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Fusion Science and Technology
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ANS hosts webinar on criticality safety standards
A diagram depicting the NRC’s regulatory structure for nuclear criticality safety. (Image: Oak Ridge National Laboratory)
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series last month. RP3C chair Steven Krahn opened the meeting with brief introductory remarks about the importance of risk-informed, performance based (RIPB) decision-making and the need for new approaches to nuclear design that go beyond conventional and deterministic methods.
Claudia Dumitrescu, Sebastian Brad, Horia Necula, Mihai Vijulie, Alin Lazar, Catalin Brill, Oleksandr Sirosh, Aleksander Grafov, Andrii Rozhentsev
Fusion Science and Technology | Volume 81 | Number 4 | May 2025 | Pages 285-293
Review Article | doi.org/10.1080/15361055.2024.2434996
Articles are hosted by Taylor and Francis Online.
A computer simulation model developed in the ANSYS Fluent 2022 version R2 package was used for the engineering analysis required to design a counterflow matrix heat exchanger (MHE) for cooling a hydrogen stream. The theoretical data obtained with the simulation model were compared with the experimental data collected during the experimental campaigns carried out in the Cryogenics Laboratory of ICSI Rm. Valcea.
The MHE was tested for three test regimes obtained by theoretical correlations applicable to the current configuration. The Nusselt number, friction factor, and performances theorized by different authors, such as Gnielinski, Miheev, and Mikulin et al. were evaluated. This paper presents comparisons between the results obtained with the simulation model, the experimental values, and the theoretical models from the literature, highlighting the possibility of developing a mathematical model that can be applied to the calculation and design of a MHE.