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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Feb 2025
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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
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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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
