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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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
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.
Peter Weimar, Wolfgang Ernst
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 81-89
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A16188
Articles are hosted by Taylor and Francis Online.
Until now, experience with the consequences of longer operation of failed mixed oxide fuel pins in liquid-metal fast breeder reactor has not been available. Mol-7B, an 18-pin bundle, was originally specified and fabricated to test the SNR-300-Mk-Ia concept under extreme operating conditions, especially with a cladding temperature of 973 K. Because of larger uncertainties of flux distribution in the BR-2 reactor in Mol, Belgium, this bundle was irradiated with a rod power that was 20% higher as expected. As a consequence, 17 of the 18 pins failed during the irradiation campaign. The main reason was mechanical interaction of the fuel with the embrittled and corroded cladding and excessive fission gas pressure. Cladding opening was followed by chemical reaction between sodium coolant and the fuel. A partial blockage occurred from the buildup of the reaction product Na3MO4 and from the diameter increase due to uranate swelling. In spite of these severe failures and large fuel release to the coolant, the bundle could be operated with a high nominal rod power without cladding melting and more severe consequences on bundle integrity and on reactor safety.