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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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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.
J. R. DiStefano, K. H. Lin
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 34-45
Technical Paper | Material | doi.org/10.13182/NT73-A31316
Articles are hosted by Taylor and Francis Online.
The power density of 244Cm2O3 makes it an attractive fuel form for a variety of radioisotopic applications. To evaluate the compatibility of 244Cm2O3 with refractory metals for high-tem-perature applications, Ta, Ta - 10 wt% W, T-111, Mo, TZM, W, and W- 26 wt% Re were tested at 1650 and 1850°C, and Nb, Nb -1 wt% Zr, Ta, Ta- 10 wt% W, Mo, V, and Zr were tested at 1250°C for times up to 10 000 h. Serious reactions of 244Cm2O3 with Zr occurred at 1250°C and with Ta - 10 wt% W and T-111 at 1650°C. At both 1250 and 1650°C, the remaining materials showed good resistance to 244Cm2O3 with only limited attack, mainly in the form of shallow intergranular subsurface voids. At 1850°C, there was evidence of dissolution of tantalum and the tantalum alloys by 244Cm2O3. After 5000 and 10 000 h, tantalum had transferred from one portion of the capsule to another, and tantalum particles were found in the fuel. Less extensive mass transfer was noted with the other materials, although significant amounts of tungsten from the unalloyed tungsten and W - 26 wt% Re tests were found in the fuel.