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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
L. Böhm
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 422-425
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32900
Articles are hosted by Taylor and Francis Online.
A semi-empirical model is developed that shows iodine filter behavior under normal and anomalous conditions. A two-stage accident is assumed in a 300-MW(electric) liquid-metal fast breeder reactor (LMFBR). Normal behavior is expected when there is a 10 to 30% adsorption of the inventory of 131I, released during a core meltdown of the LMFBR. No serious rise in temperature and desorption is expected in the filter under normal conditions. Under anomalous conditions, however, i.e., when >60% of the 131I that is released is adsorbed in the filter, high desorption and probably burning of the charcoal may result.
