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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
W. Raskob
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 934-939
Tritium Safety | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30525
Articles are hosted by Taylor and Francis Online.
In view of the public acceptance and the licensing procedure of projected fusion reactors, the release of tritium during normal operation as well as after accidents is a significant safety aspect. Tritium, being chemically identical to hydrogen and thus interacting directly with water and organic substances, differs considerably from the behaviour of other radionuclides in the environment. Therefore, the two consequence assessment codes UFOTRI and NORMTRI have been developed and applied to estimate the doses to the public from releases of tritium under accidental and routine conditions, respectively. In the frame of ITER (International Thermonuclear Experimental Reactor) and SEAFP (Safety and Environmental Aspects of Fusion Power) the dose/release translation has been determined for typical and various worst case release scenarios. Under worst case accidental release conditions, the dose/release translation for the early dose to an individual at the fence may range from 0.5 to 1 mSv/g HTO. The result for the EDE at the fence is up to 3 mSv/g HTO. The collective accidental dose/release translation is about 2.5 manSv/g HTO. However, due to processes inside the facility, only a small fraction of the mobilised activity may be released into the environment. Finally, the current status of the present assessment models is shortly analysed with regard to the strength and weakness of their approaches which led to the recommendation to concentrate on the plant physiological parts of the tritium codes.