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Volume 170

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European Experiments on 2-D Molten Core Concrete Interaction: HECLA and VULCANO

Christophe Journeau, Jean Michel Bonnet, Eric Boccaccio, Pascal Piluso, Jose Monerris, Michel Breton, Gerald Fritz, Tuomo Sevón, Pekka H. Pankakoski, Stefan Holmström, Jouko Virta

Nuclear Technology / Volume 170 / Number 1 / Pages 189-200

April 2010

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Transient Conduction Heat Transfer Modeling in Concrete for the Simulation of Long-Term Phase of Molten Core-Concrete Interaction

B. Tourniaire, B. Spindler, M. Guillaumé

Nuclear Technology / Volume 170 / Number 1 / Pages 201-209

April 2010

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Interaction Between Molten Corium UO2+X-ZrO2-FeOy and VVER Vessel Steel

S. V. Bechta, V. S. Granovsky, V. B. Khabensky, E. V. Krushinov, S. A. Vitol, A. A. Sulatsky, V. V. Gusarov, V. I. Almiashev, D. B. Lopukh, D. Bottomley, M. Fischer, P. Piluso, A. Miassoedov, W. Tromm, E. Altstadt, F. Fichot, O. Kymalainen

Nuclear Technology / Volume 170 / Number 1 / Pages 210-218

April 2010

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The DEFOR-S Experimental Study of Debris Formation with Corium Simulant Materials

Pavel Kudinov, Aram Karbojian, Weimin Ma, Truc-Nam Dinh

Nuclear Technology / Volume 170 / Number 1 / Pages 219-230

April 2010

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Development of the Fission Product Release Analysis Code COPA-FPREL

Young Min Kim, Moon Sung Cho

Nuclear Technology / Volume 170 / Number 1 / Pages 231-243

April 2010

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Analysis and Justification of MAAP4.0.7 for PRA Level 1 Mission Success Criteria

Jennifer S. Butler, Darvin Kapitz, Robert P. Martin, Farrokh Seifaee, Ramu K. Sundaram

Nuclear Technology / Volume 170 / Number 1 / Pages 244-260

April 2010

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Corrosion Studies of Candidate Materials for European HPLWR

Sami Penttilä, Aki Toivonen, Liisa Heikinheimo, Radek Novotny

Nuclear Technology / Volume 170 / Number 1 / Pages 261-271

April 2010

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Comparison of the High-Temperature Steam Oxidation Kinetics of Advanced Cladding Materials

M. Grosse

Nuclear Technology / Volume 170 / Number 1 / Pages 272-279

April 2010

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Automatic Power Ascension Search for a Boiling Water Reactor Using Ant Colony Optimization Algorithm

Chaung Lin, Wei-Tinh Yen

Nuclear Technology / Volume 170 / Number 2 / Pages 281-289

May 2010

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New Design Options Free from a Potential Sodium Freezing Issue for a Passive DHR System of KALIMER

Jae-Hyuk Eoh, Ji-Woong Han, Tae-Ho Lee, Seong-O Kim

Nuclear Technology / Volume 170 / Number 2 / Pages 290-305

May 2010

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Validation of the DALTON-THERMIX Code System with Transient Analyses of the HTR-10 and Application to the PBMR

B. Boer, D. Lathouwers, J. L. Kloosterman, T. H. J. J. Van Der Hagen, G. Strydom

Nuclear Technology / Volume 170 / Number 2 / Pages 306-321

May 2010

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Estimating the Frequencies of Drop Events During the Preclosure Emplacement Period at Yucca Mountain, Nevada

Leah Spradley, Mark Abkowitz, James H. Clarke

Nuclear Technology / Volume 170 / Number 2 / Pages 322-335

May 2010

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The Thermal-Hydrological Impact on Increased Spent-Fuel Storage Capacity in Yucca Mountain Repository

Wei Zhou, Michael J. Apted, John H. Kessler

Nuclear Technology / Volume 170 / Number 2 / Pages 336-352

May 2010

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Gamma-Spectroscopy Methodology for Simultaneous Determination of Mass and Isotopic Composition of Large Plutonium Samples

Anatoly Bushuev, Alexander Kozhin, Viktor Zubarev, Tatiana Aleeva, Ekaterina Petrova, Anatoly Myrzin, Alexey Syrosev, Genadiy Vlaskin, Timur Ragimov, Valentin Timoshin, Andrey Samoilov

Nuclear Technology / Volume 170 / Number 2 / Pages 353-359

May 2010

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Acoustic Leak Detection Technology for Water/Steam Small Leaks and Microleaks into Sodium to Protect an SFR Steam Generator

Tae-Joon Kim, Valeriy S. Yugay, Ji-Young Jeong, Jong-Man Kim, Byeung-Ho Kim, Tae-Ho Lee, Yong-Bum Lee, Yeong-Il Kim, Dohee Hahn

Nuclear Technology / Volume 170 / Number 2 / Pages 360-369

May 2010

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Resolution of Proliferation Issues for a Sodium Fast Reactor Blanket

N. E. Stauff, M. J. Driscoll, B. Forget, P. Hejzlar

Nuclear Technology / Volume 170 / Number 3 / Pages 371-382

June 2010

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Formal Considerations in Establishing Risk-Consistent Acceptance Criteria for Reactor Safety

Yuri Orechwa

Nuclear Technology / Volume 170 / Number 3 / Pages 383-396

June 2010

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Validation Status of the ASTEC Integral Code for Severe Accident Simulation

J. P. Van Dorsselaere, P. Chatelard, M. Cranga, G. Guillard, N. Trégourès, L. Bosland, G. Brillant, N. Girault, A. Bentaïb, N. Reinke, W. Luther

Nuclear Technology / Volume 170 / Number 3 / Pages 397-415

June 2010

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GNEP Hydrided Metal Alloy Fuel-Based Recycling Reactor

Gregory A. Johnson

Nuclear Technology / Volume 170 / Number 3 / Pages 416-421

June 2010

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Placing Acetic Acid Removal into the UREX+ Process

Jessica Mitchell, Robert M. Counce, Jack S. Watson, B. B. Spencer, G. D. Del Cul

Nuclear Technology / Volume 170 / Number 3 / Pages 422-429

June 2010

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