JOPSS - Search Results

Journal Articles

Recent progress and future plan on the JENDL project

Iwamoto, Osamu

JAEA-Conf 2020-001, p.11 - 16, 2020/12

https://doi.org/10.11484/jaea-conf-2020-001

Journal Articles

Calculation of neutron cross-sections on copper-63 and -65

Nakayama, Shinsuke

Journal of Nuclear Science and Technology, 55(6), p.614 - 622, 2018/06

https://doi.org/10.1080/00223131.2017.1419887

Times Cited Count：2 Percentile：20.93(Nuclear Science & Technology)

Toward the development of the next version of Japanese Evaluated Nuclear Data Library (JENDL) general-purpose file, we calculate neutron cross-sections on $^{63,65}$ Cu from 50 keV to 20MeV, which is the incident energy range above the resolved resonance region in JENDL-4.0. A dispersive optical model potential is adopted with a coupled-channel method for interaction between neutron and $^{63, 65}$ Cu. Direct, pre-equilibrium, and compound processes are taken into account in the calculation. All cross-sections, differential and double-differential cross-sections are consistently calculated with a single set of model parameters. The calculation results reproduce the measured data very well. In addition, disagreement between the calculated and experimental values seen in an integral test for the $^{63}$ Cu $(n,alpha)^{60}$ reaction is improved by using the cross-section data obtained from the present work.

Journal Articles

Evaluation of neutron nuclear data on platinum isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 54(2), p.147 - 157, 2017/02

https://doi.org/10.1080/00223131.2016.1223561

Times Cited Count：4 Percentile：37.06(Nuclear Science & Technology)

Neutron nuclear data on platinum isotopes have been evaluated for the next version of Japanese Evaluated Nuclear Data Library general-purpose file in the energy region from $10^{-5}$ eV to 20 MeV. Resolved resonance parameters of naturally-occurring isotopes were taken from the compilation work of Mughabghab. Unresolved resonance parameters were obtained by fitting to the total and capture cross sections calculated from nuclear models. A statistical model code CCONE was applied to evaluate cross sections above the resolved resonance region. Compound, pre-equilibrium and direct-reaction processes were considered for cross-section calculation. Coupled-channel optical model parameters were employed for the interaction between neutrons and nuclei. The present results reproduce experimental data very well, and are much better than the existing evaluations. The evaluated data are compiled into ENDF-formatted data files.

Journal Articles

Evaluation of neutron nuclear data on copper isotopes by a consistent method

Nakayama, Shinsuke

JAEA-Conf 2016-004, p.147 - 152, 2016/09

https://doi.org/10.11484/jaea-conf-2016-004

Copper is an important element relevant to heat sink material for fusion reactors, structural material for accelerator-driven systems, and so on. Therefore, more precise neutron nuclear data on copper isotopes are currently required. In addition, covariance data are also required to estimate uncertainties of various integral quantities obtained from calculation using the nuclear data. Covariance includes correlated uncertainties between different nuclear data, e.g. cross sections of different reactions. In evaluation on $^{63,65}$ Cu of JENDL-4.0, the cross sections and angular distributions for several reactions were calculated by various computational codes. Towards preparation of covariance data, we evaluated neutron nuclear data on $^{63,65}$ Cu by a consistent method using the CCONE code.

Journal Articles

Evaluation of neutron nuclear data on tellurium isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 52(4), p.490 - 502, 2015/04

https://doi.org/10.1080/00223131.2014.956157

Times Cited Count：7 Percentile：51.25(Nuclear Science & Technology)

Neutron nuclear data on $^{120,121m,122,123,124,125,126,127m,128,129m,130,131m,132}$ Te have been evaluated for the next release of JENDL general purpose file in the energy region from 10 $^{-5}$ eV to 20 MeV. Concerning the target nuclei for which resolved resonance parameters are unavailable, the thermal capture cross sections were determined from measurements or from a simplified formula. Unresolved resonance parameters were obtained for self-shielding calculations. On the other hand, a statistical model code CCONE was applied to calculate cross sections above the resolved resonance region. Coupled-channel optical-model potentials were employed for the interaction between neutrons and nuclei. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The presently evaluated results are consistent with available experimental data, and found to be much better than the JENDL-4.0 evaluation. The evaluated data are compiled into ENDF formatted data files.

JAEA Reports

Improvement of covariance data for fast reactors

*; *

JNC TJ9400 2000-004, 109 Pages, 2000/02

JNC-TJ9400-2000-004.pdf:4.96MB

We estimated covariances of the JENDL-3.2 data on the nuclides and reactions needed to analyze fast-reactor cores for the past three years, and produced covariance files. The present work was undertaken to re-examine the covariance files and to make some improvements. The covariances improved are the ones for the inelastic scattering cross section of $^{16}$ O, the total cross section of $^{23}$ Na, the fission cross section of $^{235}$ U, the capture cross section of $^{238}$ U, and the resolved resonance parameters for $^{238}$ U. Moreover, the covariances of $^{233}$ U data were newly estimated by the present work. The covariances obtained were compiled in the ENDF-6 format.