Abstract
The JENDL Dosimetry File based on JENDL-3 was compiled and integral tests of cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Data stored in the JENDL Dosimetry File are the cross sections and their covariance data for 61 reactions. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. For some reactions, data were adopted from other evaluated data files. The data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-5 format. In order to confirm reliability of the data, several integral tests were carried out; comparison with the data in IRDF-85 and average cross sections measured in fission neutron fields, fast reactor spectra, DT neutron fields and Li(d,n) neutron fields. As a result, it has been found that the JENDL Dosimetry File gives better results than IRDF-85 but there are some problems to be improved in future. The contents of the JENDL Dosimetry File and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form.
Nakazawa, Masaharu;
Iguchi, Tetsuo;
[1]
Kobayashi, Katsuhei;
[2]
Iwasaki, Shin;
[3]
Sakurai, Kiyoshi;
Ikeda, Yujior;
Nakagawa, Tsuneo
[4]
- Tokyo Univ. (Japan). Faculty of Engineering
- Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.
- Tohoku Univ., Sendai (Japan). Faculty of Engineering
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Nakazawa, Masaharu, Iguchi, Tetsuo, Kobayashi, Katsuhei, Iwasaki, Shin, Sakurai, Kiyoshi, Ikeda, Yujior, and Nakagawa, Tsuneo.
JENDL Dosimetry File.
Japan: N. p.,
1992.
Web.
Nakazawa, Masaharu, Iguchi, Tetsuo, Kobayashi, Katsuhei, Iwasaki, Shin, Sakurai, Kiyoshi, Ikeda, Yujior, & Nakagawa, Tsuneo.
JENDL Dosimetry File.
Japan.
Nakazawa, Masaharu, Iguchi, Tetsuo, Kobayashi, Katsuhei, Iwasaki, Shin, Sakurai, Kiyoshi, Ikeda, Yujior, and Nakagawa, Tsuneo.
1992.
"JENDL Dosimetry File."
Japan.
@misc{etde_10144838,
title = {JENDL Dosimetry File}
author = {Nakazawa, Masaharu, Iguchi, Tetsuo, Kobayashi, Katsuhei, Iwasaki, Shin, Sakurai, Kiyoshi, Ikeda, Yujior, and Nakagawa, Tsuneo}
abstractNote = {The JENDL Dosimetry File based on JENDL-3 was compiled and integral tests of cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Data stored in the JENDL Dosimetry File are the cross sections and their covariance data for 61 reactions. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. For some reactions, data were adopted from other evaluated data files. The data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-5 format. In order to confirm reliability of the data, several integral tests were carried out; comparison with the data in IRDF-85 and average cross sections measured in fission neutron fields, fast reactor spectra, DT neutron fields and Li(d,n) neutron fields. As a result, it has been found that the JENDL Dosimetry File gives better results than IRDF-85 but there are some problems to be improved in future. The contents of the JENDL Dosimetry File and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form.}
place = {Japan}
year = {1992}
month = {Mar}
}
title = {JENDL Dosimetry File}
author = {Nakazawa, Masaharu, Iguchi, Tetsuo, Kobayashi, Katsuhei, Iwasaki, Shin, Sakurai, Kiyoshi, Ikeda, Yujior, and Nakagawa, Tsuneo}
abstractNote = {The JENDL Dosimetry File based on JENDL-3 was compiled and integral tests of cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Data stored in the JENDL Dosimetry File are the cross sections and their covariance data for 61 reactions. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. For some reactions, data were adopted from other evaluated data files. The data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-5 format. In order to confirm reliability of the data, several integral tests were carried out; comparison with the data in IRDF-85 and average cross sections measured in fission neutron fields, fast reactor spectra, DT neutron fields and Li(d,n) neutron fields. As a result, it has been found that the JENDL Dosimetry File gives better results than IRDF-85 but there are some problems to be improved in future. The contents of the JENDL Dosimetry File and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form.}
place = {Japan}
year = {1992}
month = {Mar}
}