Application of CENDL-3.2 and ENDF/B-VIII.0 on the reactor physics simulation of PWR

Zu, Tiejun; Huang, Yihan; Teng, Qichen; Han, Fenglin; Huang, Xing; Wan, Chenghui; Cao, Liangzhi; Wu, Hongchun

doi:10.1016/j.anucene.2021.108238

Cited by 4 publications

(2 citation statements)

References 17 publications

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“…Based on GNDS-Toolkit, some common application libraries in specific formats could be generated based on GNDS libraries. To verify the GNDS-Toolkit, the ACE format libraries for Monte Carlo codes, NECL format libraries [11] for deterministic lattice physics simulation For comparison, these application libraries are also generated based on the ENDF-6 format libraries of ENDF/B-VIII.0. Fig.…”

Section: Verificationmentioning

confidence: 99%

Development and Verification of Capability for Processing the Generalised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas

Huang

Cao

et al. 2023

EPJ Web of Conf.

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The latest evaluated nuclear data libraries, including ENDF/B-VIII.0, TENDL2019, all have two formats, the Evaluated Nuclear Data File (ENDF-6) nuclear data format, and the Generalised Nuclear Database Structure (GNDS) format. The first official public documentation of all of the options for storing data in GNDS was released by the Working Party on International Nuclear Data Evaluation Cooperation (WPEC) of the Nuclear Energy Agency. The generalized derived class is designed to be compatible with ENDF-6 and GNDS in nuclear data processing code NECP-Atlas, and the GNDS-Toolkit is developed in NECP-Atlas to parse and convert GNDS. ACE format library and multi-group library are generated based on GNDS, and they are used in the Monte-Carlo code and deterministic based code to compare with ENDF-6. The numerical results show that GNDS libraries can be processed by NECP-Atlas competently to generate specific format library and the difference in ENDF-6 and GNDS is very small.

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Section: Verificationmentioning

confidence: 99%

Development and Verification of Capability for Processing the Generalised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas

Huang

Cao

et al. 2023

EPJ Web of Conf.

Self Cite

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“…The verification of nuclear libraries by using developed benchmarks is important to their applications and improvement. The performances of CENDL-3.2 were reported to be acceptable by verifications on reactor designs and shielding benchmarks (Shu et al, 2021;Hu et al, 2021;(Zu et al, 2021). More verifications on ENDF/B-VIII.0 were performed, which consisted of critical and shielding benchmark tests (Park et al, 2019;Zhang et al, 2021), as well as sensitivity and uncertainty (S/U) analyses (Hartanto and Liem, 2021).…”

Section: Introductionmentioning

confidence: 99%

Verification of CENDL-3.2 and ENDF/B-VIII.0 Evaluated Nuclear Data Library on HTR-10 Benchmark

Tian-yi

Shi-hang

et al. 2022

Front. Energy Res.

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CENDL-3.2 and ENDF/B-VIII.0 referring to the latest version of CENDL and ENDF/B, respectively, evaluated nuclear data library. To examine the applicability the libraries to high-temperature reactors (HTRs), the HTR-10 benchmark calculations are conducted by adopting CENDL-3.2, ENDF/B-VIII.0, and ENDF/B-VII.1 library. The calculated results are compared with the experimental results. As indicated from the comparison, the results of ENDF/B-VIII.0 show the optimal consistency with the experimental results, and CENDL-3.2 outperforms ENDF/B-VII.1. A semi-quantitative analysis method, on the basis of the sensitivity result, is employed to assess the effect of the cross-section change to keff. As revealed from the further calculations and analyses, the difference between cross-sections of C-12 (n, γ) channel primarily causes the inconsistent performance of CENDL-3.2 and ENDF/B-VIII.0 on the benchmark.

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Uncertainty analysis of infinite multiplication factor and nuclide number density based on the UAM-PWR benchmark with respect to cross sections, fission yields and decay half-life

Han

et al. 2022

Annals of Nuclear Energy

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Application of CENDL-3.2 and ENDF/B-VIII.0 on the reactor physics simulation of PWR

Cited by 4 publications

References 17 publications

Development and Verification of Capability for Processing the Generalised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas

Development and Verification of Capability for Processing the Generalised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas

Verification of CENDL-3.2 and ENDF/B-VIII.0 Evaluated Nuclear Data Library on HTR-10 Benchmark

Uncertainty analysis of infinite multiplication factor and nuclide number density based on the UAM-PWR benchmark with respect to cross sections, fission yields and decay half-life

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