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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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Jean-Pierre Leveque, Bernard Andre, Gérard Ducros, Gilles Le Marois, Gilbert Lhiaubet
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 33-44
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35041
Articles are hosted by Taylor and Francis Online.
Between 1983 and 1989, the Fuel Behavior Studies Branch of the Commissariat à l’Energie Atomique-Grenoble performed eight tests in the HEVA (helium and vapor) program. This program, which is a part of the general French Institute for Nuclear Protection and Safety program concerning severe accident studies, is devoted to the measurement of fission product (FP) release rates under severe accident conditions. Each test was performed with a small section (three pellets) of a standard pressurized water reactor fuel rod in its original cladding, heated in a high frequency furnace, at temperatures up to 2300 K, in a steam and hydrogen environment. The volatile FP release rates were measured by gamma spectrometry. Posttest examinations supplied further information about the behavior of the FP, mainly concerning the aerosol sizing and the chemical speciation of the deposits. The results were compared with those obtained by other laboratories and with the calculated values. The measured release rates are generally lower than those calculated using the CORSOR model. A large influence of the environment is evidenced. The aerosol mean aerodynamic diameter is ∼0.3 µm. The HEVA program is extended by the VERCORS program mainly devoted to low volatile FP release rates and kinetics.