXED-OXIDE FUELFABRICATION FACILITY..........................................................................................................................15 5. DEVELOPMENT OFCRITICALEXPERIMENTDATABASE........................................19 5.1. PLUTONIUM SYSTEMS..........................................................................................19 5.1.1. PlutoniumMetalSystems..............................................................................19 5.1.2. PlutoniumOxide Systems..............................................................................21 5.2. MIXED PLUTONIUM AND URANIUM SYSTEMS................................................21 5.2.1. Mixed Plutoniumand UraniumSolutionSystems..........................................21 5.2.2. Mixed Plutoniumand Uranium FuelPin Lattices...........................................22 5.2.3. Mixed Plutoniumand UraniumSolid Systems...............................................23 5.2.4. Mixed Plutoniumand UraniumMetalSystem...............................................24 5.3. LOW-ENRICHED URANIUM OXIDE SYSTEMS...................................................24 6. RESULTS...........................................................................................................................25 6.1. AOA3 – PUO POWDERS........................................................................................25 2 iii CONTENTS (continued) Page 6.2. AOA4 – MOX POWDERS........................................................................................32 6.2.1. Nuclide-Reaction-Specific Analysis ofAOA4-2...........................................45 6.2.2. Analysis ofMass Variations for AOA4-4.....................................................48 6.2.3. IdentificationofAdditionalBenchmarks for 238U..........................................53 7. CONCLUSIONS................................................................................................................55 8. REFERENCES...................................................................................................................57 APPENDIX A— COMPLETENESSPARAMETER................................................................61 APPENDIX B — INTEGRALVALUES...................................................................................65 iv LIST OF FIGURES Figure Page 1. Energy-dependent-sensitivityprofiles for 239Pu fissionfor AOA4-2, Experiment 4 from Table 5 ofNSE55,and Experiment 1 fromTable 4ofNSE55.............................................47 2. Energy-dependent-sensitivityprofiles for 239Pufission for AOA4-2 and AOA4-4.............49 3. Energy-dependent-sensitivityprofiles for 239Pu fissionfor varying mass cases of AOA4-4 and benchmark experiment PU-29-1....................................................................51 4. Energy-dependent-sensitivityprofiles for 238U capture for varying mass cases of AOA4-4 and benchmark experiment PU-29-1....................................................................52 5. Energy-dependent-sensitivityprofiles for 238U capture for AOA4-4, AOA4-4-P8, PU-29-1 and LEU-COMP-THERM-049-01........................................................................54 v vi LIST OF TABLES Table Page 1. SummaryofS/U parameters...............................................................................................11 2. Proposed designapplicationspecification for AOA 3 (PuO powders)ofMFFF.................17 2 3. Proposed designapplicationspecification for AOA 4 (MOX powders)ofMFFF................18 4. Summarydescriptionofbenchmark experiments................................................................20 5. Calculated characteristics ofdesignsystems fromAOA3...................................................25 6. Experimentalconfigurations withc coefficients ≥ 0.8 for AOA3-1...................................27 k 7. Experimentalconfigurations withc coefficients ≥ 0.8 for AOA3-2...................................28 k 8. Experimentalconfigurations withc coefficients ≥ 0.8 for AOA3-3...................................30 k 9. Calculated characteristics ofdesignsystems fromAOA4...................................................32 10. Experimentalconfigurations withc coefficients ≥ 0.8 for AOA4-1...................................34 k 11. Experimentalconfigurations withc coefficients ≥ 0.8 for AOA4-2...................................36 k 12. Experimentalconfigurations withc coefficients ≥ 0.8 for AOA4-3...................................38 k 13. Experimentalconfigurations withc coefficients ≥ 0.7 for AOA4-4...................................40 k 14. Experimentalconfigurations withc coefficients ≥ 0.7 for AOA4-4-P163..........................41 k 15. Experimentalconfigurations withc coefficients ≥ 0.8 for AOA4-4-P40............................42 k 16. Experimentalconfigurations withc coefficients ≥ 0.8 for AOA4-4-P8.............................43 k 17. Properties ofsystems considered for nuclide-reaction-specific analysis ofAOA4-2...........45 18. Nuclide-reaction-specific-sensitivitydata for AOA4-2 withT(c ) values k for benchmarks NSE55T4-01 and NSE55T5-04.................................................................46 19. Nuclide-reaction-specific-sensitivitydata for the various masses analyzed for AOA4-4 withT(c ) values for benchmark PU-29-1............................................................50 k vii LIST OF TABLES (continued) Table Page A.1. Completeness parameter (R) for eachdesignsystemusing the 318-benchmark- experiment set..................................................................................................................64 B.1 Tabulated c values and calculated parameters for designsystems and benchmark k experiments......................................................................................................................67 B.2 Tabulated E values and calculated parameters for designsystems and benchmark sum experiments......................................................................................................................79 viii

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