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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
Kenichi Yoshioka, Mitsuaki Yamaoka, Kouji Hiraiwa, Takanori Kitada
Nuclear Science and Engineering | Volume 195 | Number 1 | January 2021 | Pages 101-117
Technical Note | doi.org/10.1080/00295639.2020.1788847
Articles are hosted by Taylor and Francis Online.
The void reactivity of a fuel assembly with a streaming channel was measured in a simulated light water reactor critical lattice. The void reactivity was defined as the difference of reactivity ρ between different void conditions. Stainless steel and Zircaloy are candidates for the streaming channel material. Aluminum was used in this measurement because it is inexpensive and its absorption cross section is similar to that of Zircaloy. Two types of streaming channels were used: one made of aluminum and the other made of stainless steel. The two streaming channels were compared in terms of the difference in void reactivity. Measured values were calculated using a continuous-energy Monte Carlo code, MCNP6.1, with the JENDL-4.0 and ENDF/B-VIII.0 nuclear data libraries. The measured values and the calculated values agree within an error range of approximately 10% for the aluminum streaming channel and approximately 20% for the stainless steel streaming channel. The streaming effect of reactivity was deduced from the changes of migration area and buckling, which were measured using the water-height coefficient of reactivity and the axial fission-rate distribution.