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Journal Articles

Report on the 29th Meeting of Working Party on International Nuclear Data Evaluation Co-operation (WPEC)

Harada, Hideo; Iwamoto, Osamu; Kimura, Atsushi; Yokoyama, Kenji; Tada, Kenichi

Kaku Deta Nyusu (Internet), (117), p.36 - 51, 2017/06

no abstracts in English

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:1 Percentile:83.64(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

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

Nakayama, Shinsuke

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

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 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:3 Percentile:58.5(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

Report on the 28th Meeting of Working Party on International Nuclear Data Evaluation Co-operation

Fukahori, Tokio; Harada, Hideo; Iwamoto, Osamu; Yokoyama, Kenji

Kaku Deta Nyusu (Internet), (114), p.35 - 43, 2016/06

no abstracts in English

Journal Articles

Report on the 27th Meeting of Working Party on International Nuclear Data Evaluation Co-operation

Harada, Hideo; Iwamoto, Osamu; Yokoyama, Kenji

Kaku Deta Nyusu (Internet), (111), p.51 - 62, 2015/06

no abstracts in English

Journal Articles

Activity report of Japanese Nuclear Data Committee in period of April 1999 to March 2001

Japanese Nuclear Data Committee

Nippon Genshiryoku Gakkai-Shi, 44(1), p.106 - 114, 2002/01

no abstracts in English

Journal Articles

Activity report of Japanese nuclear data committee in period of April 1997 to March 1999

Japanese Nuclear Data Committee

Nippon Genshiryoku Gakkai-Shi, 41(12), p.1213 - 1221, 1999/00

no abstracts in English

Journal Articles

Activity report of Japanese Nuclear Data Committee in period of April 1995 to March 1997

Japanese Nuclear Data Committee

Nippon Genshiryoku Gakkai-Shi, 39(12), p.1019 - 1027, 1997/00

no abstracts in English

Journal Articles

Measurement and evaluation of nuclear data

Takahashi, Akito*; Shibata, Keiichi; Ikeda, Yujiro

Purazuma, Kaku Yugo Gakkai-Shi, 71(11), p.1113 - 1122, 1995/11

no abstracts in English

Journal Articles

Activity report of Japanese Nuclear Data Committee in period of April 1993 to March 1995

Japanese Nuclear Data Committee

Nippon Genshiryoku Gakkai-Shi, 37(12), p.1095 - 1103, 1995/00

no abstracts in English

Journal Articles

Impacts of data transformations on least-squares solutions and their significance in data analysis and evaluation

Chiba, Satoshi; D.L.Smith*

Journal of Nuclear Science and Technology, 31(8), p.770 - 781, 1994/08

 Times Cited Count:12 Percentile:27.27(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Nuclear data evaluation for JENDL actinide file and high energy data files

Nakagawa, Tsuneo; Fukahori, Tokio; Chiba, Satoshi;

Proc. of the Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options; GLOBAL 93, p.467 - 474, 1993/00

no abstracts in English

Journal Articles

Japanese evaluated nuclear data library, JENDL-3

Asami, Tetsuo*; Iijima, Shungo*; ; Ihara, Hitoshi; Kawai, Masayoshi*; ; Komuro, Yuichi; Shibata, Keiichi; Takano, Hideki; *; et al.

Nippon Genshiryoku Gakkai-Shi, 31(11), p.1190 - 1217, 1989/11

no abstracts in English

JAEA Reports

Proceedings of the 1982 Seminar on Nuclear Data

JAERI-M 83-041, 236 Pages, 1983/03

JAERI-M-83-041.pdf:6.07MB

no abstracts in English

Journal Articles

Activities of the nuclear data center ; An introduction to the use of nuclear data

Nippon Genshiryoku Gakkai-Shi, 20(5), p.323 - 328, 1978/05

 Times Cited Count:0

no abstracts in English

JAEA Reports

JAERI fast reactor group constants set, Version II

; ; Nakagawa, Masayuki; ; Katsuragi, Satoru

JAERI 1255, 200 Pages, 1978/03

JAERI-1255.pdf:12.07MB

no abstracts in English

Oral presentation

High-energy nuclear data library JENDL-4.0/HE

Kunieda, Satoshi; Iwamoto, Osamu; Iwamoto, Nobuyuki; Minato, Futoshi; Okamoto, Tsutomu; Sato, Tatsuhiko; Nakashima, Hiroshi; Iwamoto, Yosuke; Iwamoto, Hiroki; Kitatani, Fumito; et al.

no journal, , 

Neutron- and proton-induced evaluated nuclear data are required in a wide energy range for the design of accelerator applications. New evaluations are performed with recent progresses in the optical and pre-equilibrium model calculations. We also evaluated cross-sections for p + $$^{6,7}$$Li and p + $$^{8}$$Be which are highly requested from medical field. Our present high-energy nuclear data library, JENDL-4.0/HE, includes cross-sections for 132 nuclei up to 200 MeV. In this talk, we present the evaluation methods, evaluated double-differential cross-sections and results of benchmark calculations.

Oral presentation

Reduction and resource recycling of high-level radioactive wastes through nuclear transformation; Theoretical predictions of the nuclear reaction data for nuclei involved in the nuclear transformation system

Furutachi, Naoya; Minato, Futoshi; Iwamoto, Osamu

no journal, , 

For the feasibility study of the nuclear transmutation system for the long-lived fission products(LLFPs), the simulation calculation to estimate the efficiency of the transmutation system is essential. The precision of the simulation calculation largely depends on the evaluated nuclear data used in the calculation. To improve the precision of the simulation calculation, developing nuclear data not only of LLFPs but also of all the nuclei involved in the simulation calculation is desirable. When we study the transmutation system using the nuclear reaction such as spallation reaction, it is anticipated that a wide range of nuclei including unstable nuclei with no or scarce experimental are produced. In particular, the shortage of nuclear experimental data in resonance region is a problem for nuclear data evaluation, because it is difficult to predict the resonant structure precisely in a theoretical way. One of the methods mitigating this problem is to use the resonance parameters randomly determined from the statistical properties of the resonance parameters. This approach is already adopted in TENDL nuclear data library. However, the cross section calculated using such a method would have a large uncertainty arising from the statistical fluctuation of the resonance parameters in principle. This uncertainty wasn't discussed in the previous study. In this study, we investigated the statistical method to predict the nuclear reaction data in resonance region focusing on its statistical uncertainties. Particularly, we shall discuss the neutron capture cross sections of nuclei expected to be produced via the transmutation of Se-79, Zr-93, Pd-107 and Cs-135.

Oral presentation

Evaluation of neutron nuclear data on copper isotopes in fast energy region

Nakayama, Shinsuke

no journal, , 

Toward development of an activation cross section file, we evaluated neutron cross sections on copper isotopes in the incident energy range from 50 keV to 20 MeV. Although copper is important material, the evaluated values of activation cross sections on copper isotopes have not been updated for about thirty years, and some large discrepancies can be seen between the evaluated values and the recently measured ones. In the present study, therefore, we aimed to improve accuracy of activation cross sections. We used the CCONE code for nuclear reaction calculation. Direct component was calculated by the dispersive coupled-channel optical model and the distorted wave Born approximation. Pre-equilibrium and compound components were calculated by the two component exciton model and the Hauser-Feshbach model, respectively. The present evaluation results reproduced the existing measured data better than the evaluated data of JENDL-4.0.

24 (Records 1-20 displayed on this page)