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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Michael J. Gaeta, Brad J. Merrill, Hans-Werner Bartels, Carine Rachel Laval, Leonid Topilski
Fusion Science and Technology | Volume 32 | Number 1 | August 1997 | Pages 23-34
Technical Paper | First-Wall Technology | doi.org/10.13182/FST97-A19877
Articles are hosted by Taylor and Francis Online.
The possibility of a beryllium-steam reaction during severe accidents in the International Thermonuclear Experimental Reactor (ITER) is a safety concern because the hydrogen produced from this reaction could pose a flammability or detonation hazard. The physical mechanisms governing the production of hydrogen are examined, and the sequence of events during a postulated ex-vessel loss-of-coolant accident (LOCA) are presented. A MELCOR simulation of an ex-vessel LOCA with simultaneous failure of the plasma shutdown system indicates that an in-vessel breach of the coolant system occurs because of first-wall melt-through. For the ITER interim first-wall/shield-blanket (FW/SB) design, this accident results in ∼67 kg of hydrogen being produced. A similar simulation for the divertor predicts only 0.3 kg of hydrogen because of additional cooling experienced by the divertor during the blowdown of coolant into the vacuum vessel. There is evidence to indicate that beryllium evaporation from the first wall at a surface temperature of 1100°C is enough to cause plasma termination through beryllium evaporation. This plasma termination occurs prior to first-wall melt-through and could minimize or eliminate significant hydrogen production. Sensitivity studies were performed by varying the first-wall temperature at which plasma termination and in-vessel breach occurs for an ex-vessel LOCA scenario. This study shows that if the plasma is terminated before 150 s (i.e., a maximum first-wall temperature of 777°C) after the ex-vessel LOCA, the amount of hydrogen generated is ∼1 kg, which is well below the flammability limit of 10 kg and gives a reasonable margin for model uncertainty. Other sensitivity studies using the FW/SB model indicated a relatively weak dependence of the hydrogen produced on in-vessel and ex-vessel breach size. In addition, a 60% reduction in coolant inventory resulted in only a one-third decrease in hydrogen production from the base case. Preliminary calculations for an in-vessel LOCA indicate that 100 kg of 50-µm dust in the vacuum vessel could generate 2 kg of hydrogen.