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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
J. E. Houghtaling, J. E. Grund
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 412-426
Technical Paper | doi.org/10.13182/NSE69-A18738
Articles are hosted by Taylor and Francis Online.
Reactor kinetics investigations have been performed for cold-start-up, hot-start-up, hot-standby, and operating-power reactivity accidents using the UO2-fueled, pressurized-water type SPERT-III reactor. Power excursion behavior was predicted for every SPERT-III experiment by digital computer calculations using the SPERT-developed PARET code. Extrapolations for severe cold-start-up excursion consequences were obtained from severe transient tests on SPERT-III fuel samples in the SPERT-IV capsule driver core. Analyses of the SPERT-III data show that prompt moderator heating was as significant as the Doppler effect in limiting the magnitude of power excursions in the SPERT-III core at operating temperatures. Comparisons of calculations and experimental data demonstrate that PARET is capable of predicting power excursion behavior in SPERT-III within experimental uncertainty for the range of conditions investigated. The SPERT-III integral-core tests also provide a broad base of experimental data for demonstrations of the capabilities of other existing models in predicting non-damaging power excursion behavior in UO2-fueled reactors.
