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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.
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.
H. Jochem Rütten, Eberhard Teuchert
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 164-171
Technical Paper | Reactor | doi.org/10.13182/NT76-A31679
Articles are hosted by Taylor and Francis Online.
A favorable distribution of the fuel temperature in combination with a high cooling gas outlet temperature as necessary for a helium-turbine power plant can be achieved in a pebble-bed reactor with “once-through-then-out” fueling without leaving the scope of present feasibility. The equilibrium cycle is reached after a well-balanced and short running-in period. For non-base-load operation, the reactor can be controlled by moving the control rods in the upper void above the pebble bed. Withdrawing the rods causes an increase of the maximum fuel temperature by only 56°C. To avoid replacing of the side reflector during a time of 30 yr, the fast-neutron flux in the reflector can be remarkably lowered by inserting a certain amount of neutron poison into the reflector graphite and by an outer ring of “breeding” fuel elements, respectively.