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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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April 3–5, 2025
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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An Assessment of Large-Eddy Simulation Toward Thermal Fatigue Prediction
A. K. Kuczaj, E. M. J. Komen
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 2-15
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9441
Thermal-Fluid Characterizations of ZnO and SiC Nanofluids for Advanced Nuclear Power Plants
In Cheol Bang, Ji Hyun Kim
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 16-27
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9442
Condensation Correlation for a Vertical Passive Condenser System
Shripad T. Revankar, Seungmin Oh, Wenzhong Zhou, Gavin Henderson
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 28-39
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9443
Summary for Three Different Validation Cases of Coolant Flow in Supercritical Water Test Sections with the CFD Code ANSYS CFX 11.0
Attila Kiss, Attila Aszódi
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 40-53
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9444
Parametric Sensitivity Study on the Reflooding Models of the MARS Code Based on 6 × 6 Rod Bundle Test Results
Ki-Yong Choi, Seok Cho, Hyoung-Kyu Cho, Chul-Hwa Song
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 54-67
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9445
The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability
Michael L. Fensin, John S. Hendricks, Samim Anghaie
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 68-79
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Fuel Cycle and Management | doi.org/10.13182/NT10-2
Development of an Automated Testing System for Verification and Validation of Nuclear Data and Simulation Code
Brian S. Triplett, Samim Anghaie, Morgan C. White
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 80-89
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Radiation Measurements and Instrumentation | doi.org/10.13182/NT10-A9447
Heat Transfer in Intermediate Heat Exchanger Under Low Flow Rate Conditions
Hiroyasu Mochizuki
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 90-99
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9448
An Integral Effect Test on the Reflood Period of a Large-Break LOCA for the APR1400 Using ATLAS
Hyun Sik Park, Ki Yong Choi, Seok Cho, Kyoung Ho Kang, Nam Hyun Choi, Dong Jin Euh, Yeon Sik Kim, Won Pil Baek
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 100-113
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9449
Optimal Geometric Configuration for a Natural Circulation Loop
Jin Ho Song
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 114-122
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9450
Large Break Loss-of-Coolant Accident Analysis of VVER-1000 Reactor Using CATHARE Code
Luben Sabotinov, Abhishek Srivastava
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 123-132
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9451
Development of Advanced Loop-Type Fast Reactor in Japan
Shoji Kotake, Yoshihiko Sakamoto, Takatsugu Mihara, Shigenobu Kubo, Nariaki Uto, Yoshio Kamishima, Kazumi Aoto, Mikio Toda
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 133-147
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Fission Reactors | doi.org/10.13182/NT10-7
System Design and Analysis of a 900-MW(thermal) Lead-Cooled Fast Reactor
Sang Ji Kim, Yonghee Kim, Sergi Hong, Chung Ho Cho, Jae-Hyuk Eoh, Jong Bum Kim, Myung Hwan Wi, Kwi Seok Ha, Eui Kwang Kim
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 148-158
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Fission Reactors | doi.org/10.13182/NT10-A9453
Technological Feasibility of Two-Loop Cooling System in JSFR
Hidemasa Yamano, Shigenobu Kubo, Ken-Ichi Kurisaka, Yoshio Shimakawa, Hiromi Sago
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 159-169
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT09-6
Minor Actinide-Bearing Oxide Fuel Core Design Study for the JSFR
Masayuki Naganuma, Takashi Ogawa, Shigeo Ohki, Tomoyasu Mizuno, Shoji Kotake
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 170-180
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Fuel Cycle and Management | doi.org/10.13182/NT10-A9455
Development of Passive Shutdown System for SFR
Shigeyuki Nakanishi, Takusaburo Hosoya, Shigenobu Kubo, Shoji Kotake, Misao Takamatsu, Takafumi Aoyama, Iwao Ikarimoto, Jungo Kato, Yoshio Shimakawa, Kiyoshi Harada
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 181-188
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Nuclear Plant Operations and Control | doi.org/10.13182/NT10-A9456
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 | April 2010 | Pages 189-200
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9457
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 | April 2010 | Pages 201-209
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-6
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 | April 2010 | Pages 210-218
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Materials for Nuclear Systems | doi.org/10.13182/NT10-A9459
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 | April 2010 | Pages 219-230
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9460
Development of the Fission Product Release Analysis Code COPA-FPREL
Young Min Kim, Moon Sung Cho
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 231-243
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Fuel Cycle and Management | doi.org/10.13182/NT10-A9461
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 | April 2010 | Pages 244-260
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Reactor Safety | doi.org/10.13182/NT10-A9462
Corrosion Studies of Candidate Materials for European HPLWR
Sami Penttilä, Aki Toivonen, Liisa Heikinheimo, Radek Novotny
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 261-271
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Materials for Nuclear Systems | doi.org/10.13182/NT10-A9463
Comparison of the High-Temperature Steam Oxidation Kinetics of Advanced Cladding Materials
M. Grosse
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 272-279
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Materials for Nuclear Systems | doi.org/10.13182/NT10-A9464
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 | May 2010 | Pages 281-289
Technical Paper | Fission Reactors | doi.org/10.13182/NT10-A9483
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 | May 2010 | Pages 290-305
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9484
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 | May 2010 | Pages 306-321
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9485
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 | May 2010 | Pages 322-335
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A9486
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 | May 2010 | Pages 336-352
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A9487
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 | May 2010 | Pages 353-359
Technical Paper | Human Factors | doi.org/10.13182/NT10-A9488
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 | May 2010 | Pages 360-369
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT10-A9489
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 | June 2010 | Pages 371-382
Technical Paper | Fission Reactors | doi.org/10.13182/NT10-1
Formal Considerations in Establishing Risk-Consistent Acceptance Criteria for Reactor Safety
Yuri Orechwa
Nuclear Technology | Volume 170 | Number 3 | June 2010 | Pages 383-396
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A10325
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 | June 2010 | Pages 397-415
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A10326
GNEP Hydrided Metal Alloy Fuel-Based Recycling Reactor
Gregory A. Johnson
Nuclear Technology | Volume 170 | Number 3 | June 2010 | Pages 416-421
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT10-A10327
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 | June 2010 | Pages 422-429
Technical Paper | Reprocessing | doi.org/10.13182/NT10-A10328
PRAGAMAN: A Computer Code for Simulation of Electrotransport During Molten Salt Electrorefining
Suddhasattwa Ghosh, B. Prabhakara Reddy, K. Nagarajan, P. R. Vasudeva Rao
Nuclear Technology | Volume 170 | Number 3 | June 2010 | Pages 430-443
Technical Paper | Reprocessing | doi.org/10.13182/NT10-A10329
Analysis of the Waterside Corrosion Kinetics of Zircaloy-4 Fuel Cladding in French PWRs
Vincent Bouineau, Gilles Bénier, Dominique Pêcheur, Joël Thomazet, Antoine Ambard, Martine Blat
Nuclear Technology | Volume 170 | Number 3 | June 2010 | Pages 444-459
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT10-A10330
Validation of the Monte Carlo Model of the Greek Research Reactor Core
D. Kontogeorgakos, I. E. Stamatelatos
Nuclear Technology | Volume 170 | Number 3 | June 2010 | Pages 460-464
Technical Note | Fission Reactors | doi.org/10.13182/NT10-A10331
