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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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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