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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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PR: American Nuclear Society welcomes Senate confirmation of Ted Garrish as the DOE’s nuclear energy secretary
Washington, D.C. — The American Nuclear Society (ANS) applauds the U.S. Senate's confirmation of Theodore “Ted” Garrish as Assistant Secretary for Nuclear Energy at the U.S. Department of Energy (DOE).
“On behalf of over 11,000 professionals in the fields of nuclear science and technology, the American Nuclear Society congratulates Mr. Garrish on being confirmed by the Senate to once again lead the DOE Office of Nuclear Energy,” said ANS President H.M. "Hash" Hashemian.
J. C. Courtney, K. R. Ferguson, J. P. Bacca
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 30-41
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16199
Articles are hosted by Taylor and Francis Online.
The Hot Fuel Examination Facility/South, located at the Idaho National Engineering Laboratory, supports the nation’s nuclear energy program by providing a facility for destructive and nondestructive testing of reactor fuels and materials. Irradiated subassemblies and test devices are transferred from the adjacent Experimental Breeder Reactor II or other irradiation facilities into the hot cells. The reliability of those systems required to inhibit the release of radioactivity to the environment is reviewed, and the operations at the facility are described. For each of two hypothetical accidents, release fractions were developed for noble gases, iodines, cesiums, and particulate radionuclides based on realistic but conservative data. The methodologies of the International Commission on Radiological Protection (ICRP)— both ICRP-2 and ICRP-30—were used to determine the radiological consequences at off-site receptors. By either technique, dose commitments from inhalation and submersion were small fractions of current federal guidelines. The relative contribution of each radionuclide was determined; iodine and cesium were more significant than plutonium for the decay times considered.