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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Junichi Tanji, Shunsuke Utena
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 580-589
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33680
Articles are hosted by Taylor and Francis Online.
A symptom-oriented method for providing operational guidelines under posttrip conditions is developed to support operators of boiling water reactor power plants. The method is dedicated to providing the operator with two levels of operational guidelines for a plant cold shutdown. Level I involves a selection of basic operating tactics, and level II involves a determination of operation priority and a confirmation of operation results. Technical evaluation of the guidance algorithm is made using off-line simulation tests postulating the events in loss-of-feedwater and loss-ofcoolant accidents. Results show that the developed method is adequate.