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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
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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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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Determination of Code Accuracy in Predicting Small-Break LOCA Experiment
Borut Mavko, Andrej Prošek, Francesco D’auria
Nuclear Technology | Volume 120 | Number 1 | October 1997 | Pages 1-18
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35427
A Radiation Barrier Alloy for Long-Term Storage of Special Nuclear Materials: Definition and Preliminary Assessment
Carl A. Beard, John J. Buksa, J. Wiley Davidson, Stacey L. Eaton, John J. Park, James W. Toevs, Kenneth A. Werley
Nuclear Technology | Volume 120 | Number 1 | October 1997 | Pages 19-40
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35428
Solvent-Washing Process Using Butylamine in Fuel Reprocessing
Gunzo Uchiyama, Sachio Fujine, Mitsuru Maeda
Nuclear Technology | Volume 120 | Number 1 | October 1997 | Pages 41-47
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35429
Chemical Behavior of Aqueous Iodine at the Forsmark Boiling Water Reactor Nuclear Power Plants
Rikard Malmbeck, Gunnar Skarnemark
Nuclear Technology | Volume 120 | Number 1 | October 1997 | Pages 48-56
Technical Paper | Material | doi.org/10.13182/NT97-A35430
Thermal-Hydraulic Analysis of Bulk Evaporation and Condensation in a Multiphase Nuclear Fuel Cell
Samim Anghaie, Zhongtao Ding
Nuclear Technology | Volume 120 | Number 1 | October 1997 | Pages 57-70
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35431
Quantitative Indicators of Detector String Impacting
Ola Thomson, Ninos S. Garis,†, Imre Pázsit
Nuclear Technology | Volume 120 | Number 1 | October 1997 | Pages 71-80
Technical Paper | Reactor Operation | doi.org/10.13182/NT97-A35432
Characteristics of Nonlinear Dynamics Dependent on TBP Concentration Change in the Extraction Process for Nuclear Fuel Reprocessing
Masaru Todoriki, Atsuyuki Suzuki
Nuclear Technology | Volume 120 | Number 1 | October 1997 | Pages 81-85
Technical Note | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35433
On the Determination of Bottom Drain Oxygen in Boiling Water Reactors
Digby D. Macdonald, Iouri Balachov
Nuclear Technology | Volume 120 | Number 1 | October 1997 | Pages 86-93
Technical Note | Material | doi.org/10.13182/NT97-A35434
Experimental and Analytical Study on Pool Scrubbing Under JET Injection Regime
Luis E. Herranz, Virginia Peyrés, Jesús Polo, María J. Escudero, Manuel M. Espigares, José López-Jiménez
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 95-109
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35419
The Commissariat à l’Énergie Atomique Spin Program: Minor Actinide Fuel and Target Aspects
Claude Prunier, Yannick Guérin, Jean-Luc Faugère, Nadine Cocuaud, Jean-Marc Adnet
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 110-120
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35420
Numerical Calculation and Measurement of Bubble Shape and Excess Pressure in Dip-Tube Pressure Measurement
Takashi Hosoma, Masanori Aritomi, Tsunemichi Kawa
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 121-135
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35421
Radionuclide Transport in Fractured Porous Media—Analytical Solutions for a System of Parallel Fractures with a Kinetic Solubility-Limited Dissolution Model
Shih-Hai Li, Chu-Tien Chen
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 136-148
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT97-A35422
Optimization of Electrolytic Plants for Deuterium Production: Steady-State Analysis
David A. White, Suttichai Assabumrungrat, Ahmad Moheb
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 149-157
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT97-A35423
Supercritical Vapor Explosions: Comparisons Between Thermodynamic and Mechanistic Models
Bassam I. Shamoun, Michael L. Corradini
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 158-170
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35424
An Effect of the Side-Tube Configuration on the Void Fraction Measurement
Kuo-Hsiang Chien, Wei-Keng Lin, Yih-Chean Tsai
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 171-178
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35425
Monte Carlo Simulation of the Triga Mark II Benchmark Experiment
Robert Jeraj, Bogdan Glumac, Marko Maučec
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 179-187
Technical Paper | Fission Reactor | doi.org/10.13182/NT97-A35409
Adaptive Vector Quantization Optimized by Genetic Algorithm for Real-Time Diagnosis Through Fuzzy Sets
Marco Antonio Bayout Alvarenga, Aquilino Senra Martinez, Roberto Schirru
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 188-197
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35410
Study on a Nuclear Fuel Reprocessing System Based on the Precipitation Method in Mild Aqueous Solutions
Yuichiro Asano, Noriko Asanuma, Toshihiko Ito, Makoto Kataoka, Shinya Fujino, Tomoo Yamamura, Wataru Sugiyama, Hiroshi Tomiyasu, Kunihiko Mizumachi, Yasuhisa Ikeda, Yukio Wada, Masami Asou
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 198-210
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35411
A Stratified Channel Model with Local Longitudinal Dispersion
Dong-Kwon Keum, Chung-Kyun Park, Pil-Soo Hahn, Tjalle T. Vandergraaf
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 211-223
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT97-A35412
Isotropic Analog—a Method for Penetration Dose Rate Analysis
Sushil K. Bhatnagar
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 224-230
Technical Paper | Radiation Protection | doi.org/10.13182/NT97-A35413
Development of a Bench-Scale Metal Distillation Furnace
Michael A. Vest, Edward F. Lewandowski, R. Dean Pierce, James L. Smith
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 232-242
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35414
Operation of a Bench-Scale Metal Distillation Furnace
Michael A. Vest, Gerald K. Johnson, R. Dean Pierce, Eugene J. Wesolowski
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 243-252
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35415
A Multisystem Modeling Approach for Uranium-Series Dating
Kari Rasilainen, Juhani Suksi
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 254-260
Technical Note | Radioisotopes and Isotope | doi.org/10.13182/NT97-A35416
