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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.
Grover Tuck
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 177-188
Chemical Processing | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT23-177
Articles are hosted by Taylor and Francis Online.
Simplified methods of estimating the results of accidental solution excursions in tanks have been developed. With these methods, an estimate of the number of fissions in the burst, total fissions, or maximum power level can usually be obtained with a desk calculator. The equation parameters are tank diameter, height, and fill rate. The fissile material concentration is not required since, in each case, the “worst-case” concentration was assumed in the derivation of the equation. These methods are sufficiently accurate for most calculations required for safety analysis reports and process plant design. The severity of an excursion can be limited by several methods which include criticality alarm activated shut-off valves in the feed lines, remote tank drain capability, minimizing tank size, etc.