Determination of resonance parameters and their covariances from neutron induced reaction cross section data
P Schillebeeckx, B Becker, Y Danon, K Guber… - Nuclear Data …, 2012 - Elsevier
Cross section data in the resolved and unresolved resonance region are represented by
nuclear reaction formalisms using parameters which are determined by fitting them to …
nuclear reaction formalisms using parameters which are determined by fitting them to …
EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5
N Otuka, O Iwamoto - Journal of Nuclear Science and Technology, 2022 - Taylor & Francis
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 238U and 240Pu from …
library for 233,235 U and 239,241 Pu from 10 keV to 200 MeV and for 238U and 240Pu from …
Neutron-induced fission cross sections of and up to 1 GeV using parallel plate avalanche counters at the CERN n_TOF facility
D Tarrío, L Tassan-Got, I Duran, LS Leong, C Paradela… - Physical Review C, 2023 - APS
The neutron-induced fission cross sections of Th 232 and U 233 were measured relative to
U 235 in a wide neutron energy range up to 1 GeV (and from fission threshold in the case of …
U 235 in a wide neutron energy range up to 1 GeV (and from fission threshold in the case of …
Nuclear data evaluations for jendl high‐energy file
Y Watanabe, T Fukahori, K Kosako, N Shigyo… - AIP conference …, 2005 - pubs.aip.org
An overview is presented of recent nuclear data evaluations performed for the JENDL high‐
energy (JENDL‐HE) file, in which neutron and proton cross sections for energies up to 3 …
energy (JENDL‐HE) file, in which neutron and proton cross sections for energies up to 3 …
A fast ionization chamber for fission cross-section measurements at n_TOF
M Calviani, P Cennini, D Karadimos, V Ketlerov… - Nuclear Instruments and …, 2008 - Elsevier
An ionization chamber with fast timing properties was built at CERN for measuring fission
cross-sections of minor actinides at the n_TOF neutron beam. The design of this new …
cross-sections of minor actinides at the n_TOF neutron beam. The design of this new …
High-accuracy cross-section measurement at the white-neutron source n_TOF from near-thermal to MeV neutron energy
M Calviani, J Praena, U Abbondanno, G Aerts… - Physical Review C …, 2009 - APS
The U 233 (n, f) cross section has been measured at the white neutron source n_TOF in a
wide energy range with a dedicated fission ionization chamber. We report here the results …
wide energy range with a dedicated fission ionization chamber. We report here the results …
Measurement of the neutron-induced capture-to-fission cross section ratio in at LANSCE
E Leal-Cidoncha, A Couture, EM Bond, TA Bredeweg… - Physical Review C, 2023 - APS
The neutron-induced capture-to-fission cross section ratio of U 233 has been measured at
the Los Alamos Neutron Science Center at Los Alamos National Laboratory in the energy …
the Los Alamos Neutron Science Center at Los Alamos National Laboratory in the energy …
[PDF][PDF] EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5: Inputs and outputs
N Otuka, O Iwamoto - Japan Atomic Energy Agency, 2022 - nds.iaea.org
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 238U and 240Pu from …
library for 233,235 U and 239,241 Pu from 10 keV to 200 MeV and for 238U and 240Pu from …
Progress on the reevaluation and validation of the n+ 233U neutron cross sections
The set of 233 U resonance parameters of the ENDF/B-VIII. 0 nuclear data library was
adopted from the previous ENDF/B-VII. 1 evaluation using the external levels to update the …
adopted from the previous ENDF/B-VII. 1 evaluation using the external levels to update the …
Evaluation of uranium-233 neutron capture cross section in keV region
N Otuka, K Tada, O Cabellos, O Iwamoto - Annals of Nuclear Energy, 2025 - Elsevier
The uranium-233 neutron capture cross section between 3 keV and 1 MeV was evaluated
with the alpha value recently measured at the Los Alamos National Laboratory LANCE …
with the alpha value recently measured at the Los Alamos National Laboratory LANCE …