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

https://doi.org/10.3327/jnst.48.1

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.

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.

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, temperature coefficient , and Doppler reactivity worth 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.

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

https://doi.org/10.3327/jnst.39.1125

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 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.

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

https://doi.org/10.3327/jnst.38.261

no abstracts in English

Evaluation of fission cross sections and covariances for U,U,U,Pu,Pu,and 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

Preparation of computer codes for estimating the accuracy in nuclear design of Doppler reactivities

*; Sanda, Toshio*; *

PNC TJ9124 95-005, 467 Pages, 1995/03

PNC-TJ9124-95-005.pdf:12.46MB

To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-sections library had been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR cores had been achieved. And the computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared to improve the prediction accuracy for burnup characteristics using many burnup data of "Joyo" effectively. As compared with critical experiment, Doppler reactivity is one of the great characteristics of LMFBR. Doppler reactivity is very important to assure core character of self-control and it is claimed to improve the prediction accuracy for it. But it is impossible to estimate the accuracy for present codes because it is much depend on self-shielding factor. Therefore in this work the system for estimating the accuracy in nuclear design of Doppler reactivity by improving present computer codes was studied. The results are as follows: (1)The method of analyzing sensitivity coefficients of Doppler reactivity was studied and computer codes was prepared by improving present codes. (2)Uncertainty of the gradient toward temperature of self-shielding factor of U238 capture reaction which is the most important reaction for Doppler reactivity was estimated preparatorily and formalized for using adjustment. (3)Uncertainties of experiment and analysis for Doppler reactivities in ZPPR-9 were arranged. (4)It was clarified that it is possible to improve C/E values of Doppler reactivities without affecting other neutronic characteristics by doing preparatorily adjustment.

JENDL-3 FP nuclear data library

Nakagawa, Tsuneo; Kawai, Masayoshi*; Iijima, Shungo*; Matsunobu, Hiroyuki*; Watanabe, Takashi*; Nakajima, Yutaka; Sugi, Teruo; *; *; *; et al.

Nuclear Data for Science and Technology, p.939 - 941, 1992/00

no abstracts in English

None

*; Zukeran, Atsushi*

PNC TJ202 83-09, 143 Pages, 1983/06

PNC-TJ202-83-09.pdf:3.06MB

None

Evaluation of Resonance Parameters of U,U,U,Pu,Pu,Pu and Pu

Nakagawa, Tsuneo; Kikuchi, Yasuyuki; *; *; *;

JAERI-M 9823, 62 Pages, 1981/11

JAERI-M-9823.pdf:1.65MB

no abstracts in English