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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.
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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.
Kyle E. Brumback, Seth R. Cadell, Brian G. Woods (Oregon State Univ)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 701-713
An investigation into the onset of natural circulation during a depressurized conduction cooldown was conducted at the High Temperature Test Facility at Oregon State University. In this set of four tests, the primary loop of the facility was filled with helium and then heated until a temperature difference across the core was: 125°C, 250°C, 375°C, and 500°C. The Reactor Cavity Simulation Tank (RCST) was filled with nitrogen gas. During the heating phase of the test the primary loop and RCST were held at pressures greater than 130 kPa. Once the desired temperature was achieved the primary loop and RCST pressures were reduced to 112 and 110 kPa, respectively. The cold leg break valve was opened and then the hot leg break valve was opened. The hot helium in the primary loop began to flow into the RCST displacing the cold nitrogen, in a lock exchange flow. Once the density differences equalized in the two tanks, a natural circulation will develop as the gas is heated in the core, flows from into the RCST through the upper plenum, upcomer, and cold leg. Once cooled in the RCST the gas then flows through the hot leg and returns into the core. This paper discusses the findings for each of the four tests and compares the time required for the natural circulation to establish as a function of temperature across the core.