Absolute and relative cross section measurements of<sup>237</sup>Np(n,f) and<sup>238</sup>U(n,f) at the National Physical Laboratory

Salvador-Castiñeira, P.; Hambsch, F.‐J.; Göök, Alf; Vidali, M.; Hawkes, N. P.; Roberts, Neil; Taylor, G C; Thomas, David J.

doi:10.1051/epjconf/201714604050

Cited by 6 publications

(4 citation statements)

References 5 publications

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“…This figure shows the ENDF/B-VIII.0 gives much higher cross section than the ENDF/B-VII.1 and present evaluation between 1.7 and 2.0 MeV. In this energy region, the ENDF/B-VIII.0 cross section is higher than the majority of the experimental cross sections, but more consistent with the recently published cross sections from an absolute measurement at National Physical Laboratory (NPL) with neutron flux determined by a long counter [87]. The ENDF/B-VIII.0 cross section is based on IAEA-2017 which difference from the present evaluation in this energy region is visible in Fig.…”

Section: B Validation By Californium-252 Spontaneous Fission Neutron ...supporting

confidence: 89%

“…7. 238 U fission prior and posterior cross sections with the experimental cross sections used for evaluation [52,71,74,[87][88][89][90][91][92][93][94][95][96]. The prior cross section is taken from JENDL-4.0 (below 20 MeV) and JENDL-4.0/HE (above 20 MeV).…”

Section: Resultsmentioning

confidence: 99%

“…18 U(n,f) cross sections from the present evaluation with the evaluated cross sections in ENDF/B-VIII.0 and ENDF/B-VII.1 as well as absolute cross sections in the EXFOR library compiled from the articles published no earlier than 1970. The solid circles show the data points from a recent (2017) absolute measurement at NPL [87]. The neutron field of a coupled thermal/fast uranium and boron carbide spherical assembly ΣΣ-ITN (Bucharest) was developed for benchmark of the fast neutron dosimetry [182].…”

Section: B Validation By Californium-252 Spontaneous Fission Neutron ...mentioning

confidence: 99%

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EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

Otuka,

Iwamoto

2022

Preprint

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The neutron-induced fission cross sections were simultaneously evaluated for the JENDL-5 library for 233,235 U and 239,241 Pu from 10 keV to 200 MeV and for 238 U and 240 Pu from 100 keV to 200 MeV. Evaluation was performed by least-squares fitting of Schmittroth's roof function to the logarithms of the experimental cross sections and cross section ratios in the EXFOR library. A simultaneous evaluation code SOK was used with its extension to data in arbitrary unit. The outputs of the code were adopted as the evaluated cross sections without any further corrections. The newly obtained evaluated cross sections were compared with the evaluated cross sections in the JENDL-4.0 library and the IAEA Neutron Data Standards 2017. The evaluated cross sections were also validated against the californium-252 spontaneous fission neutron spectrum averaged cross sections, ΣΣ (coupled thermal/fast uranium and boron carbide spherical assembly) neutron spectrum averaged cross sections, and small-sized LANL fast system criticalities. The changes in the obtained evaluated cross sections from those in the JENDL-4.0 library are within 4% ( 241 Pu), 3% ( 233 U, 240 Pu), or 2% ( 235 U, 239 Pu). The newly evaluated 235 U, 238 U and 239 Pu cross sections agree with the IAEA Neutron Data Standards 2017 within 2% with some exceptions.(This is a preprint of N. Otuka and O. Iwamoto, J. Nucl. Sci. Technol., to be published online as an open access article.)

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Section: B Validation By Californium-252 Spontaneous Fission Neutron ...supporting

confidence: 89%

Section: Resultsmentioning

confidence: 99%

Section: B Validation By Californium-252 Spontaneous Fission Neutron ...mentioning

confidence: 99%

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EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

Otuka,

Iwamoto

2022

Preprint

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“…Analysis of both experiments is in progress. Some preliminary results were reported at the ND2016 Conference on Nuclear Data for Science and Technology [15].…”

Section: Neutron-induced Fission Cross Section Of 237 Npmentioning

confidence: 99%

Neutron induced fission of ²³⁷Np – status, challenges and opportunities

et al. 2018

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Abstract. Nowadays, there is an increased interest in a complete study of the neutroninduced fission of 237 Np. This is due to the need of accurate and reliable nuclear data for nuclear science and technology. 237 Np is generated (and accumulated) in the nuclear reactor core during reactor operation. As one of the most abundant long-lived isotopes in spent fuel ("waste"), the incineration of 237 Np becomes an important issue. One scenario for burning of 237 Np and other radio-toxic minor actinides suggests they are to be mixed into the fuel of future fast-neutron reactors, employing the so-called transmutation and partitioning technology. For testing present fission models, which are at the basis of new generation nuclear reactor developments, highly accurate and detailed neutron-induced nuclear reaction data is needed. However, the EXFOR nuclear database for 237 Np on neutron-induced capture cross-section, σ γ , and fission cross-section, σ f , as well as on the characteristics of capture and fission resonance parameters (Γ γ , Γ f , σ o Γ f , fragments mass-energy yield distributions, multiplicities of neutrons ν n and γ-rays ν γ ), has not been updated for decades.

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Absolute cross section measurements of ²³⁸U(n,f) and ²³⁷Np(n,f) in the neutron energy range 1-2.4 MeV

Salvador-Castiñeira

Hambsch²,

Göök³

et al. 2019

EPJ Web Conf.

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New standard (n,f) cross sections other than 235 U are important to study the relevant cross sections for Generation-IV power plants. A specific need for such standards is for performing new experiments with quasimonoenergetic neutron beams, such as those produced by Van de Graaf accelerators. Neutrons down-scattered to low energies in the experimental environment, so called room-return, become relevant for this type of measurements. Hence, a standard (n,f) cross section with a fission threshold is of great interest, in order to suppress the contribution from room-return background. For this reason we have performed two experiments at the VDG of the National Physical Laboratory to measure absolutely the (n,f) cross sections of 235 U, 238 U and 237 Np in the fast neutron energy region. Our preliminary results are in agreement with the most up-to-date evaluations.

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Absolute and relative cross section measurements of²³⁷Np(n,f) and²³⁸U(n,f) at the National Physical Laboratory

Cited by 6 publications

References 5 publications

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

Neutron induced fission of ²³⁷Np – status, challenges and opportunities

Absolute cross section measurements of ²³⁸U(n,f) and ²³⁷Np(n,f) in the neutron energy range 1-2.4 MeV

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Absolute and relative cross section measurements of237Np(n,f) and238U(n,f) at the National Physical Laboratory

Cited by 6 publications

References 5 publications

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

Neutron induced fission of 237Np – status, challenges and opportunities

Absolute cross section measurements of 238U(n,f) and 237Np(n,f) in the neutron energy range 1-2.4 MeV

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Product

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Absolute and relative cross section measurements of²³⁷Np(n,f) and²³⁸U(n,f) at the National Physical Laboratory

Neutron induced fission of ²³⁷Np – status, challenges and opportunities

Absolute cross section measurements of ²³⁸U(n,f) and ²³⁷Np(n,f) in the neutron energy range 1-2.4 MeV