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
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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May 2025
Latest News
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
Myron B. Reynolds
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 386-391
Technical Paper | doi.org/10.13182/NSE64-A20981
Articles are hosted by Taylor and Francis Online.
A differential-type pressure transducer suitable for use in a fast-neutron environment at elevated temperatures has been developed. The sensitivity of this device is approximately 0.25 lb/in.2 with the ability to withstand an unbalance pressure of over 1500 lb/in.2 from either direction. A number of stainless-steel-clad, UO2-filled fuel rods equipped with these transducers have been irradiated in the Vallecitos Boiling Water Reactor to exposures up to roughly 4000 MWd/t peak. These experiments have shown that fission-gas release is negligible from UO2 operated below the recrystallization temperature. For operation at higher temperatures, observed fission-gas pressures were in qualitative agreement with measured void volume and quantity of free gas found in post-irradiation examination. The decrease in void volume during operation has been calculated for a fuel rod and the calculated value used to estimate a mean fuel temperature.