Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 155

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Status of JENDL

Iwamoto, Osamu; Iwamoto, Nobuyuki; Shibata, Keiichi; Ichihara, Akira; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke

EPJ Web of Conferences, 239, p.09002_1 - 09002_6, 2020/09

 Times Cited Count:46 Percentile:99.95(Nuclear Science & Technology)

Journal Articles

Cutting-edge studies on nuclear data for continuous and emerging need, 8; Evolution of the nuclear data library JENDL

Iwamoto, Osamu; Shibata, Keiichi; Iwamoto, Nobuyuki; Chiba, Go*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 60(6), p.357 - 361, 2018/06

Nuclear data library consists of the results of related studies on nuclear data. Nuclear data can show worth through utilization of the nuclear data library which is the outcome of the nuclear data study. As the last lecture over 8 serial ones, the Japanese nuclear data library JENDL is explained. Sections of "General purpose file and its history", "recent progress of special purpose file", and "international status of nuclear data library" are introduced and one of "prospect of JENDL and nuclear data study" is shown.

Journal Articles

Status of the JENDL project

Iwamoto, Osamu; Shibata, Keiichi; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Ichihara, Akira; Nakayama, Shinsuke

EPJ Web of Conferences, 146, p.02005_1 - 02005_6, 2017/09

 Times Cited Count:1 Percentile:61.21(Nuclear Science & Technology)

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

 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 mercury isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 53(10), p.1595 - 1607, 2016/10

 Times Cited Count:4 Percentile:36.53(Nuclear Science & Technology)

Neutron nuclear data on mercury 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 $$^{200,202}$$Hg were supplemented with the data which had not been considered in the previous library. 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 mercury isotopes except $$^{203}$$Hg. The present results reproduce experimental data very well, and are much better than the JENDL-4.0 evaluation. The evaluated data are compiled into ENDF-formatted data files.

Journal Articles

Activation cross-section file for decommissioning of LWRs

Shibata, Keiichi; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Iwamoto, Osamu

JAEA-Conf 2016-004, p.47 - 52, 2016/09

It is required to estimate radioactive products accurately for the decommissioning of LWRs. We have developed the neutron-induced activation cross-section file for this purpose. The products consist of 227 nuclides with half-lives larger than 30 days and 12 nuclides with very long half-lives. Target nuclei were selected by considering possible paths leading to the required products. The activation cross sections of these targets were taken from JENDL-4.0, JENDL/A-96 and the post JENDL-4.0 evaluations. As a result, we produced the activation cross-section file with 302 nuclides. Comparing with other evaluations, there exists a large difference especially for the capture cross sections leading to meta-stable states. The data will be released in FY2016 after achieving further improvements.

Journal Articles

Evaluation of neutron nuclear data on tantalum isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 53(7), p.957 - 967, 2016/07

AA2015-0199.pdf:0.39MB

 Times Cited Count:5 Percentile:43.41(Nuclear Science & Technology)

Neutron nuclear data on $$^{179,180m,181,182}$$Ta 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 were selected from experimental data, while unresolved ones were obtained from nuclear model calculations. 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. Giant-dipole and pygmy resonance parameters for E1 $$gamma$$-ray transition from tantalum isotopes were determined so as to reproduce measured $$gamma$$-ray spectrum. The present results reproduce experimental data very well, and are much better than the JENDL-4.0 evaluation. The evaluated data are compiled into ENDF-formatted data files.

Journal Articles

Toward advancement of nuclear data research in the resonance region

Kunieda, Satoshi; Shibata, Keiichi; Fukahori, Tokio; Kawano, Toshihiko*; Paris, M.*; Hale, G.*

JAEA-Conf 2015-003, p.33 - 38, 2016/03

We present recent progress of nuclear data evaluation method in the resolved resonance range. Our multi-channel R-matrix code now includes photon-channel and computational capability of charged-particle elastic scattering. We also present the physical constraint from the theory in the analysis of experimental data. Example analysis results are shown for $$^8$$Be and $$^{17}$$O compound system. Finally, perspectives are discussed toward the advancement of nuclear data in the resonance region including those for medium-heavy nuclei.

Journal Articles

The CCONE code system and its application to nuclear data evaluation for fission and other reactions

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Shibata, Keiichi

Nuclear Data Sheets, 131, p.259 - 288, 2016/01

 Times Cited Count:73 Percentile:97.96(Physics, Nuclear)

A computer code system, CCONE, was developed for nuclear data evaluation in the JENDL project. The CCONE code system integrates various nuclear reaction models needed to describe nucleon, light charged nuclei up to alpha-particle and photon induced reactions. The code is written in the C++ programming language using an object-oriented technology. At first, it was applied to neutron-induced reaction data on actinides, which were compiled into JENDL Actinide File 2008 and JENDL-4.0. It has been extensively used in various nuclear data evaluation not only for actinides but also for non-actinide nuclei. The CCONE code has been upgraded to nuclear data evaluation at higher incident energies for neutron-, proton-, and photon-induced reactions. It was also used for estimating $$beta$$-delayed neutron emission. This paper describes the CCONE code system indicating the concept and design of coding and inputs. Details of formulation formodelings of the direct, pre-equilibrium and compound reactions are presented. Applications to the nuclear data evaluations such as neutron-induced reactions on actinides and medium-heavy nuclei, high-energy nucleon-induced reactions, photonuclear reaction and $$beta$$-delayed neutron emission are mentioned.

Journal Articles

Evaluation of neutron nuclear data on iodine isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 52(9), p.1174 - 1185, 2015/09

 Times Cited Count:4 Percentile:33.25(Nuclear Science & Technology)

Neutron nuclear data on 6 isotopes of iodine have been evaluated for the next release of JENDL general purpose file in the energy region from 10$$^{-5}$$ eV to 20 MeV. Except for $$^{127,129}$$I, the thermal capture cross sections were determined 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. The $$gamma$$-ray strength functions for iodine isotopes were determined so as to reproduce measured $$gamma$$-ray spectrum for $$^{127}$$I. 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.

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

 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.

Journal Articles

Covariance of neutron cross sections for $$^{16}$$O through R-matrix analysis

Kunieda, Satoshi; Kawano, Toshihiko*; Paris, M.*; Hale, G. M.*; Shibata, Keiichi; Fukahori, Tokio

Nuclear Data Sheets, 123, p.159 - 164, 2015/01

 Times Cited Count:6 Percentile:42.02(Physics, Nuclear)

The collision matrix in the R-matrix theory is unitary, hence theory brings strong constraints to behavior of the parameters. An unitarity-imposed R-matrix analysis is carried out for $$^{17}$$O system to evaluate $$^{16}$$O neutron cross-sections in the resolved resonance range. Covariance matrices are also estimated both for the cross-sections and angular distributions with a deterministic method. Present results mirror the nature in the theory as well as experimental information.

Journal Articles

Estimation of neutron cross-sections for $$^{16}$$O up to 5.2 MeV through R-matrix analysis

Kunieda, Satoshi; Kawano, Toshihiko*; Paris, M.*; Hale, G. M.*; Shibata, Keiichi; Fukahori, Tokio

NEA/NSC/DOC(2014)13 (Internet), p.33 - 39, 2014/07

There still remain differences among measured data, which makes the evaluated cross-sections uncertain, and which consequently affects some integral calculation. $$^{16}$$O is one of the important nuclei in the nuclear application, but such kinds of issues appears in elastic-scattering and (n,$$alpha$$) reaction cross-sections. Purpose of this study is to solve those issues as they are common concerns in the world. We present estimated cross sections and their covariance data which are "physically" constrained by the R-matrix theory. The differences between the estimated and the measured cross-sections will be also discussed.

Journal Articles

R-matrix analysis for n + $$^{16}$$O cross-sections up to E$$_{rm n}$$ = 6.0 MeV with covariances

Kunieda, Satoshi; Kawano, Toshihiko*; Paris, M.*; Hale, G. M.*; Shibata, Keiichi; Fukahori, Tokio

Nuclear Data Sheets, 118, p.250 - 253, 2014/04

 Times Cited Count:12 Percentile:62.86(Physics, Nuclear)

Oxygen is one of the most important materials in nuclear applications. However, there are big discrepancies among experimental and evaluated data in $$^{16}$$O($$n,alpha$$) cross section. Also, there are increasing demands for giving uncertainties in evaluated cross section to estimate the margin of integral calculations. We analyzed experimental cross sections with R-matrix theory, and estimated cross sections with their uncertainties. In this analysis, not only the neutron but also an inverse reactions were included. The systematic uncertainties were also considered for each measurement. The resulting cross sections and uncertainties mirror both experimental and theoretical knowledges.

Journal Articles

Meeting nuclear data needs for advanced reactor systems

Harada, Hideo; Shibata, Keiichi; Nishio, Katsuhisa; Igashira, Masayuki*; Plompen, A.*; Hambsch, F.-J.*; Schillebeeckx, P.*; Gunsing, F.*; Ledoux, X.*; Palmiotti, G.*; et al.

NEA/NSC/WPEC/DOC(2014)446, 111 Pages, 2014/02

Journal Articles

Evaluation of neutron nuclear data on antimony isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 51(4), p.425 - 436, 2014/01

 Times Cited Count:10 Percentile:60.98(Nuclear Science & Technology)

Neutron nuclear data on $$^{121,123,124,125,126}$$Sb have been evaluated for the next release of JENDL general purpose file in the energy region from 10$$^{-5}$$ eV to 20 MeV. For $$^{121,123}$$Sb, the latest resolved resonance parameters were considered. The thermal capture cross sections of $$^{125,126}$$Sb, for which no measurements exist, were determined by using a simplified formula. The statistical model was applied to calculate the cross sections above the resolved resonance region. In the calculations, coupled-channel optical model parameters were used for the interaction between neutrons and odd-mass targets. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The present evaluation is consistent with available experimental data. The evaluated results are compiled into an ENDF-formatted data file.

Journal Articles

Evaluation of neutron nuclear data on ruthenium isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 50(12), p.1177 - 1187, 2013/12

 Times Cited Count:4 Percentile:32.48(Nuclear Science & Technology)

Neutron nuclear data on $$^{96,98,99-106}$$Ru have been evaluated for the next release of JENDL general purpose file in the energy region from 10$$^{-5}$$ eV to 20 MeV. The thermal capture cross sections of $$^{96,102}$$Ru were modified so as to reproduce the latest measured data. The statistical model was applied to calculate the cross sections above the resolved resonance region. In the calculations, coupled-channel optical model parameters were used for neutrons. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The present evaluation is consistent with available experimental data. The evaluated results are compiled into an ENDF-formatted data file.

Journal Articles

JENDL; Nuclear databases for science and technology

Shibata, Keiichi

Journal of Nuclear Science and Technology, 50(5), p.449 - 469, 2013/05

 Times Cited Count:8 Percentile:41.1(Nuclear Science & Technology)

It is exactly 50 years since the Japanese Nuclear Data Committee was founded both in the Atomic Energy Society of Japan and in the former Japan Atomic Energy Research Institute. The committee promoted the development of Japan's own evaluated nuclear data libraries. As a result, we managed to produce a series of Japanese Evaluated Nuclear Data Libraries (JENDL's) to be used in various fields for science and technology. The libraries are categorized into general-purpose and special-purpose ones. The general-purpose libraries have been updated periodically by considering the latest knowledge on experimental and theoretical nuclear physics that was available at the time of the updates. On the other hand, the special-purpose libraries have been issued in order to meet the needs. This paper reviews the research and development for those libraries.

Journal Articles

Evaluation of neutron nuclear data for gallium

Shibata, Keiichi

Journal of Nuclear Science and Technology, 50(3), p.277 - 286, 2013/03

 Times Cited Count:5 Percentile:38.62(Nuclear Science & Technology)

Neutron nuclear data on $$^{69,71}$$Ga have been evaluated for the next release of JENDL general purpose file in the energy region from 10$$^{-5}$$ eV to 20 MeV. The resolved resonance parameters at negative energies were adjusted so as to reproduce measured capture cross sections. The statistical model was applied to calculate the cross sections above the resolved resonance region. In the calculations, coupled-channel optical model parameters were used for neutrons. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The present evaluation is consistent with available experimental data. The evaluated results are compiled into an ENDF-formatted data file.

Journal Articles

Evaluation of neutron nuclear data for erbium

Shibata, Keiichi

Journal of Nuclear Science and Technology, 49(7-8), p.824 - 835, 2012/07

 Times Cited Count:6 Percentile:43.52(Nuclear Science & Technology)

Neutron nuclear data on $$^{162,164,166,167,168,170}$$Er have been evaluated for the next release of JENDL general purpose file in the energy region from 10$$^{-5}$$ eV to 20 MeV. The resolved resonance parameters remain unchanged from JENDL-4.0, while the unresolved resonance parameters were revised. The statistical model was applied to calculate the cross sections above the resolved resonance region. In the calculations, coupled-channel optical model parameters were used for neutrons. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The present evaluation is consistent with available experimental data. The evaluated results are compiled into an ENDF-formatted data file.

155 (Records 1-20 displayed on this page)