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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.
2020 ANS Virtual Winter Meeting
November 15–19, 2020
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Fusion Science and Technology
UWC 2020: A call for transformational change
Bowing to current COVID-19 realities but buoyed by the success of June’s virtual Annual Meeting, ANS event planners returned to the virtual realm for this year’s Utility Working Conference. Originally scheduled for August 9–12 at Marco Island, Fla., the condensed event was held Wednesday, August 11, wherever registrants’ computer devices happened to be located.
In addition to 26 educational sessions and workshops, UWC 2020 featured an opening plenary session titled “Achieving Transformational Change: A leadership discussion,” moderated by Bob Coward, MPR Associates principal officer and ANS past president (2017–2018). Plenary panelists included representatives from three utilities—Arizona Public Service (APS), Exelon, and Xcel Energy—plus the Institute of Nuclear Power Operations (INPO) and the Nuclear Regulatory Commission.
Saerom Kwon, Masayuki Ohta, Satoshi Sato, Chikara Konno, Kentaro Ochiai
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 362-367
Technical Paper | dx.doi.org/10.1080/15361055.2017.1330622
Articles are hosted by Taylor and Francis Online.
A new benchmark experiment on lead with DT neutrons was designed and carried out with a large lead assembly covered with Li2O blocks at JAEA/FNS to validate nuclear data of lead for measurement of reaction rates without impact of background neutrons. The experiment was analyzed by using the MCNP5-1.40 code with the latest nuclear data libraries, ENDF/B-VII.1, JEFF-3.2 and JENDL-4.0. The calculated reaction rates underestimated the measured ones with the depth. Moreover, the tendencies of C/Es were different among the nuclear data libraries. In order to find out the reasons of the differences, we examined reaction cross-sections of lead in the nuclear data libraries in detail. The potential reactions to cause the underestimation issue of the calculated reaction rates were indicated through this study.