12208 Full 3D Visualization Toolkit for Monte Carlo and Deterministic Transport Codes (Englisch)
- Neue Suche nach: Frambati, S.
- Neue Suche nach: Frignani, M.
- Neue Suche nach: American Nuclear Society
- Neue Suche nach: Frambati, S.
- Neue Suche nach: Frignani, M.
- Neue Suche nach: American Nuclear Society
In:
Advances in nuclear power plants; (ICAPP 2012)
;
1723-1728
;
2012
-
ISBN:
- Aufsatz (Konferenz) / Print
-
Titel:12208 Full 3D Visualization Toolkit for Monte Carlo and Deterministic Transport Codes
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Beteiligte:
-
Kongress:International Conference, Advances in nuclear power plants; (ICAPP 2012) ; 2012 ; Chicago, IL
-
Erschienen in:Advances in nuclear power plants; (ICAPP 2012) ; 1723-1728
-
Verlag:
- Neue Suche nach: Curran Associates, Inc.
-
Erscheinungsort:Red Hook, N. Y.
-
Erscheinungsdatum:01.01.2012
-
Format / Umfang:6 pages
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Anmerkungen:Includes bibliographical references and index
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ISBN:
-
Medientyp:Aufsatz (Konferenz)
-
Format:Print
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Sprache:Englisch
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Schlagwörter:
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Datenquelle:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Inhaltsverzeichnis Konferenzband
Die Inhaltsverzeichnisse werden automatisch erzeugt und basieren auf den im Index des TIB-Portals verfügbaren Einzelnachweisen der enthaltenen Beiträge. Die Anzeige der Inhaltsverzeichnisse kann daher unvollständig oder lückenhaft sein.
- 1
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Experimental and Analytical Analyses of a Station Blackout Scenario for APR1400 with Test Facility ATLAS and MARS CodeYu, X.-G. / Kim, Y.-S. / Choi, K.-Y. / Park, H.-S. / Cho, S. / Kang, K.-H. / Choi, N.-Y. / American Nuclear Society et al. | 2012
- 11
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12159 Investigations on Optimization of Accident Management Measures following a Station Blackout Accident in a VVER-1000 Pressurized Water ReactorTusheva, P. / Schafer, F. / Kliem, S. / American Nuclear Society et al. | 2012
- 25
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12366 KERENA Safety Concept in the Context of the Fukushima AccidentZacharias, T. / Novotny, C. / Bielor, E. / American Nuclear Society et al. | 2012
- 30
-
12361 ESBWR Response to an Extended Station Blackout/Loss of All AC PowerBarrett, A.J. / Marquino, W. / American Nuclear Society et al. | 2012
- 37
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12063 The AP1000® Nuclear Power Plant Innovative Features for Extended Station Blackout MitigationVereb, F. / Winters, J. / Schulz, T. / Cummins, E. / Oriani, L. / American Nuclear Society et al. | 2012
- 45
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12445 ESBWR - Robust Design for Natural Circulation and Stability Performance EffectivenessAlamgir, M.D. / Marquino, W. / Yang, J. / Saha, P. / Fennern, L. / Colby, M. / American Nuclear Society et al. | 2012
- 55
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12402 Development of Advanced BWR Fuel Bundle with Spectral Shift Rod -BWR Core Characteristics with SSRHino, T. / Kondo, T. / Chaki, M. / Ohga, Y. / Makigami, T. / American Nuclear Society et al. | 2012
- 63
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12356 ESBWR Enhanced Flow Distribution with Optimized Orificing and Related Fuel Cycle PerformancePearson, G.J. / Karve, A.A. / Fawcett, R.M. / American Nuclear Society et al. | 2012
- 69
-
12065 The Power of Simplification: Operator Interface with the AP1000® During Design-Basis and Beyond Design-Basis EventsWilliams, M.G. / Mouser, M.R. / Simon, J.B. / American Nuclear Society et al. | 2012
- 79
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12378 Pool Scrubbing under Jet Injection Regime: An Enhancement of the SPARC90 CodeHerranz, L.E. / Berna, C. / Escriva, A. / Munoz-Cobo, J.L. / American Nuclear Society et al. | 2012
- 87
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12133 A Study on the Effect of Various Design Parameters on the Natural Circulation Flow Rate of the Ex-Vessel Core Catcher Cooling System of EU-APR1400Rhee, B.W. / Ha, K.S. / Park, R.J. / Song, J.H. / American Nuclear Society et al. | 2012
- 94
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12091 AP1000® Design Robustness against Extreme Events - Seismic, Flooding, and Aircraft CrashPfister, A. / Goossen, C. / Coogler, K. / Gorgemans, J. / American Nuclear Society et al. | 2012
- 102
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12067 AP1000® Nuclear Power Plant Safety Overview for Spent Fuel CoolingGorgemans, J. / Mulhollem, L. / Glavin, J. / Pfister, A. / Conway, L. / Schulz, T. / Oriani, L. / Cummins, E. / Winters, J. / American Nuclear Society et al. | 2012
- 110
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12293 A Platform for Effective Requirements Management and Collaboration in Nuclear Compliance and LicensingFechtelkotter, P. / American Nuclear Society et al. | 2012
- 117
-
12043 Management and Integration of Engineering and Construction Activities: Lessons Learned from the AP1000 China ProjectMcCullough, M.C. / Ebeling-Koning, D. / Evans, M.C. / American Nuclear Society et al. | 2012
- 122
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12032 Olkiluoto 1 and 2 - Plant Efficiency Improvement and Lifetime Extension-Project (PELE) Implemented During Outages 2010 and 2011Kosonen, M. / Hakola, M. / American Nuclear Society et al. | 2012
- 127
-
12448 AP1000® Licensing and Deployment in the United StatesJordan, R.P. / Russ, P.A. / Filiak, P.P. / Castiglione, L.L. / American Nuclear Society et al. | 2012
- 136
-
12395 Infrastructure Development Assistance Modeling for Nuclear Power PlantPark, J.-h. / Hwang, K. / Park, K.-m. / Kim, S.-w. / Lee, S.-m. / American Nuclear Society et al. | 2012
- 145
-
12353 Towards a Framework for Nuclear CompetenceGhitescu, P. / American Nuclear Society et al. | 2012
- 150
-
12333 The AP1000® China Projects Move Forward to Construction Completion and Equipment InstallationHarrop, G. / American Nuclear Society et al. | 2012
- 157
-
12268 Progress on the Development of New Correlations under the Framework of the IAEA Coordinated Research Programme on Heat Transfer in SCWR'sJackson, J.D. / Anderson, M. / Cheng, X. / Zahlan, H. / Bae, Y.Y. / Yamada, K. / American Nuclear Society et al. | 2012
- 170
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12182 Summary on the Depressurization from Supercritical Pressure ConditionsAnderson, M. / Yuzhou, C. / Ammirabile, L. / Novog, D. / Yamada, K. / American Nuclear Society et al. | 2012
- 186
-
12160 International Contributions to IAEA-NEA Heat Transfer Databases for Supercritical FluidsLeung, L.K.H. / Yamada, K. / American Nuclear Society et al. | 2012
- 198
-
12084 Effect of Property Variations on the Mixing of Turbulent Supercritical Water Streams in a T-junctionBu, L. / Zhao, J. / American Nuclear Society et al. | 2012
- 206
-
12442 Subchannel Analysis on CGNPC SCWRZhang, B. / Yang, J. / Chen, C. / Shan, J. / Gou, J. / American Nuclear Society et al. | 2012
- 214
-
12429 On the Correlation of Buoyancy-Influenced Turbulent Convective Heat Transfer to Fluids at Supercritical PressureJackson, J.D. / Jiang, P.X. / Liu, B. / American Nuclear Society et al. | 2012
- 223
-
12425 Heat Transfer Deterioration in Tubes Caused by Bulk Flow Acceleration due to Thermal and Frictional InfluencesJackson, J.D. / American Nuclear Society et al. | 2012
- 231
-
12296 On the Multidimensional Modeling of Fluid Flow and Heat Transfer in SCWRsGallaway, T. / Antal, S.P. / Podowski, M.Z. / American Nuclear Society et al. | 2012
- 240
-
12295 Numerical Simulation of Supercritical Heat Transfer under Severe Axial Density Gradient in a Narrow Vertical TubeBae, Y.Y. / Hong, S.S. / Kim, Y.W. / American Nuclear Society et al. | 2012
- 250
-
12463 Human Factor Engineering Based Design and Modernization of Control Rooms with New I&C SystemsLarraz, J. / Rejas, L. / Ortega, F. / American Nuclear Society et al. | 2012
- 259
-
12455 Mitsubishi Experience on Digital I&C and ModernizationShirasawa, H. / Samples, R.P. / American Nuclear Society et al. | 2012
- 267
-
12346 Digital I&C System Upgrade Integration TechniqueHuang, H.-W. / Shih, C. / Kao, T.-M. / Tseng, M.-S. / American Nuclear Society et al. | 2012
- 276
-
12312 Cyber Security Best Practices for the Nuclear IndustryBadr, I. / American Nuclear Society et al. | 2012
- 280
-
12398 Reliability Enhancement of APR+ Diverse Protection System Regarding Common Cause FailuresOh, Y.G. / Kim, Y.M. / Yim, H.S. / Lee, S.J. / American Nuclear Society et al. | 2012
- 285
-
12389 The Application of Plant Reliability Data Information System (PRINS) to CANDU Reactor)Hwang, S.-W. / Lim, Y.-H. / Park, H.-C. / American Nuclear Society et al. | 2012
- 290
-
12270 Assessment of Different Fuel Design Options with SiC Cladding for Light Water ReactorsXu, S. / Kazimi, M.S. / American Nuclear Society et al. | 2012
- 298
-
12024 Application of Systems Engineering Techniques to Component Design - Capturing Functionality and Linking Part `Critical to Quality' Features to RequirementsPatel, C.M. / Moorby, J.S. / Sulley, J.L. / American Nuclear Society et al. | 2012
- 310
-
12363 Shape Optimization of a Printed-Circuit Heat Exchanger to Enhance Thermal-Hydraulic PerformanceLee, S.-M. / Kim, K.-Y. / American Nuclear Society et al. | 2012
- 317
-
12215 Development of Flow Network Analysis Code for Block Type VHTR Core by Linear Theory MethodLee, J.H. / Yoon, S.J. / Park, J.W. / Park, G.C. / American Nuclear Society et al. | 2012
- 324
-
12124 Effects of Turbulence Model on Convective Heat Transfer of Coolant Flow in a Prismatic Very High Temperature Reactor CoreLee, S.N. / Tak, N.-i. / Kim, M.-H. / Noh, J.M. / American Nuclear Society et al. | 2012
- 332
-
12061 An Effective Thermal-Hydraulics Methodology of a Prismatic Core HTGR and VHTRTravis, B.W. / El-Genk, M.S. / American Nuclear Society et al. | 2012
- 341
-
12415 Nuclear Design of Small-Sized High Temperature Gas-Cooled Reactor for Developing CountriesGoto, M. / Seki, Y. / Inaba, Y. / Ohashi, H. / Sato, H. / Fukaya, Y. / Tachibana, Y. / American Nuclear Society et al. | 2012
- 349
-
12379 Effective Thermal Conductivity of Binary Mixed Materials With and Without Heat Generation-An Empirical ApproachSaleem, R.A.A. / Rizwan-uddin / American Nuclear Society et al. | 2012
- 357
-
12352 Coupled Field-Structural Analysis of HGTR Fuel Brick Using ABAQUSMohanty, S. / Jain, R. / Majumdar, S. / Tautges, T.J. / Makuteswara, S. / American Nuclear Society et al. | 2012
- 367
-
12119 The Effects of Temperatures on the Pebble Flow in a Pebble Bed High Temperature ReactorSen, R.S. / Cogliati, J.J. / Gougar, H.D. / American Nuclear Society et al. | 2012
- 375
-
12111 Daily Thermal Predictions of the AGR-1 Experiment with Gas Gaps Varying with TimeHawkes, G. / Sterbentz, J. / Maki, J. / Pham, B. / American Nuclear Society et al. | 2012
- 387
-
12290 RELAP5-3D Results for Phase I (Exercise 2) of the OECD/NEA MHTGR-350 MW BenchmarkStrydom, G. / Epiney, A.S. / American Nuclear Society et al. | 2012
- 396
-
12123 A Study of Improved MHR 50/100 toward a Higher Level of Inherent SafetyMinatsuki, I. / Otani, T. / Shimizu, K. / Oyama, S. / Tsukamoto, H. / Kunitomi, K. / American Nuclear Society et al. | 2012
- 404
-
12023 Comparison of Gasification Kinetics Parameters of Different Types of Nuclear GraphiteEl-Genk, M.S. / Tournier, J.-M.P. / American Nuclear Society et al. | 2012
- 415
-
12022 Diffusion Velocity Correlation for Nuclear Graphite Gasification at High Temperature and Low Reynolds NumbersEl-Genk, M.S. / Tournier, J.-M.P. / American Nuclear Society et al. | 2012
- 422
-
12373 Improvement Design Study on Steam Generator of MHR-50/100 Aiming Higher Safety Level after Water Ingress AccidentOyama, S. / Minatsuki, I. / Shimizu, K. / American Nuclear Society et al. | 2012
- 431
-
12340 Development of a Coolant Channel Helium and Nitrogen Gas Ratio Sensor for a High Temperature Gas ReactorCadell, S.R. / Woods, B.G. / American Nuclear Society et al. | 2012
- 440
-
12329 Preliminary Analysis of Graphite Dust Releasing Behavior in Accident for HTRPeng, W. / Yang, X.-y. / Yu, S.-y. / Wang, J. / American Nuclear Society et al. | 2012
- 447
-
12328 Granular Flow in Pebble Bed Reactors: Dust Generation and ScalingRycroft, C.H. / Lind, T. / Guntay, S. / Dehbi, A. / American Nuclear Society et al. | 2012
- 456
-
12301 Enhancing VHTR Passive Safety and Economy with Thermal Radiation Based Direct Reactor Auxiliary Cooling SystemZhao, H. / Zhang, H. / Zou, L. / Sun, X. / American Nuclear Society et al. | 2012
- 465
-
12391 Design Study and Comparative Evaluation of JSFR Failed Fuel Detection SystemAizawa, K. / Chikazawa, Y. / Ishikawa, N. / Kubo, S. / Okazaki, H. / Mito, M. / Tozawa, K. / Hayashi, M. / American Nuclear Society et al. | 2012
- 475
-
12390 Evaluation and Improvement on External-hazard Proof of JSFR Fuel Handling SystemKatoh, A. / Chikazawa, Y. / Uzawa, M. / American Nuclear Society et al. | 2012
- 483
-
12383 Design Study on Safety Protection System of JSFRIshikawa, N. / Chikazawa, Y. / Fujita, K. / Yamada, Y. / Okazaki, H. / Suzuki, S. / American Nuclear Society et al. | 2012
- 490
-
12129 Integrity Assessment of the Ferritic / Austenitic Dissimilar Weld Joint between Intermediate Heat Exchanger with Steam Generator in Fast ReactorJayakumar, T. / Laha, K. / Chandravathi, K.S. / Parameswaran, P. / Goyal, S. / Kumar, J.G. / Mathew, M.D. / American Nuclear Society et al. | 2012
- 500
-
12387 Conceptual Design Study of JSFR Reactor BuildingYamamoto, T. / Katoh, A. / Chikazawa, Y. / Ohya, T. / Iwasaki, M. / Hara, H. / Akiyama, Y. / American Nuclear Society et al. | 2012
- 509
-
12344 ADRIANA Project: Identification of Research Infrastructures for the SFR, within the Frame of European Industrial Initiative for Sustainable Nuclear FissionLatge, C. / Gastaldi, O. / Vala, L. / Gerbeth, G. / Homann, C. / Benoit, P. / Papin, J. / Girault, N. / Roelofs, F. / Bucenieks, I. et al. | 2012
- 521
-
12316 Study on Natural Convection Capability of Liquid Gallium for Passive Decay Heat Removal System (PDHRS)Kang, S. / Ha, K.-S. / Lee, S.W. / Park, S.D. / Kim, S.M. / Seo, H. / Kim, J.H. / Bang, I.C. / American Nuclear Society et al. | 2012
- 528
-
12309 Inherent Safety of Minimum Burnup Breed & Burn ReactorsQvist, S. / Greenspan, E. / American Nuclear Society et al. | 2012
- 538
-
12300 Innovative Power Conversion System for the French SFR Prototype, ASTRIDCachon, L. / Biscarrat, C. / Morin, F. / Haubensack, D. / Rigal, E. / Moro, I. / Baque, F. / Madeleine, S. / Rodriguez, G. / Laffont, G. et al. | 2012
- 553
-
12214 Optimization of a Heterogeneous Fast Breeder Reactor Core with Improved Behavior during Unprotected TransientsPoumerouly, S. / Schmitt, D. / Massara, S. / Maliverney, B. / American Nuclear Society et al. | 2012
- 563
-
12205 Use of Freeze-Casting in Advanced Burner Reactor Fuel DesignLang, A.L. / Yablinsky, C.A. / Allen, T.R. / Burger, J. / Hunger, P.M. / Wegst, U.G.K. / American Nuclear Society et al. | 2012
- 572
-
12173 Pre-conceptual Design Study of ASTRID CoreVaraine, F. / Marsault, P. / Chenaud, M.-S. / Bernardin, B. / Conti, A. / Sciora, P. / Venard, C. / Fontaine, B. / Devictor, N. / Martin, L. et al. | 2012
- 580
-
12163 Innovative Technologies on Fuel Assembly Cleaning for Sodium Fast Reactors: First Considerations on Cleaning ProcessSimon, N. / Lorcet, H. / Beauchamp, F. / Guigues, E. / Lovera, P. / Fleche, J.-L. / Lacroix, M. / Carra, O. / Dechelette, F. / Prele, G. et al. | 2012
- 592
-
12098 Performance of Supercritical CO~2 Brayton Cycle with Additive Gases at Varying Critical Points for SFR ApplicationJeong, W.S. / Jeong, Y.H. / American Nuclear Society et al. | 2012
- 602
-
12070 The Pre-conceptual Design of the Nuclear Island of ASTRIDSaez, M. / Menou, S. / Uzu, B. / American Nuclear Society et al. | 2012
- 612
-
12291 A Resting Bottom Sodium Cooled Fast ReactorCostes, D. / American Nuclear Society et al. | 2012
- 621
-
12220 Evaluation on Double-Wall-tube Residual Stress Distribution of Sodium-Heated Steam Generator by Neutron Diffraction and Numerical AnalysisKisohara, N. / Suzuki, H. / Akita, K. / Kasahara, N. / American Nuclear Society et al. | 2012
- 631
-
12029 Transmutation Abilities of the SFR Low Void Effect Core Concept CFV 3600 MWthBuiron, L. / Fontaine, B. / Andriolo, L. / American Nuclear Society et al. | 2012
- 638
-
12020 Analysis & Methodology for Measuring Oxygen Concentration in Liquid Sodium with a Plugging MeterNollet, B.K. / Hvasta, M. / Anderson, M. / American Nuclear Society et al. | 2012
- 648
-
12013 A Vented Inverted Fuel Assembly Design for an SFRVitillo, F. / Todreas, N.E. / Driscoll, M.J. / American Nuclear Society et al. | 2012
- 658
-
12428 On the Use of Moderating Material to Enhance the Feedback Coefficients in SFR Cores with High Minor Actinide ContentMerk, B. / Weiss, F.-P. / American Nuclear Society et al. | 2012
- 667
-
12416 Review of Fuel/Cladding Eutectic Formation in Metallic SFR Fuel PinsDenman, M. / Todreas, N. / Driscoll, M. / American Nuclear Society et al. | 2012
- 677
-
12384 Evaluation of Earthquake and Tsunami on JSFRChikazawa, Y. / Enuma, Y. / Kisohara, N. / Yamano, H. / Kubo, S. / Hayafune, H. / Sagawa, H. / Okamura, S. / Shimakawa, Y. / American Nuclear Society et al. | 2012
- 687
-
12358 GIF Sodium Fast Reactor Project-R&D on Safety and OperationVasile, A. / Sofu, T. / Jeong, H.Y. / Sakai, T. / American Nuclear Society et al. | 2012
- 692
-
12338 Validation of the Integration of CFD and SAS4A/SASSYS-1: Analysis of EBR-II Shutdown Heat Removal Test 17Thomas, J.W. / Fanning, T.H. / Vilim, R.B. / Briggs, L.L. / American Nuclear Society et al. | 2012
- 701
-
12456 New Investigations of the Phenix Negative Reactivity EventsDumaz, P. / Alpy, N. / Broc, D. / Bucci, M. / Cardolaccia, J. / Guenaut, C. / Hourcade, E. / Martin, L. / Jolly, J.A. / Masoni, P. et al. | 2012
- 707
-
12337 Analysis of the Phenix End-of-Life Natural Convection Test with SAS4A/SASSYS-1Thomas, J.W. / Fanning, T.H. / Dunn, F.E. / Sofu, T. / American Nuclear Society et al. | 2012
- 716
-
12324 Use of Simplified PSA Studies in Support of the ASTRID Design ProcessGauthe, P. / Curnier, F. / Bertrand, F. / Vincon, L. / Jouve, S. / Balmain, M. / Richkov, V. / Banchieri, Y. / American Nuclear Society et al. | 2012
- 725
-
12323 The Phenix Ultimate Natural Convection TestGauthe, P. / Pialla, D. / Tenchine, D. / Vasile, A. / Rochwerger, D. / American Nuclear Society et al. | 2012
- 735
-
12292 Preliminary High-Fidelity Simulation of Duct Wall Deformation in the Sodium Fast Reactor SubassemblyHu, R. / Yacout, A. / American Nuclear Society et al. | 2012
- 745
-
12245 Dynamical Analysis of Innovative Core Designs Facing Unprotected Transients with the MAT5 DYN CodeDarmet, G. / Massara, S. / American Nuclear Society et al. | 2012
- 756
-
12294 Validation of a Plant Dynamics Code for 4S - Test Analysis of Natural Circulation BehaviorSebe, F. / Horie, H. / Matsumiya, H. / Fanning, T.H. / American Nuclear Society et al. | 2012
- 765
-
12287 Overall Results of and Lessons Learned from the IAEA CRP on Sodium Natural Circulation Test Performed during the PHENIX End-of-Life ExperimentsMonti, S. / Toti, A. / Tenchine, D. / Pialla, D. / American Nuclear Society et al. | 2012
- 774
-
12266 Benchmark Specifications for EBR-II Shutdown Heat Removal TestsSofu, T. / Briggs, L.L. / American Nuclear Society et al. | 2012
- 779
-
12259 Parametric Analysis of Thermal Stratification during the MONJU Turbine Trip TestSofu, T. / American Nuclear Society et al. | 2012
- 787
-
12285 An Overview of the Activities Carried out by the IAEA Technical Working Group on Fast ReactorsMonti, S. / Toti, A. / American Nuclear Society et al. | 2012
- 793
-
12216 Validation of Nuclear Design Method by Measured Data Obtained in the Physics Test at a Small Fast ReactorNagata, A. / Tsuboi, Y. / Moriki, Y. / Kawashima, M. / American Nuclear Society et al. | 2012
- 803
-
12213 Behavior of an Heterogeneous Annular FBR core during an Unprotected Loss of Flow Accident: Analysis of the Primary Phase with SAS-SFRMassara, S. / Schmitt, D. / Bretault, A. / Lemasson, D. / Darmet, G. / Verwaerde, D. / Struwe, D. / Pfrang, W. / Ponomarev, A. / American Nuclear Society et al. | 2012
- 813
-
12158 Safety Design Approach for External Events in Japan Sodium-Cooled Fast ReactorYamano, H. / Kubo, S. / Tani, A. / Nishino, H. / Sakai, T. / American Nuclear Society et al. | 2012
- 826
-
12100 Development of Integrated Core Disruptive Accident Analysis Code for FBR - ASTERIA-FBRIshizu, T. / Endo, H. / Tatewaki, I. / Yamamoto, T. / Shirakawa, N. / American Nuclear Society et al. | 2012
- 836
-
12354 Comparison of JSFR Design with EDF Requirements for Future SFRUematsu, M.M. / Prele, G. / Mariteau, P. / Sauvage, J.-F. / Hayafune, H. / Chikazawa, Y. / American Nuclear Society et al. | 2012
- 850
-
12152 Characterization of the Liquid Sodium Spray Generated by a Pipework HoleTorsello, G. / Parozzi, F. / Nericcio, L. / Araneo, L. / Cozzi, F. / Carcassi, M. / Mattei, N. / American Nuclear Society et al. | 2012
- 860
-
12048 LWR Codes Capability to Address SFR BDBA Scenarios: Modeling of the ABCOVE TestsHerranz, L.E. / Garcia, M. / Morandi, S. / American Nuclear Society et al. | 2012
- 868
-
12035 CATHARE Calculations of Phenix Ultimate Natural Convection TestPialla, D. / Tenchine, D. / Gauthe, P. / Vasile, A. / American Nuclear Society et al. | 2012
- 882
-
12021 Analysis of Phenix End-of-Life Natural Convection Test with the MARS-LMR CodeJeong, H.-Y. / Ha, K.-S. / Lee, K.-L. / Chang, W.-P. / Kim, Y.-I. / American Nuclear Society et al. | 2012
- 890
-
12460 Development of Strong-Sense Validation Benchmarks for the Fluoride Salt-Cooled High-Temperature ReactorBlanford, E.D. / American Nuclear Society et al. | 2012
- 900
-
12413 Pebble Fuel Design for the PB-FHRCisneros, A.T. / Scarlat, R.O. / Laufer, M.R. / Greenspan, E. / Peterson, P.F. / American Nuclear Society et al. | 2012
- 911
-
12342 Current Status of the Advanced High Temperature ReactorHolcomb, D.E. / Ilas, D. / Qualls, A.L. / Peretz, F.J. / Varma, V.K. / Bradley, E.C. / Cisneros, A.T. / American Nuclear Society et al. | 2012
- 920
-
12190 Chemistry Control and Corrosion Mitigation of Heat Transfer Salts for the Fluoride Salt Reactor (FHR)Kelleher, B.C. / Sellers, S.R. / Anderson, M.H. / Sridharan, K. / Scheele, R.D. / American Nuclear Society et al. | 2012
- 928
-
12025 The Preliminary Analysis on the Steady-State and Kinetic Features of the Molten Salt Pebble-Bed ReactorXia, B. / Lu, Y. / American Nuclear Society et al. | 2012
- 937
-
12464 Preliminary Requirements for a Fluoride Salt-Cooled High-Temperature Test ReactorMassie, M. / Forsberg, C. / Forget, B. / Hu, L.-w. / American Nuclear Society et al. | 2012
- 943
-
12394 Progress in Development of MOSART Concept with Th SupportIgnatiev, V. / Feynberg, O. / Merzlyakov, A. / Surenkov, A. / Zagnitko, A. / Afonichkin, V. / Bovet, A. / Khokhlov, V. / Subbotin, V. / Fazilov, R. et al. | 2012
- 953
-
12189 Materials Corrosion in Molten LiF-NaF-KF Eutectic Salt under Different Reduction-Oxidation ConditionsSellers, R.S. / Cheng, W.J. / Anderson, M.H. / Sridharan, K. / Wang, C.J. / Allen, T.R. / American Nuclear Society et al. | 2012
- 962
-
12019 Secondary Heat Exchanger Design and Comparison for Advance High Temperature ReactorSabharwall, P. / Kim, E.S. / Siahpush, A. / McKellar, M. / Patterson, M. / American Nuclear Society et al. | 2012
- 973
-
12248 Westinghouse Small Modular Reactor Nuclear Steam Supply System DesignMemmott, M.J. / Harkness, A.W. / Van Wyk, J. / American Nuclear Society et al. | 2012
- 984
-
12253 Westinghouse Small Modular Reactor Balance of Plant and Supporting Systems DesignMemmott, M.J. / Stansbury, C. / Taylor, C. / American Nuclear Society et al. | 2012
- 993
-
12250 Overview of the Westinghouse Small Modular Reactor Building LayoutCronje, J.M. / Van Wyk, J. / Memmott, M.J. / American Nuclear Society et al. | 2012
- 1001
-
12157 Westinghouse Small Modular Reactor Passive Safety System Response to Postulated EventsSmith, M.C. / Wright, R.F. / American Nuclear Society et al. | 2012
- 1007
-
12094 AFR-100 Safety AnalysesSumner, T. / Moisseytsev, A. / Wei, T.Y.C. / American Nuclear Society et al. | 2012
- 1017
-
12246 Development of an Object-Oriented Dynamics Simulator for a LFR DEMOPonciroli, R. / Bortot, S. / Lorenzi, S. / Cammi, A. / American Nuclear Society et al. | 2012
- 1028
-
12423 SILER: Seismic-Initiated Events Risk Mitigation in LEad-Cooled ReactorsForni, M. / De Grandis, S. / American Nuclear Society et al. | 2012
- 1036
-
12144 The GUINEVERE Experiment: First PNS Measurements in a Lead Moderated Sub-critical Fast CoreThyebault, H.-E. / Baeten, P. / Billebaud, A. / Chabod, S. / Kochetkov, A. / Lecolley, F.-R. / Lecouey, J.-L. / Lehaut, G. / Marie, N. / American Nuclear Society et al. | 2012
- 1046
-
12279 A Search for Minimum Volume of Breed and Burn CoresDiSanzo, C.D. / Greenspan, E. / American Nuclear Society et al. | 2012
- 1054
-
12280 Design and Analysis of Megawatt-Class Heat-Pipe Reactor ConceptsPoston, D.I. / Kapernick, R. / American Nuclear Society et al. | 2012
- 1064
-
12255 Core Design of Long Life-Cycle Fast Reactors Operating Without Reactivity MarginAristova, E.N. / Baydin, D.F. / Gol din, V.Y. / Pestryakova, G.A. / Stoynov, M.I. / American Nuclear Society et al. | 2012
- 1072
-
12145 Feasibility Study on the Thorium Fueled Boiling Water Breeder ReactorPetrus, N.T. / American Nuclear Society et al. | 2012
- 1077
-
12125 Fuel and Cladding Nano-Technologies Based Solutions for Long Life Heat-pipe Based ReactorsPopa-Simil, L. / American Nuclear Society et al. | 2012
- 1088
-
12168 Advantages and Applications of Megawatt Sized Heat Pipe ReactorsMcClure, P.R. / Reid, R.S. / Dixon, D. / American Nuclear Society et al. | 2012
- 1094
-
12047 Thermal-Hydraulics and Safety Analysis of Sectored Compact Reactor for Lunar Space PowerSchriener, T.M. / El-Genk, M.S. / American Nuclear Society et al. | 2012
- 1104
-
12229 GEN IV Reactors: Where We Are, Where We Should GoLocatelli, G. / Mancini, M. / Todeschini, N. / American Nuclear Society et al. | 2012
- 1114
-
12044 Fuel Loading of PeBR for a Long Operation Life on Lunar SurfaceSchriener, T.M. / El-Genk, M.S. / American Nuclear Society et al. | 2012
- 1122
-
12014 The Fast-spectrum Transmutation Experimental Facility FASTEF: Main Design Achievements (Part 1: Core & Primary System) Within The FP7-CDT Collaborative Project of the European CommissionDe Bruyn, D. / Fernandez, R. / Mansani, L. / Woaye-Hune, A. / Sarotto, M. / Bubelis, E. / American Nuclear Society et al. | 2012
- 1131
-
12201 Acoustic Emission and Guided Ultrasonic Waves for Detection and Continuous Monitoring of Cracks in Light Water Reactor ComponentsMeyer, R.M. / Coble, J. / Ramuhalli, P. / Watson, B. / Cumblidge, S.E. / Doctor, S.R. / Bond, L.J. / American Nuclear Society et al. | 2012
- 1141
-
12393 Application and Development of Technologies for Engine Condition Based Maintenance on Emergency Diesel GeneratorsChoi, K.-H. / Lee, S.-G. / Choi, Y.-S. / Lee, B.-O. / American Nuclear Society et al. | 2012
- 1148
-
12196 Refurbishment Program of HANARO Control Computer SystemsKim, H.K. / Choe, Y.S. / Lee, M.W. / Doo, S.K. / Jung, H.S. / American Nuclear Society et al. | 2012
- 1153
-
12001 Keeping Cool While Planning a Major Cooling System Modification for a Large Base-Loaded Power PlantMallory, J. / Randels, R. / Penrose, J. / Ludovisi, D. / American Nuclear Society et al. | 2012
- 1161
-
12222 How Individual Traces and Interactive Timelines Could Support Outage Execution - Toward an Outage Historian Concept Contaminant Transport AnalysisParfouru, S. / de-Beler, N. / American Nuclear Society et al. | 2012
- 1169
-
12122 On-Line Maintenance Methodology Development and Its ApplicationsKim, J. / Jae, M. / American Nuclear Society et al. | 2012
- 1175
-
12385 Alternative Cooling Resource for Removing the Residual Heat of ReactorPark, H.C. / Lee, J.H. / Jung, C.Y. / Lee, D.S. / Choi, K.Y. / American Nuclear Society et al. | 2012
- 1179
-
12221 Design and Field Test of Collaborative Tools in the Service of an Innovative OrganizationDe Beler, N. / Parfouru, S. / American Nuclear Society et al. | 2012
- 1186
-
12304 A Preliminary User-friendly, Digital Console for the Control Room Parameters Supervision in Old-Generation Nuclear Power PlantsMemmi, F. / Falconi, L. / Cappelli, M. / Palomba, M. / Santoro, E. / Bove, R. / Sepielli, M. / American Nuclear Society et al. | 2012
- 1194
-
12117 Innovative Applications of Technology for Nuclear Power Plant Productivity ImprovementsNaser, J.A. / American Nuclear Society et al. | 2012
- 1203
-
12197 Fatigue Monitoring Desktop GuideWoods, K. / Thomas, K. / American Nuclear Society et al. | 2012
- 1211
-
12303 A Decision Support System Prototype Including Human Factors Based on the TOGA Meta-Theory ApproachCappelli, M. / Memmi, F. / Gadomski, A.M. / Sepielli, M. / American Nuclear Society et al. | 2012
- 1219
-
12302 Cognitive Decision Errors and Organization Vulnerabilities in Nuclear Power Plant Safety Management: Modeling Using the TOGA Meta-Theory FrameworkCappelli, M. / Gadomski, A.M. / Sepielli, M. / Wronikowska, M.W. / American Nuclear Society et al. | 2012
- 1227
-
12262 Regression Analysis of Technical Parameters Affecting Nuclear Power Plant PerformancesGhazy, R. / Ricotti, M.E. / Trucco, P. / American Nuclear Society et al. | 2012
- 1237
-
12198 Development of an Equipment Management Model to Improve Effectiveness of the ProcessesChang, H.-S. / Ju, T.-Y. / Song, T.-Y. / American Nuclear Society et al. | 2012
- 1243
-
12347 Preliminary LOCA Analysis of the Westinghouse Small Modular Reactor Using the WCOBRA/TRAC-TF2 Thermal-Hydraulics CodeLiao, J. / Kucukboyaci, V.N. / Nguyen, L. / Frepoli, C. / American Nuclear Society et al. | 2012
- 1249
-
12405 Experimental Study of Siphon Breaker about Size Effect in Real Scale Reactor DesignKang, S.H. / Ahn, H.S. / Kim, J.M. / Joo, H.M. / Lee, K.-Y. / Seo, K. / Chi, D.Y. / Kim, M.H. / American Nuclear Society et al. | 2012
- 1257
-
12134 Analysis of the Absorbed Hydrogen in Cladding Tubes Applied in the QUENCH-LOCA TestsGrosse, M. / Rossger, C. / Stuckert, J. / Steinbrueck, M. / Walter, M. / Klimenjov, M. / Kaestner, A. / American Nuclear Society et al. | 2012
- 1266
-
12421 Effect of Spray Parameter on Containment Depressurization during LOCA in KAPP 3&4 700 MWe IPHWRSharma, S.K. / Bhartia, D.K. / Mohan, N. / Malhotra, P.K. / Ghadge, S.G. / American Nuclear Society et al. | 2012
- 1274
-
12011 Radiological Impact Assessment (RIA) Following a Postulated Accident in PHWRsSoni, N. / Kansal, M. / Rammohan, H.P. / Malhotra, P.K. / American Nuclear Society et al. | 2012
- 1283
-
12374 Experimental Investigation on the Chemical Precipitation Generation under the Loss of Coolant Accident of Nuclear Power PlantsKim, C.H. / Sung, J.J. / Chung, Y.W. / American Nuclear Society et al. | 2012
- 1288
-
12141 Joint Probability Safety Assessment for NPP Defense Infrastructure Against Extreme External Natural HazardsLiu, G. / Liu, D. / Li, H. / Wang, F. / Zou, T. / American Nuclear Society et al. | 2012
- 1295
-
12113 Understanding the Nature of Nuclear Power Plant RiskDenning, R.S. / American Nuclear Society et al. | 2012
- 1301
-
12089 Assessment of Core Damage Frequency Owing to Possible Fires at NP with RBMK Type ReactorsVinnikov, B. / American Nuclear Society et al. | 2012
- 1307
-
12046 Insights from the WGRISK Workshop on the PSA of Advanced and New ReactorsGeorgescu, G. / Ahn, K.I. / Amri, A. / American Nuclear Society et al. | 2012
- 1316
-
12452 Impact of B~4C on the Stratification of Molten Steel and BWR-Type Core Material under IVR ConditionsFischer, M. / Sulatsky, A.A. / Krushinov, E.V. / American Nuclear Society et al. | 2012
- 1326
-
12419 Hydrogen Combustion in a Flat Semi-Confined Layer with Respect to the Fukushima Daichii AccidentKuznetsov, M. / Yanez, J. / Grune, J. / Friedrich, A. / Jordan, T. / American Nuclear Society et al. | 2012
- 1336
-
12106 Effects of Molybdenum and Silver on Iodine Transport in Primary Circuit on Severe Nuclear AccidentsKalilainen, J. / Rantanen, P. / Karkela, T. / Lipponen, M. / Auvinen, A. / Jokiniemi, J. / American Nuclear Society et al. | 2012
- 1343
-
12072 Aerosol Retention during SGTR Meltdown Sequences: Experimental Insights of the Effect of Size and Shape of the BreachHerranz, L.E. / Tardaguila, R.D. / Lopez, C. / American Nuclear Society et al. | 2012
- 1351
-
12049 Experimental Results of the QUENCH-16 Bundle Test on Air IngressStuckert, J. / Steinbruck, M. / American Nuclear Society et al. | 2012
- 1359
-
12325 The EU-ROSATOM ERCOSAM-SAMARA Projects on Containment Thermal-Hydraulics of Current and Future LWRs for Severe Accident ManagementPaladino, D. / Guentay, S. / Andreani, M. / Tkatschenkos, I. / Brister, J. / Dabbene, F. / Kelm, S. / Allelein, H.-J. / Visser, D.C. / Benz, S. et al. | 2012
- 1369
-
12281 CFD Modeling of Debris Melting Phenomena during Late Phase CANDU 6 Severe AccidentNicolici, S. / Dupleac, D. / Prisecaru, I. / American Nuclear Society et al. | 2012
- 1377
-
12012 BWR Ex-Vessel Steam Explosion Analysis with MC3D CodeLeskovar, M. / American Nuclear Society et al. | 2012
- 1386
-
12052 Evaluation of In-Vessel Corium Retention through External Reactor Vessel Cooling for Integral Type ReactorPark, R.-J. / Lee, J.R. / Kim, S.-B. / Jin, Y. / Kim, H.Y. / American Nuclear Society et al. | 2012
- 1392
-
12447 Diffusive Deposition of Aerosols in Phebus Containment During FPT-2 TestKontautas, A. / Urbonavicius, E. / American Nuclear Society et al. | 2012
- 1399
-
12350 AP1000® Severe Accident Features and Post-Fukushima ConsiderationsScobel, J.H. / Schulz, T.L. / Williams, M.G. / American Nuclear Society et al. | 2012
- 1412
-
12348 Modeling of Melt Retention in EU-APR1400 Ex-Vessel Core CatcherGranovsky, V.S. / Sulatsky, A.A. / Khabensky, V.B. / Sulatskaya, M.B. / Gusarov, V.V. / Almyashev, V.I. / Komlev, A.A. / Bechta, S. / Kim, Y.S. / Park, R.J. et al. | 2012
- 1422
-
12453 Design Change Management in Regulation of Nuclear FleetsSwinburn, R. / Borysova, I. / Waddington, J. / Head, J.G. / Raidis, Z. / American Nuclear Society et al. | 2012
- 1433
-
12370 Renovated Korean Nuclear Safety and Security System : A Review and Suggestions to Successful SettlementChung, W.-S. / Yun, S.-W. / Lee, D.-S. / Go, D.-Y. / American Nuclear Society et al. | 2012
- 1438
-
12257 Enhancement of NRC Station Blackout Requirements for Nuclear Power PlantsMcConnell, M.W. / American Nuclear Society et al. | 2012
- 1443
-
12238 The Use of Latin Hypercube Sampling for the Efficient Estimation of Confidence IntervalsGrabaskas, D. / Denning, R.S. / Aldemir, T. / Nakayama, M. / American Nuclear Society et al. | 2012
- 1453
-
12112 BWR Transient Analysis Using Neutronic / Thermal Hydraulic Coupled Codes Including Uncertainty QuantificationHartmann, C. / Sanchez, V. / Tietsch, W. / Stieglitz, R. / American Nuclear Society et al. | 2012
- 1460
-
12085 Supporting Qualified Database for Uncertainty EvaluationPetruzzi, A. / Fiori, F. / Kovtonyuk, A. / D Auria, F. / American Nuclear Society et al. | 2012
- 1469
-
12315 Development of the IPRO-ZONE for Fire PSA and Its ApplicationsKang, D.I. / Han, S.-H. / American Nuclear Society et al. | 2012
- 1478
-
12283 Prediction of Number of Breached Rods following a LBLOCA of CANDU Plants Using a BEPU ApproachBang, Y.S. / Kim, K. / Seul, K.W. / Woo, S.W. / Han, B.S. / American Nuclear Society et al. | 2012
- 1484
-
12195 Upgrades to Monteburns, Version 3.0Galloway, J.D. / Trellue, H.R. / American Nuclear Society et al. | 2012
- 1493
-
12107 Environment-Based Pin-Power Reconstruction Method for Homogeneous Core CalculationsLeroyer, H. / Brosselard, C. / Girardi, E. / American Nuclear Society et al. | 2012
- 1503
-
12090 Automatic Treatment of the Variance Estimation Bias in TRIPOLI-4 Criticality CalculationsDumonteil, E. / Malvagi, F. / American Nuclear Society et al. | 2012
- 1512
-
12083 Feasibility of a Wavelet Expansion Method to Treat Energy in Cell Calculationsvan Rooijen, W.F.G. / American Nuclear Society et al. | 2012
- 1520
-
12417 Generation of Bondarenko F Factors with MCNP5 for use in Scale Transport CodesHart, S. / Maldonado, G.I. / American Nuclear Society et al. | 2012
- 1527
-
12359 Application of Fully Ceramic Microencapsulated Fuels in Light Water ReactorsGentry, C. / George, N. / Maldonado, I. / Godfrey, A. / Terrani, K. / Gehin, J. / American Nuclear Society et al. | 2012
- 1536
-
12305 The New MCNP6 Depletion CapabilityFensin, M.L. / James, M.R. / Hendricks, J.S. / Goorley, J.T. / American Nuclear Society et al. | 2012
- 1546
-
12210 Examination of Temperature Dependent Subgroup Formulations in Direct Whole Core Transport Calculation for Power ReactorsJung, Y.S. / Lee, U.C. / Joo, H.G. / American Nuclear Society et al. | 2012
- 1554
-
12050 Nuclear Analyses of Supercritical Water Cooled Reactor with Carbon Nanotube CladdingUenohara, Y. / Yamano, N. / American Nuclear Society et al. | 2012
- 1562
-
12016 A Survey of Alternative Once-Through Fast Reactor Core DesignsFei, T. / Richard, J.G. / Kersting, A.R. / Don, S.M. / Oi, C. / Driscoll, M.J. / Shwageraus, E. / American Nuclear Society et al. | 2012
- 1572
-
12028 Impact of the Control Rod Consumption on the Reactivity Control of a SFR Break-Even CoreBlanchet, D. / Fontaine, B. / American Nuclear Society et al. | 2012
- 1581
-
12223 Core Loading Pattern Optimization of Thorium Fueled Heavy Water Breeder Reactor Using Genetic AlgorithmSoewono, C.N. / Takaki, N. / American Nuclear Society et al. | 2012
- 1588
-
12109 Potential of Pin-By-Pin SPN Calculations as an Industrial ReferenceFliscounakis, M. / Girardi, E. / Courau, T. / Couyras, D. / American Nuclear Society et al. | 2012
- 1599
-
12093 Uncertainty Analysis on Reactivity and Discharged Inventory for a Pressurized Water Reactor Fuel Assembly Due to ^2^3^5^,^2^3^8U Nuclear Data Uncertaintiesda Cruz, D.F. / Rochman, D. / Koning, A.J. / American Nuclear Society et al. | 2012
- 1607
-
12128 Application of the Modified Neutron Source Multiplication Method to the Prototype FBR MonjuTruchet, G. / van Rooijen, W.F.G. / Shimazu, Y. / American Nuclear Society et al. | 2012
- 1617
-
12087 100%MOX BWR Experimental Program Design Using Multi-parameter RepresentativityBlaise, P. / Fougeras, P. / Cathalau, S. / American Nuclear Society et al. | 2012
- 1627
-
12086 Interpretation of 3D Void Measurements with TRIPOLI4.6/JEFF3.1.1 Monte Carlo CodeBlaise, P. / Colomba, A. / American Nuclear Society et al. | 2012
- 1635
-
12077 Burnup Estimation of Fuel Sourcing Radioactive Material Based on Monitored Cs and Pu Isotopic Activity Ratios in Fukushima N. P. S. AccidentYamamoto, T. / Suzuki, M. / Ando, Y. / American Nuclear Society et al. | 2012
- 1643
-
12027 Main Results of Phenix Final Core Physics TestsPascal, V. / Prulhiere, G. / Vanier, M. / Fontaine, B. / American Nuclear Society et al. | 2012
- 1653
-
12331 Detection Rate Evaluation of Ex-Core Detectors in the Subcritical OPR-1000 ReactorWon, B.-H. / Shin, C.-H. / Kim, S.H. / Kim, H.-C. / Park, J.-J. / Kim, J.K. / American Nuclear Society et al. | 2012
- 1659
-
12289 Development of 3D Full-core ERANOS-2.2/MCNPX-2.7.0 Models and Neutronic Analysis of the BFS-2 Zero-Power FacilityGirardin, G. / Mercedes, A. / Mikityuk, K. / American Nuclear Society et al. | 2012
- 1668
-
12176 Calculation of the PHENIX End-of-Life Test ``Control Rod Withdrawal'' with the ERANOS CodeTiberi, V. / American Nuclear Society et al. | 2012
- 1675
-
12136 Application of the JENDL-4.0 Nuclear Data Set for the Uncertainty Analysis of the Prototype FBR MonjuTamagno, P. / van Rooijen, W.R.G. / Takeda, T. / Konomura, M. / American Nuclear Society et al. | 2012
- 1685
-
12411 Benchmarking of Software and Methods for Use in Transient Multi-Dimensional Fuel Performance with Spatial Reactor KineticsBanfield, J.E. / Clarno, K.T. / Hamilton, S.P. / Maldonado, G.I. / Philip, B. / Baird, M.L. / American Nuclear Society et al. | 2012
- 1695
-
12110 Uncertainties Propagation in the Framework of a Rod Ejection Accident Modeling Based on a Multiphysics ApproachLe Pallec, J.C. / Crouzet, N. / Bergeaud, V. / Delavaud, C. / American Nuclear Society et al. | 2012
- 1704
-
12080 The Harmony between Nuclear Reactions and Nuclear Reactor Structures and SystemsPopa-Simil, L. / American Nuclear Society et al. | 2012
- 1715
-
12341 RGG: Reactor Geometry (and mesh) GeneratorJain, R. / Tautges, T. / American Nuclear Society et al. | 2012
- 1723
-
12208 Full 3D Visualization Toolkit for Monte Carlo and Deterministic Transport CodesFrambati, S. / Frignani, M. / American Nuclear Society et al. | 2012
- 1729
-
12164 MANCINTAP: Time and Space Dependent Neutron Activation Tool Algorithm Improvement and Analysis of a PWR Nozzle GalleryFrambati, S. / Firpo, G. / Frignani, M. / American Nuclear Society et al. | 2012
- 1736
-
12095 Uncertainty Methodology for the Strongly Coupled Physical Phenomena Associated with Annular FlowLane, J.W. / Aumiller, D.L. / American Nuclear Society et al. | 2012
- 1747
-
12057 Calculation of the PHENIX End-of-life Test in Natural Circulation with the CATHARE CodeMaas, L. / Cocheme, F. / American Nuclear Society et al. | 2012
- 1756
-
12040 The Developments and Verifications of TRACE Model on IIST LOCA ExperimentsZhuang, W.-X. / Wang, J.-R. / Lin, H.-T. / Shih, C. / Huang, K.-C. / American Nuclear Society et al. | 2012
- 1763
-
12018 Identifying and Bounding Uncertainties in Nuclear Reactor Thermal Power CalculationsPhillips, J. / Hauser, E. / Estrada, H. / American Nuclear Society et al. | 2012
- 1771
-
12104 Calculation of Natural Convection Test at Phenix using the NETFLOW++ CodeMochizuki, H. / Kikuchi, N. / Li, S. / American Nuclear Society et al. | 2012
- 1781
-
12261 Best-Estimate Plus Uncertainty Thermal-Hydraulic Stability Analysis Of BWR Using TRACG CodeVedovi, J. / Yang, J. / Klebanov, L. / Vreeland, D.G. / Zino, J.F. / American Nuclear Society et al. | 2012
- 1793
-
12247 TRACE and TRAC-BF1 Benchmark against Leibstadt Plant Data during the Event Inadvertent Opening of Relief ValvesSekhri, A. / Baumann, P. / Wicaksono, D. / American Nuclear Society et al. | 2012
- 1801
-
12179 Simulation of 1% Hot Leg SBLOCA with TRACE5Gallardo, S. / Querol, A. / Verdu, G. / American Nuclear Society et al. | 2012
- 1810
-
12444 Analysis of Phenix Natural Convection Test with the TRACE CodeChenu, A. / Mikityuk, K. / Chawla, R. / American Nuclear Society et al. | 2012
- 1819
-
12401 APR1400 LBLOCA Uncertainty Quantification using Monte Carlo Method and Comparison with Wilks' FormulaHwang, M. / Bae, S.W. / Chung, B.D. / American Nuclear Society et al. | 2012
- 1825
-
12377 Thermal Hydraulic Limits Analysis Using Statistical Propagation of Parametric UncertaintiesChiang, K.-y. / Hu, L.-w. / Forget, B. / American Nuclear Society et al. | 2012
- 1835
-
12351 Use of Scaled BWR Lower Plenum Boron Mixing Tests to Qualify the Boron Transport Model used in TRACGCook, M.M. / Straka, M. / Chu, Y.-C. / Heck, C.L. / Andersen, J.G.M. / Jacobs, R.H. / American Nuclear Society et al. | 2012
- 1843
-
12267 Quantitative Phenomena Identification and Ranking Table (QPIRT) for Bayesian Uncertainty QuantificationYurko, J.P. / Buongiorno, J. / American Nuclear Society et al. | 2012
- 1854
-
12143 Analysis of the KROTOS KFC Test by Coupling X-Ray Image Analysis and MC3D CalculationsBrayer, C. / Charton, A. / Grishchenko, D. / Fouquart, P. / Bullado, Y. / Compagnon, F. / Correggio, P. / Cassiaut-Louis, N. / Piluso, P. / American Nuclear Society et al. | 2012
- 1864
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12130 Contribution to Modeling of the Reflooding of a Severely Damaged Reactor Core Using PRELUDE Experimental ResultsBachrata, A. / Fichot, F. / Repetto, G. / Quintard, M. / Fleurot, J. / American Nuclear Society et al. | 2012
- 1873
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12060 The MAX Facility for CFD Code ValidationLomperski, S. / Merzari, E. / Obabko, A. / Pointer, W.D. / Fischer, P. / American Nuclear Society et al. | 2012
- 1880
-
12339 Experiments on Large Scale Plume Interaction with a Stratified Gas Environment Resembling the Thermal Activity of Autocatalytic RecombinerMignot, G. / Kapulla, R. / Paladino, D. / Zboray, R. / American Nuclear Society et al. | 2012
- 1890
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12319 An Experimental Study of External Reactor Vessel Cooling Strategy on the Critical Heat Flux using the Graphene Oxide NanofluidPark, S.D. / Lee, S.W. / Kang, S. / Kim, S.M. / Seo, H. / Bang, I.C. / American Nuclear Society et al. | 2012
- 1897
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12318 Simulation of the Passive Condensation Cooling Tank of the PASCAL Test Facility using the Component Thermal-Hydraulic Analysis Code CUPIDCho, H.K. / Lee, S.J. / Kang, K.-H. / Yoon, H.Y. / American Nuclear Society et al. | 2012
- 1906
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12185 PWR Internal Flow Modeling With Fuel Assemblies DetailsPopov, E. / Yan, J. / Karoutas, Z. / Gehin, J. / Brewster, R. / Baglietto, E. / American Nuclear Society et al. | 2012
- 1911
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12365 The Impact Assessment of Eccentric Installation and Roughness Change in Piping on the Orifice Flow MeasurementNishi, Y. / Eguchi, Y. / Nishihara, T. / Kanai, T. / Kondo, M. / American Nuclear Society et al. | 2012
- 1921
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12435 Heat Transfer Research on Supercritical Water Flow Upward in TubeLi, H. / Yang, J. / Gu, H. / Zhao, M. / Lu, D. / Zhang, J. / Wang, F. / Zhang, Y. / American Nuclear Society et al. | 2012
- 1927
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12380 Implementation of Non-Condensable Gases Condensation Suppression Model into the WCOBRA/TRAC-TF2 LOCA Safety Evaluation CodeLiao, J. / Ohkawa, K. / Frepoli, C. / American Nuclear Society et al. | 2012
- 1935
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12204 Study on the Well-Posednes, Convergence and the Stability of the Semi-implicit Upwind Numerical Solver for the Multi-fluid ModelLee, S.Y. / Park, C.E. / Hibiki, T. / Ishii, M. / Ransom, V.H. / American Nuclear Society et al. | 2012
- 1945
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12127 Improvement of Three-Field Based Safety Analysis Code, SPACE, through Verification & ValidationYang, J.-H. / Kim, J.-H. / Park, G.-C. / American Nuclear Society et al. | 2012
- 1959
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12099 Coupled Simulation of the Reactor Core Using CUPID/MASTERLee, J.R. / Cho, H.K. / Yoon, H.Y. / Jeong, J.J. / American Nuclear Society et al. | 2012
- 1966
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12008 Evaluation of Anticipatory Signal to Steam Generator Pressure Control Program for 700MWe Indian Pressurized Heavy Water ReactorPahari, S. / Hajela, S. / Rammohan, H.P. / Malhotra, P.K. / Ghadge, S.G. / American Nuclear Society et al. | 2012
- 1972
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12286 PHISICS Multi-group Transport Neutronics Capabilities for RELAP5Epiney, A. / Rabiti, C. / Alfonsi, A. / Wang, Y. / Cogliati, J. / Strydom, G. / American Nuclear Society et al. | 2012
- 1982
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12273 Theoretical and Computational Analysis of Flow Oscillations in S-CO2 Natural Circulation LoopSmith, W.C. / Podowski, M.Z. / American Nuclear Society et al. | 2012
- 1988
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12263 Predictions of One-Group Interfacial Area Transport in TRACEWorosz, T. / Talley, J.D. / Kim, S. / Bajorek, S.M. / Ireland, A. / American Nuclear Society et al. | 2012
- 1999
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12177 Simulation of the PBF-CANDU Test with Coupled Thermal-Hydraulic and Fuel Thermo-Mechanical ResponsesBaschuk, J.J. / American Nuclear Society et al. | 2012
- 2009
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12458 SPACE Code Simulation of Cold Leg Small Break LOCA in the ATLAS Integral TestKim, B.J. / Kim, H.T. / Kim, J. / Kim, K.D. / American Nuclear Society et al. | 2012
- 2015
-
12422 CATHARE Thermal-Hydraulic System Code for HLM Preliminary Validation in Natural Convection TestsPolidori, M. / Meloni, P. / Lombardo, C. / Bandini, G. / Geffraye, G. / Kadri, D. / American Nuclear Society et al. | 2012
- 2024
-
12392 MARS-KS Code Validation Activity through the ATLAS Domestic Standard ProblemChoi, K.-Y. / Kim, Y.-S. / Kang, K.-H. / Park, H.-S. / Cho, S. / American Nuclear Society et al. | 2012
- 2032
-
12376 IJS Procedure for RELAP5 to TRACE Input Model Conversion using SNAPProsek, A. / Berar, O.-A. / American Nuclear Society et al. | 2012
- 2042
-
12375 Scalable Three-Dimensional Thermal-Hydraulic Best-Estimate Code BAGIRAVasenin, V.A. / Krivchikov, M.A. / Kroshilin, V.E. / Kroshilin, A.E. / Roganov, V.A. / American Nuclear Society et al. | 2012
- 2051
-
12277 Multiscale Approach to the Modeling of Fission Gas Discharge during Hypothetical Loss-of-Flow Accident in Gen-IV Sodium Fast ReactorBehafarid, F. / Shaver, D.R. / Jansen, K.E. / Antal, S.P. / Podowski, M.Z. / American Nuclear Society et al. | 2012
- 2062
-
12274 Multidimensional Mechanistic Modelling of Interfacial Heat and Mass TransferShaver, D.R. / Antal, S.P. / Podowski, M.Z. / American Nuclear Society et al. | 2012
- 2073
-
12217 Effect of Gaps on the Performance of the Vertically Installed Wet Thermal InsulatorKim, S.H. / Kim, Y.I. / Park, C.T. / Choi, S. / Yoon, J. / American Nuclear Society et al. | 2012
- 2081
-
12206 Experimental Study on the Operational and the Cooling Performance of the APR+ Passive Auxiliary Feedwater SystemKang, K.H. / Bae, B.U. / Kim, S. / Cho, Y.J. / Park, Y.S. / Kim, B.D. / American Nuclear Society et al. | 2012
- 2088
-
12155 Validation of CONTAIN-LMR Code for Accident Analysis of Sodium-Cooled Fast Reactor ContainmentsGordeev, S. / Hering, W. / Schikorr, M. / Stieglitz, R. / American Nuclear Society et al. | 2012
- 2096
-
12457 Major Results from Safety-Related Integral Effect Tests with VISTA-ITL for the SMART DesignPark, H.-S. / Min, B.-Y. / Shin, Y.-C. / Yi, S.-J. / American Nuclear Society et al. | 2012
- 2105
-
12443 LOFA and LOCA Analysis for CGNPC SCWRWu, P. / Gou, J. / Shan, J. / Jiang, Y. / Zhang, B. / Yang, J. / American Nuclear Society et al. | 2012
- 2116
-
12440 An Analysis of the Sliding Pressure Start-Up of SCWRWang, F. / Yang, J. / Li, H. / Zhang, Y. / Shan, J. / Gou, J. / Zhang, B. / Chen, C. / American Nuclear Society et al. | 2012
- 2124
-
12408 Validation of a Radial-Inflow Turbine Model for Super-critical CO~2 ApplicationsVilim, R.B. / American Nuclear Society et al. | 2012
- 2135
-
12368 Experimental Study on Heat Transfer to Supercritical Water Flowing through TubesZhao, M. / Gu, H. / Cheng, X. / American Nuclear Society et al. | 2012
- 2145
-
12360 Condensation Model for the ESBWR Passive CondensersRevankar, S.T. / Zhou, W. / Wolf, B. / Oh, S. / American Nuclear Society et al. | 2012
- 2153
-
12131 A Scaling Study of the Natural Circulation Flow of the Ex-Vessel Core Catcher Cooling System of EU-APR1400 for Designing a Scale-Down Test Facility for Design VerificationRhee, B.W. / Ha, K.S. / Park, R.J. / Song, J.H. / Revankar, S.T. / American Nuclear Society et al. | 2012
- 2158
-
12036 A Three-Fluid Model for the Simulation of Counter-Current Stratified Flows in the Hot Leg of a Pressurized Water ReactorAli, A.B.H. / Laurien, E. / American Nuclear Society et al. | 2012
- 2168
-
12033 Critical Heat Flux in Natural Convection Cooled TRIGA Reactors with Hexagonal BundleYang, J. / Avery, M. / De Angelis, M. / Anderson, M. / Corradini, M. / Feldman, E.E. / Dunn, F.E. / Matos, J.E. / American Nuclear Society et al. | 2012
- 2175
-
12004 Supercritical Carbon Dioxide Tubular Flow under Temporally Varying Thermal Boundary ConditionSon, H.M. / Halimi, B. / Suh, K.Y. / American Nuclear Society et al. | 2012
- 2182
-
12317 Study on Critical Heat Flux Enhancement in Flow Boiling of SiC Nanofluids under Low Pressure and Low Flow ConditionsLee, S.W. / Park, S.D. / Kang, S. / Kim, S.M. / Seo, H. / Lee, D.W. / Bang, I.C. / American Nuclear Society et al. | 2012
- 2191
-
12237 On the Prediction of Horizontal Bubbly Flows Using the Interfacial Area Transport EquationTalley, J.D. / Kim, S. / American Nuclear Society et al. | 2012
- 2199
-
12199 Effect of Rolling Motion on Critical Heat Flux for Subcooled Flow Boling in Vertical TubeHwang, J.-S. / Park, I.-U. / Park, M.-Y. / Park, G.-C. / American Nuclear Society et al. | 2012
- 2206
-
12166 Velocity and Void Distribution in a Counter-Current Two-phase FlowGabriel, S. / Schulenberg, T. / Laurien, E. / American Nuclear Society et al. | 2012
- 2214
-
12174 Application of the CFD CONV Code to the Analysis of LIVE L-6 TestPalagin, A. / Kretzschmar, F. / Miassoedov, A. / Chudanov, V. / American Nuclear Society et al. | 2012
- 2222
-
12071 Development of One-dimensional Computational Fluid Dynamics Code ``GFLOW'' for Groundwater Flow and Contaminant Transport AnalysisRahatgaonkar, P.S. / Datta, D. / Malhotra, P.K. / Ghadge, S.G. / American Nuclear Society et al. | 2012
- 2231
-
12437 CFD Study of Natural Convection Mixing in a Steam Generator Mock-Up: Comparison between Full Geometry and Porous Media ApproachesDehbi, A. / Badreddine, H. / American Nuclear Society et al. | 2012
- 2239
-
12349 Numerical Study on Interaction of Local Air Cooler with Stratified Hydrogen Cloud in a Large VesselLiang, Z. / Andreani, M. / American Nuclear Society et al. | 2012
- 2248
-
12184 Stability and Error Analysis of Nodal Expansion Method for the Convection-Diffusion EquationDeng, Z. / Rizwan-uddin / Li, F. / Sun, Y. / American Nuclear Society et al. | 2012
- 2258
-
12139 Impact of Porous Medium on the High Cycle Temperature Fluctuations in a Mixing TeeBu, L. / Zhao, J. / American Nuclear Society et al. | 2012
- 2268
-
12055 Cross Flow Characteristics in a Three Fuel AssembliesBae, J.H. / Euh, D.J. / Park, C.K. / Youn, Y.J. / Kwon, T.S. / American Nuclear Society et al. | 2012
- 2274
-
12026 Results from a Scaled Reactor Cavity Cooling System with Water at Steady-StateLisowski, D.D. / Albiston, S.M. / Tokuhiro, A. / Anderson, M.H. / Corradini, M.L. / American Nuclear Society et al. | 2012
- 2280
-
12334 Condensation in Horizontal Heat Exchanger TubesLeyer, S. / Zacharias, T. / Maisberger, F. / Lamm, M. / Vallee, C. / Beyer, M. / Hampel, U. / American Nuclear Society et al. | 2012
- 2286
-
12306 Experimental Characterization of Pressure Drops and Channel Instabilities in Helical Coil SG TubesColombo, M. / Cammi, A. / De Amicis, J. / Ricotti, M.E. / American Nuclear Society et al. | 2012
- 2296
-
12269 Benchmark Studies of Thermal Jet Mixing in SFRs Using a Two-Jet ModelOmotowa, O.A. / Skifton, R. / Tokuhiro, A. / American Nuclear Society et al. | 2012
- 2302
-
12235 Measurement of Interfacial Structures in Horizontal Air-Water Bubbly FlowsTalley, J.D. / Worosz, T. / Dodds, M.R. / Kim, S. / American Nuclear Society et al. | 2012
- 2312
-
12140 Critical Heat Flux on Micro-Structured Zircaloy Surfaces for Flow Boiling of Water at Low PressuresHaas, C. / Miassoedov, A. / Schulenberg, T. / Wetzel, T. / American Nuclear Society et al. | 2012
- 2320
-
12264 Experimental Study of Heat Transfer in a 7-Element Bundle Cooled With Supercritical Freon-12Richards, G. / Shelegov, A.S. / Kirillov, P.L. / Pioro, I.L. / Harvel, G. / American Nuclear Society et al. | 2012
- 2328
-
12260 Heat Transfer and Pressure Drop of Supercritical Carbon Dioxide Flowing in Several Printed Circuit Heat Exchanger Channel PatternsCarlson, M. / Kruizenga, A. / Anderson, M. / Corradini, M. / American Nuclear Society et al. | 2012
- 2337
-
12242 Gas and Liquid Measurements in Air-Water Bubbly FlowsZhou, X. / Doup, B. / Sun, X. / American Nuclear Society et al. | 2012
- 2349
-
12326 Steady State RANS Simulations of Temperature Fluctuation in a Single Phase Turbulent MixingKickhofel, J. / Fokken, J. / Kapulla, R. / Prasser, H.-M. / American Nuclear Society et al. | 2012
- 2360
-
12226 Turbulence Analysis of Rough Wall Channel Flows Based on Direct Numerical SimulationMishra, A.V. / Bolotnov, I.A. / American Nuclear Society et al. | 2012
- 2370
-
12200 Analysis of BWR OPRM Plant Data and Detection Algorithms with DSSPPYang, J. / Vedovi, J. / Chung, A.K. / Zino, J.F. / American Nuclear Society et al. | 2012
- 2376
-
12114 Semi-Analytic Prediction of Hydraulic Resistance and Heat Transfer for Pipe and Channel Flows of Water at Supercritical PressureLaurien, E. / American Nuclear Society et al. | 2012
- 2389
-
12002 Programmable AC Power Supply for Simulating Power Transient Expected in Fusion ReactorHalimi, B. / Suh, K.Y. / American Nuclear Society et al. | 2012
- 2394
-
12284 Surveillance of PLUS7 Fuel for PWR Nuclear Power PlantJang, Y.K. / Kim, J.I. / Shin, J.C. / Chung, J.G. / Chung, S.K. / Kim, M.S. / Lee, T.H. / Yoon, Y.B. / Kim, T.W. / American Nuclear Society et al. | 2012
- 2401
-
12231 Improvements of Fuel Failure Detection in Boiling Water Reactors using Helium MeasurementsLarsson, I. / Sihver, L. / Grundin, A. / Helmersson, J.-O. / American Nuclear Society et al. | 2012
- 2407
-
12116 Effects of Cooling Time on a Closed LWR Fuel CycleArnold, R.P. / Forsberg, C.W. / Shwageraus, E. / American Nuclear Society et al. | 2012
- 2415
-
12399 Development of Pyroprocessing Technology for Thorium-fuelled Molten Salt ReactorUhlir, J. / Straka, M. / Szatmary, L. / American Nuclear Society et al. | 2012
- 2419
-
12142 Technical and Economical Impacts of the Transmutation of the Minor Actinides in a SFRGautier, G.-M. / Morin, F. / Dechelette, F. / Sanseigne, E. / Chabert, C. / American Nuclear Society et al. | 2012
- 2429
-
12054 Modelling of the Nitric Acid Reduction Process: Application to Materials Behavior in Reprocessing PlantsSicsic, D. / Balbaud-Celerier, F. / Tribollet, B. / American Nuclear Society et al. | 2012
- 2440
-
12042 Advanced Reprocessing Developments in Europe-Contribution of European Projects ACSEPT and ACTINET-I3Bourg, S. / Poinssot, C. / Geist, A. / Cassayre, L. / Rhodes, C. / Ekberg, C. / American Nuclear Society et al. | 2012
- 2447
-
12097 Gaseous Fission Product Management for Molten Salt Reactors and Vented Fuel SystemsMessenger, S.J. / Forsberg, C. / Massie, M. / American Nuclear Society et al. | 2012
- 2457
-
12202 Thermal Analysis for Ion-Exchange Column SystemLee, S.Y. / King, W.D. / American Nuclear Society et al. | 2012
- 2468
-
12343 Role of Alkyl Alcohol on Viscosity of Silica-Based Chemical Gels for Decontamination of Highly Radioactive Nuclear FacilitiesChoi, B.-S. / Yoon, S.B. / Jung, C.-H. / Lee, K.-W. / Moon, J.-K. / American Nuclear Society et al. | 2012
- 2475
-
12313 Modeling Analysis for Grout Hopper Waste TankLee, S.Y. / Ryans, J.M. / American Nuclear Society et al. | 2012
- 2485
-
12230 Radioactive Waste Management Treatments: A Selection for the Italian ScenarioLocatelli, G. / Mancini, M. / Sardini, M. / American Nuclear Society et al. | 2012
- 2495
-
12369 Path to a Commercial Fast Reactor Option in the United StatesMurray, P. / McCullum, R. / Nesbit, S. / Sowder, A. / Stout, D. / American Nuclear Society et al. | 2012
- 2502
-
12327 Impact of the Deployment Schedule of Fast Breeding Reactors in the Frame of the French Act for Nuclear Materials and Radioactive Waste ManagementLe Mer, J. / Garzenne, C. / Lemasson, D. / American Nuclear Society et al. | 2012
- 2512
-
12115 Sensitivity Analysis and Optimization of the Nuclear Fuel CyclePasserini, S. / Kazimi, M.S. / Shwageraus, E. / American Nuclear Society et al. | 2012
- 2520
-
12030 Assessment of Transition Fuel Cycle Performance with and without Modified-Open Fuel CycleFeng, B. / Kim, T.K. / Taiwo, T.A. / American Nuclear Society et al. | 2012
- 2529
-
12007 Integrating Repositories with Fuel Cycles: The Airport Authority ModelForsberg, C. / American Nuclear Society et al. | 2012
- 2537
-
12276 Micromechanical Tests of Ion Irradiated Materials: Atomistic Simulations and ExperimentsShin, C. / Jin, H. / Kwon, J. / American Nuclear Society et al. | 2012
- 2545
-
12162 Ways of Improvement for the Materials of Sodium Cooled Fast ReactorsHorowitz, E. / American Nuclear Society et al. | 2012
- 2556
-
12075 Improved Cladding Nano-structured Materials with Self-Repairing CapabilitiesPopa-Simil, L. / American Nuclear Society et al. | 2012
- 2563
-
12051 Characterization of High Performance Austenitic and ODS Alloys for SCWR ConditionsPenttila, S. / Toivonen, A. / Auerkari, P. / Novotny, R. / American Nuclear Society et al. | 2012
- 2576
-
12265 Oxidation of SiC Under Loss of Coolant Accident (LOCA) Conditions in LWRsLee, Y. / Yue, C. / Arnold, R.P. / McKrell, T.J. / Kazimi, M.S. / American Nuclear Society et al. | 2012
- 2587
-
12218 Controlling RPV Embrittlement through Wet Annealing In Support of Life Attainment and Life Extension DecisionsKrasikov, E.A. / American Nuclear Society et al. | 2012
- 2591
-
12192 An Improved Model for Pellet-Clad Interaction for FRAPCONMieloszyk, A. / Kazimi, M.S. / American Nuclear Society et al. | 2012
- 2601
-
12175 Severe Accident Modeling of a PWR Core with Different Cladding MaterialsJohnson, S.C. / Henry, R.E. / Paik, C.Y. / American Nuclear Society et al. | 2012
- 2610
-
12074 Uranium Mononitride as a Potential Commercial LWR FuelXu, P. / Yan, J. / Lahoda, E.J. / Ray, S. / American Nuclear Society et al. | 2012
- 2618
-
12372 Seismic Fragility Evaluation of a Piping System in a Nuclear Power Plant by Shaking Table Test and Numerical AnalysisKim, M.K. / Kim, J.H. / Choi, I.-K. / American Nuclear Society et al. | 2012
- 2627
-
12438 Evaluation of Irradiation Effects on Concrete StructureKontani, O. / Ishizawa, A. / Maruyama, I. / Takizawa, M. / Sato, O. / American Nuclear Society et al. | 2012
- 2635
-
12412 Analysis of Flexible Structures under Lateral ImpactRamirez, D.F. / Razavi, H. / American Nuclear Society et al. | 2012
- 2643
-
12120 Element Based Concrete Design with Three-dimensional Finite Element ModelsO Leary, M. / Huberty, K. / Winch, S. / American Nuclear Society et al. | 2012
- 2652
-
12272 Reliability of Thickness of Oxide Layer of Stainless Steels with Chromium Using Cellular Automaton ModelLan, K.-C. / Chen, Y. / Yu, G.-P. / Hung, T.-C. / American Nuclear Society et al. | 2012
- 2655
-
12314 Assessment of a Mechanistic Model in U-Pu-Zr Metallic-alloy Fuel Fission-Gas Behavior SimulationsYun, D. / Rest, J. / Yacout, A.M. / American Nuclear Society et al. | 2012
- 2663
-
12151 Microstructure Analysis for Chemical Interaction between Cesium and SUS 316 Steel in Fast Breeder Reactor ApplicationSasaki, K. / Fukumoto, K.-i. / Oshima, T. / Tanigaki, T. / Masayoshi, U. / American Nuclear Society et al. | 2012
- 2673
-
12053 Selection of Materials for Sodium Fast Reactor Steam GeneratorsGoff, S.D.-l. / Garnier, S. / Gelineau, O. / Dalle, F. / Blat-Yrieix, M. / Augem, J.M. / American Nuclear Society et al. | 2012
- 2682
-
12017 Design and Development of a High-Temperature Sodium Compatibility Materials Testing FacilityHvasta, M.G. / Nollet, B.K. / Anderson, M.H. / American Nuclear Society et al. | 2012
- 2689
-
12015 The Fast-spectrum Transmutation Experimental Facility FASTEF: Main Design Achievements (Part 2 : Reactor Building Design & Plant Layout) within the FP7-CDT Project of the European CommissionDe Bruyn, D. / Engelen, J. / Orden, A. / Aguado, M.P. / American Nuclear Society et al. | 2012
- 2695
-
12096 Flow Accelerated Erosion-Corrosion (FAC) Considerations for Secondary Side Piping in the AP1000® Nuclear Power Plant DesignVanderhoff, J.F. / Rao, G.V. / Stein, A. / American Nuclear Society et al. | 2012
- 2703
-
12150 German Experiences in Local Fatigue MonitoringAbib, E. / Bergholz, S. / Rudolph, J. / American Nuclear Society et al. | 2012
- 2711
-
12335 Development of Advanced Off-Design Models for Supercritical Carbon Dioxide Power CyclesDyreby, J.J. / Klein, S.A. / Nellis, G.F. / Reindl, D.T. / American Nuclear Society et al. | 2012
- 2719
-
12108 Preliminary Studies on the Heat Exchanger for S-CO^2 Power Conversion Cycle Coupled to Water Cooled SMRAhn, Y. / Lee, J. / Lee, J.I. / American Nuclear Society et al. | 2012
- 2728
-
12446 Gigawatt-Year Nuclear-Geothermal Energy Storage for Light-Water and High-Temperature ReactorsForsberg, C.W. / Lee, Y. / Kulhanek, M. / Driscoll, M.J. / American Nuclear Society et al. | 2012
- 2738
-
12178 Life Cycle Assessment of Hydrogen Production from S-I Thermochemical Process Coupled to a High Temperature Gas ReactorGiraldi-Diaz, M.R. / Francois, J.-L. / Castro-Uriegas, D. / American Nuclear Society et al. | 2012
- 2747
-
12039 Preliminary Design Studies on a Nuclear Seawater Desalination SystemWibisono, A.F. / Jung, Y.H. / Choi, J. / Kim, H.S. / Lee, J.I. / Jeong, Y.H. / No, H.C. / American Nuclear Society et al. | 2012
- 2758
-
12006 A Nuclear Wind/Solar Oil-Shale System for Variable Electricity and Liquid Fuels ProductionForsberg, C. / American Nuclear Society et al. | 2012
- 2766
-
12010 OECD/NEA Study on the Economics of the Long-term Operation of Nuclear Power PlantsLokhov, A. / Cameron, R. / American Nuclear Society et al. | 2012
- 2773
-
12233 Using Real Options to Evaluate the Flexibility in the Deployment of SMRLocatelli, G. / Mancini, M. / Ruiz, F. / Solana, P. / American Nuclear Society et al. | 2012
- 2783
-
12322 Investment in Different Sized SMRs: Economic Evaluation of Stochastic Scenarios by INCAS CodeBarenghi, S. / Boarin, S. / Ricotti, M.E. / American Nuclear Society et al. | 2012
- 2793
-
12005 Carbon Pricing, Nuclear Power and Electricity MarketsCameron, R. / Keppler, J.H. / American Nuclear Society et al. | 2012