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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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Latest News
Canada begins regulatory approval process for spent fuel repository
Canada has formally initiated the regulatory process of licensing its proposed deep geological repository for spent nuclear fuel, with the country’s Nuclear Waste Management Organization (NWMO) announcing that it has submitted an initial project description to the Canadian government.
According to the NWMO, the initial project description is a foundational document, detailing the repository’s purpose, need, and expected benefits and explaining how the project will be implemented. It also provides a preliminary assessment of potential impacts and describes measures to avoid or mitigate them. The NWMO is the not-for-profit organization responsible for managing Canada’s nuclear waste.
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.
