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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.
Ronald J. Lipinski
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 53-66
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33373
Articles are hosted by Taylor and Francis Online.
A one-dimensional model is developed for boiling heat removal and dryout in particulate debris. The model can be used for predicting the coolability of postaccident debris from a nuclear reactor (either light water or liquid-metal fast breeder). The model includes the effects of both laminar and turbulent flow, two-phase friction, gravity, capillary force, and channels at the top of the debris. The model is applicable to debris on permeable supports with liquid entering the debris bottom or to debris on impermeable plates. In the latter case, the plate can be either adiabatic or cooled on the bottom. The model predicts channel length, the liquid fraction within the debris as a function of elevation, the incipient dryout power, the dry zone thickness as a function of power, and the existence of downward heat removal by boiling (in bottom-cooled debris), all for both uniform and stratified debris.