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Division Spotlight
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
S. Niikura, N. Ueda, I. Yanagisawa, T. Tone, Y. Seki
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 602-607
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40105
Articles are hosted by Taylor and Francis Online.
A computer program system THERMECH for THERmoMECchanical and THERmal-Hydraulic design of fusion blanket has been developed. The THERMECH executes blanket design by following processes: 1) preliminary thermal-hydraulic design of blanket by one-dimensional analysis, 2) pre-processing, calculation, modifying and post-processing of two-dimensional thermal-hydraulic and thermomechanical analyses, 3) pre-processing, calculation and post-processing of three-dimensional thermomechanical analysis, 4) calculation of inelastic strain and resultant stress by one-dimensional analysis. This paper presents the outline of the THERMECH program system and the application to JAERI Tokamak Power Reactor.
