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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
F. A. Garner, C. W. Hunter, G. D. Johnson, E. P. Lippincott, J. O. Schiffgens, Harry Farrar IV
Nuclear Technology | Volume 58 | Number 2 | August 1982 | Pages 203-217
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32932
Articles are hosted by Taylor and Francis Online.
The inner surfaces of both fuel pin cladding and helium-pressurized creep tubes develop near-surface enhancements of helium above that generated in the cladding by (n,α) events. The amount and distribution of the additional helium can be predicted from knowledge of the neutron spectrum, component geometry, and adjacent materials. The major sources of injected helium are ternary fission events in the fuel, recoil-injected helium from the cover gas, and (n,α) events occurring both in the tube and its surrounding materials. While the near-surface enhancement is shown not to be solely responsible for the loss of strength and ductility observed in fuel cladding, it appears that the additional helium acts synergistically with other phenomena associated with fuel adjacency to cause a reduction of cladding lifetime.