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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.
T. Itoh, T. Hayashi, K. Isobe, K. Kobayashi, T. Yamanishi
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 701-705
Technical Paper | The Technology of Fusion Energy - Tritium, Safety, and Environment | doi.org/10.13182/FST07-A1572
Articles are hosted by Taylor and Francis Online.
In order to handle high-level tritiated water (HTO) safely, the self-decomposition behavior has been investigated as functions of tritium concentration (from 16 GBq/cm3 to 2 TBq/cm3) and storage temperature (269K ~ 303K). The representative decomposition products such as H2 in the gas phase and H2O2 in the liquid phase were measured periodically, storing HTO in a leak-tight vessel. The effective production rate of H2 increased with tritium concentration, however, the normalized production rate by tritium decay, like effective G-value, decreased with tritium concentration. The effective production rate of H2O2 also increased with tritium concentration and the normalized one also decreased under consideration of its natural decomposition rate, though it thought that the almost H2O2 calculated by the reported G-value decomposed by extra stimulus in tritiated water. The effective production rates of H2 and H2O2 increased with temperature.