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Division Spotlight
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.
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.
Salim N. Jahshan, William K. Terry
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 93-105
Fission Reactor | Burnup Credit | doi.org/10.13182/NT95-A35099
Articles are hosted by Taylor and Francis Online.
The Broad-Application Test Reactor has been proposed for testing and isotope production missions in the early twenty-first century. Two conceptual designs, both employing metal plate fuel, light water coolant, and a heavy-water primary or secondary reflector region, survived an initial screening process. The Monte Carlo neutronics code (MCNP) was used to select one of these designs for future development. For each design, alternative fuel and pressure vessel materials were considered, and a preferred material was identified for each of the candidate designs. The design judged superior contains seven test regions, each surrounded by Zircaloy fuel annuli and enclosed by its own separate Zircaloy pressure boundary tube.