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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Apr 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
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Interpretation of the Phébus FPT0 and FPT1 Circuit Results Using the SOPHAEROS/ASTEC V1 Module
A. Bujan, B. Tóth, A. Bieliauskas, R. Zeyen, C. Housiadas
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 1-17
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A9339
Importance Ranking of Parameters Affecting Reactor Dynamics Using the Taguchi Method
Luv Sharma, Tunc Aldemir, Robert Parker
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 18-33
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A9340
RELAP5 Analysis of Two-Phase Decompression and Rarefaction Wave Propagation Under a Temperature Gradient
Nathan Lafferty, Victor Ransom, Martin Lopez De Bertodano
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 34-49
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT169-3
Analysis of a Coupled Blowdown from Both RPV and BOP with RELAP5-3D/K for a Limiting FWLB of an ABWR for Containment Design
Thomas K. S. Liang, Show-Chyuan Chiang, Chung-Yu Yang, Liang-Che Dai
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 50-60
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9342
Enhanced Thermal Conductivity for LWR Fuel
Jamil A. Khan, Travis W. Knight, Sujan B. Pakala, Wei Jiang, Ruixian Fang, James S. Tulenko
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 61-72
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9343
Three-Dimensional X-Ray CT Image of an Irradiated FBR Fuel Assembly
Kozo Katsuyama, Koji Maeda, Tsuyoshi Nagamine, Hirotaka Furuya
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 73-80
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT10-A9344
Benchmark Study on Fuel Bundle Degradation in the Phebus FPT2 Test Using State-of-the-Art Severe Accident Analysis Codes
B. Tóth, A. Bieliauskas, G. Bandini, J. Birchley, H. Wada, J. Hohorst, C. Jamond, K. Trambauer
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 81-96
Technical Paper | Reactor Saftey | doi.org/10.13182/NT10-A9354
Modeling Molten Fuel-Moderator Interactions for the CANDU Flow Blockage Accident
Aya Diab, Michael Corradini
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 97-113
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9355
Long-Term Validation of the Molten Fuel-Moderator Interactions Model
Aya Diab, Michael Corradini, Carl Martin
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 114-125
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9356
Analysis of Flow Instability for OTSG Using Frequency Domain Control Theory
Suxia Hou, Fuyu Zhao, Yun Tai, Liu Cheng
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 126-133
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9357
Simulation of the EBR-II Loss-of-Flow Tests Using the MARS Code
Kwi-Seok Ha, Hae-Yong Jeong, Chungho Cho, Young-Min Kwon, Yong-Bum Lee, Dohee Hahn
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 134-142
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9358
Loading Capacities for Uranium, Plutonium, and Neptunium in High Caustic Nuclear Waste Storage Tanks Containing Selected Sorbents
Lawrence N. Oji, William R. Wilmarth, David T. Hobbs
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 143-149
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A9359
A Container Based on Polymer Composite Materials for the Ultimate Disposal of Spent Nuclear Fuel and Radioactive Waste
H. W. Bonin, J. R. Van Tine, V. T. Bui
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 150-179
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A9360
Estimating Surface Facility Throughput During the Preclosure Emplacement Period at Yucca Mountain
Leah Spradley, Mark Abkowitz, James H. Clarke
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 180-194
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A9361
Analytical and Experimental Investigation of Recent Challenges to Neutron Attenuation and the Relationship with Criticality Analyses
Stanley E. Turner, Thomas G. Haynes III
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 195-203
Technical Note | Radiation Protection | doi.org/10.13182/NT10-A9362
A Study on Dynamic Characteristics of Plate-Fin Recuperator in High-Temperature Gas-Cooled Reactor Closed Cycle
Ming Ding, Xiaoyong Yang, Jie Wang
Nuclear Technology | Volume 169 | Number 3 | March 2010 | Pages 205-217
Technical Paper | Fission Reactors | doi.org/10.13182/NT10-A9374
LWR Severe Accident Simulation Fission Product Behavior in FPT2 Experiment
N. Girault, L. Bosland, J. Dienstbier, R. Dubourg, C. Fiche
Nuclear Technology | Volume 169 | Number 3 | March 2010 | Pages 218-238
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A9375
Triggered Steam Explosions with Corium Melts of Various Compositions in a Narrow Interaction Vessel in the TROI Facility
J. H. Kim, B. T. Min, I. K. Park, S. W. Hong
Nuclear Technology | Volume 169 | Number 3 | March 2010 | Pages 239-251
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT169-239
Critical Discretization Issues in 3-D SN Simulations Relevant to Dosimetry and Medical Physics
Ahmad K. Al-Basheer, Glenn E. Sjoden, Monica Ghita
Nuclear Technology | Volume 169 | Number 3 | March 2010 | Pages 252-262
Technical Paper | Radiation Protection | doi.org/10.13182/NT10-A9377
Dissolution of Zircaloy-2-Clad UO2 Commercial Reactor Fuel
G. F. Kessinger, M. C. Thompson
Nuclear Technology | Volume 169 | Number 3 | March 2010 | Pages 263-270
Technical Paper | Reprocessing | doi.org/10.13182/NT10-A9378
Raman and SEM/EDS Characterization of Cr-Doped Natural Diamond Particles
Adrián E. Méndez Torres, Mark Antonio Prelas, Louis M. Ross, Jr., Tushar K. Ghosh
Nuclear Technology | Volume 169 | Number 3 | March 2010 | Pages 271-278
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT10-A9379
Industrial-Scale Production of 99mTc Generators for Clinical Use Based on Zirconium Molybdate Gel
M. Ghannadi Maragheh, M. R. Davarpanah, M. Fazlali, M. Kazemi Boudani, B. Pour Emadi, S. Attar Nosrati
Nuclear Technology | Volume 169 | Number 3 | March 2010 | Pages 279-284
Technical Paper | Radioisotopes | doi.org/10.13182/NT10-A9380
