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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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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The deadline is fast approaching for submitting an application to become a technical reviewer for the Nuclear Regulatory Commission’s fiscal year 2025 research grant proposals.
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Radioactive Fission Product Release from Defective Light Water Reactor Fuel Elements
Vadim V. Konyashov, Alexander M. Krasnov
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 1-16
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3273
Thorium Fuel Performance in a Tight-Pitch Light Water Reactor Lattice
Taek Kyum Kim, Thomas J. Downar
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 17-29
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3274
Heavy-Metal Aerosol Transport in a Lead-Bismuth-Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation
J. Buongiorno, N. E. Todreas, M. S. Kazimi
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 30-43
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3275
Modeling of Hydrogen Flame Propagation in Multicompartment Buildings
Wison Luangdilok, Hidetsugu Morota, Michael Epstein
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 44-57
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3276
Incorporating Plutonium Particle Size Effects in the Assessment of Active Mode Measurement Uncertainty in Passive-Active Neutron Radioassay Systems
Larry G. Blackwood, Yale D. Harker
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 58-68
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3277
The Effect of Hydrogen on Oxidative Dissolution of Spent Fuel
Longcheng Liu, Ivars Neretnieks
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 69-78
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT02-A3278
Analysis of External Cooling of the Reactor Vessel During Severe Accidents
Jin Ho Song, Sang Baik Kim, Hee Dong Kim
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 79-89
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT02-A3279
An Estimate of the Crust Thickness on the Surface of a Thermally Convecting Liquid-Metal Pool
Askar A. Gubaidullin, Bal Raj Sehgal
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 90-92
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT02-A3280
Cost of Electricity from Molten Salt Reactors
R. W. Moir
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 93-95
Technical Note | Economics of Nuclear Systems | doi.org/10.13182/NT02-A3281
Revised Burnup Code System SWAT: Description and Validation Using Postirradiation Examination Data
Kenya Suyama, Hiroki Mochizuki, Takehide Kiyosumi
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 97-110
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3282
Assessment of Homogeneous Thorium/Uranium Fuel for Pressurized Water Reactors
Alexander Galperin, Eugene Shwageraus, Michael Todosow
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 111-122
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-21
Advantages of Irradiated DUPIC Fuels from the Perspective of Environmental Impact
Won Il Ko, Ho Dong Kim, Myung Seung Yang
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 123-139
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3284
Lateral Mixing Mechanisms in Vertical and Horizontal Interconnected Subchannel Two-Phase Flows
Sarman Gençay, Alberto Teyssedou, Peter Tye
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 140-161
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT138-140
Chemical Speciation of Iodine Source Term to Containment
Joanna McFarlane, Jungsook C. Wren, Robert J. Lemire
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 162-178
Technical Paper | Reactor Safety | doi.org/10.13182/NT138-162
Integrated Analytic Radionuclide Transport Model for a Spent Nuclear Fuel Repository in Saturated Fractured Rock
Allan Hedin
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 179-205
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3287
Pyrolysis Kinetics of Spent Low-Level Radioactive Resin
Y.-J. Huang, H. Paul Wang, S. H. Liu, M. C. Hsiao
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 206-210
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3288
A Comparison of Direct Gamma Dose Rates from a Stationary Gaussian Plume Using Different Models
S. Shoaib Raza, Rubén R. Avila
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 211-216
Technical Note | Environmental Science, Technology and Effects | doi.org/10.13182/NT02-A3289
Spatial Control of a Large PHWR via Reduced Model
Dhananjay B. Talange, B. Bandyopadhyay, Akhilanand Pati Tiwari
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 217-237
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT02-A3290
ODS Steel Clad MOX Fuel-Pin Fabrication and Irradiation Performance in EBR-II
James Bottcher, Shigeharu Ukai, Masaki Inoue
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 238-245
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3291
High-Burnup BWR Fuel Behavior Under Simulated Reactivity-Initiated Accident Conditions
Takehiko Nakamura, Kazuyuki Kusagaya, Toyoshi Fuketa, Hiroshi Uetsuka
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 246-259
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3292
A Fission Gas Release Model for High-Burnup LWR ThO2-UO2 Fuel
Yun Long, Yi Yuan, Mujid S. Kazimi, Ronald G. Ballinger, Edward E. Pilat
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 260-272
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3293
Thermal-Hydraulic Analyses of Steam Generator Tube Rupture Accident for the Kori Nuclear Unit 1 Pressurized Thermal Shock Study
Soon-Joon Hong, Jae-Hak Kim, Yong-Soo Kim, Goon-Cherl Park
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 273-283
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3294
Transmutation in the Nuclear Fuel Cycle: Approaches and Impacts
Micah D. Lowenthal
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 284-299
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3295
Neutronics Study on Accelerator Driven Subcritical Systems with Thorium-Based Fuel for Comparison Between Solid and Molten-Salt Fuels
Shunsuke Ishimoto, Kenji Ishibashi, Hideki Tenzou, Toshinobu Sasa
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 300-312
Technical Paper | Accelerators | doi.org/10.13182/NT02-1
