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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
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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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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.
G. A. Ratz
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 153-159
Technical Paper | Material | doi.org/10.13182/NT73-A31242
Articles are hosted by Taylor and Francis Online.
The changes that occurred in composition, microstructure, and mechanical properties of a sample of welded AISI Type 304 stainless-steel pipe that had been exposed to liquid sodium for 21 000 h within the range 300 to 800°C have been determined. The results of the investigation showed that under the liquid-sodium service conditions studied, Type 304 steel pipe did not undergo any marked deleterious change in mechanical properties. The tensile strength of the exposed sample was above the minimum value specified by the ASTM for welded Type 304 steel pipe, whereas the yield strength was at the minimum value specified. The results of standard flattening tests on specimens from the exposed sample indicated that they could be flattened without cracking. However, a compositional change occurred on the inner surface of the pipe (the surface that had been exposed to the liquid sodium for 21 000 h). Nitrogen, sulfur, and sodium were absorbed, and a relatively brittle layer, ∼0.05 mm thick, was formed at the inner surface. Thus, when Type 304 steel is used for liquid-sodium service, sodium should be kept as free as possible of contaminants such as nitrogen and sulfur, in addition to oxygen.