ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
C. Parisi, E. Negrenti, M. Pecchia
Nuclear Science and Engineering | Volume 178 | Number 4 | December 2014 | Pages 524-538
Technical Paper | doi.org/10.13182/NSE14-40
Articles are hosted by Taylor and Francis Online.
This paper summarizes the evaluation for core I and core VIII of the Babcock & Wilcox Spectral Shift Control Reactor critical experiment program. The Spectral Shift Control Reactor concept, moderated and cooled by a variable mixture of heavy and light water, envisaged changing of the thermal neutron spectrum during the operation to encourage breeding and to sustain the core criticality. Core I contained 484 fuel rods with 4% UO2 fuel in light water while core VIII contained 2188 fuel rods with 93% enriched UO2-ThO2 fuel in a moderator mixture of heavy and light water. For core I, the criticality experiment and measurements of the thermal disadvantage factor were evaluated. For core VIII, only the criticality experiment was evaluated. For both cores, experimental uncertainties were determined confirming the good level of accuracy achieved by the experimentalists. Based on the experimental configurations, benchmarks were proposed, and their biases were determined.