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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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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.
Yasushi Nomura, Takanori Shimooke
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 340-349
Technical Paper | Criticality Safety | doi.org/10.13182/NT84-A33416
Articles are hosted by Taylor and Francis Online.
Some 500 cases of benchmark calculations on criticality problems for homogeneous experimental systems have been made with the KENO-IV Monte Carlo calculation code using the MGCL cross-section data library. The calculation results have been analyzed to classify the experimental systems so as to make the variance of calculated keff bias as small as possible in each classified system. The trends of bias are identified and illustrated to be optimumly expressed by a multiple variable regression equation in terms of several variables, which adequately correlate with the bias value of keff calculated for the experiments. The uncertainty accompanied by bias correction for calculated keff is clearly determined, and the margin set aside for the experimental error is assessed. Finally, the procedure to estimate nuclear criticality safety is proposed.
