Average Radiative Capture Cross Sections for 7- to 170-kev Neutrons

Gibbons, John H.; Macklin, R. L.; Miller, P. D.; Neiler, J. H.

doi:10.1103/physrev.122.182

Cited by 202 publications

(24 citation statements)

References 27 publications

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“…Capture cross sections for 141 Pr are compared to recent libraries and measurements as shown in fall 4. Our results reproduce the experimental data [12][13][14][15][16][17][18] below and above the URR. Sm-isotopes (n,2n) Sm-isotopes (n,2n) Fig.…”

Section: Resultssupporting

confidence: 81%

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Kim

Lee

Herman

et al. 2007

Nd2007

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Abstract. Neutron cross sections for fission products play an important role not only in the design of extended burnup core and fast reactors, but also in the study of the backend fuel cycle and the criticality analysis of spent fuel. New evaluations for the ENDF/B-VII.0 library were performed by the KAERI-BNL collaboration for the following 32 fission products: 95 Nd, 144,147,[148][149][150][151][152][153][154] and 156,158,[160][161][162][163][164] Dy. The evaluations cover a large amount of reaction channels, from 10 −5 eV to 20 MeV, including thermal, resolved, unresolved resonance regions, and fast neutron region.

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Section: Resultssupporting

confidence: 81%

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Kim

Lee

Herman

et al. 2007

Nd2007

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“…5, the agreement between Popov's 06 l, Weston's< 17 J and the present data are fairly good within the experimental error. Gibbons' data< 14 J have slightly steep gradient in the energy dependence in the same way as their 93 Nb(n, 7) data, which may be the effect of using In shows about a 10% higher value than the present result.…”

Section: Resultscontrasting

confidence: 54%

Neutron Capture Cross Section Measurements of Nb-93, 1-127, Ho-165, Ta-181 and U-238 between 3.2 and 80keV

Yamamuro

Saitô

Emoto

et al. 1980

Journal of Nuclear Science and Technology

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The neutron capture cross sections of 93 Nb, 127 1, 1 "'Ho, mTa and ""'U were measured from 3.2 to 80 keV using the time-of-flight method. The neutron beam was produced by the KURRI 46-MeV linear accelerator and capture r-rays were detected by a C 0 F 0 or C 0 D 6 liquid scintillation detector. As the result of the use of a direct-coupled operational preamplifier, the detector recovered rapidly from the r-flash such that data for higher energy '!eutrons can be obtained in spite of the short flight path of 11.7 m. The neutron sensitivities of both detectors are compared and the superiority of the C 0 D, detector is shown.The experimental results of capture cross sections, corrected for resonance self-shielding and multiple scattering and normalized to the 24-keV absolute values, are shown numerically and graphically, and compared with other data. The agreement between the data is fairly good for 165 Ho and 238 U, but not for 93 Nb, 127 1 and 181 Ta. The discrepancy between the data may be caused by the difference of the reference cross sections used for each experiment.

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“…For some data, special corrections were introduced. In particular, Gibbons et al [17] have used the nat In(n, ) reaction as a monitor in relative measurements. The new recommended monitor cross sections for this experiment was calculated as a sum of the ENDF/B-VII.1 evaluations for the 113 In(n, ) and 115 In(n, ) reaction cross-sections.…”

Section: The Experimental Data Basementioning

confidence: 99%

“…The results of 33 experiments have been analysed. A part of the experimental data ( [13][14][15], [17,18], [21], [23], [26], [28][29][30], [35][36][37][38]) was corrected to new recommended monitor reaction cross-sections and decay data. For some data, special corrections were introduced.…”

Section: The Experimental Data Basementioning

confidence: 99%

Evaluation of the⁹³Nb(n,γ) Reaction Cross-Section

Zolotarev

Badikov

2016

EPJ Web of Conferences

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Abstract. New evaluation of the 93 Nb(n, ) 94 Nb reaction cross-section important for retrospective reactor dosimetry was carried out. At neutron energies below 7.5 keV the evaluation is based on the experimental data. The results of measurements extracted from the EXFOR library were corrected (when necessary) to new recommended values of monitor reaction cross-sections and decay data. The resonance analysis of the 93 Nb(n, ) and the 93 Nb(n,tot) reaction cross-sections was carried out within the Reich-Moore formalism. 48 new resonances were identified as compared to the Mughabghab systematics. In the energy range from 7.5 keV to 20 MeV the evaluation is based on the experimental data and theoretical model calculations. The recommended cross-sections and their covariances in this energy range were evaluated by an approximation of the experimental and calculated values with the PADE2 code. The new evaluation provides, essentially, better agreement with the experimental data and the recommended value of the resonance integral compared to other evaluations.

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Average Radiative Capture Cross Sections for 7- to 170-kev Neutrons

Cited by 202 publications

References 27 publications

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Neutron Capture Cross Section Measurements of Nb-93, 1-127, Ho-165, Ta-181 and U-238 between 3.2 and 80keV

Evaluation of the⁹³Nb(n,γ) Reaction Cross-Section

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Average Radiative Capture Cross Sections for 7- to 170-kev Neutrons

Cited by 202 publications

References 27 publications

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Neutron Capture Cross Section Measurements of Nb-93, 1-127, Ho-165, Ta-181 and U-238 between 3.2 and 80keV

Evaluation of the93Nb(n,γ) Reaction Cross-Section

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Evaluation of the⁹³Nb(n,γ) Reaction Cross-Section