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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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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.
R. Förthmann, H. Grübmeier, D. Stöver
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 548-556
Advanced and Improved Fuel and Application | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31915
Articles are hosted by Taylor and Francis Online.
The retention of metallic fission products in coated particles with ceramic kernel additives is studied out-of-pile and in-pile. The ceramic additives are easily introduced without any significant change of kernel fabrication processes. The excellent efficiency of alumina-silica kernel additives for retaining 90Sr and 140Ba is demonstrated in-pile: The fractional release is reduced by two orders of magnitude. Silver-110m is not retained by the kernel additives. Cesium forms compounds in the alumina-silica additives, which become unstable at temperatures above 1400°C (1673 K). At normal high-temperature gas-cooled reactor operation temperatures [1000 to 1200°C (1273 to 1473 K)], the diffusion coefficient of cesium in oxide kernels with alumina-silica additives is reduced by about two orders of magnitude. The effective diffusion coefficients in these kernels are given by the equationDeff = 5.649 × 104 cm2 s−1 exp (−63 833.5/T)[Deff = 5.649 m2 · s−1 exp (−63 833.5/T)] .