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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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May 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
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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
