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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Pekka Jauho, Lasse Mattila
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 472-478
Technical Paper | Reactor | doi.org/10.13182/NT72-A31216
Articles are hosted by Taylor and Francis Online.
A versatile computer program is used to investigate the effects of variation in several essential reactor plant operation parameters, such as coolant leakage rates, reactor power history, and the amount and date of organized release, on the distribution of tritium in the primary system process waters of a WWER-type pressurized water power reactor plant. All the primary process waters ultimately reach a tritium saturation activity of ∼1.5 µCi/cm3 if no organized release is employed. An annual organized release of about one primary circuit water volume is needed to keep the maximum process water tritium activities encountered during an operation year below 0.5 µCi/cm3. The date of the annual release period usually has a rather slight effect on process water maximum activities. Hence, the date for release may be chosen so that, for example, the accompanying release of fission and corrosion product activities is minimized.