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

Validation of nuclide depletion capabilities in Monte Carlo code MCS

DC Field Value Language
dc.contributor.author Ebiwonjumi, Bamidele ko
dc.contributor.author Lee, Hyunsuk ko
dc.contributor.author Kim, Wonkyeong ko
dc.contributor.author Lee, Deokjung ko
dc.date.available 2020-08-27T07:56:59Z -
dc.date.created 2020-08-20 ko
dc.date.issued 2020-09 ko
dc.identifier.citation NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.9, pp.1907 - 1916 ko
dc.identifier.issn 1738-5733 ko
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/47846 -
dc.description.abstract In this work, the depletion capability implemented in Monte Carlo code MCS is investigated to predict the isotopic compositions of spent nuclear fuel (SNF). By comparison of MCS calculation results to post irradiation examination (PIE) data obtained from one pressurized water reactor (PWR), the validation of this capability is conducted. The depletion analysis is performed with the ENDF/B-VII.1 library and a fuel assembly model. The transmutation equation is solved by the Chebyshev Rational Approximation Method (CRAM) with a depletion chain of 3820 isotopes. 18 actinides and 19 fission products are analyzed in 14 SNF samples. The effect of statistical uncertainties on the calculated number densities is discussed. On average, most of the actinides and fission products analyzed are predicted within +/- 6% of the experiment. MCS depletion results are also compared to other depletion codes based on publicly reported information in literature. The code-to-code analysis shows comparable accuracy. Overall, it is demonstrated that the depletion capability in MCS can be reliably applied in the prediction of SNF isotopic inventory. (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/). ko
dc.language 영어 ko
dc.publisher KOREAN NUCLEAR SOC ko
dc.title Validation of nuclide depletion capabilities in Monte Carlo code MCS ko
dc.type ARTICLE ko
dc.identifier.scopusid 2-s2.0-85081901703 ko
dc.identifier.wosid 000553761000003 ko
dc.type.rims ART ko
dc.identifier.doi 10.1016/j.net.2020.02.017 ko
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S1738573319302165?via%3Dihub ko
Appears in Collections:
MNE_Journal Papers

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

Show simple item record

qrcode

  • mendeley

    citeulike

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

MENU