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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
F. L. Leverenz, Jr., A. A. Garcia, J. E. Kelly
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 5-12
Technical Paper | Reactor | doi.org/10.13182/NT78-A32085
Articles are hosted by Taylor and Francis Online.
Received February 11, 1977 Accepted for Publication September 7, 1977 One of the important findings of the Reactor Safety Study (RSS) was the identification of the risk due to an interfacing system loss-of-coolant accident (LOCA), i.e., failure of interfaces between the high-pressure primary system and the low-pressure injection system (LPIS). Because equivalent interfaces exist in all pressurized water reactors (although not necessarily with the LPIS), the U.S. Nuclear Regulatory Commission (NRC) has included in its Standard Review Plan three equally acceptable designs intended to decrease the risk due to potential interface failures by decreasing the probability of an interfacing system LOCA. The present analysis of the RSS system configuration is in general agreement with the RSS results; however, the RSS presented a linearized estimate of the exact result, such that the probability of occurrence is overestimated from 0 to 5 yr of plant life and underestimated for plant life beyond 5 yr. In addition, this analysis shows that the NRC design options are not probabilistically equivalent; probabilistically, these options vary by four orders of magnitude, and one option could be implemented in such a way as to yield a probability of occurrence greater than the RSS evaluated design. Finally, as a demonstration of the power inherent in the probabilistic methods, the analysis itself reveals the dominate system failure (gross check valve leaks) leading to a limiting design that eliminates this failure mode and reduces the probability to an insignificant level