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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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Latest News
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
H. J. Uitslag-Doolaard, K. Zwijsen, F. Roelofs, M. M. Stempniewicz
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2543-2560
Research Article | doi.org/10.1080/00295639.2022.2148809
Articles are hosted by Taylor and Francis Online.
Increasing the computational power enables the nuclear community to combine existing knowledge on the variety of different physical phenomena that take place in reactors and to develop tools that can simulate these combined, interacting phenomena simultaneously. This includes phenomena related to structural mechanics, fluid dynamics, and reactor physics among others. Coupling different codes developed specifically for the analysis of separate phenomenon is currently a topic high on the research and development agenda of the international community.
Based on the experience of successfully computing the dissymmetric benchmark in the Phénix reactor by coupling the system thermal-hydraulic (STH) code SPECTRA to the computational fluid dynamics (CFD) code CFX in the H2020 SESAME project, the Nuclear Research and Consultancy Group (NRG) is currently developing the code-coupling tool myMUSCLE: MultiphYsics MUltiscale Simulation CoupLing Environment. MyMUSCLE is an independent, external, Fortran-based code that arranges the efficient and robust coupling of different codes. It aims at being flexible with respect to the codes being coupled, i.e., commercial and open-source codes, while having a single coupling tool that enhances quality assurance. It is currently set up to couple SPECTRA as a STH code to CFX, Fluent, STAR-CCM+, or OpenFOAM as a CFD code. This paper presents the proof of principle and first verification of the myMUSCLE tool under development by applying it to multiscale thermal-hydraulic applications.
First, a flow through a pipe is modeled as proof of principle for explicit coupling at a single coupling interface. Second, in preparation for modeling liquid-metal-cooled fast reactors, a piping system with a pool with natural convection is modeled. The results of the multiscale calculations show good agreement among the different coupled CFD codes. Finally, the preparations for simulating the TALL-3D experiment, used for generating data for validation of simulation tools for liquid-metal pools, are presented.