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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
Framatome, KHNP to investigate producing Lu-177 in South Korea
Framatome and Korea Hydro & Nuclear Power (KHNP) announced the signing of a memorandum of understanding to explore the possibility of producing the medical isotope Lutetium-177 at KHNP’s Wolsong nuclear power plant in South Korea. The companies also will investigate the feasibility of using the plant to support Korean production of medical radioisotopes in the future.
Satoshi Sato, Hideyuki Takatsu, Yasushi Seki, Toshihisa Utsumi
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1129-1133
Neutronics Experiments and Analyses | doi.org/10.13182/FST96-A11963100
Articles are hosted by Taylor and Francis Online.
Shielding analyses of the inboard blanket, the vacuum vessel and the Toroidal Field Coil (TFC) in International Thermonuclear Experimental Reactor OTTER) were performed by Monte Carlo and 2-dimensional discrete ordinate methods taking the radiation streaming through the 20 mm wide gap between the adjacent blanket modules into account, and their peak nuclear responses were evaluated The nuclear responses of the TFC could fully satisfy the radiation limits. On the other hand, the helium production rates of the branch pipe, the leg and the front surface of the vacuum vessel behind the gap were about 2-3 times higher than the radiation limit at the end of the operation, i.e. the neutron fluence of 3 MWa/m2. So the shielding module is required to be increased by 80 mm to satisfy the radiation limit. Also, shielding analyses for 20 - 100 mm wide gaps were performed, and it was found that the gap width could be increased by up to 50 mm from the TFCs protection for their peak nuclear responses point of view.