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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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.
Norbert Eickelpasch, Reinhard W. Seepolt, Johann Müllauer, Werner Spalthoff
Nuclear Technology | Volume 60 | Number 3 | March 1983 | Pages 362-366
Technical Paper | LWR Control Materials—I and II / Fission Reactor | doi.org/10.13182/NT83-A33123
Articles are hosted by Taylor and Francis Online.
The control rods of the KRB-I 250-MW(electric) boiling water reactor contain Vipac B4C powder in Type 304 stainless steel tubes as a neutron-absorbing material Because of an increase in the reactor coolant 3H activity, defective control rods were suspected. The hot cell examination of a highly exposed control rod revealed B4C losses. The mechanism of failure was shown to be B4C swelling and stress corrosion cracking of the absorber tubes, followed by B4C washout. The B4C volume swelling is ΔV(%) = 0.851x + 0.0449x2 [x = 10B decays in 1021(n,α)/cm3]. The tube cracking starts at 30 to 35% and the B4C washout at 50 to 55% local 10B burnup in the tubes.
