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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
Chien Chung, Chin-Hsuen Tsai
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 346-353
Technical Paper | Radiation Protection | doi.org/10.13182/NT96-A35214
Articles are hosted by Taylor and Francis Online.
A method to monitor in situ the dose rate from the gaseous radionuclide 41 Ar is developed using a portable gamma-ray spectrometer. A high-purity germanium detector with a sensitivity of 0.358 nSv/h per count per minute is used to calibrate 1294-keV gamma rays emitted from radioactive 41 Ar. Field measurements are conducted both inside and outside of the containment of a nuclear reactor during full-power operation, and iso-dose rate contour curves are mapped. The in situ measurement can be readily performed at various locations near a nuclear reactor with a 14-kg portable spectrometric unit. The detection limit for a 1-h counting period is as low as 0.35 nSv/h for the gaseous 41 Ar. One can use the method and field measurements developed in this research to quantitatively determine the gaseous fission products of krypton and xenon dispersed from a nuclear power plant.