Power Conversion System (PCS) Evaluation for the Next Generation Nuclear Plant (NGNP) (Englisch)
- Neue Suche nach: Johnson, G.A.
- Neue Suche nach: American Nuclear Society
- Neue Suche nach: Johnson, G.A.
- Neue Suche nach: American Nuclear Society
In:
Advances in nuclear power plants; ICAPP 2008
;
238-253
;
2008
-
ISBN:
- Aufsatz (Konferenz) / Print
-
Titel:Power Conversion System (PCS) Evaluation for the Next Generation Nuclear Plant (NGNP)
-
Beteiligte:Johnson, G.A. ( Autor:in ) / American Nuclear Society
-
Kongress:International conference, Advances in nuclear power plants; ICAPP 2008 ; 2008 ; Anaheim, CA
-
Erschienen in:
-
Verlag:
- Neue Suche nach: American Nuclear Society
-
Erscheinungsort:LaGrange Park, Ill.
-
Erscheinungsdatum:01.01.2008
-
Format / Umfang:16 pages
-
Anmerkungen:Includes bibliographical references and index
-
ISBN:
-
Medientyp:Aufsatz (Konferenz)
-
Format:Print
-
Sprache:Englisch
-
Schlagwörter:
-
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
-
IRIS: A Comprehensive Approach to Nuclear Power in Smaller Size and Developing CountriesCarelli, M.D. / Petrovic, B. / Sandell, L. / Storrick, G.D. / American Nuclear Society et al. | 2008
- 8
-
Justification and Manufacturing Quality Assurance for the Use of Hot Isostatically Pressed, Reactor Coolant System Components in PWR PLANTSulley, J.L. / Hookham, I.D. / American Nuclear Society et al. | 2008
- 21
-
EPR : High Load Variation Performances with the ``Tmode'' Core ControlGrossetete, A. / American Nuclear Society et al. | 2008
- 26
-
An Integrated PWR for Marine PropulsionLetouze, A. / Marecaux, A. / Rollason, J. / Heap, S. / Foster, A. / Jewer, S. / Thompson, A.C. / Williams, A.M. / Beeley, P.A. / American Nuclear Society et al. | 2008
- 30
-
European Passive Plant (AP1000 - Europe) Design StatusDemetri, K.J. / Saiu, G. / American Nuclear Society et al. | 2008
- 39
-
The Safety Concept of the SWR 1000 with Active and Passive Safety SystemsPasler, D. / American Nuclear Society et al. | 2008
- 46
-
SWR 1000: Efficient Design for Operational ExcellenceBrettschuh, W. / American Nuclear Society et al. | 2008
- 53
-
ESBWR Power Maneuvering Via Feedwater Temperature ControlSaha, P. / Marquino, W. / Tucker, L.J. / American Nuclear Society et al. | 2008
- 62
-
Role of Human Factors in System SafetyBrooks, D. / Robert, C. / Graham, T. / American Nuclear Society et al. | 2008
- 76
-
Coupled Regional Stability Analysis of Natural Circulation BWRsHu, R. / Kazimi, M.S. / American Nuclear Society et al. | 2008
- 87
-
SWR 1000 Integral and Full Scale Tests of the Passive Safety SystemsLeyer, S. / Wich, M. / Schafer, H. / American Nuclear Society et al. | 2008
- 93
-
Optimization Planning for the Construction of the U.S. EPRPhillips, M.K. / American Nuclear Society et al. | 2008
- 102
-
Experimental Investigation of Non-Condensable Gases Effect on Operation of VVER Steam Generator in Condensation ModeEfanov, A.D. / Kalyakin, S.G. / Morozov, A.V. / Remizov, O.V. / Tsyganok, A.A. / Generalov, V.N. / Berkovich, V.M. / Taranov, G.S. / American Nuclear Society et al. | 2008
- 110
-
European Research on Issues Concerning Hydrogen Behaviour in Containment within the SARNET Network of ExcellenceWilkening, H. / Kljenak, I. / Ambrosini, W. / Bentaib, A. / Blumenfeld, L. / Dabbene, F. / Malet, J. / Reinecke, E.-A. / Takasuo, E. / Travis, J.R. et al. | 2008
- 120
-
Economic Advantage of the Korean Nuclear Plants By Shortening the Construction SchedulePark, K.C. / Ryu, D.S. / American Nuclear Society et al. | 2008
- 127
-
Study on High Conversion Type Core of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) for Minor Actinide (MA) RecyclingFukaya, Y. / Nakano, Y. / Okubo, T. / American Nuclear Society et al. | 2008
- 136
-
A Review of Dopants Used to Increase UO~2 Burnup Capabilities by Grain Size ModificationDooies, B. / Anghaie, S. / American Nuclear Society et al. | 2008
- 145
-
A Comparative Evaluation of Pressurizer Surge Line Thermal LoadsPournaras, T. / Wiley, T. / Smouse, J. / Brice-Nash, R. / Swamy, S.A. / American Nuclear Society et al. | 2008
- 152
-
Why HTR/VHTR? A European Point of ViewBasini, V. / Bogusch, E. / Breuil, E. / Buckthorpe, D. / Chauvet, V. / Futterer, M. / van Heek, A. / Hittner, D. / von Lensa, W. / Pirson, J. et al. | 2008
- 161
-
Design, Analysis and Development of the Modular PB-AHTRBardet, P. / Blandford, E. / Fratoni, M. / Niquille, A. / Greenspan, E. / Peterson, P.F. / American Nuclear Society et al. | 2008
- 179
-
Using Helicoids to Eliminate ``Hot Streaking'' and Stratification in the Very High Temperature Reactor Lower PlenumRodriguez, S.B. / El-Genk, M. / American Nuclear Society et al. | 2008
- 188
-
Risk Minimization for Near-Term Deployment of the Next Generation Nuclear PlantLommers, L. / Southworth, F. / Riou, B. / Lecomte, M. / American Nuclear Society et al. | 2008
- 198
-
Neutronic Performance of High Molecular Weight Coolants for a Prismatic VHTRSchriener, T.M. / El-Genk, M. / American Nuclear Society et al. | 2008
- 208
-
Gas Cooled Fast Reactor 2400 MWth, End of the Preliminary Viability PhaseMalo, J.Y. / Alpy, N. / Bertrand, F. / Cadiou, T. / Chauvin, N. / Dumaz, P. / Haubensack, D. / Geffraye, G. / Jonqueres, N. / Lorenzo, D. et al. | 2008
- 219
-
Studies of Unprotected Transients and Alternative Decay Heat Removal System for the Gas Cooled Fast Reactor (GFR)Dumaz, P. / Epiney, A. / Alpy, N. / Broxtermann, P. / Malo, J.Y. / Tosello, A. / American Nuclear Society et al. | 2008
- 228
-
Preliminary Safety Analysis of the 2400 MWth Gas-Cooled Fast ReactorBertrand, F. / Bassi, C. / Bentivoglio, F. / Messie, A. / Tosello, A. / Malo, J.Y. / American Nuclear Society et al. | 2008
- 238
-
Power Conversion System (PCS) Evaluation for the Next Generation Nuclear Plant (NGNP)Johnson, G.A. / American Nuclear Society et al. | 2008
- 254
-
Means, Methods and Performances of the AREVA's HTR Compact ControlsBanchet, J. / Guillermier, P. / Tisseur, D. / Vitali, M.P. / American Nuclear Society et al. | 2008
- 260
-
Developments and Economical Aspects in the Fabrication of HTR Fuel ElementsFroschauer, K. / Brahler, G. / Heit, W. / American Nuclear Society et al. | 2008
- 265
-
Development of a Fission Product Release Analysis Code COPA-FPRELKim, Y.M. / Cho, M.S. / Lee, Y.W. / Lee, W.J. / American Nuclear Society et al. | 2008
- 273
-
Review of the Material Properties of Pyrolytic Carbon Coating Layers in Relation to QC Measurements for HTR Coated Particle FuelsLee, Y.-W. / Kim, Y.M. / Kim, W.K. / Kim, W.J. / Park, J.Y. / Cho, M.S. / American Nuclear Society et al. | 2008
- 282
-
Alloy 617 for the High Temperature Diffusion-Bonded Compact Heat ExchangersLi, X. / Kininmont, D. / Le Pierres, R. / Dewson, S.J. / American Nuclear Society et al. | 2008
- 289
-
An Optimal Loading Principle of Burnable Poisons for an OTTO Refueling Scheme in Pebble Bed HTGR CoresTran, H.N. / Kato, Y. / American Nuclear Society et al. | 2008
- 298
-
Out-of-Core Fuel Cycle Characteristics of VHTRs with No On-Site RefuelingTsvetkov, P.V. / Alajo, A.B. / Lewis, T.G. / Ames, D.E. / American Nuclear Society et al. | 2008
- 303
-
Deployment of FBR/VHTR Systems for Japan's Future Energy DemandsRichards, M. / Kunitomi, K. / American Nuclear Society et al. | 2008
- 313
-
Implications of Air Ingress Induced by Density-difference Driven Stratified FlowOh, C. / Kim, E.S. / Schultz, R. / Petti, D. / Liou, C.P. / American Nuclear Society et al. | 2008
- 323
-
A Three-Dimensional Heat Transfer Analysis on the Prismatic Fuel Elements in the Very High Temperature ReactorTak, N.-i. / Kim, M.-H. / Lee, W.-J. / American Nuclear Society et al. | 2008
- 330
-
3D Thermal Simulation of Decay Heat Removal in a HTR Half GeometryPeniguel, C. / Rupp, I. / Archambeau, F. / American Nuclear Society et al. | 2008
- 340
-
TINTE Transient Results for the OECD 400 MW PBMR BenchmarkStrydom, G. / American Nuclear Society et al. | 2008
- 351
-
Alternative Working Fluids to Reduce Size of Turbomachinery for VHTR PlantsTournier, J.-M. / El-Genk, M. / American Nuclear Society et al. | 2008
- 361
-
Thermo-Economic Performance of HTGR Brayton Power CyclesLinares, J.I. / Herranz, L.E. / Moratilla, B.Y. / Fernandez-Perez, A. / American Nuclear Society et al. | 2008
- 368
-
Thermo-Chemical Behavior of a Laboratory Scale SO~3 DecomposerKim, C.S. / Hong, S.-D. / Kim, J.-H. / Kim, Y.-W. / Lee, W.J. / American Nuclear Society et al. | 2008
- 377
-
Sodium Fast Reactors (SFRs) and RecyclersLevy, S. / American Nuclear Society et al. | 2008
- 390
-
Near-term Deployment of the Prism Sodium-fast ReactorLoewen, E.P. / American Nuclear Society et al. | 2008
- 396
-
Approach for FBR Commercialization in JapanOgata, K. / American Nuclear Society et al. | 2008
- 405
-
An Innovative Design Approach to a Cost Effective Commercial Liquid Metal ReactorCarelli, M.D. / Garkisch, H.D. / Hundal, R. / Arie, K. / Handa, H. / Ota, H. / Matsuyama, S. / Todreas, N. / Hejzlar, P. / Wells, P. et al. | 2008
- 407
-
Design Approaches from Breakeven Core to TRU Burner Core based on KALIMER-600 ReactorLim, J.-Y. / Kim, S.-J. / Kim, Y.-I. / American Nuclear Society et al. | 2008
- 414
-
Conceptual Core Designs for a 1200MWe Sodium Cooled Fast ReactorJoo, H.-K. / Lee, K.-B. / Yoo, J.-W. / Kim, Y.-I. / American Nuclear Society et al. | 2008
- 421
-
Improving SFR Economics Through Innovations from Thermal Design and Analysis AspectsZhao, H. / Zhang, H. / Mousseau, V.A. / Peterson, P.F. / American Nuclear Society et al. | 2008
- 437
-
RELAP5 Analysis of the Hybrid Loop-Pool Design for Sodium Cooled Fast ReactorsZhang, H. / Zhao, H. / Davis, C. / Memmott, M. / American Nuclear Society et al. | 2008
- 450
-
Design Studies on a Large-Scale Sodium-Cooled TRU BurnerSong, H. / Kim, S.-J. / Jeong, H.-Y. / Kim, Y.-I. / American Nuclear Society et al. | 2008
- 458
-
Inherent Safety Evaluation of Pool-type Liquid Metal Fast Reactors by a Multidimensional Thermal-hydraulic CalculationKwon, Y.M. / Ha, K.S. / Jeong, H.Y. / Chang, W.P. / Lee, Y.B. / Hahn, D. / American Nuclear Society et al. | 2008
- 466
-
Global Cooperation and Conceptual DesignIkeda, K. / Stein, K. / Nakazato, W. / Mito, M. / American Nuclear Society et al. | 2008
- 476
-
An Assessment of Annular Fuel for Sodium-Cooled Fast ReactorsMemmott, M. / Buongiorno, J. / Hejzlar, P. / American Nuclear Society et al. | 2008
- 486
-
Development of Advanced Loop-Type Fast Reactor in Japan (1): Current Status of JSFR DevelopmentKotake, S. / Mihara, T. / Kubo, S. / Aoto, K. / Toda, M. / American Nuclear Society et al. | 2008
- 496
-
Development of Advanced Loop-Type Fast Reactor in Japan (2): Technological Feasibility of Two-Loop Cooling System in JSFRYamano, H. / Kubo, S. / Kurisaka, K.-i. / Shimakawa, Y. / Sago, H. / American Nuclear Society et al. | 2008
- 505
-
Development of Advanced Loop-Type Fast Reactor in Japan (3): Easy Inspection and High Reliable Reactor Structure in JSFRSakamoto, Y. / Kubo, S. / Kotake, S. / Kamishima, Y. / American Nuclear Society et al. | 2008
- 512
-
Development of Advanced Loop-Type Fast Reactor in Japan (4): An Advanced Design of the Fuel Handling System for the Enhanced Economic CompetitivenessUsui, S. / Mihara, T. / Obata, H. / Kotake, S. / American Nuclear Society et al. | 2008
- 519
-
Development of Advanced Loop-Type Fast Reactor in Japan (5): Adoption of Self-Actuated Shutdown System to JSFRNakanishi, S. / Kubo, S. / Takamatsu, M. / Ikarimoto, I. / Kato, J. / Shimakawa, Y. / Harada, K. / American Nuclear Society et al. | 2008
- 526
-
Development of Advanced Loop-Type Fast Reactor in Japan (6): Minor Actinide Containing Oxide Fuel Core Design Study for the JSFRNaganuma, M. / Ogawa, T. / Ohki, S. / Mizuno, T. / Kubo, S. / American Nuclear Society et al. | 2008
- 536
-
Studies on French SFR Advanced Core DesignsMignot, G. / Klein, J.C. / Chenaud, M.S. / Thevenot, C. / Ravenet, A. / Pelletier, M. / Valentin, B. / Masoni, P. / Dubuisson, P. / Delafontaine, S. et al. | 2008
- 546
-
Innovative Steam Generator Concepts for Sodium Fast ReactorsGiraud, B. / Mauget, C. / Capitaine, A. / Laffont, G. / American Nuclear Society et al. | 2008
- 553
-
Sodium Fast Reactor ConceptsFrancois, G. / Serpantie, J.P. / Sauvage, J.F. / Pinto, P.L. / American Nuclear Society et al. | 2008
- 565
-
The Use of Gas Based Energy Conversion Cycles for Sodium Fast ReactorsSaez, M. / Haubensack, D. / Aply, N. / Gerber, A. / David, F. / American Nuclear Society et al. | 2008
- 574
-
Scoping Investigation into Viability of a Lead-Cooled Fast Reactor Demonstration Test Reactor (Demo)Sienicki, J.J. / Moisseytsev, A. / Tzanos, C.P. / American Nuclear Society et al. | 2008
- 584
-
A Design and Safety Features of Small CANDLE Fast ReactorSekimoto, H. / Yan, M. / American Nuclear Society et al. | 2008
- 593
-
Nuclear Safety Evaluation of a LBE Cooled Transmutation Reactor - PEACER-300Lim, J.-Y. / Kim, M.-H. / Hwang, I.-S. / American Nuclear Society et al. | 2008
- 601
-
Development of Transportable Capsule Version of PEACER DesignHwang, I.S. / Kim, M.H. / Joo, H.G. / Yoo, B. / Oh, S.R. / Yi, K.W. / Han, D.Y. / Lim, J. / Nam, H.O. / American Nuclear Society et al. | 2008
- 611
-
Design and Analysis of 900 MWt Lead-Cooled Fast ReactorKim, S.J. / Kim, Y. / Hong, S. / Cho, C.H. / Eoh, J.-h. / Kim, J.B. / Wi, M.H. / Ha, K.S. / Kim, E.K. / American Nuclear Society et al. | 2008
- 620
-
A 2400 MWth Liquid Lead-Cooled Flexible Conversion Ratio (FCR) ReactorNikiforova, A. / Hejzlar, P. / Todreas, N. / Fong, C.J. / American Nuclear Society et al. | 2008
- 632
-
Corrosion Test of Cr- and Al-containing Alloys in Static LBE at 550 ^oCLim, J. / Nam, H.O. / Hwang, I.S. / American Nuclear Society et al. | 2008
- 638
-
Comparison of the Hydraulics in Concentric and Three Feeder XT-ADS Windowless Spallation Target DesignsRoelofs, F. / Siccama, N.B. / de Jager, B. / van Tichelen, K. / Dierckx, M. / Heyse, J. / Rosseel, K. / Schuurmans, P. / American Nuclear Society et al. | 2008
- 643
-
Application of a Controlled Swirl in the XT-ADS Spallation TargetRoelofs, F. / Siccama, N.B. / Jeanmart, H. / van Tichelen, K. / Dierckx, M. / Schuurmans, P. / American Nuclear Society et al. | 2008
- 649
-
Progress within the European Project: ``High Performance Light Water Reactor Phase 2'' (HPLWR Phase 2)Starflinger, J. / Schulenberg, T. / Marsault, P. / Bittermann, D. / Maraczy, C. / Laurien, E. / Lycklama, J.-A. / Anglart, H. / Aksan, N. / Ruzickova, M. et al. | 2008
- 660
-
Coolant Mixing in the Plenum of the HPLWR Three Pass CoreWank, A. / Schulenberg, T. / Class, A. / American Nuclear Society et al. | 2008
- 670
-
Determination of Mixing Coefficients in a Wire-Wrapped HPLWR Fuel Assembly using CFDHimmel, S. / Class, A. / Laurien, E. / Schulenberg, T. / American Nuclear Society et al. | 2008
- 680
-
Numerical Simulation of a HPLWR Fuel Assembly Flow With Wrapped Wire SpacersKiss, A. / Laurien, E. / Aszodi, A. / American Nuclear Society et al. | 2008
- 690
-
Thermo-Mechanical Stress and Deformation Analysis of a HPLWR Pressure Vessel and Steam PlenumFischer, K. / Redon, T. / Millet, G. / Koehly, C. / Schulenberg, T. / American Nuclear Society et al. | 2008
- 700
-
Coupling Analysis on a New SCWR Core DesignLiu, X.J. / Cheng, X. / American Nuclear Society et al. | 2008
- 708
-
Prediction of Overheated Zones along the Wall of Strongly Heated Quasi-Fully Developed Pipe Flow at Supercritical PressureLaurien, E. / Rashid, M. / American Nuclear Society et al. | 2008
- 716
-
Summary for Three Different Validation Cases of Coolant Flow in Supercritical Water Test Sections with the Code ANSYS CFX 11.0Kiss, A. / Aszodi, A. / American Nuclear Society et al. | 2008
- 726
-
Reactor Physical Program in the frame of the MSR-SPHINX Transmuter Concept DevelopmentHron, M. / Mikisek, M. / American Nuclear Society et al. | 2008
- 733
-
Design Options for the Advanced High-Temperature ReactorForsberg, C.W. / Peterson, P.F. / Kochendarfer, R.A. / American Nuclear Society et al. | 2008
- 750
-
Use of a Liquid Salt Nuclear Reactor to Transmute Minor ActinidesStein, K.O. / Kochendarfer, R.A. / Maddox, J.W. / American Nuclear Society et al. | 2008
- 755
-
Designing the Advanced High-Temperature Reactor for Low Radionuclide Releases in Beyond-Design-Basis AccidentsForsberg, C.W. / American Nuclear Society et al. | 2008
- 768
-
Initial Status and Test Results from a Supercritical CO~2 Brayton Cycle Test LoopWright, S.A. / Fuller, R. / Pickard, P.S. / Vernon, M.E. / American Nuclear Society et al. | 2008
- 776
-
Design of Small Centrifugal Compressor Test Model for a Supercritical CO~2 Compressor in the Fast Reactor Power PlantMuto, Y. / Ishizuka, T. / Aritomi, M. / American Nuclear Society et al. | 2008
- 784
-
Dynamic Modeling of the S-CO~2 Recompression CycleCarstens, N.A. / Vilim, R.B. / Hejzlar, P. / Driscoll, M.J. / American Nuclear Society et al. | 2008
- 799
-
Controllability of the Supercritical Carbon Dioxide Brayton Cycle Near the Critical PointMoisseytsev, A. / Sienicki, J.J. / American Nuclear Society et al. | 2008
- 810
-
Supercritical CO~2 Brayton Cycle Compression and Control Near the Critical PointWright, S.A. / Fuller, R. / Noall, J. / Radel, R. / Vernon, M.E. / Pickard, P.S. / American Nuclear Society et al. | 2008
- 820
-
Comparative Analysis of Supercritical CO~2 Power Conversion System Control SchemesVilim, R.B. / Moisseytsev, A. / American Nuclear Society et al. | 2008
- 831
-
Preliminary Design of Turbomachinery for the Supercritical Carbon Dioxide Brayton Cycle Coupled to the KALIMER-600Cha, J.E. / Kim, S.O. / Kim, T.W. / Seo, K.Y. / American Nuclear Society et al. | 2008
- 837
-
Dynamic System Analysis of a Supercritical CO~2 Compression LoopVilim, R.B. / Wright, S.A. / Vernon, M. / Radel, R. / Pickard, P.S. / American Nuclear Society et al. | 2008
- 844
-
Instrumentation and Control and Human Machine Interface Science and Technology Roadmap in Support of Advanced Reactors and Fuel Programs in the U.SMiller, D.W. / Arndt, S.A. / Dudenhoeffer, D. / Hallbert, B. / Bond, L.J. / Holcomb, D.E. / Wood, R.T. / Naser, J.A. / O Hara, J. / Quinn, E.L. et al. | 2008
- 853
-
A Novel Approach to Modeling Single Event Upsets in Digital Microelectronic DevicesCetiner, S.M. / Celik, C. / Unlu, K. / Narayanan, V. / Irwin, M.J. / Xie, Y. / American Nuclear Society et al. | 2008
- 861
-
Licensing of Simple Digital DevicesJackson, T.W. / American Nuclear Society et al. | 2008
- 865
-
Switching Scheme of Data Communication Network for Safety System in Nuclear Power PlantPark, J.-Y. / Keum, J.-Y. / Koo, I.-S. / American Nuclear Society et al. | 2008
- 871
-
An Advanced Protection System for the SHIN-KORI 3&4 Nuclear Power PlantKim, Y.H. / Kwon, J.S. / Choi, W.S. / Ridolfo, C.F. / Wilkosz, S. / American Nuclear Society et al. | 2008
- 878
-
Top-Mounted Incore Instrumentation Insertion Test for Westinghouse AP1000Kindred, T.A. / Kistler, D.P. / Prible, M.C. / Hahn, J. / Iacovino, J. / Heibel, M.D. / American Nuclear Society et al. | 2008
- 888
-
Design of a Software Training System for Severe Accident Mitigation of Korean Standard Nuclear Power PlantsKim, K.-R. / Park, S.-Y. / Song, Y.-M. / American Nuclear Society et al. | 2008
- 892
-
APR1400 I&C Architecture with the Advanced Design Feature Including High Reliability and MaintainabilityKang, S.K. / Bae, B.H. / Ye, S.H. / American Nuclear Society et al. | 2008
- 899
-
Strategy for Establishing Integrated I&C Reliability of Operating Nuclear Power Plants in KoreaKang, H.T. / Chung, H.Y. / Lee, Y.H. / American Nuclear Society et al. | 2008
- 904
-
Westinghouse AP1000 Protection and Safety Monitoring SystemOdess-Gillett, W.R. / Vitalbo, C.A. / American Nuclear Society et al. | 2008
- 911
-
Steam Generator Asset Management Model ApplicationPop, M.G. / Shoemaker, P. / Colgan, K. / Griffith, J. / American Nuclear Society et al. | 2008
- 918
-
An Experience in Low Temperature Stress Corrosion Cracking at Steam Generator Coldleg Drain Nozzle for YGN 3 UnitLee, S.K. / Lee, S.H. / American Nuclear Society et al. | 2008
- 928
-
Fatigue Crack Growth Impact on Leak-Before-Break Due to Mechanical Stress Improvement ProcessHankinson, S.F. / Pournaras, T.J. / Wiley, T.F. / Smouse, J.A. / Ng, C.K. / Bhowmick, D. / Swamy, S.A. / American Nuclear Society et al. | 2008
- 934
-
Effect of Structural Weld Overlay on Recommended Leak - Before - Break MarginsBhowmick, D. / Swamy, S. / Udyawar, A. / American Nuclear Society et al. | 2008
- 938
-
Technology Success: Integration of Power Plant Reliability and Effective MaintenanceFerguson, K. / American Nuclear Society et al. | 2008
- 945
-
Reliability Database Development and Plant Performance Improvement Effort at Korea Hydro & Nuclear Power CoOh, S.-J. / Hwang, S.-W. / Na, J.-H. / Lim, H.-S. / American Nuclear Society et al. | 2008
- 950
-
Risk-Informed Assessment of the Scope and Frequency of Technical Service and Repair at the Kozloduy Nuclear Power PlantPopov, V. / Vladimirova, V. / Georgiev, G. / Ivanov, I. / Andre, G. / Kitzmiller, J. / American Nuclear Society et al. | 2008
- 959
-
Risk-Informed Assessment of the Scope and Frequency of Testing at the Kozloduy Nuclear Power PlantKichev, E. / Topalov, T. / Mancheva, K. / Ivanov, L. / Kamenov, K. / Andre, G. / McLaughlin, D. / American Nuclear Society et al. | 2008
- 968
-
Application of Systems Engineering to Nuclear Power Plant DesignKim, H.H. / Baik, J.H. / Choi, T.S. / Oh, K.S. / Kim, D.H. / American Nuclear Society et al. | 2008
- 975
-
Passing of Reactors WWER-1000 of NPP Kozloduy - Bulgaria to Extended Fuel Cycle Operation (Implementation of ^2^3^5U Higher Enriched Fuel)Dobrevski, I.D. / Zaharieva, N.N. / Minkova, K. / Peychinov, T. / Ivanova, R.A. / Michaylov, G.D. / Penev, P.G. / Gerchev, N. / American Nuclear Society et al. | 2008
- 984
-
Assessment of Core Cooling Capability of Emergency Core Cooling System in LBLOCA Condition for TAPS#3&4Kumar, N. / Yadav, S.K. / Khan, T.A. / Singhal, M. / Rammohan, H.P. / Malhotra, P.K. / Ghadge, S.G. / American Nuclear Society et al. | 2008
- 994
-
Large Break LOCA Analysis for TAPS-3&4 using RELAP-5/MOD 3.2Sharma, S.L. / Rammohan, H.P. / Malhotra, P.K. / Ghadge, S.G. / American Nuclear Society et al. | 2008
- 1001
-
Large Break Loss of Coolant Accident Analysis of VVER-1000 Reactor Using CATHARE CodeSabotinov, L. / Srivastava, A. / American Nuclear Society et al. | 2008
- 1010
-
Assessment on the Integrity of Component Cooling Water System During DBA with LOOP for Kori 3&4Kim, H.T. / Lee, S.B. / Lee, S.W. / Park, Y.C. / American Nuclear Society et al. | 2008
- 1017
-
Improvement of the Interfacial Drag Model in TRAC-PF1/IBER to Simulate Downcomer Boiling PhenomenaBermejo, J.A. / Concejal, A. / Orive, R. / Garcia, P. / American Nuclear Society et al. | 2008
- 1024
-
Sensitivity Studies on Uncertainty Parameters and Code Modeling During LBLOCAOh, D.-Y. / Bang, Y.S. / Huh, B.G. / Woo, S.W. / Cho, Y.J. / American Nuclear Society et al. | 2008
- 1031
-
Evaluation of Radiological Effects Due to Injection of Argon Gases into Reactor Coolant SystemNam, K. / Im, C. / Sohn, W. / Kang, D.-w. / American Nuclear Society et al. | 2008
- 1039
-
Dynamic Structural Analysis Concerning Integrity Assessment of a Reinforced Concrete Ceiling Due to Impact LoadsSievers, J. / Eisert, P. / Bachmann, P. / American Nuclear Society et al. | 2008
- 1057
-
Effect of Break Size on Severe Core Damage Behaviour for VVER 1000 Reactor with the ASTEC V1 CodeChatterjee, B. / Mukhopadhyay, D. / Lele, H.G. / Ghosh, A.K. / American Nuclear Society et al. | 2008
- 1064
-
MAAP4.0.7 Analysis and Justification for PRA Level 1 Mission Success CriteriaButler, J.S. / Kapitz, D. / Martin, R.P. / Seifaee, F. / Sundaram, R.K. / American Nuclear Society et al. | 2008
- 1076
-
MAAP4.0.7 Severe Accident Source Term AnalysisSlaga, A.C. / Levinson, S.H. / Prior, R. / Gerlits, D. / American Nuclear Society et al. | 2008
- 1086
-
Analysis of Station Blackout in the Gosgen Nuclear PlantHaste, T. / Birchley, J. / Klugel, J.-U. / American Nuclear Society et al. | 2008
- 1095
-
SCDAP/RELAP5 Investigation on Coolability of Severely Degraded CANDU 6 Core - Preliminary ResultsDupleac, D. / Prisecaru, I. / Mladin, M. / Negut, G. / American Nuclear Society et al. | 2008
- 1102
-
Relevant Scenarios and Uncertainty Analysis of Severe Accidents in the U.S. EPRMartin, R.P. / Bingham, M.W. / Williams, E. / Caillaux, A. / American Nuclear Society et al. | 2008
- 1110
-
Recent Revisions to MAAP4 for U.S. EPR Severe Accident ApplicationsWilliams, E. / Martin, R. / Gandrille, P. / Meireles, R. / Prior, R. / Henry, C. / Zhou, Q. / American Nuclear Society et al. | 2008
- 1122
-
AREVA NP's Severe Accident Safety Issue Resolution Methodology for the U.S. EPRMartin, R.P. / Bingham, M.W. / Bonilla, C.A. / Butler, J.S. / Duncan-Whiteman, P.D. / Gruenewald, P. / Slaga, A.C. / Williams, E. / Azarian, G. / Nie, M. et al. | 2008
- 1132
-
Influence of Jet Breakup Modeling on Ex-Vessel Steam Explosion Simulation ResultsLeskovar, M. / American Nuclear Society et al. | 2008
- 1141
-
Modeling of Two-Phase Natural Convection Flows in a Water Pool with a Decay-Heated Debris BedYakush, S. / Kudinov, P. / Dinh, T.-N. / American Nuclear Society et al. | 2008
- 1151
-
Thermodynamic Analysis for the Melt Pool Configuration During the Severe Accidents in the APR1400Kang, K.-H. / Park, R.-J. / Hong, S.-W. / American Nuclear Society et al. | 2008
- 1156
-
Transient Conduction Heat Transfer Modelling in Concrete for the Simulation of Long Term Phase of Molten Core Concrete InteractionTourniaire, B. / Spindler, B. / Guillaume, M. / American Nuclear Society et al. | 2008
- 1163
-
Interaction Between Molten Corium UO~2~+~x- ZrO~2- FeO~y and VVER Vessel SteelBechta, S.V. / Granovsky, V.S. / Khabensky, V.B. / Krushinov, E.V. / Vitol, S.A. / Sulatsky, A.A. / Gusarov, V.V. / Almiashev, V.I. / Lopukh, D.B. / Bottomley, D. et al. | 2008
- 1172
-
European Research on the Corium Issues within the SARNET Network of ExcellenceJourneau, C. / Bonnet, J.M. / Godin-Jacqmin, L. / Piluso, P. / Tarabelli, D. / American Nuclear Society et al. | 2008
- 1182
-
Pre-Test Calculational Support for the QUENCH-13 ExperimentHaste, T. / Birchley, J. / Lamy, J.-S. / Maliverney, B. / Austregesilo, H. / Bals, C. / Trambauer, K. / Steinbruck, M. / Stuckert, J. / American Nuclear Society et al. | 2008
- 1191
-
An Experimental Study on Debris Formation with Corium Simulant MaterialsKudinov, P. / Karbojian, A. / Ma, W. / Dinh, T.-N. / American Nuclear Society et al. | 2008
- 1200
-
An Investigation on the Material Effect on the Result of Fuel Coolant Interactions in the TROI ExperimentsPark, I.K. / Kim, J.H. / Min, B.T. / Hong, S.W. / American Nuclear Society et al. | 2008
- 1209
-
Comparison of the High Temperature Steam Oxidation Kinetics of Advanced Cladding MaterialsGrosse, M. / American Nuclear Society et al. | 2008
- 1215
-
Towards a Comprehensive Interpretation of MCCI 2D testsSeiler, J.M. / Tourniaire, B. / American Nuclear Society et al. | 2008
- 1223
-
Measurements of the Mechanical Strength of Corium CrustsLomperski, S. / Farmer, M.T. / American Nuclear Society et al. | 2008
- 1233
-
Differences Between Silica and Limestone Concretes That May Affect Their Interaction with CoriumJourneau, C. / Haquet, J.-F. / Piluso, P. / Bonnet, J.-M. / American Nuclear Society et al. | 2008
- 1241
-
Current European Experiments on 2D Molten Core Concrete Interaction: HECLA and VULCANOJourneau, C. / Bonnet, J.M. / Boccaccio, E. / Piluso, P. / Sevon, T. / Pankakoski, P.H. / Holmstrom, S. / Virta, J. / American Nuclear Society et al. | 2008
- 1251
-
Interpretation of Real Material 2D MCCI Experiments in Homogeneous Oxidic Pool with the ASTEC/MEDICIS CodeCranga, M. / Mun, C. / Michel, B. / Duval, F. / Barrachin, M. / American Nuclear Society et al. | 2008
- 1261
-
Application of the ASTEC V1 Code to the LIVE-L1 ExperimentMiassoedov, A. / Godin-Jacqmin, L. / Bachrata, A. / Cron, T. / Gaus-Liu, X. / Wenz, T. / American Nuclear Society et al. | 2008
- 1270
-
Experimental and Post-Test Calculation Results of the Integral Reflood Test QUENCH-12 with a VVER-type BundleStuckert, J. / Birchley, J. / Grosse, M. / Haste, T. / Sepold, L. / Steinbruck, M. / American Nuclear Society et al. | 2008
- 1280
-
Direct Containment Heating Experiments for Konvoi Power PlantsMeyer, L. / Albrecht, G. / American Nuclear Society et al. | 2008
- 1291
-
Triggered Steam Explosions with Corium Melts of Various Compositions in a Narrow Interaction Vessel in the TROI FacilityKim, J.H. / Min, B.T. / Park, I.K. / Kim, H.D. / Hong, S.W. / American Nuclear Society et al. | 2008
- 1300
-
A Study on the Operator's Communication Pattern Characteristics Under Abnormal Operating Situation of Nuclear Power PlantsKim, S.H. / Park, J. / American Nuclear Society et al. | 2008
- 1307
-
Mechanism-based Ageing Management of Primary Water Stress Corrosion Cracking of Ni-base Components in PWR EnvironmentsLee, T.H. / Hwang, I.S. / American Nuclear Society et al. | 2008
- 1315
-
A Study on the Verification and Validation of Programmable Logic Component in a Nuclear Power PlantPark, G.Y. / Kim, D.I. / Jung, C.H. / American Nuclear Society et al. | 2008
- 1320
-
U.S. NRC's Generic Issues ProgramKauffman, J.V. / Foster, J.W. / American Nuclear Society et al. | 2008
- 1324
-
Korean Experience in Periodic Safety Reviews and Safety Improvements of Operating Nuclear Power PlantsKim, I.-G. / Ha, J.-T. / Kim, K.-T. / American Nuclear Society et al. | 2008
- 1332
-
Introduction of Regulatory Guide on Cyber Security of I&C Systems in Nuclear FacilitiesKang, Y. / Jeong, C.-H. / Kim, D.I. / American Nuclear Society et al. | 2008
- 1338
-
Resolution of Digital Instrumentation and Control and Human Factors Technical and Regulatory Issues for New Plants and for Modernization of Operating PlantsNaser, J.A. / Torok, R.C. / Canavan, K.T. / American Nuclear Society et al. | 2008
- 1347
-
Treatment of Complementary Events in Event Trees in Constructing Linked Fault Trees for Level 1 and Level 2 PRAJo, Y.G. / American Nuclear Society et al. | 2008
- 1357
-
Spatial Interactions Database Development for Effective Probabilistic Risk AssessmentLiming, J.K. / Dunn, R.F. / American Nuclear Society et al. | 2008
- 1364
-
SIMPROC: Procedures Simulator for Operator Actions in NPPsGil, J. / Esperon, J. / Gamo, L. / Fernandez, I. / Gonzalez, P. / Moreno, J. / Queral, C. / Exposito, A. / Jimenez, G. / Hortal, J. et al. | 2008
- 1373
-
A Study on Uncertainties Evaluation in Containment Event TreeSugiyama, H. / Hamazaki, R. / Matsumoto, T. / Hirokawa, N. / American Nuclear Society et al. | 2008
- 1382
-
The Comparison of Frequency-Consequence (F-C) Criteria In Evaluating the Risk of New or Existing ReactorMyeng, O.K. / Ahn, S.-K. / Yoon, W.-H. / Lee, H.-J. / American Nuclear Society et al. | 2008
- 1391
-
Overview of the Activities of the OECD/NEA/NSC Working Party on Nuclear Criticality SafetyRugama, Y. / Blomquist, R. / Raap, M.B. / Briggs, B. / Gulliford, J. / Miyoshi, Y. / Suyama, K. / American Nuclear Society et al. | 2008
- 1394
-
Drafting and Implementation of a ``Practical Elimination'' Approach for GEN IV Nuclear ReactorsClement, C. / Maliverney, B. / Mulet-Marquis, D. / Sauvage, J.F. / Blanchard, M.T. / Guesdon, B. / Carluec, B. / Ehster, S. / Greneche, D. / Anzieu, P. et al. | 2008
- 1399
-
EFIT Reactor Simulation Coupling Neutronics/Thermal-hydraulics with the RELAP5/PARCS CodeMeloni, P. / Bandini, G. / Polidori, M. / American Nuclear Society et al. | 2008
- 1407
-
Comparative Review of Design and Improved Safety Features of New LWR PlantsChomat, A. / Anghaie, S. / American Nuclear Society et al. | 2008
- 1421
-
Verification and Validation of Almaraz NPP TRACE ModelQueral, C. / Exposito, A. / Jimenez, G. / Valle, L. / Martinez-Murillo, J.C. / American Nuclear Society et al. | 2008
- 1429
-
Parametric Sensitivity Study on the Reflooding Models of the MARS Code Based on 6x6 Rod Bundle Test ResultsChoi, K.-Y. / Cho, S. / Cho, H.-K. / Song, C.-H. / American Nuclear Society et al. | 2008
- 1436
-
Implementation of a New Controlling Function in MELCOR Computer Code for Uncertainty EvaluationsPetkov, P.V. / American Nuclear Society et al. | 2008
- 1443
-
TRACG Statistical Method for BWR Loss-of-coolant Accident AnalysesSarikaya, B. / Andersen, J.G.M. / Bolger, F.T. / Fitch, J.R. / Heck, C.L. / Klebanov, L.A. / Muftuoglu, A.K. / Shiralkar, B.S. / Shum, F.D. / Rock, D.T. et al. | 2008
- 1447
-
BFBT Benchmark Sub-Channel Analysis with RELAP5-3D CodeKovtonyuk, A. / Petruzzi, A. / D Auria, F. / American Nuclear Society et al. | 2008
- 1457
-
Assessment of Compensating Error in the WCOBRA/TRAC-TF2 Thermal-Hydraulic CodeShockling, M.A. / Frepoli, C. / American Nuclear Society et al. | 2008
- 1466
-
Development and Qualification of the Coupled Code System COBRATF/THREEDANT for the Pin-by-Pin Power CalculationSanchez, V. / Al-Hamry, A. / Broeders, C.H.M. / American Nuclear Society et al. | 2008
- 1474
-
An Improved Horizontal Flow Regime Map For The 1-D Module of WCOBRA/TRACTF2Frepoli, C. / Liao, J. / Ohkawa, K. / American Nuclear Society et al. | 2008
- 1486
-
Full-size and Scaled 3-loop Reactor Vessel Simulation for Boron Dilution Studies Using CFDDury, T.V. / Dhotre, M.T. / American Nuclear Society et al. | 2008
- 1498
-
MELCOR Validation Against a PUMA Facility Main Steam Line Break Integral TestLiao, Y. / Vierow, K. / Han, J.T. / American Nuclear Society et al. | 2008
- 1506
-
An Integral Effect Test on the Reflood Period of a Large-Break LOCA for the APR1400 Using the ATLASPark, H.S. / Choi, K.Y. / Cho, S. / Kang, K.H. / Choi, N.H. / Euh, D.J. / Kim, Y.S. / Baek, W.P. / American Nuclear Society et al. | 2008
- 1516
-
Experimental Validation of a Core Heat Transfer Model in the TASS/SMR Code Using Film Boiling DataLee, S.W. / Kim, S.H. / Chung, Y.J. / American Nuclear Society et al. | 2008
- 1520
-
PC-based Simulator PCTRAN for Advanced Nuclear Power PlantsCliff, L.-c. / American Nuclear Society et al. | 2008
- 1528
-
Analysis of Dynamic Behavior of MEGAPIE Cooling SystemCheng, X. / Class, A. / American Nuclear Society et al. | 2008
- 1537
-
Development of Evaluation System of Safety Margin effects for Degradation of CANDU Reactors Using RELAP-CANDUChoi, Y.W. / Yoo, J.S. / Lee, U.C. / Kim, M. / Lee, S.-K. / American Nuclear Society et al. | 2008
- 1547
-
Testing Programs Related to Potential Adverse Flow Effects In Nuclear Power PlantsRajan, J. / Turlin, A. / Scarbrough, T. / American Nuclear Society et al. | 2008
- 1556
-
The TRABSMABRE for 3D Plant Transient and Accident AnalysesMiettinen, J. / Raty, H. / Daavittila, A. / American Nuclear Society et al. | 2008
- 1566
-
Analysis of Beyond Design Basis Accidents in Spent Fuel Pools of the Ignalina NPPKaliatka, A. / Ognerubov, V. / Vaisnoras, M. / Uspuras, E. / Trambauer, K. / American Nuclear Society et al. | 2008
- 1576
-
Subchannel Analysis of CANDU-SCWR FuelLi, C. / Shan, J. / Leung, L.K.H. / American Nuclear Society et al. | 2008
- 1585
-
GNF2 Counter-Current Flow Limitation TestingDiller, P.R. / Abdollahian, D. / Andersen, J.G.M. / American Nuclear Society et al. | 2008
- 1593
-
Interfacial Momentum Exchange Models Used in Nuclear Reactor System Analysis CodesPark, J.-W. / Chung, B.-D. / American Nuclear Society et al. | 2008
- 1597
-
Thermohydrodynamic Analysis of Reactor Vessel Auxiliary Cooling System for Lead-Cooled Battery Omnibus Reactor Integral SystemSon, H.M. / Suh, K.Y. / American Nuclear Society et al. | 2008
- 1606
-
Development of a High Fidelity System Analysis Code for Generation IV ReactorsZhang, H. / Mousseau, V.A. / Zhao, H. / American Nuclear Society et al. | 2008
- 1616
-
Multidimensional Analysis of Developing Two-phase Flows in an ESBWR Chimney with and without Riser ChannelsMurakawa, H. / Antal, S.P. / Lahey, R.T. / American Nuclear Society et al. | 2008
- 1635
-
On the Modeling of Channel-to Channel Oscillations in Boiling Water ReactorsRoubaud, S. / Podowski, M.Z. / American Nuclear Society et al. | 2008
- 1650
-
Heat Transfer in Intermediate Heat Exchanger Under Low Flow Rate ConditionsMochizuki, H. / American Nuclear Society et al. | 2008
- 1659
-
Identification of the Relation between Turbulence Coefficient and Local Wall Thinning inside Carbon Steel PipingHwang, K.M. / Woo, L. / Jin, T.E. / Kim, K.H. / American Nuclear Society et al. | 2008
- 1666
-
Theoretical and Experimental Study of Steam Condensation Induced Water Hammer PhenomenaBarna, I.F. / Baranyai, G. / Ezsol, G. / American Nuclear Society et al. | 2008
- 1673
-
Transient Accident Analysis of the Glovebox System in a Large Process RoomLee, S.Y. / American Nuclear Society et al. | 2008
- 1682
-
Pressure Drop Characteristics of Cross-Shaped Spiral (CSS) Rod Bundles for LWRsConboy, T. / McKrell, T. / Hejzlar, P. / Kazimi, M.S. / American Nuclear Society et al. | 2008
- 1692
-
Application of the Subchannel Analysis Code MATRA for Low Flow and Low Pressure ConditionsSeo, K.-W. / Hwang, D.-H. / Lee, C.-C. / American Nuclear Society et al. | 2008
- 1699
-
Optimizing Critical Heat Flux Enhancement Through Nanoparticle-Based Surface ModificationsTruong, B. / Hu, L.-W. / Buongiorno, J. / American Nuclear Society et al. | 2008
- 1707
-
Applications of Nanofluids to Enhance LWR Accidents Management in Invessel Retention and Emergency Core Cooling SystemsChupin, A. / Hu, L.-W. / Buongiorno, J. / American Nuclear Society et al. | 2008
- 1715
-
Thermal-fluid characterizations of ZnO and SiC Nanofluids for Advanced Nuclear Power PlantsBang, I.C. / American Nuclear Society et al. | 2008
- 1725
-
Evaluation of Crack Opening Area, Leak Rate and Probabilistic Models in CANTIARevankar, S.T. / Wolf, B. / Riznic, J.R. / American Nuclear Society et al. | 2008
- 1735
-
Condensation Correlation for a Vertical Passive Condenser SystemRevankar, S.T. / Oh, S. / Zhou, W. / Henderson, G. / American Nuclear Society et al. | 2008
- 1744
-
Pressure Loss Coefficient Evaluation Based on CFD Analysis for Simple Geometries and PWR Reactor Vessel Without Geometry SimplificationKo, B.I. / Park, J.P. / Jeong, J.H. / American Nuclear Society et al. | 2008
- 1754
-
CFD Estimation of the Heat Transfer Due to the Natural Convection in a CEA Extension Shaft Guide TubeKim, S.H. / Kim, Y.I. / Park, C.T. / Seo, J.K. / American Nuclear Society et al. | 2008
- 1762
-
System / CFD Coupling For Reactor Transient Analysis. An Application to the Gas Fast Reactor with CATHARE And TRIO_UPerdu, F. / Vandroux, S. / American Nuclear Society et al. | 2008
- 1770
-
A CFD Solver with Variable Gas Properties for Applications to High Temperature Gas-Cooled ReactorsCharmeau, A. / Anghaie, S. / American Nuclear Society et al. | 2008
- 1779
-
Free Surface Modeling and Simulation of the Water Experiment for the XT ADS Spallation TargetBatta, A. / Class, A. / American Nuclear Society et al. | 2008
- 1787
-
CFD Calculations of the Fuel Assembly of VVER-440 Type PWR ReactorsFarkas, I. / American Nuclear Society et al. | 2008
- 1792
-
RANS-based CFD Simulations of Wire-Wrapped Fast Reactor Fuel AssembliesPointer, W.D. / Fischer, P. / Siegel, A. / Smith, J. / American Nuclear Society et al. | 2008
- 1802
-
CFD Predictions of Heat Transfer in the Super Critical Flow RegimeVisser, D.C. / Nijeholt, J.A.L.a. / Roelofs, F. / American Nuclear Society et al. | 2008
- 1813
-
CFD Study on Coolant Mixing in VVER-440 Fuel Assembly HeadToth, S. / Aszodi, A. / American Nuclear Society et al. | 2008
- 1824
-
Evaluation of Two-phase Flow Characteristics in Steam Separator by Using a CFD CodeChaki, M. / Katono, K. / Kataoka, H. / Tomiyama, A. / American Nuclear Society et al. | 2008
- 1832
-
k-E modeling using Modified Nodal Integral MethodSingh, S. / Rizwan-uddin, R. / American Nuclear Society et al. | 2008
- 1843
-
Supercritical Water Heat Transfer in a Vertical Bare Tube: Normal, Improved and Deteriorated RegimesPioro, I.L. / Kirillov, P.L. / Mokry, S.J. / Gospodinov, Y.K. / American Nuclear Society et al. | 2008
- 1853
-
LWR Containment Safety Research in PANDAPaladino, D. / Huggenberger, M. / Andreani, M. / Gupta, S. / Guentay, S. / Dreier, J. / Prasser, H. / American Nuclear Society et al. | 2008
- 1862
-
Interfacial Area Transport in Horizontal Bubbly Flow with Elbow RestrictionsTalley, J. / Kim, S. / Kojasoy, G. / American Nuclear Society et al. | 2008
- 1873
-
High Temperature Irradiation Resistant Thermocouples - A Low Cost Sensor for In-Pile Testing at High TemperaturesKnudson, D.L. / Rempe, J.L. / Condie, K.G. / Wilkins, S.C. / Daw, J.E. / Crepeau, J.C. / American Nuclear Society et al. | 2008
- 1883
-
Analysis of Two-Phase Flow and Boiling Heat Transfer in Inclined Channel of CorecatcherTahara, M. / Suzuki, Y. / Abe, N. / Kurita, T. / Hamazaki, R. / Kojima, Y. / American Nuclear Society et al. | 2008
- 1891
-
Performance and Scaling Analysis for the Two-Phase Natural CirculationSong, J. / American Nuclear Society et al. | 2008
- 1899
-
Development of the Cooling Technology on TRU Fuel Pin Bundle During Fuel Fabrication Process (1) Whole Study Plan and Fabrication of Test ApparatusesItoh, K. / Ikeda, K. / Hishida, K. / Kuroda, T. / Yamaguchi, A. / Takata, T. / American Nuclear Society et al. | 2008
- 1906
-
Development of the Cooling Technology on TRU Fuel Pin Bundle During Fuel Fabrication Process (2) High-Speed PIV Measurements in Gap among Fuel PinsHishida, K. / Kuroda, T. / Itoh, K. / Ikeda, K. / Yamaguchi, A. / Takata, T. / American Nuclear Society et al. | 2008
- 1916
-
Development of the Cooling Technology on TRU Fuel Pin Bundle During Fuel Fabrication Process (3) Development of Analytical ToolTakata, T. / Yamaguchi, A. / Hishida, A. / Kuroda, T. / Itoh, K. / Ikeda, K. / American Nuclear Society et al. | 2008
- 1923
-
An Assessment of Large-eddy Simulation for Thermal Fatigue PredictionKuczaj, A.K. / de Jager, B. / Komen, E. / American Nuclear Society et al. | 2008
- 1934
-
Experimental Investigation of Hematite Particulate Deposition Under Sub-cooled Boiling ConditionsBindra, H. / Rao, Q. / Jones, B.G. / American Nuclear Society et al. | 2008
- 1942
-
Investigation of Heat Transfer for Gas Cooled SystemsHering, W. / Arbeiter, F. / Bologa, A. / Jianu, A. / Zhuang, J. / American Nuclear Society et al. | 2008
- 1948
-
Mixing Process by Natural Convection and Molecular Diffusion of Two Component Gases in a Stable Stratified Fluid LayerTakeda, T. / American Nuclear Society et al. | 2008
- 1953
-
Design Considerations for Compact Heat ExchangersSouthall, D. / Le Pierres, R. / Dewson, S.J. / American Nuclear Society et al. | 2008
- 1969
-
A Contingency Safe, Responsible, Economic, Increased Capacity Spent Nuclear Fuel (SNF) Advance Fuel CycleLevy, S. / American Nuclear Society et al. | 2008
- 1980
-
Market Share Scenarios for Gen-III and Gen-IV Reactors in EuropeRoelofs, F. / van Heek, A. / Van Den Durpel, L. / American Nuclear Society et al. | 2008
- 1988
-
Progress in Development of Erbia-Bearing Super High Burnup FuelYamasaki, M. / Kuroishi, T. / Takeda, T. / Yamamoto, A. / Unesaki, H. / Mori, M. / American Nuclear Society et al. | 2008
- 1996
-
Radioactive Waste Management in RomaniaNegut, G. / Ionita, G. / Niculae, O. / Durdun, I. / Diaconu, S. / American Nuclear Society et al. | 2008
- 2005
-
Prospects of Thorium-fuel Reprocessing for Molten-Salt Reactor SystemsUhlir, J. / American Nuclear Society et al. | 2008
- 2009
-
A Study on Methodology of Optimal Characterization and Disposal Priority for Low and Intermediate Level Radioactive Wastes (LILWs) in KoreaAhn, M.H. / Lee, S.C. / Lee, K.J. / American Nuclear Society et al. | 2008
- 2014
-
Development of an Integrated Systems Engineering Modeling Package for Chemical Separation Processes under Advanced Fuel Cycle InitiativeChang, M. / Hsieh, H.-T. / Chen, Y. / Hodges, M. / Vandegrif, G. / Copple, J. / Laidler, J. / American Nuclear Society et al. | 2008
- 2019
-
Development of FR Fuel Cycle in Japan (1) Development Scope of Fuel Cycle TechnologyNakamura, H. / Funasaka, H. / Namekawa, T. / American Nuclear Society et al. | 2008
- 2029
-
Development of FR Fuel Cycle in Japan (2) Basic Design and Verification of U-Pu-Np Co-recovery Flowsheets for Engineering Scale Hot Examinations in JapanNakabayashi, H. / Nagai, T. / American Nuclear Society et al. | 2008
- 2036
-
Development of FR Fuel Cycle in Japan (3) Current State on Unified Technology of Denitration Conversion and Granulation for the Simplified Pellet Fuel Production Based on Microwave HeatingSuzuki, M. / Ishii, K. / Yamamoto, T. / Kato, Y. / Kurita, T. / Yoshimoto, K. / Kihara, Y. / Namekawa, T. / Fujii, K.-i. / American Nuclear Society et al. | 2008
- 2046
-
Development of FR Fuel Cycle in Japan (4) Consideration of transition from LWR-cycle to FR-cycleSato, F. / Nakamura, H. / American Nuclear Society et al. | 2008
- 2051
-
Evaluation of the Possibility of Plutonium and Minor Actinides Transmutation in HWRGhitescu, P. / Ghizdeanu, N.B. / American Nuclear Society et al. | 2008
- 2060
-
Preliminary Analysis by means of the TRANSURANUS Code of Mixed Oxide Fuel Rod for Gen IV Lead Fast ReactorVettraino, F. / Calabrese, R. / Artioli, C. / Luzzi, L. / Sobolev, V. / American Nuclear Society et al. | 2008
- 2068
-
Mixed Plutonium Conversion and Actinides Burning in Fast Molten Salt ReactorsKamiyama, Y. / Shimazu, Y. / Narabayashi, T. / Tsuji, M. / American Nuclear Society et al. | 2008
- 2075
-
New Nuclear Power Plants in Europe - Design Aspects for Constructional EngineeringMeiswinkel, R. / Schluter, F.-H. / American Nuclear Society et al. | 2008
- 2081
-
Multiscale Modeling Approach to Stress Corrosion CrackingTirtom, I. / Das, N.K. / Suzuki, K. / Ogawa, K. / Shoji, T. / American Nuclear Society et al. | 2008
- 2090
-
Influence of Non Linear Geometrical Parameter on Curved Thin Shell Buckling BehaviourFrano, R.L. / Forasassi, G. / American Nuclear Society et al. | 2008
- 2100
-
Correlation Between Intrinsic Hardness and Defect Structures of Ion Irradiated Fe AlloysShin, C. / Jin, H.H. / Kwon, J. / American Nuclear Society et al. | 2008
- 2108
-
Dynamics of Frictional Interaction of a Fuel Rod Cladding and Spacer Grid Cell in a Fuel AssemblyDrozdov, Y. / Makarov, V. / Afanasiev, A. / Matvienko, I. / Savinova, T. / American Nuclear Society et al. | 2008
- 2116
-
Ultrasonic TOFD Method Application for Steel Components and Welds of 10mm Wall Thickness Using Ultrasonic Flaw Detector and ULTRA7 TOFD SoftwareKasarov, K. / Tabakova, B. / American Nuclear Society et al. | 2008
- 2121
-
Study of the Tunneling Effect Within Lattices with Cubic Structure on Varying TemperatureFrisone, F. / American Nuclear Society et al. | 2008
- 2127
-
High Temperature Thermal and Structural Material Properties for Metals used in LWR VesselsRempe, J.L. / Knudson, D.L. / Daw, J.E. / Crepeau, J.C. / American Nuclear Society et al. | 2008
- 2135
-
Flaw Tolerance Evaluation to Support Alternative Examination Volume and/or Inspection Interval for Nickel-Based Alloy ComponentsNg, C.K. / Udyawar, A. / Swamy, S. / American Nuclear Society et al. | 2008
- 2142
-
Oxide Fouling Mitigation Technology in BWRKim, Y.-J. / Dulka, C. / American Nuclear Society et al. | 2008
- 2151
-
Flexural Behavior of Concrete Beam with Mechanical Splices of Reinforcement Subjected to Cyclic LoadingNah, H.S. / Kim, K.S. / American Nuclear Society et al. | 2008
- 2158
-
Creep Behaviors of Alloy 617 at Temperatures Between 800 and 1000^oCKim, D. / Jang, C. / Ryu, W.S. / American Nuclear Society et al. | 2008
- 2163
-
Corrosion Studies of Candidate Materials for European HPLWRPenttila, S. / Toivonen, A. / Heikinheimo, L. / Novotny, R. / American Nuclear Society et al. | 2008
- 2175
-
Theoretical Design of SCC Resistant Ni-base Alloy by a Computational Chemistry ApproachDas, N.K. / Suzuki, K. / Takeda, Y. / Ogawa, K. / Shoji, T. / American Nuclear Society et al. | 2008
- 2183
-
Study on an Innovative Fast Reactor Utilizing Hydride Neutron AbsorberKonashi, K. / Iwasaki, T. / Itoh, K. / Hirai, M. / Sato, I. / Kurosaki, K. / Suzuki, A. / Matsumura, Y. / Tahara, Y. / American Nuclear Society et al. | 2008
- 2191
-
Comparison of Inelastic Behaviors Between Cold Worked 316L and Solution Annealed 316L Stainless SteelsKim, J.B. / Lee, H.Y. / Park, C.G. / Lee, J.H. / American Nuclear Society et al. | 2008
- 2198
-
Effects of Alloying Elements on the Microstructure and Mechanical Properties in SA508 Gr.4N Low Alloy SteelKim, M.-C. / Park, S.-G. / Lee, Y.-S. / Lee, B.-S. / American Nuclear Society et al. | 2008
- 2206
-
Effects of Welding on Toughness of Mod. 9Cr-1Mo SteelRyu, W.-S. / Kim, S.-H. / Yoon, J.-H. / American Nuclear Society et al. | 2008
- 2210
-
Development of Digital Materials Database for Design and Construction of New Power PlantsRen, W. / American Nuclear Society et al. | 2008
- 2220
-
IAEA'S Study on Advanced Applications of Water Cooled Nuclear Power PlantsCleveland, J. / McDonald, A. / Rao, A. / American Nuclear Society et al. | 2008
- 2228
-
Analytical Hierarchy Process for the Selection of Nuclear Reactors for MexicoMartin-del-Campo, C. / Nelson, P.F. / Francois, J.L. / American Nuclear Society et al. | 2008
- 2237
-
New Power Expansion Strategy and a Low GHG Emitting Economy in KoreaChung, W.-S. / Yun, S.-W. / Lee, D.S. / Jeong, J.-W. / American Nuclear Society et al. | 2008
- 2241
-
The Role of Nuclear Power in a CO~2 Emission Reduction in KoreaKim, S.-S. / Lee, M.-K. / American Nuclear Society et al. | 2008
- 2248
-
Evaluation of the Scenario for Innovative Russian Nuclear Power DevelopmentChebeskov, A. / Dekusar, V. / American Nuclear Society et al. | 2008
- 2257
-
Risks and Benefits of Nuclear Energy in a Sustainable Development PerspectiveBertel, E. / American Nuclear Society et al. | 2008
- 2266
-
The Norwegian Thorium InitiativeAsphjell, O. / Saethre, B. / Kelly, J. / American Nuclear Society et al. | 2008
- 2269
-
High-Temperature Reactors for Underground Liquid-Fuels Production With Direct Carbon SequestrationForsberg, C.W. / American Nuclear Society et al. | 2008
- 2278
-
Novel Reactor Designs to Burn Non-Fissile FuelsGilleland, J. / Ahlfeld, C. / Dadiomov, D. / Hyde, R. / Ishikawa, Y. / McAlees, D. / McWhirter, J. / Myhrvold, N. / Nuckolls, J. / Odedra, A. et al. | 2008
- 2285
-
Initial Operation of the High Temperature Electrolysis Integrated Laboratory Scale Experiment at INLStoots, C.M. / O Brien, J.E. / Condie, K. / Herring, J.S. / Hartvigsen, J.J. / American Nuclear Society et al. | 2008
- 2295
-
Commercial Scale Performance Predictions for Hightemperature Electrolysis Plants Coupled to Three Advanced Reactor TypesO Brien, J.E. / McKellar, M.G. / Herring, J.S. / American Nuclear Society et al. | 2008
- 2307
-
Hydrogen Production for Transportation Fuels Using Nuclear EnergyHerring, J.S. / Condie, K. / O Brien, J.E. / Stoots, C.M. / Hartvigsen, J.J. / American Nuclear Society et al. | 2008
- 2315
-
Initial Assessment of the Operability of the VHTR-HTE Nuclear Hydrogen PlantVilim, R.B. / American Nuclear Society et al. | 2008
- 2326
-
Once-through Hybrid Sulfur Process for Nuclear Hydrogen ProductionJeong, Y.H. / American Nuclear Society et al. | 2008
- 2335
-
Integrating Large-scale Co-generation of Hydrogen and Electricity from Wind and Nuclear Sources (NUWINDZ™)Miller, A.I. / Duffey, R.B. / American Nuclear Society et al. | 2008
- 2345
-
Integration of New Nuclear power Plants into Transmission Grids Part I: Transmission System IssuesAbi-Samra, N. / American Nuclear Society et al. | 2008
- 2350
-
Integration of New Nuclear Power Plants into Transmission Grids Part II: Zones of Vulnerabilities (ZoV)Abi-Samra, N. / American Nuclear Society et al. | 2008
- 2358
-
Advanced Cooling TechnologiesMaulbetsch, J.S. / American Nuclear Society et al. | 2008
- 2369
-
Application of Hybrid Cooling Technology for North Anna Unit 3Waddill, J.D. / Kemp, D.A. / American Nuclear Society et al. | 2008
- 2375
-
Human Resource Development for the New Nuclear Power Plant Unit in ArmeniaGevorgyan, A. / Galstyan, A. / Donovan, M. / American Nuclear Society et al. | 2008
- 2377
-
Near-Term Deployment of Advanced Light Water ReactorsHamel, J.F. / American Nuclear Society et al. | 2008
- 2382
-
How an EAM Solution Could Support a New Build Project?Luanco, E. / American Nuclear Society et al. | 2008
- 2389
-
Design of Integrated Managing System for NPP Safety Based on CIMS and Fractal Modeling MethodLi, F.-y. / Wang, X.-y. / Liu, Y. / American Nuclear Society et al. | 2008
- 2394
-
A Heterogeneous Model for Burnup Calculation in High Temperature Gas-Cooled ReactorsPerfetti, C.M. / Anghaie, S. / Baxter, A. / Ellis, C. / American Nuclear Society et al. | 2008
- 2402
-
The Enhancements and Testing for the MCNPX Depletion CapabilityFensin, M.L. / Hendricks, J.S. / Anghaie, S. / American Nuclear Society et al. | 2008
- 2413
-
A New Method to Compute the Dominance Ratio in Monte Carlo Simulations - Application to a Simple Pin Cell with the 3-D Monte Carlo Code TRIPOLI4Dumonteil, E. / Courau, T. / American Nuclear Society et al. | 2008
- 2421
-
Pin-by-Pin Power Reconstruction in the Future EDF Calculation SchemeGirardi, E. / Cometto, M. / Courau, T. / Couyras, D. / Schwartz, N. / American Nuclear Society et al. | 2008
- 2431
-
Elements of Validation of Microscopic Depletion for the Future EDF Calculation Scheme Based on APOLLO2 and COCAGNE CodesHoareau, F. / Laugier, F. / Couyras, D. / American Nuclear Society et al. | 2008
- 2439
-
Elements of Validation of Pin-by-Pin Calculations with the Future EDF Calculation Scheme Based on APOLLO2 and COCAGNE CodesCourau, T. / Cometto, M. / Girardi, E. / Couyras, D. / Schwartz, N. / American Nuclear Society et al. | 2008
- 2449
-
ZPPR-21 Critical Benchmark Analyses with ENDF/B-V and -VII DataLee, C. / Kim, S.J. / Yang, W.S. / American Nuclear Society et al. | 2008
- 2457
-
An Application Method of Benchmark Experiment Results to Small Innovative Fast Reactor DesignsTsuboi, Y. / Moriki, Y. / Kawashima, M. / American Nuclear Society et al. | 2008
- 2461
-
Development of an Automated Testing System for Verification and Validation of Nuclear DataTriplett, B.S. / Anghaie, S. / White, M.C. / American Nuclear Society et al. | 2008
- 2469
-
Identification of the Doppler Coefficient from a Low Power Transient Observed in a Zero-Power Reactor Physics Test of PWRsTsuji, M. / Shimazu, Y. / Narabayashi, T. / Hanayama, Y. / Ohoka, Y. / Yamasaki, M. / American Nuclear Society et al. | 2008
- 2479
-
Improvement of Prediction Accuracy for Fuel Fabrication System with Erbia Bearing FuelTakeda, T. / Sano, T. / Kuroishi, T. / Yamasaki, M. / Unesaki, H. / American Nuclear Society et al. | 2008
- 2487
-
Checkmate[unknown] - a New Concept in Core DesignKruners, M. / Fuentes, E. / American Nuclear Society et al. | 2008
- 2494
-
A Minimum Shuffle Core Design Strategy for ESBWRKarve, A.A. / Fawcett, R.M. / American Nuclear Society et al. | 2008
- 2499
-
Neutronic Study for Introduction of Erbium As a Burnable Poison Into the Fuel Cladding Tube to Enable PWR Core ControlChabert, C. / Brachet, J.C. / Olier, S. / American Nuclear Society et al. | 2008
- 2505
-
Modification of the Japanese First Nuclear Ship Reactor for a Regional Energy Supply SystemSato, K. / Shimazu, Y. / Narabayashi, T. / Tsuji, M. / American Nuclear Society et al. | 2008
- 2512
-
Validation of Shielding Design for Spent Fuel Cask Storage Facility Using Various CodesNakano, H. / Nemezawa, S. / Tsukiyama, T. / Nemoto, Y. / American Nuclear Society et al. | 2008
- 2518
-
Reactor Physics Aspects of the Incident Occurred at Paks NPP in 2003Feher, S. / Wirth, A. / Kophazi, J. / Czifrus, S. / American Nuclear Society et al. | 2008
- 2527
-
Core Monitoring Combining Measurements from Different Nuclear InstrumentationsRio, G. / Battel, B. / American Nuclear Society et al. | 2008
- 2533
-
Decay Heat Analysis of a VHTR Core Using the HELIOS and ORIGEN-2 CodesNoh, J.M. / Bae, K.-M. / American Nuclear Society et al. | 2008
- 2540
-
Criticality Calculations on Realistic Modelling of Pebble-bed HTR-proteus as a Validation for the Woodcock Tracking Method Implemented in the MORET 5 Monte Carlo CodeForestier, B. / Miss, J. / Jacquet, O. / Bernard, F. / Verboomen, B. / American Nuclear Society et al. | 2008
- 2549
-
Optimal Control Search of Xenon Oscillation Control in Large PWRs Using a Characteristic Ellipse Trajectory Drawn by Three Axial OffsetsShimazu, Y. / American Nuclear Society et al. | 2008
- 2559
-
Compact, Readily Deployable Reactor Systems for Secure Power for Civilian and Defense ApplicationsPowell, J.R. / Farrell, J.P. / American Nuclear Society et al. | 2008
- 2571
-
A Basic LEGO Reactor Design for the Provision of Lunar Surface PowerBess, J.D. / American Nuclear Society et al. | 2008
- 2581
-
Modeling and Analysis of a Lunar Space Reactor with the Computer Code RELAP5-3D/ATHENACarbajo, J.J. / Qualls, L. / American Nuclear Society et al. | 2008
- 2589
-
Modifications to the Fission Surface Power Primary Test Circuit (FSP-PTC)Garber, A.E. / American Nuclear Society et al. | 2008
- 2598
-
Experimental and Research Study of Novel Nuclear Concepts (Survey of Current Results of ISTC Programs)Tocheny, L.V. / American Nuclear Society et al. | 2008
- 2605
-
Computational Thermohydrodynamic Analysis of Thermal Engine Rocket Adventurer for Space Nuclear ApplicationNam, S.H. / Kang, S.G. / Jung, I.K. / Suh, K.Y. / American Nuclear Society et al. | 2008
- 2618
-
Recent Developments of the MOA Thruster, a High Performance Plasma Accelerator for Nuclear Power and Propulsion ApplicationsFrischauf, N. / Hettmer, M. / Grassauer, A. / Bartusch, T. / Koudelka, O. / American Nuclear Society et al. | 2008
- 2631
-
Thermal-hydraulic Analysis of the MIT Research Reactor Low Enrichment Uranium (LEU) CoreKo, Y.-C. / Hu, L.-W. / Kazimi, M.S. / American Nuclear Society et al. | 2008
- 2640
-
Advanced Test Reactor - National Scientific User Facility: Research Proposal Process and Lessons LearnedStanley, C.J. / Marshall, F.M. / Thelen, M.C. / American Nuclear Society et al. | 2008
- 2645
-
Proposed Fuel Pin Irradiation Facilities for the High Flux Isotope ReactorMcDuffee, J.L. / Gehin, J.C. / Ellis, R.J. / Hobbs, R.W. / Primm, R.T. / American Nuclear Society et al. | 2008
- 2652
-
Innovations in Design for the Enhancement of Experimental Neutron Flux at the Massachusetts Institute of Technology Research ReactorEllis, T. / Newton, T. / American Nuclear Society et al. | 2008
- 2657
-
The ATR National Scientific User Facility: A New Role for a National AssetMeyer, M.K. / Marshall, F. / American Nuclear Society et al. | 2008
- 2663
-
General Purpose Heat Source SimulatorEmrich, W.J. / American Nuclear Society et al. | 2008
- 2667
-
NaK Plugging Meter Design for the Feasibility Test LoopsPearson, J.B. / Godfroy, T.J. / Reid, R.S. / Polzin, K.A. / American Nuclear Society et al. | 2008
- 2674
-
Concept of Direct Energy Conversion Nuclear Cogeneration PlantYarygin, V.I. / Lazarenko, G.E. / Mironov, V.S. / Pyshko, A.P. / Ovcharenko, M.K. / Krotov, A.D. / Linnik, V.A. / Mikheyev, A.S. / Sonko, A.V. / Lazarenko, D.G. et al. | 2008
- 2681
-
Competitive Paths to New Plant LicensingRestrepo, A. / Anghaie, S. / American Nuclear Society et al. | 2008
- 2689
-
Special Treatment for Important to Safety Structures, Systems and Components (SSCs) in the Licensing of Light Water ReactorsMcNally, R.W. / American Nuclear Society et al. | 2008