Engineering Science

Submit a Manuscript

Publishing with us to make your research visible to the widest possible audience.

Propose a Special Issue

Building a community of authors and readers to discuss the latest research and develop new ideas.

Review of Inaccuracies in the Analysis of the Flow Stability Specific of the LW-SMR Modular Design

The presented analysis has been issued to express doubts about the correctness of the engineering and operational safety assessment, which arises from the modeling of transient modes and methodologically should help light water small modular nuclear reactor designers/developers to correct the model they are usually creating for studying the stability of the thermal-hydraulic circuit of the light water small modular nuclear reactor with the natural circulation of primary coolant. After the NuScale report publication and the following presentation review, additional questions arise regarding the analysis methodology, which was carried out and presented as part of the licensing package presented to NRC. After having carefully and critically read the available part of the presented report on the study of instabilities and the presentation issued by NuScale, the answer to the NRC safety committee request could be concluded that the instability analysis has not been performed correctly not only technically, but theoretically. Some clarification of the problem of analysis of instabilities is required additional explanations for further integral light water small modular nuclear reactor design developments and correct analysis implementations.

SMR, Natural Circulation, Primary Circuit Instabilities, Two-Phase Flow, Once-Through Steam Generator

APA Style

Aleksey Rezvoi. (2023). Review of Inaccuracies in the Analysis of the Flow Stability Specific of the LW-SMR Modular Design. Engineering Science, 8(1), 1-5. https://doi.org/10.11648/j.es.20230801.11

ACS Style

Aleksey Rezvoi. Review of Inaccuracies in the Analysis of the Flow Stability Specific of the LW-SMR Modular Design. Eng. Sci. 2023, 8(1), 1-5. doi: 10.11648/j.es.20230801.11

AMA Style

Aleksey Rezvoi. Review of Inaccuracies in the Analysis of the Flow Stability Specific of the LW-SMR Modular Design. Eng Sci. 2023;8(1):1-5. doi: 10.11648/j.es.20230801.11

Copyright © 2023 Authors retain the copyright of this article.
This article is an open access article distributed under the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0/) which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

1. US NRC Audit Summary Report for the Regulatory Audit of NuScale Power LLC. Topical Report tr-0516-49417-p, “Evaluation Methodology for Stability Analysis of the NuScale Power Module”
2. NuScale Power LLC. Submittal of Presentation Materials Titled "ACRS Subcommittee Presentation: NuScale FSAR - Steam Generator Design," PM-0220-68568, Rev. 0.
3. NRC ACRS Letter. “NuScale Area of Focus – Helical Tube Steam Generator Design”. 03.24.2020.
4. Instability of the Coolant Flow in the Elements of Power Equipment. Khabensky V. B., Gerliga V. A. "Nauka". Saint-Petersburg, Russia. 1994.
5. Pulsating Characteristics of the NC Circuit of a Large-Scale Model of a Low-Boiling Nuclear Reactor. R. Babykin A. S., Balunov B. F. and others. "Atomic Energy", Volume 58, Issue 4. Russia. April 1985.
6. Naval Nuclear Power. N. S. Khlopkin. Tutorial. MEPhI State University, Department of Thermal Physics. Published "Trovant". Moscow, Russia. 2007.
7. Thermodynamic Tables of Water and Steam. Vukalovich M. P. "Energy". Moscow - Leningrad, USSR. 1965.
8. Naval Nuclear Steam-Generating Unit. Shamanov N. P., Peich N. N., Dyadik A. N. "Sudostroenie". Leningrad, USSR. 1990.
9. Nuclear systems. Books I & II. Neil E. Todreas, Mujid S. Kazimi. “Taylor & Francis”. USA. 1989.
10. Flow Instabilities in the Core and the Coolant Circuit of Advanced Low-Boiling LWR. A. Rezvyi. MS Thesis. Nuclear Engineering Department. Texas A&M University. USA. November 2002.