Newly Evaluated Neutron Reaction Data on Chromium Isotopes

Nobre, G. P. A.; Pigni, Marco T.; Brown, David; Capote, R.; Trkov, A.; Guber, K. H.; Arcilla, R.; J., Gutierrez,; Cuadra, A.; Arbanas, Goran; Kos, Bor; Bernard, D.; Leconte, Pierre

doi:10.1016/j.nds.2021.04.002

Cited by 8 publications

(3 citation statements)

References 107 publications

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“…Reactivity predicted for some of the benchmarks is closer to the benchmark reference, but there are outliers, which were not affected significantly by the changes. A biggest improvement is observed for the ZPR-6/10 benchmark (pmi002 -Case 24 in Table 1), but this improvement is mainly due to the improvements of Cr cross sections [14]. This benchmark is also sensitive to the nickel cross sections, further investigations are warranted.…”

Section: Performance In Criticality Benchmarksmentioning

confidence: 94%

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Progress in the Evaluation and Validation of n+^56,57Fe Cross Sections

et al. 2023

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There has been a continued effort since 2019 within the IAEA INDEN collaboration to improve the evaluation of neutron induced reactions on iron isotopes. The reason for the 30% underestimation of the neutron leakage spectrum from a thick iron sphere was found primarily to be due to the overestimation of the inelastic cross sections in the 56Fe evaluated data file produced within the CIELO project of the OECD/NEA Data Bank. The over-estimation of the neutron flux between the resonances near 300 keV was traced to neglecting the fluctuating nature of the total cross section of 57Fe in the fast neutron energy range, since the evaluated resolved resonance range of 57Fe extended only up to 190 keV. The added 1/v background in the "iron window" below 28 keV is in excellent agreement with the independently evaluated one in the JENDL-5.0 library that included the direct capture component in the evaluation. Performance of the updated 56,57Fe evaluations was tested on a set of criticality benchmarks from the ICSBEP Handbook, including the dependence on reflector thickness and on new deep penetration shielding benchmark using a 252Cf(sf) neutron source undertaken at Rez, Czech Republic. Neutron leakage for 43 MeV incident neutrons was also validated.

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Section: Performance In Criticality Benchmarksmentioning

confidence: 94%

“…Validation measurements at CEA within the MAESTRO project [13] at the MINERVE reactor did not support such a decrease (see discussion at p.31 of Ref. [14]). The same validation showed that JEFF-3.1.1 evaluation was essentially correct, so the recommended value of the thermal capture cross section for 56 Fe of 2.577 barns was adopted.…”

Section: Introductionmentioning

confidence: 95%

Progress in the Evaluation and Validation of n+^56,57Fe Cross Sections

et al. 2023

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“…There were also results from leakage benchmarks sensitive to stainless steel and its components. The overall results showed that the new library performs much better than ENDF/B-VIII.0, even leading to users from industry to endorse the performance of the new iron and chromium [10] files, as shown in Ref. [11].…”

Section: Endf/b-viii1-β11mentioning

confidence: 99%

Progress towards the ENDF/B-VIII.1 release

Nobre,

Brown,

Arcilla

et al. 2024

EPJ Web of Conf.

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The efficient, safe, and high-performance design and operation of nuclear reactors, and other nuclear systems, rely on complete and accurate nuclear data files. The ENDF/B library is the main nuclear reaction data library in the United States and one of the main ones in the world. It encompasses sub-libraries for neutron, proton, alpha, deuteron, 3He, and gamma projectiles, in addition to thermal neutron scattering law, fission product yields and three atomic sub-libraries. The last release of ENDF/B was ENDF/B-VIII.0 in 2018. Since then, many important and impactful developments have been made for actinides, structural materials and light elements. Some of these contributions are part of the IAEA-coordinated International Nuclear Data Evaluation Network (INDEN). The scale and impact of these changes warrant a new library release, namely ENDF/B-VIII.1, which is scheduled for early 2024. This release is planned to happen in both ENDF-6 and GNDS-2.0 formats. The present work describes the updates expected to be present in ENDF/B-VIII.1, as well as the review process and quality control procedures developed and implemented at the National Nuclear Data Center (NNDC). Preliminary results from the Beta versions already released are also shown.

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