Zirconium Diboride Burnable Absorbers Using Multiple Concentrations (English)
- New search for: Bryson, D.
- New search for: ANS
- New search for: Bryson, D.
- New search for: ANS
In:
Advances in nuclear fuel management
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686-692
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2009
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ISBN:
- Conference paper / Print
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Title:Zirconium Diboride Burnable Absorbers Using Multiple Concentrations
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Contributors:Bryson, D. ( author ) / ANS
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Conference:Topical Meeting; 4th, Advances in nuclear fuel management ; 2009 ; Hilton Head Island, SC
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Published in:Advances in nuclear fuel management ; 686-692
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Publisher:
- New search for: Curran
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Place of publication:New York
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Publication date:2009-01-01
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Size:7 pages
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Remarks:Includes bibliographical references and index
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ISBN:
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Type of media:Conference paper
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Type of material:Print
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Language:English
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Keywords:
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Source:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents conference proceedings
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 1
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Mitigation of CIPS Risk Through Core Design OptimizationKern, B.J. / ANS et al. | 2009
- 9
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Optimum In-core Power Sharing with Multi-cycle Coupling EffectYamamoto, A. / Iwata, T. / Yamane, Y. / ANS et al. | 2009
- 22
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Utilization of Temperature Spectral Effects in Core DesignBishop, T. / Brown, J.A. / ANS et al. | 2009
- 31
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Design and Optimization of an Equilibrium Reload with MOX Fuel with Minor ActinidesFrancois, J.-L. / Guzman, J.-R. / Martin-del-Campo, C. / Palomera, M.-A. / ANS et al. | 2009
- 41
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High-Fidelity System Modeling Of Advanced Nuclear Energy Systems Approaching A Zeronuclear-Waste LimitTsvetkov, P.V. / ANS et al. | 2009
- 48
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A Minimal-Content Gadolinia in Above-5wt% Enrichment Fuel for Criticality Safety in Next-Generation LWRYoshioka, K.-i. / Watanabe, S. / Mitsuhashi, I. / Gunji, S. / Yamaokaa, M. / Hiraiwab, K. / ANS et al. | 2009
- 57
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Criticality Safety Issues Associated with Uranium Enriched Up to Ten Weight PercentLancastera, D. / Romboughb, C. / Alcornc, F. / McLaughlind, T.P. / ANS et al. | 2009
- 68
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Exploratory Studies for Challenges to Design Constraints with Higher EnrichmentKarve, A.A. / Sloma, T.N. / Stachowski, R.E. / Fawcett, R.M. / ANS et al. | 2009
- 79
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The Concept of Erbia Bearing Super-High-Burnup FuelSugimura, N. / Imamura, M. / Moria, M. / Yamasakib, M. / ANS et al. | 2009
- 87
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The Outline of Development Project on Erbia Bearing Super-High-Burnup FuelYamasaki, M. / Kuroishia, T. / Takedab, T. / Yamamotoc, A. / Unesaki, H. / Sanod, T. / Morie, M. / ANS et al. | 2009
- 98
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Verification of SHIKOKU Code Based on Axially Simplified Method of Characteristics in Three-Dimensional GeometryGiho, A. / Sakai, K. / Imamuraa, Y. / Sakuragi, H. / Miyawakib, K. / ANS et al. | 2009
- 116
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Validation of NFI BWR Fuel Assembly Design Code NEUPHYS with Critical ExperimentKanayama, Y. / Matsuoka, S. / Ito, T. / ANS et al. | 2009
- 129
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Validation of NFI BWR Nuclear Design system for MOX loading Core Analysis: Tracking Analysis of Gundremmingen Unit BTokashiki, M. / Matsuoka, S. / Ito, T. / ANS et al. | 2009
- 145
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Application of SIMULATE-3K to PWR Reactivity Insertion AccidentEller, J.L. / ANS et al. | 2009
- 162
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Monte Carlo Analysis of Degraded High-Density Spent Fuel Storage RacksMetwally, W.A. / Mills, V.W. / ANS et al. | 2009
- 171
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Analysis of Irradiated-Fuel Compositions of a BWR 9x9-7 UO^2 Fuel AssemblyAndo, Y. / Yamamoto, T. / Sasagawa, M. / ANS et al. | 2009
- 182
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Verification and Validation of AEGIS/SCOPE2 In-Core Fuel Management System with ENDF/B-VL8 and ENDF/B-VIL0 LibrariesTatsumi, M. / Ohokaa, Y. / Sugimura, N. / Tabuchi, M. / ANS et al. | 2009
- 194
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First GNF2 Advantage™ Reload Experience For Fitzpatrick Cycle 19 DesignYilmaz, S. / Schmitt, B. / Trosmana, L. / Szwarc, K. / ANS et al. | 2009
- 200
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Environmentally Correct Spent Nuclear Fuel Dry Interim Storage InstallationRomanatoa, L.S. / Rzyski, B.M. / ANS et al. | 2009
- 209
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Advanced Dryout Correlation and Cpr Methodology for Westinghouse Svea-96 Optima3 FuelBergmann, U. / Adamsson, C. / Norback, G. / ANS et al. | 2009
- 226
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SNF: Spent Fuel Analyses Based On CASMO/SIMULATE In-Core Fuel ManagementBecker, A. / Antona, G. / Borresen, S. / ANS et al. | 2009
- 238
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Investigation of Nuclear Fuel Design with the N-Streaming ConceptCheng, H. / Land, R. / Ljungblad, A. / ANS et al. | 2009
- 246
-
The Pearls™ Loading Pattern Search Tool in PracticePopa, F. / ANS et al. | 2009
- 256
-
Minimum Shuffling Model In The Bwr Loading Pattern Optimization Code Fineload-3Fukao, A. / ANS et al. | 2009
- 267
-
Advanced ePrometheus™ Gnf Fuel Cycle Optimization ToolYilmaz, S. / Kvaall, G. / Suttona, S. / Huffb, G. / ANS et al. | 2009
- 273
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Performance Analysis Of Discontinuous Penalty Function Based Simulated AnnealingPark, T.K. / Joo, H.G. / Kim, C.H. / ANS et al. | 2009
- 286
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Development of a New Gnf Shuffling Sequence System, ``ePimetheus''Sato, H. / Tojo, M. / Iwamotoa, T. / Elam, J. / ANS et al. | 2009
- 298
-
Development of Multi-Stage Stochastic PWR Loading Pattern Search Code SAMPLSIshitani, K. / Adachi, M. / Uenoa, J. / Yamamoto, A. / ANS et al. | 2009
- 310
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Genetic Algorithms To Automatically Optimize PWR Fuel Management CalculationsAlim, F. / Yilmaz, S. / Ivanov, K. / Levine, S.H. / ANS et al. | 2009
- 323
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Genetic Algorithms Approach for Radial Fuel Lattice Optimazation in BWRsCarmona, R. / Martin-del-Campo, C. / Oropeza, I. / Francois, J.-L. / ANS et al. | 2009
- 334
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Highly Constrained Loading Pattern Searches with ROSAVerhagen, F.C.M. / Wakker, P.H. / ANS et al. | 2009
- 346
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Development of a Graphical User Interface for In-Core Fuel Management using MCODERomano, P.K. / Forget, B. / Newton, T.H. / ANS et al. | 2009
- 359
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COPERNICUS: A Multi-Cycle Nuclear Fuel Optimization Code Based on Coupled In-core ConstraintsKropaczek, D.J. / ANS et al. | 2009
- 374
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BWR In-core Fuel Management Optimization using Parallel Simulated Annealing in FORMOSA-BHays, R. / Turinsky, P. / ANS et al. | 2009
- 386
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Added Features and MPI-Based Parallelization of The FORMOSA-L Lattice Loading Optimization CodeHernandez-Noyola, H. / Maldonado, G.I. / ANS et al. | 2009
- 394
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``MARLA'' - BWR Shuffle Design and Licensing-Grade SDM AnalysisKnott, D. / Oyarzun, C. / ANS et al. | 2009
- 412
-
The Industrial Sodium Cooled Fast ReactorBays, S.E. / Zhang, H. / Zhao, H. / ANS et al. | 2009
- 429
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Minor Actinide Recycle in Sodium Cooled Fast Reactors Using Heterogeneous TargetsBays, S. / Medvedev, P. / Pope, M. / Ferrer, R. / Asgaria, M. / Forget, B. / ANS et al. | 2009
- 446
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An Evaluation of the Implementation of Blended Uranium Fuel in PWR CoresNaugle, K. / Catalanotto, B. / ANS et al. | 2009
- 462
-
Comparison of 12-month vs Two Year Fuel Cycle with GNF2 FuelPinchuka, N. / Rubinaccio, G. / ANS et al. | 2009
- 469
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A Minimum Hot Excess Core Design Strategy For ESBWRKarve, A.A. / Fawcett, R.M. / ANS et al. | 2009
- 487
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Exercising The AETNA02 Natural Circulation Loop Model for ESBWRKarve, A.A. / Lamas, J.A. / Godfrey, A.T. / Moore, B.R. / ANS et al. | 2009
- 494
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Fuel Management Simulations for a Plutonium-Thorium Fuel Cycle in a CANDU® 6 ReactorMao, J. / Chan, P.S.W. / Kuran, S. / ANS et al. | 2009
- 509
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Selection Of Isotopes And Elements For Fuel Cycle AnalysisPiet, S.J. / ANS et al. | 2009
- 527
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Advanced LWR Fuel Testing Capabilities in the ORNL High Flux Isotope ReactorOtt, L.J. / McDuffee, J.L. / Spellman, D.J. / ANS et al. | 2009
- 536
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VISION: Verifiable Fuel Cycle Simulation ModelJacobson, J.J. / Matthern, G.E. / Piet, S.J. / Shropshirea, D.E. / Yacout, A.M. / ANS et al. | 2009
- 556
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A Fuel Cycle Scenario Assessment For The UK Covering The Next 100 YearsGregg, R. / ANS et al. | 2009
- 575
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Lessons Learned on Fuel Cycle Simulation DynamicsPiet, S.J. / Dixon, B.W. / Jacobson, J.J. / Matthern, G.E. / Shropshire, D.E. / ANS et al. | 2009
- 595
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Use of Core Analyses in Assessments of Fuel Failure Risk Due to Pellet-Cladding InteractionNesbita, S. / Kennardb, M. / Yagnik, S. / ANS et al. | 2009
- 615
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BWR Core Design Strategies to Mitigate Control Rod Induced Shadow CorrosionEnica, A. / ANS et al. | 2009
- 626
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``ONUS'': ON-line Fuel Performance Surveillance - Linking Studsvik's CMS with UK NNL's ENIGMA-BWorrall, A. / DiGiovine, A.S. / ANS et al. | 2009
- 638
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Integrating Advanced Recycling Centers into the Nuclear Fuel CycleBerger, J. / Loewena, E. / Benedict, R. / ANS et al. | 2009
- 651
-
The Use Of Response Surface Methodology (RSM) To Scope Gen IV Super Critical Water Reactor (SCWR) Thorium Fuel Cycle ParametersDworschak, R.G. / ANS et al. | 2009
- 671
-
Minimizing the Fissile Inventory of the Molten Salt Fast ReactorMerle-Lucotte, E. / Heuer, D. / Allibert, M. / Doligez, X. / Ghetta, V. / ANS et al. | 2009
- 686
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Zirconium Diboride Burnable Absorbers Using Multiple ConcentrationsBryson, D. / ANS et al. | 2009
- 693
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Thermal Hydraulics and Economic Potential of High Performance Annular Fuel in PWRsZhang, L. / Beccherle, J. / Hejzlar, P. / Kazimi, M. / ANS et al. | 2009
- 708
-
A Simple Algorithm for Designing MOX Fuel with Minor ActinidesGuzman, J.-R. / Francois, J.-L. / Martin-del-Campo, C. / ANS et al. | 2009
- 718
-
CASMO-5 Gamma LibraryGheorghiu, H.-N.M. / Rhodes, J. / ANS et al. | 2009
- 725
-
Testing 3-D Nodal Codes SIMULATE-3/5 For Refueling Shutdown Margin Predictions With CASMO-5MXu, Z. / Rhodes, J. / Smith, K. / ANS et al. | 2009
- 736
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Benchmarking the HELIOS-2 ENDF/B-VII Library: B&W-1484 and DIMPLE S-06 CriticalsWemple, C.A. / ANS et al. | 2009
- 751
-
Two-Dimensional Recycling Reactor Whole Core Benchmark ProblemDouglass, S. / Rahnemaa, F. / Szilard, R. / ANS et al. | 2009
- 764
-
ENDF/B-VII Nuclear Data Libraries for SCALE 6Williams, M.L. / Ilas, G. / ANS et al. | 2009
- 772
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Benchmarking of CASMO-5 ENDF/B-VII Nuclear Data Against Critical ExperimentsRhodes, J. / Xu, Z. / Lee, D. / Smith, K. / ANS et al. | 2009
- 784
-
Cycle Specific BWR Reload Analysis Using SIMULATE-3KJonsson, C. / Belblidia, L. / Grandia, G. / Kettunenb, T. / Moberg, L. / ANS et al. | 2009
- 799
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Validation of SCALE/TRITON and HELIOS for prediction of isotopic inventories of high burnup LWR fuelTittelbach, S. / Mispagel, T. / Phlippen, P.-W. / ANS et al. | 2009
- 809
-
A Best-Estimate Coupled Code for Reactor Safety Analyses Using SIMULATE-3K and RELAP5-3DJudd, J. / Grandia, G. / Redwine, J. / ANS et al. | 2009
- 820
-
Modelling of Venus Reactor Configurations 9 and 9/1 using CASMO-4Grove, C. / ANS et al. | 2009
- 830
-
Examination of Multigroup Fission Yield Data Using PENBURN/PENTRAN Fuel Depletion and Transport CodesManalo, K. / Plower, T. / Rowe, M. / Sjoden, G. / ANS et al. | 2009
- 839
-
Probabilistic Rop Detector Layout Optimization Using Simulated Annealing Technique For CANDU® ReactorsKastanya, D. / Caxaj, V. / ANS et al. | 2009
- 851
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Improved Water Volume Addition Predictions In Application Providing Plant Operations GuidancePihl, G.G. / Clark, B.R. / Johnson, M.K. / Wilson, L.A. / ANS et al. | 2009
- 860
-
Implementation of the Gardel Core Monitoring System in the Cooper Nuclear Station Training SimulatorCovington, L.J. / Waddell, B. / ANS et al. | 2009
- 871
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Core Monitoring Applications in the Simulator Control RoomBorkowski, J.A. / Belblidia, L. / Noel, A. / ANS et al. | 2009
- 883
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Implementation of Power Shape Adaption Technique for the Use of Automated Fixed In-Core ProbesVivas, G.F.C. / Metwally, W.A. / Rea, J.P. / Moorea, B.R. / Moen, S.C. / ANS et al. | 2009
- 893
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Advances in Core Monitoring at Studsvik ScandpowerNoel, A. / Antona, G. / Ona, C. / Patino, N. / ANS et al. | 2009
- 903
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Comparison Of Thorium-Based Fuels With Different Fissile Components In Existing Boiling Water ReactorsBjork, K.I. / Fhagera, V. / Demaziere, C. / ANS et al. | 2009
- 921
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An Online Reprocessing Facility for a One-Fluid U-233/Th-232 FLiBe Molten Salt Breeder ReactorCramera, C.M. / Shroy, B.C. / ANS et al. | 2009
- 933
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Investigation of Fuel Assembly Design Options for High Conversion Thorium Fuel Cycle in PWRsShwageraus, E. / Volaskia, D. / Fridman, E. / ANS et al. | 2009
- 943
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Physics Design Aspects of Thorium Fueled Advanced Heavy water Reactor (AHWR)Kannan, U. / Pushpam, N.P. / Kumar, A. / Ganesan, S. / Krishnani, P.D. / Srivenkatesan, R. / Sinha, R.K. / ANS et al. | 2009
- 954
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Some Vision Of Initial Stage Of Fuel Cycle With Use Of Thorium And Uranium-233 In RussiaChebeskov, A.N. / Dekusar, V.M. / Kalashnikov, A.G. / ANS et al. | 2009
- 968
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Thorium Molten-Salt Nuclear Energy Synergetics (THORIMS-NES) For The Huge Size Fission IndustryKameia, T. / Katob, Y. / Mitachic, K. / Shimazud, Y. / Yoshiokae, R. / Furukawa, K. / ANS et al. | 2009
- 983
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Hetrogeneous Assembly Design for Utilization of Thorium in VVER ReactorsTodosowa, M. / Galperin, A. / ANS et al. | 2009
- 992
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Studsvik's next generation nodal code SIMULATE-5Bahadira, T. / Lindahl, S.-O. / ANS et al. | 2009
- 1004
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Development of a Control Rod Depletion Methodology for the Westinghouse NEXUS SystemFranceschini, F. / Zhang, B. / Mayhuea, L. / Muller, E. / Guimaraes, P.F. / ANS et al. | 2009
- 1017
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Quadratic Depletion Model for Gadolinium Isotopes in CASMO-5Lee, D. / Rhodes, J. / Smith, K. / ANS et al. | 2009
- 1027
-
An Approach for Gadolinia Lattice Evaluation for PWR-Type FuelNaugle, K. / Catalanotto, B. / ANS et al. | 2009
- 1043
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UK-Titled Thorp Plutonium Stockpile Evaluation For Potential Loading In Sizewell `B' And An AP-1000Thomas, M. / ANS et al. | 2009
- 1058
-
Readiness of the U.S. Reactor Fleet for MOX Fuel UtilizationSowder, A. / Machiels, A. / Hamela, J. / Wenzinger, E. / Dixon, T. / ANS et al. | 2009
- 1076
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Reactor Physics Assessment Of The Inclusion Of Unseparated Np In MOX Reactor FuelEllis, R.J. / ANS et al. | 2009
- 1088
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Summary of Irradiation Tests of Mixed-Oxide Fuel Prepared with Weapons-Derived PlutoniumOtt, L.J. / Spellman, D.J. / ANS et al. | 2009
- 1101
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Designing a New Fuel for HFIR - Performance Parameters for LEU Core ConfigurationsIlas, G. / Primm, R.T. / Gehin, J.C. / ANS et al. | 2009
- 1113
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Preparing The High Flux Isotope Reactor For Conversion To Low Enriched Uranium Fuel - Extending Cycle BurnupPrimm, R.T. / Chandler, D. / ANS et al. | 2009
- 1121
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Preparing The High Flux Isotope Reactor For Conversion To Low Enriched Uranium Fuel - Return To 100 MWSmith, K.A. / Primm, R.T. / ANS et al. | 2009
- 1131
-
Study on the Applicability of the Current Bwr Fuel to the Extended CycleKobayashi, T. / Fukao, A. / Yoshiia, T. / Taguchi, M. / ANS et al. | 2009
- 1143
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Mathematical Models for Quantitative Evaluation of Fissionable Materials Proliferation ProtectionKulikov, E.G. / Shmelev, A.N. / Apsea, V.A. / Kulikov, G.G. / ANS et al. | 2009
- 1155
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IRIS Core Design with Extended Cycle Length Using Nitride FuelPetrovic, B. / Franceschini, F. / ANS et al. | 2009
- 1165
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Measurement of the Doppler Reactivity Coefficient from Low Power Transient of a PWR Power PlantTsuji, M. / Shimazu, Y. / Narabayashia, T. / Hanayama, Y. / Ohoka, Y. / Yamasaki, M. / ANS et al. | 2009
- 1184
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APOLLO2.8 : A Validated Code Package For PWR Neutronics CalculationsSantamarina, A. / Bernard, D. / Blaise, P. / Erradi, L. / Leconte, P. / Le Tellier, R. / Vaglio, C. / Vidal, J.-F. / ANS et al. | 2009
- 1202
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Integral Parameter Sensitivity, Uncertainty, And Representativity Of A Fast Critical Experiment With Regard To AGEN-IV Fast Reactor ConceptStover, T.E. / Turinskya, P.J. / Baysb, S.E. / Abdel-Khalik, H.S. / Iqbal, M. / ANS et al. | 2009
- 1222
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BWR Stability Analyses With SIMULATE-3K - Benchmark Against Measured Plant DataGrandi, G. / Belblidia, L. / Jonsson, C. / ANS et al. | 2009
- 1238
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Development of Real Time Stability Monitor ``OLIMPIA'' - The concept of OLIMPIATashiro, S. / Kageyama, T. / Fukahori, T. / Saekia, J. / Head, J. / ANS et al. | 2009
- 1249
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Remarks to a Novel Nonlinear BWR Stability Analysis Approach (RAM-ROM Methodology)Lange, C. / Hennig, D. / Hurtado, A. / ANS et al. | 2009
- 1269
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MATSTAB-CMS: Implementation Of 3d Frequency Domain Methods For Stability In Studsvik's CMS Code SystemSmed, T. / Belblidia, L. / Grandia, G. / Lansaker, P. / ANS et al. | 2009
- 1285
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Examination of BWR Stability Decay Ratio Using ODYSY & TRACGIngraham, J. / Vreeland, D. / Vedovi, J. / Crider, L. / Head, J. / ANS et al. | 2009
- 1299
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Further Development Of MCOR - Monte Carlo Depletion Code For Reference LWR CalculationsPuente-Espel, F. / Ivanova, K. / Misu, S. / ANS et al. | 2009
- 1315
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Predictive Model Of The Destruction Of Transuranic Targets In A Sodium-Cooled Fast Reactor Using MCNPXAllen, K. / Knight, T. / ANS et al. | 2009
- 1328
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A Monte Carlo Linked Depletion Spent Fuel Library For Assessing Varied Nondestructive Assay Techniques For Nuclear SafeguardsFensin, M.L. / Tobin, S.J. / Sandoval, N.P. / Swinhoe, M.T. / Thompson, S.J. / ANS et al. | 2009
- 1342
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Pebble-Bed Modular Reactor Homogenization Using The RPT Method And MCNPXTrellue, H. / Marcille, T. / ANS et al. | 2009
- 1357
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Cross-Section Uncertainty Propagation And Adjustment Algorithms For BWR Core SimulationJessee, M.A. / Turinsky, P.J. / Abdel-Khalik, H.S. / ANS et al. | 2009
- 1377
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Sensitivity Analysis of Experimental Blanket/Reflector Interface Effects in Fast Reactors for Nuclear Data ImprovementPalmiotti, G. / Salvatores, M. / Hiruta, H. / ANS et al. | 2009
- 1392
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Integral Data Testing for Thermal Spectrum Critical Experiments using ENDF/B-VII.0Huria, H. / Ouisloumen, M. / ANS et al. | 2009
- 1401
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Benchmark Critical Experiments Containing RhodiumHarms, G.A. / ANS et al. | 2009
- 1417
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ENDF/B-VII.0, ENDF/B-VI, JEFF-3.1, and JENDL-3.3 - Results for Critical Lattices of Fuel Pins in WaterMosteller, R.D. / ANS et al. | 2009