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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
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Nuclear Technology
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May 2025
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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Richard D. Peters, Urban P. Jenquin, Langdon K. Holton, Jr.
Nuclear Technology | Volume 90 | Number 1 | April 1990 | Pages 78-86
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT90-A34387
Articles are hosted by Taylor and Francis Online.
Measurement and prediction of outside surface exposure rates and measurement of gamma photon spectra from radioactive sources are described. The sources were 30-cm-diam canisters filled with borosilicate glass to a height of ∼100 cm. Each canister contained up to 237 kCi of 137 Cs and 159 kCi of 90Sr. Exposure rates on the outside surfaces ranged from 26 000 to 320 000 R/h, chiefly from decay of 137 Cs. The radiation field around the canisters was modeled using two codes based on point kernel theory (ISOSHLD-II and QAD-CG) and a transport theory code (ANISN). It was found that the point kernel codes overpredicted surface exposure rates for the radioactive canisters by a factor of ∼2. The surface exposure rates calculated by the transport theory code were ∼25% higher than the measurements. Spectral measurements indicate that most exposure is associated with gamma radiation in the 0.1- to 0.5-MeV range.