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Published: 2024-04-25
Abstract Views: 26
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DOI: https://doi.org/10.53747/nst.v13i2.437
Issue
Vol. 13 No. 2 (2023)
Section
Articles
How to Cite
TAN, T. G., YAP, I., TANG, J. H., Krishna, V., XIAO, S., & CHUNG, K. Y. (2024). Preliminary MELCOR Input Deck for Steady State and Turbine Trip Analysis of the NuScale US600 SMR. Nuclear Science and Technology, 13(2), 7-17. https://doi.org/10.53747/nst.v13i2.437

Preliminary MELCOR Input Deck for Steady State and Turbine Trip Analysis of the NuScale US600 SMR

Tu Guang TAN1, Isaac YAP2, Jia Hao TANG2, Vitesh Krishna2, Sicong XIAO2, Keng Yeow CHUNG2
1 s:48:"Singapore Nuclear Research and Safety Initiative";
2 Singapore Nuclear Research and Safety Initiative

Main Article Content

Abstract

This paper models NuScale’s SMR using MELCOR by relying on specifications in the latest Final Safety Assessment Report (FSAR) submitted to the U.S. Nuclear Regulatory Commission (USNRC). The input deck was crafted from scratch using only publicly available data and reasonable assumptions. Benchmark results for steady state and a turbine trip transient are presented, with the former showing excellent agreement with the reference values, while the latter produces shows slight deviations in the mass flow rates. As a preliminary study, the results are within acceptable limits and encourage further refinement to the model for use in other accident progression cases.

Article Details

Keywords

MELCOR, small modular reactor, integral pressurized water reactor, safety analysis

References

[1]. United states nuclear regulatory commission, application documents for the nuscale us600 design — nrc.gov (2020).
[2]. URL https://www.nrc.gov/reactors/new-reactors/smr/licensing-activities/nuscale/documents.html
[3]. L. L. Humphries, B. Beeny, F. Gelbard, D. Louie, J. Phillips, Melcor: Sandia energy (2015).
[4]. URL https://energy.sandia.gov/ programs/nuclear-energy/nuclear-energy-safety-security/melcor/
[5]. C. D. Leigh, Melcor validation and verification: 1986 papers (nureg/cr-4830, revision 3) — nrc.gov (1987).
[6]. URL https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr4830/index.html
[7]. E. A. Boucheron, J. E. Kelly, Melcor analysis of the three-mile island unit 2 accident, https://doi.org/10.13182/NT89-A27696 87 (2017) 1050–1057. doi:10.13182/NT89-
[8]. A27696.
[9]. URL https://www.tandfonline.com/doi/abs/10.13182/NT89-A27696
[10]. T. Sev´on, A melcor model of fukushima daiichi unit 1 accident, Annals of Nuclear Energy 85 (2015) 1–11. doi:10.1016/J.ANUCENE.2015.04.031.
[11]. T. Sev´on, A melcor model of fukushima daiichi unit 3 accident, Nuclear Engineering and Design 284 (2015) 80–90.
[12]. doi:10.1016/J.NUCENGDES.2014.11.038.
[13]. J. J. Colbert, K. Vierow, Verification of the melcor code against scdap/relap5 for severe accident analysis (2003).
[14]. URL https://www.ipen.br/biblioteca/cd/genes4/2003/papers/1139-final.pdf
[15]. S. B. Rodriguez, Using the coupled melcorrelap5 codes for simulation of the edward’s pipe (2002).
[16]. URL https://relap53d.inl.gov/seminars/parkcity2002/Shared%20Documents/rodrig.pdf
[17]. N. P. LLC, Nuscale standard plant design certification application. chapter fifteen: Transient and accident analyses (7 2020).
[18]. URL https://www.nrc.gov/docs/
[19]. ML2022/ML20224A504.pdf