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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
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Shan H. Chien, A. R. Wazzan, D. Okrent
Nuclear Technology | Volume 60 | Number 1 | January 1983 | Pages 69-83
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33103
Articles are hosted by Taylor and Francis Online.
A fission gas code, GRABB, is developed to model intragranular and grain boundary fission gas development and release in a fast thermal transient. Transient direct electrical heating fission gas data, test 33, is simulated with GRABB and GRASS-SST. The computations show that accurate fuel modeling requires consideration of grain edge fission gas and a grain surface bubble interlinkage mechanism. Swelling data are slightly better predicted by GRABB than by GRASS-SST. Both codes underestimate the low temperature gas release data. The GRASS-SST code underestimates the intermediate temperature gas release while GRABB predictions are within the scatter of the data. The high temperature gas release is overestimated by GRASS-SST while GRABB underestimates it.
