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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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Regularization of Feedwater Flow Rate Evaluation for Venturi Meter Fouling Problem in Nuclear Power Plants
Andrei V. Gribok, Ibrahim K. Attieh, J. Wesley Hines, Robert E. Uhrig
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 3-14
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3181
A Hydraulic Model Study of Intake Structure
Jin Won Kim, Dae Soo Lee, Jong Hyun Kim
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 15-22
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3182
Predictive Modeling of Steam Condensation onto Finned Tubes in the Presence of Noncondensable Gases for Passive Safety Reactor Containment Heat Exchangers
José Luis Muñoz-Cobo, María José Palomo, Luis Enrique Herranz
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 23-36
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3183
Quantifying the Effects of Break Source Flow Rates on AP600 Containment Stratification
J. Woodcock, Per F. Peterson, D. R. Spencer
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 37-48
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3184
Phase Distribution in a BWR Fuel Assembly and Evaluation of a Multidimensional Multifield Model
Gerhard Windecker, Henryk Anglart
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 49-61
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3185
Revaporization of a CsI Aerosol in a Horizontal Straight Pipe in a Severe Accident Condition
Hiroaki Shibazaki, Yu Maruyama, Tamotsu Kudo, Kazuichiro Hashimoto, Akio Maeda, Yuhei Harada, Akihide Hidaka, Jun Sugimoto
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 62-70
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3186
Assessment of the 3-D Thermal-Hydraulic Nuclear Core Computer Code FLICA-IV on Rod Bundle Experiments
André Bergeron, Daniel Caruge, Philippe Clément
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 71-83
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3187
Turbulence Modification Due to Wave Action at Low Reynolds Numbers in Horizontal Open-Channel Flow
Evangelos Stamatiou, Peter M.-Y. Chung, Masahiro Kawaji
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 84-96
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3188
Risk-Oriented Safety Evaluation of the CAREM-25 Prototype Reactor
Jorge H. Barón, Jorge E. Núñez McLeod, Selva S. Rivera
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 97-109
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3189
Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - I: DUPIC Fuel Fabrication Cost
Hangbok Choi, Won Il Ko, Myung Seung Yang
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 110-129
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3190
Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - II: DUPIC Fuel-Handling Cost
Hangbok Choi, Won Il Ko, Myung Seung Yang, Ihn Namgung, Bok-Gyun Na
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 130-148
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3191
Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - III: Spent DUPIC Fuel Disposal Cost
Won Il Ko, Hangbok Choi, Gyuhong Roh, Myung Seung Yang
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 149-166
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3192
Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - IV: DUPIC Fuel Cycle Cost
Won Il Ko, Hangbok Choi, Myung Seung Yang
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 167-186
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3193
Numerical Study of Coolant Mixing Caused by the Flow Deflectors in a Nuclear Fuel Bundle
Wang Kee In
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 187-195
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-1
Mode K - A Core Control Logic for Enhanced Load-Follow Operations of a Pressurized Water Reactor
Soo-Youl Oh, Jonghwa Chang, Jong-Kyun Park, Manuel Carrasco
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 196-207
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT01-A3195
Radioiodine Volatilization in the Presence of Organic Compounds
Fariborz Taghipour, Greg J. Evans
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 208-220
Technical Paper | Radioisotopes | doi.org/10.13182/NT01-A3196
Startup Thermal Considerations for Supercritical-Pressure Light Water-Cooled Reactors
Toru Nakatsuka, Yoshiaki Oka, Seiichi Koshizuka
Nuclear Technology | Volume 134 | Number 3 | June 2001 | Pages 221-230
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3197
Distribution Behavior of U(VI), Pu(IV), Am(III), and Zr(IV) with N,N-Dihexyl Octanamide Under Uranium-Loading Conditions
V. K. Manchanda, P. B. Ruikar, S. Sriram, M. S. Nagar, P. N. Pathak, K. K. Gupta, R. K. Singh, R. R. Chitnis, P. S. Dhami, A. Ramanujam
Nuclear Technology | Volume 134 | Number 3 | June 2001 | Pages 231-240
Technical Paper | Reprocessing | doi.org/10.13182/NT01-A3198
Geomechanical and Thermal Effects on Moisture Flow at the Proposed Yucca Mountain Nuclear Waste Repository
Goodluck I. Ofoegbu, Scott Painter, Rui Chen, Randall W. Fedors, David A. Ferrill
Nuclear Technology | Volume 134 | Number 3 | June 2001 | Pages 241-262
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3199
A Description of the Ceramic Waste Form Production Process from the Demonstration Phase of the Electrometallurgical Treatment of EBR-II Spent Fuel
Michael F. Simpson, K. Michael Goff, Stephen G. Johnson, Kenneth J. Bateman, Terry J. Battisti, Karen L. Toews, Steven M. Frank, Tanya L. Moschetti, Tom P. O'Holleran, Wharton Sinkler
Nuclear Technology | Volume 134 | Number 3 | June 2001 | Pages 263-277
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3200
Optimization of Beam-Shaping Assemblies for BNCS Using the High-Energy Neutron Sources D-D and D-T
Jérôme M. Verbeke, Allen S. Chen, Jasmina L. Vujic, Ka-Ngo Leung
Nuclear Technology | Volume 134 | Number 3 | June 2001 | Pages 278-293
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT01-A3201
