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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
DOE issues RFI for a spent fuel consolidated interim storage facility
The Department of Energy’s Office of Nuclear Energy has issued a request for information opportunity for the design and construction of a federal consolidated interim storage facility (CISF) for spent nuclear fuel. The DOE is planning on establishing a federal CISF to manage SNF until a permanent repository is available. In May, the DOE received initial approval, known as “Critical Decision-0,” for such a facility.
The deadline for submissions is September 5.
N. Miya, M. Nemoto, N. Toyoshima
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 507-511
Fusion Material and Plasma-Facing Component | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40207
Articles are hosted by Taylor and Francis Online.
Tritium concentration measurements have been made of the tritium recovery from the JT-60U after high power neutral beam injected discharges. This work has been done to study tritium release characteristics and to assess the tritium inventory in the vacuum vessel. Cleanup operations by hydrogen divertor discharges and helium glow discharge cleanings were performed to deplete the tritium inside the wall prior to in-vessel maintenances. After the beginning of the divertor discharges the tritium release from walls increases gradually. The release rate depends on the surface temperature of divertor plates and it is enhanced by high-power neutral beam heated divertor discharges combined with high-temperature vessel baking. Helium glow discharges, furthermore, give strong release characteristics compared with divertor discharges in spite of their short duration within ∼1 hr. After the deuterium discharges and cleanup operations from July 1991 to July 1994, it is estimated that 70∼ 80% of the total tritium of 39 GBq generated in the plasma is retained inside the graphite first wall.