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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
DOE on track to deliver high-burnup SNF to Idaho by 2027
The Department of Energy said it anticipated delivering a research cask of high-burnup spent nuclear fuel from Dominion Energy’s North Anna nuclear power plant in Virginia to Idaho National Laboratory by fall 2027. The planned shipment is part of the High Burnup Dry Storage Research Project being conducted by the DOE with the Electric Power Research Institute.
As preparations continue, the DOE said it is working closely with federal agencies as well as tribal and state governments along potential transportation routes to ensure safety, transparency, and readiness every step of the way.
Watch the DOE’s latest video outlining the project here.
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Variation of Burnable Neutron Absorbers in a Heavy Water–Moderated Fuel Lattice: A Potential to Improve CANDU Reactor Operating Margins
Paul K. Chan, Stephane Paquette, Hugues W. Bonin
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 1-14
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-67
Study on Heat Removal Capacity of PCCS of Advanced Passive PWR During Severe Accidents
Lili Tong, Jie Zou, Jun Tao, Xuewu Cao
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 15-26
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-93
DART Analysis of Irradiation Behavior of U-Mo/Al Dispersion Fuels
Bei Ye, Jeff Rest, Yeon Soo Kim, Gerard Hofman, Benoit Dionne
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 27-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-56
Intelligent Analysis of Low-Count Scintillation Spectra Using Support Vector Regression and Fuzzy Logic
Miltiadis Alamaniotis, Sangkyu Lee, Tatjana Jevremovic
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 41-57
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT14-75
Corrosion Behavior of Zirconium, Titanium, and Their Alloys in Simulated Dissolver Solution of Fast Breeder Reactor Spent Nuclear Fuel Using Zircaloy-4 Mock-Up Dissolver Vessel
J. Jayaraj, K. Thyagarajan, C. Mallika, U. Kamachi Mudali
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 58-70
Technical Paper | Reprocessing | doi.org/10.13182/NT14-90
Particle Production by Rotational Abrasion Between Graphite Spheres
Raymond S. Troy, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 71-91
Technical Note | Fission Reactors | doi.org/10.13182/NT14-109
Design and Laboratory Evaluation of Future Elongation and Diameter Measurements at the Advanced Test Reactor
K. L. Davis, D. L. Knudson, J. L. Rempe, J. C. Crepeau, S. Solstad
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 92-105
Technical Note | Materials for Nuclear Systems | doi.org/10.13182/NT14-60
Degradation of Nylon 6,6 Fire-Suppression Casing from Plutonium Glove Boxes Under Alpha and Neutron Irradiation
D. W. Millsap, M. E. Cournoyer, S. Landsberger, J. Tesmer, Y. Wang
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 106-112
Technical Note | Materials for Nuclear Systems | doi.org/10.13182/NT14-47
Spent Nuclear Fuel and Graphite Management for Salt-Cooled Reactors: Storage, Safeguards, and Repository Disposal
Charles Forsberg, Per F. Peterson
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 113-121
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-88
An Investigation on Size Distribution and Physical Characteristics of Debris in TROI FCI Tests
Seong-Wan Hong, Beong-Tae Min, Seong-Ho Hong
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 122-135
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-84
MARS-KS Code and Sensitivity Analysis of a Pressure Wave Propagation Test Performed in the PMK-2 Test Facility
Xin-Guo Yu, Ki-Yong Choi, Chul-Hwa Song, Istvan Trosztel, Ivan Toth, Gyorgy Ezsol
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 136-150
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-55
Innovative Control Strategy for Fast Runback Operational Transient Applied to SMRs
Roberto Ponciroli, Stefano Passerini, Richard B. Vilim
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 151-166
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-68
Development of High-Temperature Transport System for LiCl-KCl Molten Salt in Pyroprocessing
Sung Ho Lee, Geun Il Park, Sung Bin Park
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 167-173
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-87
Monte Carlo Perturbation Analysis of Isothermal Temperature Reactivity Coefficient in Kyoto University Critical Assembly
Byoung Kyu Jeon, Cheol Ho Pyeon, Hyung Jin Shim
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 174-184
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-83
An Assessment of the Virtual Mass Force in RELAP5/MOD3.3 for the Bubbly Flow Regime
William D. Fullmer, Martin A. Lopez De Bertodano
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 185-192
Technical Note | Fission Reactors | doi.org/10.13182/NT14-110
Performance of the Explicit Euler and Predictor-Corrector–Based Coupling Schemes in Monte Carlo Burnup Calculations of Fast Reactors
Ignas Mickus, Jan Dufek, Kaur Tuttelberg
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 193-198
Technical Note | Reprocessing | doi.org/10.13182/NT14-48
The Use of Flashing Drums and Microchannel Heat Exchangers to Generate Steam in Large Integral Light Water Reactors
Matthew J Memmott, Annalisa Manera
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 199-212
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-103
Analytical Study on the Effective Thermal Conductivity of VHTR Fuel Block Geometry with Multiple Cylindrical Holes
Dong-Ho Shin, Su-Jong Yoon, Nam-Il Tak, Goon-Cherl Park, Hyoung-Kyu Cho
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 213-222
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-102
Interactive Simulation and Visualization of In-Reactor and Under-Sodium Viewing Operations
Young S. Park, Xiaorui Zhao, Pawel Dworzanski, Zachary T. Gima, Richard B. Vilim
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 223-233
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-108
TRIPOLI-4 Simulation of Core Physics Parameters for Two 3600-MW(thermal) Sodium-Cooled Fast Reactors
Yi-Kang Lee, Emeric Brun, Xavier Alexandre
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 234-245
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-85
Preliminary Evaluation of Recriticality Potential for ESFR Core and Conditions for Its Elimination
Franco Polidoro, Michael Flad, Werner Maschek
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 246-253
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-97
Designing for Inherent Control in Liquid-Metal Advanced Small Modular Reactors
Stefano Passerini, Richard B. Vilim
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 254-267
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT14-99
Fuel Performance Analysis of a (ThU)O2-Fueled, Reduced Moderation Boiling Water Reactor
Alexander J. Mieloszyk, Mujid S. Kazimi
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 268-281
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-104
Trade-Off Studies for the Fuel-Self-Sustaining RBWR-Th Core
Phillip M. Gorman, Jasmina L. Vujic, Ehud Greenspan
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 282-294
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-106
