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Journal Articles

JENDL-4.0; A New library for nuclear science and engineering

Shibata, Keiichi; Iwamoto, Osamu; Nakagawa, Tsuneo*; Iwamoto, Nobuyuki; Ichihara, Akira; Kunieda, Satoshi; Chiba, Satoshi; Furutaka, Kazuyoshi; Otsuka, Naohiko*; Osawa, Takaaki*; et al.

Journal of Nuclear Science and Technology, 48(1), p.1 - 30, 2011/01

 Times Cited Count:1249 Percentile:100(Nuclear Science & Technology)

The fourth version of Japanese Evaluated Nuclear Data Library has been produced. In the new library, much emphasis is placed on the improvements of fission product and minor actinoid data. Two nuclear model codes were developed to evaluate the cross sections of fission products and minor actinoids. Coupled-channel optical model parameters, which can be applied to wide mass and energy regions, were obtained for nuclear model calculations. Thermal cross sections of actinoids were determined by considering recent experimental data or by the systematics of neighboring nuclei. A simultaneous evaluation was performed for the fission cross sections of important uranium and plutonium isotopes above 10 keV. The data on FP were re-evaluated, and new evaluations were performed for 30 nuclides. The data on light elements and structural materials were partly re-evaluated. The new library was released as JENDL-4.0 in May 2010.

JAEA Reports

Covariances of resonance self-shielding factor and its temperature gradient for uncertainty evaluation of Doppler reactivity

Zukeran, Atsushi*; Chiba, Go; Otsuka, Naohiko*; Ishikawa, Makoto; Takano, Hideki*

JAEA-Research 2008-091, 162 Pages, 2009/02

JAEA-Research-2008-091-01.pdf:5.8MB
JAEA-Research-2008-091-02.pdf:45.78MB

Uncertainty of Doppler reactivity is theoretically formulated and then uncertainties of self-shielding factor and its temperature gradient due to errors of resonance parameters were evaluated from NJOY output. Sensitivity analysis was made for $$^{235}$$U, $$^{238}$$U, $$^{239}$$Pu and $$^{240}$$Pu of JENDL-3.3 based on JFS-3 70 group structure. Resultant sensitivity coefficients are provided for the uncertainty evaluation of Doppler reactivity.

JAEA Reports

ERRORF; A Code to calculate covariance of self-shielding factor and its temperature gradient

Otsuka, Naohiko*; Zukeran, Atsushi*; Takano, Hideki*; Chiba, Go; Ishikawa, Makoto

JAEA-Data/Code 2008-012, 17 Pages, 2008/06

JAEA-Data-Code-2008-012.pdf:1.31MB

A computer code, ERRORF, was developed for calculation of covariance of self-shielding factor and its temperature gradient. This code is based on several modules. With this code, covariance of self-shielding factor and its temperature gradient can be calculated from evaluated nuclear library in the ENDF format.

Journal Articles

Covariance analyses of self-shielding factor and its temperature gradient for uranium-238 neutron capture reaction

Otsuka, Naohiko; Zukeran, Atsushi*; Takano, Hideki*; Chiba, Go; Ishikawa, Makoto

Journal of Nuclear Science and Technology, 45(3), p.195 - 210, 2008/03

 Times Cited Count:2 Percentile:18.72(Nuclear Science & Technology)

Covariances of the self-shielding factor and its temperature gradient for the uranium-238 neutron capture reaction have been evaluated from the resonance parameter covariance matrix and sensitivity of the self-shielding factor and its temperature gradient to microscopic nuclear data. The resonance parameters and their covariance matrix for uranium-238 were taken from JENDL-3.3, while the sensitivity coefficients were calculated by varying resonance parameters and temperature. A set of computer code modules has been developed for calculation of the sensitivity coefficients at numerous resonance levels. The present result shows that the correlation among resonance parameters yields a substantial contribution to the variances of the self-shielding factor and its temperature gradient. In addition to the variances of these quantities, their correlation matrices in the JFS-3 70 group structure are also obtained.

JAEA Reports

Criticality and doppler reactivity worth uncertainty due to resolved resonance parameter errors; Formula for sensitivity analysis

Zukeran, Atsushi*; Nakagawa, Tsuneo; Shibata, Keiichi; Ishikawa, Makoto*; Hino, Tetsushi*

JAERI-Research 2004-026, 102 Pages, 2005/02

JAERI-Research-2004-026.pdf:7.68MB

Reactivity uncertainties such as effective multiplication factor can be estimated by the sensitivity coefficients of the infinitely diluted cross section and resonance self-shielding factor to the changes of resonance parameters of interest. In the present work, the uncertainties of the resolved resonance parameters for the evaluated nuclear data file JENDL-3.2 were estimated on the basis of Breit-Wigner Multi-level formula. The resonance self-shielding factor based on NR-approximation is analytically described. Reactivity uncertainty evaluation method for the effective multiplication factor k$$_{eff}$$, temperature coefficient $$alpha$$, and Doppler reactivity worth $$rho$$ is developed by means of the sensitivity coefficient against the resonance parameter. Final uncertainties are estimated by means of error propagation law using the level-wise uncertainties. Preliminary uncertainty of Doppler reactivity worth results about 4% at the temperature 728 K for large sodium-cooled FBR.

JAEA Reports

Evaluations of heavy nuclide data for JENDL-3.3

Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.

JAERI-Research 2003-026, 53 Pages, 2003/12

JAERI-Research-2003-026.pdf:2.48MB

New evaluations of neutron nuclear data for Uranium, Plutonium, and Thorium isotopes which are essential for applications to nuclear technology were carried out for the Japanese Evaluated Nuclear Data Library, JENDL-3.3. The objectives of the current release of JENDL were to fix several problems which have been reported for the previous version, to improve the accuracy of the data, and to evaluate covariances for the important nuclides. Quantities in JENDL-3.2 were extensively re-evaluated or replaced by more reliable values. The heavy nuclide data in JENDL-3.3 were validated with several benchmark tests, and it was reported that the current release gave a good prediction of criticalities.

Journal Articles

Japanese evaluated nuclear data library version 3 revision-3; JENDL-3.3

Shibata, Keiichi; Kawano, Toshihiko*; Nakagawa, Tsuneo; Iwamoto, Osamu; Katakura, Junichi; Fukahori, Tokio; Chiba, Satoshi; Hasegawa, Akira; Murata, Toru*; Matsunobu, Hiroyuki*; et al.

Journal of Nuclear Science and Technology, 39(11), p.1125 - 1136, 2002/11

 Times Cited Count:642 Percentile:96.97(Nuclear Science & Technology)

Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for $$^{235}$$U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.

Journal Articles

Evaluation of Delayed Neutron Data for JENDL-3.3

Yoshida, Tadashi*; Okajima, Shigeaki; Sakurai, Takeshi; Nakajima, Ken; Yamane, Tsuyoshi; Katakura, Junichi; Tahara, Yoshihisa*; Zukeran, Atsushi*; Oyamatsu, Kazuhiro*; Osawa, Takaaki*; et al.

Journal of Nuclear Science and Technology, 39(Suppl.2), p.136 - 139, 2002/08

no abstracts in English

Journal Articles

Re-evaluation of nuclear data of fission product nuclides for JENDL-3.2

Kawai, Masayoshi*; Nakagawa, Tsuneo; Watanabe, Takashi*; Nakajima, Yutaka*; Zukeran, Atsushi*; Matsunobu, Hiroyuki*; Sugi, Teruo*; Chiba, Satoshi

Journal of Nuclear Science and Technology, 38(4), p.261 - 269, 2001/04

no abstracts in English

Journal Articles

Simultaneous evaluation of fission cross sections of uranium and plutonium isotopes for JENDL-3.3

Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.

Journal of Nuclear Science and Technology, 37(4), p.327 - 334, 2000/04

no abstracts in English

JAEA Reports

Evaluation of fission cross sections and covariances for $$^{233}$$U,$$^{235}$$U,$$^{238}$$U,$$^{239}$$Pu,$$^{240}$$Pu,and $$^{241}$$Pu

Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.

JAERI-Research 2000-004, p.76 - 0, 2000/02

JAERI-Research-2000-004.pdf:2.39MB

no abstracts in English

Oral presentation

Evaluation of FP nuclear data for JENDL-4, 1; Update of resolved resonance parameters

Shibata, Keiichi; Nakagawa, Tsuneo; Chiba, Satoshi; Iwamoto, Nobuyuki; Furutaka, Kazuyoshi; Murata, Toru*; Zukeran, Atsushi*; Matsunobu, Hiroyuki*

no journal, , 

We are developing the 4th Version of Japanese Evaluated Nuclear Data Library (JENDL-4) as the middle-term project. The resolved resonance paramters of FP nuclides have been evaluated in cooperation with the Japanese Nuclear Data Committee. The evaluation covers about 200 nuclides from Zn (Z=30) to Er (Z=68). Evaluation procedures and results of the resolved resonance parameters will be reported in this talk.

Oral presentation

Covariance evaluation of self-shielding factor and its temperature gradient for uncertainty evaluation of doppler reactivity

Otsuka, Naohiko; Zukeran, Atsushi*; Takano, Hideki*; Chiba, Go; Ishikawa, Makoto

no journal, , 

Covariances of the self-shielding factor and its temperature gradient for the uranium-238 neutron capture reaction have been evaluated from the resonance parameter covariance matrix based on the sensitivity coefficients of the self-shielding factor and its temperature gradient to the resonance parameters. The present result shows that the correlation among resonance parameters yields a substantial contribution to the standard deviations of the self-shielding factor and its temperature gradient.

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