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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Douglas W. Croucher
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 45-57
Technical Paper | Fuel | doi.org/10.13182/NT80-A32555
Articles are hosted by Taylor and Francis Online.
Three pressurized water reactor type fuel rods that contained defects representative of those occasionally found in the cladding of commercial reactor fuel rods, that is, a hydrided region, a pinhole-type defect, and an axial crack, were tested under power ramp and power-cooling-mismatch conditions. Operation of the hydrided fuel rod in a power ramp caused a cladding rupture at the location of hydriding and degraded the thermal performance of the rod. Operation of all three defective rods for a short time in film boiling did not seriously aggravate the condition of the rods beyond that experienced by intact rods undergoing the same transient. Embrittlement of the cladding, however, was in excess of that found in intact rods. Although the defective rods withstood the stresses associated with the quenching of the cladding from high temperature film boiling conditions, two of the rods fractured during post-test handling under conditions where intact Zircaloy-clad fuel rods embrittled by oxygen absorption alone would not have fractured. Fuel washout occurred where large, open cladding defects were present. No molten fuel-coolant or molten fuel-cladding interaction was observed.