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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.
J. W. Kormuth
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 99-102
Technical Paper | Plant Water Chemistry / Reactor | doi.org/10.13182/NT78-A31976
Articles are hosted by Taylor and Francis Online.
Westinghouse pressurized water reactors have experienced soluble releases of 58Co and natural 58Ni into the reactor coolant during refueling shutdowns. When the soluble inventory of 58Co was not managed properly, the refueling water became contaminated, forcing delays in refueling operation schedules. Subsequent testing at other refueling shutdowns identified the development of oxygen species in the coolant as the prime reactant causing the dissolution. Hydrogen peroxide addition to reactor coolant under prescribed conditions was successfully used to create a controllable and soluble release of 58Co and nickel. The controlled release permitted a more deliberate removal of the activity by ion-exchange purification. A lesser, soluble release of the activity was shown to be caused by the depression in reactor coolant pH resulting from dissociation of boric acid following reactor coolant system boration and cooldown.
