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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.
Henry K. Peterson
Nuclear Technology | Volume 87 | Number 2 | October 1989 | Pages 433-442
Technical Paper | TMI-2: Health Physics and Environmental Release / Radioactive Waste Management | doi.org/10.13182/NT89-A27734
Articles are hosted by Taylor and Francis Online.
During and after the March 1979 accident at Three Mile Island Unit 2, highly contaminated water was released to the reactor building (RB) basement, which submerged basement structures to a depth of 2.59 m. When the water was removed from the RB, the radiation fields in the upper portions of the RB did not decrease as expected. Basement radiation source terms were identified and characterized with strings of personnel thermoluminescent dosimeters (TLDs). The TLD data were then used to model the radiation sources using the ISOSHLD computer code to demonstrate the significance to personnel exposures during subsequent recovery operations within the RB.