BROWSE

Related Researcher

Author's Photo

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)

ITEM VIEW & DOWNLOAD

Uncertainty quanti fi cation of PWR spent fuel due to nuclear data and modeling parameters

Cited 0 times inthomson ciCited 0 times inthomson ci
Title
Uncertainty quanti fi cation of PWR spent fuel due to nuclear data and modeling parameters
Author
Ebiwonjumi, BamideleKong, ChidongZhang, PengCherezov, AlexeyLee, Deokjung
Issue Date
2021-03
Publisher
KOREAN NUCLEAR SOC
Citation
NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.3, pp.715 - 731
Abstract
Uncertainties are calculated for pressurized water reactor (PWR) spent nuclear fuel (SNF) characteristics. The deterministic code STREAM is currently being used as an SNF analysis tool to obtain isotopic in-ventory, radioactivity, decay heat, neutron and gamma source strengths. The SNF analysis capability of STREAM was recently validated. However, the uncertainty analysis is yet to be conducted. To estimate the uncertainty due to nuclear data, STREAM is used to perturb nuclear cross section (XS) and resonance integral (RI) libraries produced by NJOY99. The perturbation of XS and RI involves the stochastic sam-pling of ENDF/B-VII.1 covariance data. To estimate the uncertainty due to modeling parameters (fuel design and irradiation history), surrogate models are built based on polynomial chaos expansion (PCE) and variance-based sensitivity indices (i.e., Sobol & rsquo; indices) are employed to perform global sensitivity analysis (GSA). The calculation results indicate that uncertainty of SNF due to modeling parameters are also very important and as a result can contribute significantly to the difference of uncertainties due to nuclear data and modeling parameters. In addition, the surrogate model offers a computationally effi-cient approach with significantly reduced computation time, to accurately evaluate uncertainties of SNF integral characteristics. (c) 2020 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
URI
https://scholarworks.unist.ac.kr/handle/201301/52816
URL
https://www.sciencedirect.com/science/article/pii/S1738573320303521?via%3Dihub
DOI
10.1016/j.net.2020.07.012
ISSN
1738-5733
Appears in Collections:
NUE_Journal Papers
Files in This Item:
000631704600002.pdf Download

find_unist can give you direct access to the published full text of this article. (UNISTARs only)

Show full item record

qrcode

  • mendeley

    citeulike

Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.

MENU