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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
ANS seeks program evaluators for ABET accreditation
When ABET visits universities for accreditation purposes, it’s crucial that a qualified nuclear expert performs the assessment of that school’s nuclear engineering, radiological engineering, and/or health physics programs. The Accreditation Policies and Procedures Committee (APPC) of the American Nuclear Society works to ensure that a program evaluator (PEV) from the Society leads these ABET assessments.
S. Ohira, E. Tada, K. Hada, Y. Neyatani, T. Maruo, M. Hashimoto, T. Araki, K. Nomoto, D. Tsuru, T. Ishida, Y. Goto, T. Tsunematsu
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 642-646
Safety and Safety System | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22666
Articles are hosted by Taylor and Francis Online.
In Japan, Fundamental approach for ensuring safety of the ITER plant was established by the Technical Advisory Committee for the Reactor Regulation Division of Science and Technology Agency of Japan in 2000. The approach settled the basic safety principles and approaches as the technical requirements on safety design and assessment derived from the safety characteristics of the ITER plant It was concluded that prevention of accidents can be achieved sufficiently by means of ensuring and maintaining the structural integrity of the enclosures containing radioactive materials against anticipated loads during operation, and low hazard potential of radioactive materials contained can be maintained within prescribed limits sufficiently by the vented detritiation/filtering clean-up system (confinement system) even if large release is postulated. For embodiment of the safety design concepts to the ITER tritium facility, some practical considerations should be taken for the tritium containment barriers, e.g., limitation of tritium permeation and leak, provision of an appropriate ventilation/detritiation system for maintenance, those to ensure the mechanical integrity etc.