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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
IAEA to help monitor plastic pollution in the Galapagos Islands
The International Atomic Energy Agency announced that its Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative has partnered with Ecuador’s Oceanographic Institute of the Navy (INOCAR) and Polytechnic School of the Coast (ESPOL) to build microplastic monitoring and analytical capacity to address the growing threat of marine microplastic pollution in the Galapagos Islands.
Chikara Konno, Fujio Maekawa, Yukio Oyama, Yujiro Ikeda, Masayuki Wada, Hiroshi Maekawa
Fusion Science and Technology | Volume 34 | Number 1 | August 1998 | Pages 6-17
Technical Paper | doi.org/10.13182/FST98-A49
Articles are hosted by Taylor and Francis Online.
An analysis of the bulk-shielding experiment on Type 316 stainless steel (SS316) for deuterium-tritium neutrons was performed at the Japan Atomic Energy Research Institute Fusion Neutronics Source to validate the nuclear data and transport codes used in the shielding design of the International Thermonuclear Experimental Reactor (ITER). The MCNP-4A and DORT3.1 codes with contemporary nuclear data libraries based on the FENDL/E-1.1 and JENDL Fusion File were used for the analyses. The MCNP calculations with the FENDL/E-1.1 and JENDL Fusion File agree within 30% with the measured data. The DORT calculations with the FENDL/E-1.1 and JENDL Fusion File with an energy structure of 175 neutrons and 42 gamma rays and a self-shielding correction represent the measurements with almost the same accuracy as the MCNP calculations. It is concluded that the uncertainty of the shielding calculation for the bulk-shielding configuration of MCNP-4A and DORT3.1 with the FENDL/E-1.1 and JENDL Fusion File on a 900-mm-thick SS316 shield is within 30%.