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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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NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
Chong Chiu, Neil E. Todreas, Warren M. Rohsenow
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 40-52
Technical Paper | Fuel | doi.org/10.13182/NT80-A17068
Articles are hosted by Taylor and Francis Online.
A flow split model for the turbulent flow in a wire-wrapped nuclear fuel rod assembly is developed taking the form drag and sweeping flow between subchannels into consideration. This model is applicable to the flow distribution between two types of subchannels, i.e., interior and edge subchannels. The constants in this model for each type of subchannel were determined using all experimental data in the literature and the results of two tests performed as part of this study to fill a gap in the available literature. These experiments to measure flow split were performed on two wire-wrapped 61 pin bundles of pin pitch-to-diameter ratio equal to 1.063 and wire lead to pin diameter ratios of 4 and 8. The predictions of this model match all experimental data in the literature within ±5%.