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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.
George R. Fegan, Daniel I. Herborn, Steven M. Lippincott
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 13-18
Technical Paper | Reactor | doi.org/10.13182/NT78-A32086
Articles are hosted by Taylor and Francis Online.
Received January 31, 1977 Accepted for Publication September 7, 1977 The net free volume of the containment is an essential parameter in the loss-of-coolant accident (LOCA) containment pressure analysis for pressurized water reactors. For an optimized emergency core cooling system performance due to the importance of backpressure during the reflood phase of a LOCA, it is necessary to have the predicted pressure quite close to the design pressure. Using a geometric analysis, an estimate of 56 241.99 m3 (1 986 167 ft3) for the net free volume has been made for the containment of the Trojan nuclear plant. Two sets of data were produced from the normally scheduled structural integrity and integrated leak-rate tests on the Trojan containment. These data sets were used to arrive at two new estimates of the net free volume. A deterministic equation giving volume as a function of the slope of a linear relationship between depressurization and time was developed. After an analysis of the reliability of the data, estimates of this linear slope were made from the two data sets. These two slopes gave net free volume estimates of 58 000 m3 (2.05 × 106 ft3) and 57 650 m3 (2.036 × 106 ft3) when used in the deterministic equation. The maximum deviation from the geometric-based estimate was <4%.
