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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
Farid Bamdad
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 578-582
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32801
Articles are hosted by Taylor and Francis Online.
Analyses of depressurization rates other than full Automatic Depressurization System (ADS) blowdown are performed to study the effect on the core cooling capability and to minimize thermal stress on the reactor vessel. Four different arbitrary conditions are demonstrated in order to verify the possibility of defining a range over which the slow depressurization can be performed without uncovering the core. The first two cases demonstrate the sensitivity to the depressurization starting time by manual blowdown at 25% capacity at 5 and 8 min into the transient. Two other cases are chosen to show the possible effects of the rate of depressurization. This is done by blowing down at 50 and 75% steam relief capacity at 5 min after the initiation of the transient. For all these cases it is assumed that an additional 25% flow discharge exists due to a stuck open relief valve. The last case demonstrated that early full ADS blowdown might flash water mixed with steam through the relief valves. This is due to the sudden expansion in the reactor vessel inventory upon pressure relief and high water level at the time of depressurization. This, however, is of paramount importance in the integrity and design operating conditions of the ADS valves and steam piping system.