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Lee, Deokjung
Computational Reactor physics & Experiment lab (CORE Lab)
Research Interests
  • Reactor Analysis computer codes development
  • Methodology development of reactor physics
  • Nuclear reactor design(SM-SFR,PWR and MSR)

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Validation of spent nuclear fuel decay heat calculation by a two-step method

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Title
Validation of spent nuclear fuel decay heat calculation by a two-step method
Author
Jang, JaerimEbiwonjumi, BamideleKim, WonkyeongPark, JinsuChoe, JiwonLee, Deokjung
Issue Date
2021-01
Publisher
한국원자력학회
Citation
NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.1, pp.44 - 60
Abstract
In this paper, we validate the decay heat calculation capability via a two-step method to analyze spent nuclear fuel (SNF) discharged from pressurized water reactors (PWRs). The calculation method is implemented with a lattice code STREAM and a nodal diffusion code RAST-K. One of the features of this method is the direct consideration of three-dimensional (3D) core simulation conditions with the advantage of a short simulation time. Other features include the prediction of the isotope inventory by Lagrange non-linear interpolation and the use of power history correction factors. The validation is performed with 58 decay heat measurements of 48 fuel assemblies (FAs) discharged from five PWRs operated in Sweden and the United States. These realistic benchmarks cover the discharge burnup range up to 51 GWd/MTU, 23.2 years of cooling time, and spanning an initial uranium enrichment range of 2.100–4.005 wt percent. The SNF analysis capability of STREAM is also employed in the code-to-code comparison. Compared to the measurements, the validation results of the FA calculation with RAST-K are within 4%, and the pin-wise results are within 4.3%. This paper successfully demonstrates that the developed decay heat calculation method can perform SNF back-end cycle analyses.
URI
https://scholarworks.unist.ac.kr/handle/201301/48693
URL
https://www.sciencedirect.com/science/article/pii/S1738573320300231
DOI
10.1016/j.net.2020.06.028
ISSN
1738-5733
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