ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
R. A. Lorenz, J. L. Collins, A. P. Malinauskas
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 404-410
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32346
Articles are hosted by Taylor and Francis Online.
Models for cesium and iodine release from light water reactor (LWR) fuel rods defected in steam were formulated based on experimental fission product release data from several types of defected LWR fuel rods. The models were applied to a pressurized water reactor undergoing a loss-of-coolant accident temperature transient. Calculated total iodine and cesium releases were 0.053 and 0.025% of the total reactor inventories of these elements, respectively, with most of the release occurring at the time of rupture. These values are approximately two orders of magnitude less than those used in WASH-1400, the Reactor Safety Study.