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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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The blossoming of cooperation between the U.S. and Canada
The United States and Canadian nuclear industries used to be an example of how two independent teams of engineers facing an identical problem—making electricity from uranium—could come up with completely different answers. In the 1950s, Canada began designing a reactor with tubes, heavy water, and natural uranium, while in the U.S. it was big pots of light water and enriched uranium.
But 80 years later, there is a remarkable convergence. The North American push for a new generation of nuclear reactors, mostly small modular reactors (SMRs), is becoming binational, with U.S. and Canadian companies seeking markets and regulatory certification on both sides of the border and in many cases sourcing key components in the other country.
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.