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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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.
Charles E. Cartmill
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 422-427
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32348
Articles are hosted by Taylor and Francis Online.
A Semiscale Mod-1 blowdown heat transfer test was conducted to supply thermal-hydraulic data concerning the fluid phenomena that occur during a small break loss-of-coolant accident. While it is easily recognized that a large break suddenly releases a great volume of coolant with rapidly falling levels and pressures, emergency core injection will also occur very early, compared to a small break. There has been concern that the longer times involved in small breaks (much longer subcooled flow periods) could lead to effects worse than for large breaks. Within the scope of the testing conducted, the small break has proven to be of lower consequences than the large break.