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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
Work advances on X-energy’s TRISO fuel fabrication facility
Small modular reactor developer X-energy, together with its fuel-developing subsidiary TRISO-X, has selected Clark Construction Group to finish the building construction phase of its advanced nuclear fuel fabrication facility, known as TX-1, in Oak Ridge, Tenn. It will be the first of two Oak Ridge facilities built to manufacture the company’s TRISO fuel for use in its Xe-100 SMR. The initial deployment of the Xe-100 will be at Dow Chemical Company’s UCC Seadrift Operations manufacturing site on Texas’s Gulf Coast.
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.