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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
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.