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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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.
Gang Jiang, Gang Chen, Weikun Ding, Yanghua Yang (State Power Investment Corporation Research Inst)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 388-398
After the Fukushima accident, the lessons involving in nuclear emergency management show that the emergency decision should enhance the capacity of analyzing and predicting severe accident. In order to improve this capability, the severe accident management training simulator (SAMTS) has been developed. This simulator has transplanted the self-developed integral severe accident code cosSA to the simulation platform to build the accident scenario, and coupled with computerized severe accident management guideline (CSAMG). The SAMTS provides several interventions to simulate different mitigation measures in SAMG, which help the operators handle to mitigate consequences and understanding the impact of mitigating actions on accident progression. This simulator could build the accident scene quickly to forecast and analysis to make central role of the information source for decision-making technical support in nuclear emergency management. The main purpose of this paper is to give a brief description of this simulator, including architecture, methodology, physical models of cosSA and a simulation case. Simulation results were compared with MELCOR (mainstream simulator calculation engine service) with the same initial and boundary conditions. Comparison results show that the calculation results of temperature, pressure and water level by SAMTS agree well with MELCOR. The good agreement proves the simulation capability of cosSA, which shows that cosSA could be applied into the severe accident simulator.