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Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask

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Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask. / Alrawash, Saed; Boravy, Muth; Yoo, Seung Uk et al.
In: annals of nuclear energy, Vol. 144, 107516, 01.09.2020.

Research output: Contribution to Journal/MagazineJournal articlepeer-review

Harvard

Alrawash, S, Boravy, M, Yoo, SU, Han, H, Kim, SY, Park, M & Park, CJ 2020, 'Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask', annals of nuclear energy, vol. 144, 107516. https://doi.org/10.1016/j.anucene.2020.107516

APA

Alrawash, S., Boravy, M., Yoo, S. U., Han, H., Kim, S. Y., Park, M., & Park, C. J. (2020). Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask. annals of nuclear energy, 144, Article 107516. https://doi.org/10.1016/j.anucene.2020.107516

Vancouver

Alrawash S, Boravy M, Yoo SU, Han H, Kim SY, Park M et al. Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask. annals of nuclear energy. 2020 Sept 1;144:107516. Epub 2020 Apr 13. doi: 10.1016/j.anucene.2020.107516

Author

Alrawash, Saed ; Boravy, Muth ; Yoo, Seung Uk et al. / Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask. In: annals of nuclear energy. 2020 ; Vol. 144.

Bibtex

@article{edf78e3c27274658935c0f3c6dbe305b,
title = "Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask",
abstract = "The objective of this study is to conduct a sensitivity analysis on multiple fuel assembly misloading within the spent nuclear fuel (SNF) cask to evaluate the reactivity change when underburned fuel assemblies are loaded. As the fuel composition changes during burnup, burnup credit has been considered involving several underburned values. The calculations have been performed on the GBC-32 Westinghouse 17 × 17 fuel design involving 1–16 misloaded assemblies with various values of discharge burnups and several different loading patterns. The isotopic depletion and decay analysis have been evaluated using ORIGEN-ARP, while the criticality calculations have been performed using KENO VI Monte Carlo criticality code. The results show that different loading patterns have significant effects on k eff for each misloaded assembly. The maximum variation of k eff is 0.12040 for six misloaded assemblies, which have 40 different loading configurations. It was also found that one misloaded assembly is acceptable for all values of underburned fuel from 0% to 70% of the minimum value required for loading, while 0% underburned cases are acceptable to be loaded for 1–16 misloaded assemblies. ",
author = "Saed Alrawash and Muth Boravy and Yoo, {Seung Uk} and Hyuk Han and Kim, {Soon Young} and Moon-ghu Park and Park, {Chang Je}",
year = "2020",
month = sep,
day = "1",
doi = "10.1016/j.anucene.2020.107516",
language = "English",
volume = "144",
journal = "annals of nuclear energy",

}

RIS

TY - JOUR

T1 - Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask

AU - Alrawash, Saed

AU - Boravy, Muth

AU - Yoo, Seung Uk

AU - Han, Hyuk

AU - Kim, Soon Young

AU - Park, Moon-ghu

AU - Park, Chang Je

PY - 2020/9/1

Y1 - 2020/9/1

N2 - The objective of this study is to conduct a sensitivity analysis on multiple fuel assembly misloading within the spent nuclear fuel (SNF) cask to evaluate the reactivity change when underburned fuel assemblies are loaded. As the fuel composition changes during burnup, burnup credit has been considered involving several underburned values. The calculations have been performed on the GBC-32 Westinghouse 17 × 17 fuel design involving 1–16 misloaded assemblies with various values of discharge burnups and several different loading patterns. The isotopic depletion and decay analysis have been evaluated using ORIGEN-ARP, while the criticality calculations have been performed using KENO VI Monte Carlo criticality code. The results show that different loading patterns have significant effects on k eff for each misloaded assembly. The maximum variation of k eff is 0.12040 for six misloaded assemblies, which have 40 different loading configurations. It was also found that one misloaded assembly is acceptable for all values of underburned fuel from 0% to 70% of the minimum value required for loading, while 0% underburned cases are acceptable to be loaded for 1–16 misloaded assemblies.

AB - The objective of this study is to conduct a sensitivity analysis on multiple fuel assembly misloading within the spent nuclear fuel (SNF) cask to evaluate the reactivity change when underburned fuel assemblies are loaded. As the fuel composition changes during burnup, burnup credit has been considered involving several underburned values. The calculations have been performed on the GBC-32 Westinghouse 17 × 17 fuel design involving 1–16 misloaded assemblies with various values of discharge burnups and several different loading patterns. The isotopic depletion and decay analysis have been evaluated using ORIGEN-ARP, while the criticality calculations have been performed using KENO VI Monte Carlo criticality code. The results show that different loading patterns have significant effects on k eff for each misloaded assembly. The maximum variation of k eff is 0.12040 for six misloaded assemblies, which have 40 different loading configurations. It was also found that one misloaded assembly is acceptable for all values of underburned fuel from 0% to 70% of the minimum value required for loading, while 0% underburned cases are acceptable to be loaded for 1–16 misloaded assemblies.

U2 - 10.1016/j.anucene.2020.107516

DO - 10.1016/j.anucene.2020.107516

M3 - Journal article

VL - 144

JO - annals of nuclear energy

JF - annals of nuclear energy

M1 - 107516

ER -