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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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Latest News
Lightbridge to test uranium-zirconium fuel alloy in INL’s ATR
Lightbridge Corporation has fabricated samples of nuclear fuel materials made of an enriched uranium-zirconium alloy, matching the composition of the alloy that the company intends to use for its future commercial Lightbridge Fuel product. The fuel is designed to improve the performance, safety, and proliferation resistance of nuclear reactors, according to the company. The enriched coupon samples will now be placed into capsules for irradiation testing in Idaho National Laboratory’s Advanced Test Reactor.
Han-Jie Cai, Fen Fu, Jian-Yang Li, Ya-Ling Zhang, Xun-Chao Zhang, Xue-Song Yan, Zhi-Lei Zhang, Jian-Ya Xv, Mei-Ling Qi, Lei Yang
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 107-115
Technical Paper | doi.org/10.13182/NSE15-59
Articles are hosted by Taylor and Francis Online.
The Institute of Modern Physics, Chinese Academy of Sciences performs research and development on the target station of an accelerator-driven system (ADS) under the China ADS project. A newly developed Monte Carlo program for the design of the target station named GMT1.0 is presented. The program is designed for a massively parallelized simulation of the initiative granular-flow target concept. Based on the combination of the Intranuclear Cascade of Leige (INCL) model and the ABLA evaporation/fission model, GMT1.0 integrates a particle transport code and a nuclear reaction code to simulate a spallation target. For validation, a series of calculations of neutronics characteristics and heat-deposit distributions of solid targets were performed, and a high degree of accuracy was shown for GMT1.0. Using GMT1.0, a systematic study of the neutron economy of the target was performed and the neutronics characteristics of the most optimal parameters were illustrated well.