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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Karl Heinemann, Ralf Hille, Kurt Jürgen Vogt
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 17-24
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33139
Articles are hosted by Taylor and Francis Online.
The initiation of emergency measures to protect the public after a nuclear accident must be based on immediate measurements of external doses and inhalation doses in inhabited areas. The external radiation exposure from the plume and soil can be determined with dose rate meters. Due to the different biological effects of the individual nuclides, the detection of the inhalation doses calls for nuclide analysis of the air concentration. Radiation exposure calculations of light-water and high-temperature reactors and other nuclear installations proved that only a few nuclides cause the main contribution to the inhalation dose. In the case of reactors, the critical nuclide is 131I. After examining accidents in other nuclear facilities, different nuclides, e.g., strontium and plutonium, may become relevant.