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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.
Claus Elter, Eberhard Haug, Helmut Morassi
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 204-226
Technical paper | Reactor | doi.org/10.13182/NT78-A31991
Articles are hosted by Taylor and Francis Online.
In the course of the evaluation of the Philippsburg 1 boiling water reactor in the Federal Republic of Germany, carried out for the licensing authorities, the behavior of the reactor internals during a bearing water line accident was analyzed by theoretical calculations. During this accident, the reactor internals are exposed to a short-time negative pressure wave that expands in the water and is rapidly attenuated. The extent of the influence this load has on the operating capability of the components, particularly of the shut-down facilities, is to be analyzed. Linearly elastic dynamic analyses were carried out on the mechanical behavior of the structure on the basis of calculations of the time- and space-dependent pressure distribution on the core shroud and vessel dome. Staggered geometries and attenuation were not taken into consideration. All calculated components were treated as axially symmetric structures. The load is not axially symmetric and is therefore represented as a Fourier series. The results are given in the form of stresses, displacements, and forces as a function of time.