Neutron total and capture cross-section measurements of <sup>155</sup>Gd and <sup>157</sup>Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·ANNRI

Kimura, A.; Nakamura, Shôji; Endo, Shunsuke; Rovira, Gerard; Iwamoto, Osamu; Iwamoto, Nobuyuki; Harada, Hideo; Katabuchi, Tatsuya; Terada, Kikuo; Hori, Jun‐ichi; Shibahara, Yuji; Fujii, Toshiyuki

doi:10.1080/00223131.2022.2134224

Journal of Nuclear Science and Technology

2022

DOI: 10.1080/00223131.2022.2134224

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Neutron total and capture cross-section measurements of ¹⁵⁵Gd and ¹⁵⁷Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·ANNRI

A. Kimura

Shôji Nakamura

Shunsuke Endo

et al.

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Cited by 4 publications

References 31 publications

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Total and Double Differential Scattering Cross-Section Measurements of Isotropic Graphite

Kimura,

Endo,

Nakamura

2024

EPJ Web of Conf.

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The total and double differential scattering cross sections (DDSCS) of isotropic graphite have been measured in the J-PARC Materials and Life Science Experimental Facility using five samples with different porosities and grain sizes. The DDSCS measurements were performed in Beam Line No.14 (AMATERAS) with nine incident neutron energies ranging from 1.2 to 94 meV. In the derived cross sections, there are no clear sample dependence. The neutron total cross sections in the energy region from 1 to 100 meV were measured using Beam Line No. 04 (ANNRI). All samples in the epithermal range (over 40 meV) tended to have values close to the free atom cross-section of graphite. However, at the first Bragg edge, the deduced total cross sections by these measurements started to vary. The difference became more significant with decreasing the neutron energy.

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Total and Double Differential Scattering Cross-Section Measurements of Isotropic Graphite

Kimura,

Endo,

Nakamura

2024

EPJ Web of Conf.

Self Cite

View full text Add to dashboard Cite

show abstract

Japanese evaluated nuclear data library version 5: JENDL-5

Iwamoto

Kunieda

et al. 2023

Journal of Nuclear Science and Technology

172

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JENDL-5 benchmarking for fission reactor applications

Tada

Nagaya

Taninaka

et al. 2023

Journal of Nuclear Science and Technology

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Neutron total and capture cross-section measurements of ¹⁵⁵Gd and ¹⁵⁷Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·ANNRI

Cited by 4 publications

References 31 publications

Total and Double Differential Scattering Cross-Section Measurements of Isotropic Graphite

Total and Double Differential Scattering Cross-Section Measurements of Isotropic Graphite

Japanese evaluated nuclear data library version 5: JENDL-5

JENDL-5 benchmarking for fission reactor applications

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Neutron total and capture cross-section measurements of 155Gd and 157Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·ANNRI

Cited by 4 publications

References 31 publications

Total and Double Differential Scattering Cross-Section Measurements of Isotropic Graphite

Total and Double Differential Scattering Cross-Section Measurements of Isotropic Graphite

Japanese evaluated nuclear data library version 5: JENDL-5

JENDL-5 benchmarking for fission reactor applications

Contact Info

Product

Resources

About

Neutron total and capture cross-section measurements of ¹⁵⁵Gd and ¹⁵⁷Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·ANNRI