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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.
Philip E. MacDonald, James M. Broughton, Jay W. Spore
Nuclear Technology | Volume 44 | Number 3 | August 1979 | Pages 401-410
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32275
Articles are hosted by Taylor and Francis Online.
A preliminary evaluation was made of the results from the LOC-11 nuclear blowdown tests conducted in the Power Burst Facility. The objective of the LOC-11 tests was to measure the thermal and mechanical deformation behavior of pressurized and unpressurized fuel rods exposed to a blowdown (coolant depressurization) similar to that expected in a pressurized water reactor (PWR) during a hypothesized double-ended cold-leg break. Incipient fuel rod cladding collapse and swelling occurred during Test LOC-11C, when the two unpressurized and two pressurized PWR-type rods were exposed to a system blowdown with measured cladding temperatures increasing to 1030 K. To better understand the test results and to evaluate prediction capability, RELAP4-calculated coolant thermal-hydraulic and fuel rod thermal behavior and FRAP-T4-calculated fuel rod mechanical deformation behavior were compared with the test LOC-11C data. The RELAP4 posttest calculations of coolant behavior generally agreed well with the measured coolant behavior; however, the calculated cladding surface temperatures were ∼50 K greater than measured. The FRAP-T4 calculations of cladding deformation using “best-estimate” models slightly overpredicted the observed ballooning of the pressurized rods and underpredicted the collapse of the unpressurized rods.