CENDL-3.2: The new version of Chinese general purpose evaluated nuclear data library

Zhang, Ge; Xu, Ruirui; Wu, Haicheng; Yue, Zhang; Chen, Guochang; Jin, Yan; Shu, Nengchuan; Chen, Yongjing; Tao, Xi; Tian, Yuan; Liu, Ping; Qian, Jing; Wang, Jimin; Zhang, Huanyu; Liu, Lile; Huang, Xiaolong

doi:10.1051/epjconf/202023909001

Cited by 86 publications

(24 citation statements)

References 16 publications

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“…Fig.7Cross-section results from this work (black points) along with the experimental data available in EXFOR[5] and the latest evaluated libraries ENDF/B-VIII.0[32] (which agrees with JEFF-3.3[40]) (black line), JENDL-4.0[41] (green line) and CENDL-3.2[42] (blue line) at a the energy region from 2.0 to 5.3 MeV, b 9.9 MeV and c at the energy region from 14.8 to 17.8 MeV…”

supporting

confidence: 65%

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Measurement of the $$^{232}$$Th(n,f) cross section with quasi-monoenergetic neutron beams in the energy range 2–18 MeV

et al. 2021

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The fission cross section of $$^{232}$$ 232 Th has been measured at fast neutron energies, using a setup based on Micromegas detectors. The experiment was performed at the 5.5 MV Van de Graaff Tandem accelerator in the neutron beam facility of the National Centre for Scientific Research “Demokritos”. The quasi-monoenergetic neutron beams were produced via the $$^{3}$$ 3 H(p,n), $$^{2}$$ 2 H(d,n) and $$^{3}$$ 3 H(d,n) reactions, while the $$^{238}$$ 238 U(n,f) and $$^{235}$$ 235 U(n,f) reactions were used as references, in order to acquire cross-section data points in the energy range 2–18 MeV. The characterization of the actinide samples was performed via $$\alpha $$ α -spectroscopy with a Silicon Surface Barrier (SSB) detector, while Monte Carlo simulations with the FLUKA code were used to achieve the deconvolution of the $$^{232}$$ 232 Th $$\alpha $$ α peak from the $$\alpha $$ α background of its daughter nuclei present in the spectrum. Special attention was given to the study of the parasitic neutrons present in the experimental area, produced via charged particle reactions induced by the particle beam and from neutron scattering. Details on the data analysis and results are presented.

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supporting

confidence: 65%

“…The systematic uncertainties are presented in Table 3. The comparison between the data of this work and the experimental data found in EXFOR [5], along with the latest evaluated libraries ENDF/B-VIII.0 [32], JEFF-3.3 [40], JENDL-4.0 [41] and CENDL-3.2 [42] is presented in Fig. 7.…”

Section: Resultsmentioning

confidence: 95%

Measurement of the $$^{232}$$Th(n,f) cross section with quasi-monoenergetic neutron beams in the energy range 2–18 MeV

et al. 2021

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“…Except the TSL data, all the other nuclear data were extracted from the newly released CENDL-3.2. Ge et al (2020) evaluated the nuclear data library.…”

Section: Results Of Critical Benchmarksmentioning

confidence: 99%

Treatments of Thermal Neutron Scattering Data and Their Effect on Neutronics Calculations

Tang

Huang

et al. 2021

Front. Energy Res.

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In the conventional method to generate thermal scattering cross section of moderator materials, only one of the coherent elastic scattering and incoherent elastic scattering is considered in neutronics calculations. For the inelastic scattering, fixed incident energy grid is used in the nuclear data processing codes. The multipoint linearization method is used to refine the incident energy grid for inelastic scattering. We select ZrHx (zirconium hydride) as an example to analyze the effects of the above described treatments on the reactivity of several critical benchmarks. The numerical results show that the incident energy grid has an obvious effect on the effective multiplication factor (keff) of the analyzed reactors; simultaneously considering the coherent and incoherent elastic scattering also affects keff by tens of pcm.

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“…On the basis of the existing experiments and evaluations, the evaluated nuclear data libraries provide necessary data for nuclear science research and engineering design. Several libraries-CENDL (Ge et al, 2020), ENDF/B (Brown et al, 2018), JEFF (Plompen et al, 2020), JENDL (SHIBATA et al, 2011), and TENDL (Koning et al, 2019)-have been developed. After being processed by nuclear data processing codes, e.g., NJOY (MacFarlane and Kahler, 2010) and RXSP (Li et al, 2012), data of the mentioned libraries can be employed for simulations.…”

Section: Introductionmentioning

confidence: 99%

“…The number of nuclides in CENDL has increased to 272, in which 137 nuclides are inherited from CENDL-3.1, 77 nuclides are partially updated, and 58 nuclides are newly evaluated. The performance of CENDL-3.2 on benchmarks has been evaluated in the report, which is significantly improved, compared with CENDL-3.1 (Ge et al, 2020). As the latest version of ENDF/B, ENDF/B-VIII.0 library was released in 2018.…”

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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CENDL-3.2: The new version of Chinese general purpose evaluated nuclear data library

Cited by 86 publications

References 16 publications

Measurement of the $$^{232}$$Th(n,f) cross section with quasi-monoenergetic neutron beams in the energy range 2–18 MeV

Measurement of the $$^{232}$$Th(n,f) cross section with quasi-monoenergetic neutron beams in the energy range 2–18 MeV

Treatments of Thermal Neutron Scattering Data and Their Effect on Neutronics Calculations

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

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