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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2025 ANS Annual Conference
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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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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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%.
