Improvement of CINDER library for PWR burnup calculations

Tavakkoli, Ehsan; Zangian, Mahdi; Minuchehr, A.; Zolfaghari, A.

doi:10.1016/j.anucene.2020.107547

Cited by 1 publication

(1 citation statement)

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“…There is always a constant fear of the proliferation of these nuclear materials and there is a focus on fuel that can be proliferation resistant. Thorium is thus another nuclear energy fuel resource that is nearly three to four times as abundant as uranium, 8,9,10 and that it can be harnessed to augment, extend, or eventually replace uranium resources, where new reactor concepts are based on thorium are being studied/constructed. The PWR pin cell was therefore selected for analysis, to study the effect of detailed burn‐up data and reaction‐wise energy release incorporated in MCNP6.2 and DRAGON5 for fuels based on thorium.…”

Section: Introductionmentioning

confidence: 99%

Neutronic and burn‐up calculations of the ( ThO2‐UO2 ) pin cell benchmark using DRAGON5 and MCNP6 .2 codes with ENDF / B‐VIII .0 nuclear data library

et al. 2021

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Summary A (ThO2‐UO2) fuel pin benchmark, consisting of 75 w/o Th and 25 w/o U, was utilized for analysis of depletion and inventory of the fuel for the pressurized water reactor (PWR) pin‐cell model. To perform this study and evaluate cross‐section data, the new version VIII.0 of the ENDF/B nuclear data library was utilized to generate a data set in ACE (A Compact ENDF) format at different temperatures (583.1, 600, 621.1, and 900 K), utilizing NJOY2016 and MAKXSF6.2 codes to process the data at the specific temperatures. In this paper, the infinite multiplication factor (kinf), neutron energy flux spectrum (utilizing 172 energy groups), the concentrations and activities of the most important products of fission, the actinide radionuclides accumulated in the pin‐cell, and the total radioactivity were calculated and compared, utilizing the MCNP6.2 and DRAGON5 codes. Furthermore, the burn‐up (BU) dependent behavior of the PWR thorium pin‐cell was validated and compared with the reference results obtained utilizing the CASMO‐4, MIT‐MOCUP, and INEEL‐MOCUP codes. The results of this study show good agreements between all codes analysed.

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Section: Introductionmentioning

confidence: 99%