Development and validation of depletion code system IMPC-Burnup for ADS

Liu, Zhao‐Qing; Zhao, Zelong; Yang, Yinping; Gao, Yucui; Meng, Hao; Gao, Qingyu

doi:10.1007/s41365-019-0560-z

Cited by 12 publications

(2 citation statements)

References 18 publications

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“…Nuclear energy is being seriously considered as one of the safest options for future large scale energy production, owing to its minimal contribution to greenhouse emissions 1,2 . Current nuclear reactors are fueled primarily by uranium and its different compounds, including uranium oxide in the case of pressurized water reactors (PWRs) 3,4 .…”

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%

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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“…This article concerns the sensitivity of the experimental determination of reactivity to its changes in a subcritical reactor. Such reactors have been proposed for the transmutation of higher actinides, removed from spent nuclear fuel [1][2][3][4][5], with the help of fast neutrons. Subcriticality provides a higher level of criticality safety than the critical fast reactors used for this purpose.…”

Section: Introductionmentioning

confidence: 99%

Sensitivity of the area method with mono isotopic fission chambers to reactivity changes in subcritical nuclear reactors

2021

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High-level waste is an important safety issue in the development of nuclear power. A proposed solution is the transmutation of waste in fast reactors. The exclusion of the risk of supercriticality by using subcritical reactors is currently under development. Controlling the subcriticality level in such reactors presents difficulties. A problem is posed by the so-called space effect observed when using in reactors many neutron detectors in different locations of the core and reflector. Reactivity obtained from measurements, for example, by the Sjöstrand method, differs by nonnegligible values. Numerical corrections can partially improve this situation. The use of a monoisotopic fission chamber set, designed for a given reactor, when each chamber is intended for a specific position in the system, can improve the situation. A question arises about the sensitivity of the results to reactivity changes. This issue is analyzed by computer simulation for possible fissionable and fissile nuclides for the total range of control rod insertion, changes in reactor fuel enrichment, and fuel temperature. The tested sensitivity was satisfactory at most levels from several dozen to several hundred pcm. A case study was conducted using the VENUS-F core model.

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Neutronic analysis of deuteron-driven spallation target

Qiu

Sun

2021

NUCL SCI TECH

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Development and validation of depletion code system IMPC-Burnup for ADS

Cited by 12 publications

References 18 publications

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

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

Sensitivity of the area method with mono isotopic fission chambers to reactivity changes in subcritical nuclear reactors

Neutronic analysis of deuteron-driven spallation target

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