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
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.
T. Shimooke
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 99-110
Technical Paper | Reactor | doi.org/10.13182/NT74-A31366
Articles are hosted by Taylor and Francis Online.
Two interesting phenomena were observed in the axial power distribution in the core of the Japan Power Demonstration Reactor. One is the control-rod and void coupled bump on the axial power shape; this is a kind of local power peaking produced by the interacted effect between the partially inserted control rod and the axial void changes in the moderator. The other may be termed a “burnup oscillation of the axial power distribution” this is a long-term, periodic change of the axial power distribution due to core exposure and to the withdrawal of the control rods. It is found that the upper and lower half-channel integrations of the local leakage of thermal neutrons are essential factors for the occurrence of those phenomena.