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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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NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
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Investigations of Hydraulic Behavior in Spallation Target Configurations
Xu Cheng, Abdalla Batta, Nam-Il Tak
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 1-12
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3714
Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap
Yong H. Kim, Sung J. Kim, Kune Y. Suh, Joy L. Rempe, F. Bill Cheung, Sang B. Kim
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 13-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3715
Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation
Daniel Westlén, Janne Wallenius
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 41-51
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3716
Subchannel Analysis of Fuel Assemblies of European Experimental ADS
X. Cheng
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 52-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3717
Accumulation and Head-Loss Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris
Ashok K. Ghosh, Arup K. Maji, Mark T. Leonard, Dasari V. Rao, Bruce C. Letellier, Girum S. Urgessa, Scott G. Ashbaugh
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 69-84
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3718
Aerosol Retention Near the Tube Breach During Steam Generator Tube Rupture Sequences
Luis E. Herranz, F. J. S. Velasco, Claudia L. Del Prá
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 85-94
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3719
Separations and Transmutation Criteria to Improve Utilization of a Geologic Repository
Roald A. Wigeland, Theodore H. Bauer, Thomas H. Fanning, Edgar E. Morris
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 95-106
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-3
Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B4C Absorber
L. Sepold, G. Schanz, M. Steinbrück, J. Stuckert, A. Miassoedov, A. Palagin, M. Veshchunov
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 107-116
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT06-A3721
Measurements of Delayed Fission Product Gamma-Ray Transmission Through Low-Enriched UO2 Fuel Pin Lattices in Air
T. H. Trumbull, D. R. Harris
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 117-127
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT06-A3722
Calculation of the Neutron Noise Induced by Shell-Mode Core-Barrel Vibrations in a 1-D, Two-Group, Two-Region Slab Reactor Model
Carl Sunde, Christophe Demazière, Imre Pázsit
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 129-141
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-1
A Conceptual Design Study of a Small Natural Convection Lead-Bismuth-Cooled Reactor Without Refueling for 30 Years
Yoshitaka Chikazawa, Mamoru Konomura, Tomoyasu Mizuno, Makoto Mito, Mikio Tanji
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 142-154
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3724
Formulation of a Single Operational Model for Risk-Informed Applications from the Decoupled Levels 1 and 2 PSA Models
Kwang-Il Ahn, Joon-Eon Yang
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 155-169
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3725
Mass Transfer Modeling With and Without Evaporation for Iodine Chemistry in the Case of a Severe Accident
L. Cantrel, P. March
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 170-185
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3726
MOX Fuel Characterization for Burnup Credit Application: Extension of Nondestructive Method Qualified for LEU Fuels
C. Riffard, H. Toubon, S. Pelletier, M. Batifol, J. M. Vidal
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 186-193
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3727
Modeling of Radiative Heat Transfer During a PWR Severe Accident
M. Zabiégo, F. Fichot, P. Rubiolo
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 194-214
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3728
The Core Characteristics of a LOCA Power Pulse in a CANDU-6 Reactor with the CANFLEX-RU Fuel
Chang Joon Jeong, Ho Chun Suk
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 215-223
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3729
Continuous Monitoring and Calibration of UTSG Process Sensors by Autoassociative Artificial Neural Network
Marzio Marseguerra, Enrico Zio, Fabio Marcucci
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 224-236
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3730
Conditions Conducive to Forming Crystalline Uranyl Silicates in High Caustic Nuclear Waste Evaporators
Lawrence N. Oji, Keisha B. Martin, Mary E. Stallings, Martine C. Duff
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 237-246
Technical Paper | Reprocessing | doi.org/10.13182/NT06-A3731
Thermal-Hydrologic Model Study for an Alternative Waste Package Design for Yucca Mountain Repository
D. Bahrami, G. Danko
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 247-264
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3732
High-Performance Supercritical Carbon Dioxide Cycle for Next-Generation Nuclear Reactors
Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 265-282
Technical Paper | Fission Reactors | doi.org/10.13182/NT154-265
The Supercritical Carbon Dioxide Power Cycle: Comparison to Other Advanced Power Cycles
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 283-301
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3734
Behavior of VVER Fuel Rods Tested Under Severe Accident Conditions in the CODEX Facility
Zoltán Hózer, László Maróti, Péter Windberg, Lajos Matus, Imre Nagy, György Gyenes, Márta Horváth, Anna Pintér, Márton Balaskó, Aladár Czitrovszky, Péter Jani, Attila Nagy, Oleg Prokopiev, Béla Tóth
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 302-317
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3735
Reduction in Workload of BWR In-Core Fuel Shuffling by New Optimization Methods
Akio Yamamoto, Masayuki Toujou, Kentarou Komori, Yasunori Kitamura, Yoshihiro Yamane
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 318-327
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3736
Analysis of the Bubbly-Churn Regime Transition in a Scaled Model Boiling Water Reactor
Khaled Meftah, Arthur E. Ruggles
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 328-334
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3737
Heat Transfer in a Supercritical Fluid: Classification of Heat Transfer Regimes
Kyoung Woo Seo, Moo Hwan Kim, Mark H. Anderson, Michael L. Corradini
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 335-349
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3738
The Effect of Material Homogenization in Calculating the Gamma-Ray Dose from Spent PWR Fuel Pins in an Air Medium
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 350-360
Technical Paper | Radiation Protection | doi.org/10.13182/NT06-A3739
Proliferation-Resistant SIGMA Uranium Enrichment Plants
M. E. Rivarola, P. C. Florido, D. O. Brasnarof, K. H. Kyung, L. Juanicó, J. Bergallo, J. Gonzalez, H. Daverio
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 361-373
Technical Paper | Enrichment | doi.org/10.13182/NT06-A3740
Deterministic Performance Assessment for a Conceptual Repository for Low- and Intermediate-Level Wastes in Korea
Daisuke Kawasaki, Joonhong Ahn, Chang-Lak Kim, Jin-Beak Park
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 374-388
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3741
