Associate professor, Research Reactor Institute, Kyoto University, Kumatori-cho, Sennan-gun, Osaka,
Professor, Faculty of Engineering, University of Tokyo, Hongo, Bunkyo-ku, Tokyo,
Research scientist, Faculty of Engineering, Tohoku University, Aza-aoba, Aramaki, Sendai,
Associate professor, Faculty of Engineering, University of Tokyo, Hongo, Bunkyo-ku, Tokyo,
Principal scientist, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki,
Senior scientist, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki,
Scientist, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki,
Research scientist, Ship Research Institute, Ministry of Transport, Tokai-mura, Naka-gun, Ibaraki,
Pages: 10 Published: Jan 1994
The JENDL Dosimetry File based on Japanese Evaluated Nuclear Data Library Version 3 (JENDL-3) was compiled, and integral tests of the dosimetry cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Sixty-one reaction cross sections and their covariance data are stored in the JENDL Dosimetry File. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. The data are given in the neutron energy region below 20 MeV in point and group files in the ENDF/B-V format.
In order to confirm reliability of data in the JENDL Dosimetry File, several integral tests were carried out: comparison with average cross sections measured in fission neutron and fast reactor spectra, DT, and Li(d,n) neutron fields. As a result, it has been found that the calculated and the measured average cross sections are in general agreement with each other. However, some of the dosimetry cross sections still showed marked discrepancies between the measured and the calculated data. These discrepant cross sections have been reevaluated and the integral tests have been repeated.
Japanese Evaluated Nuclear Data Library (JENDL) Dosimetry File, JENDL-3, energy dependent cross section, spectrum-averaged cross section, integral test, standard neutron field, reference neutron field, 252, Cf spontaneous fission spectrum, 235, U fission spectrum, fast reactor spectrum, DT neutron field, Li(n,d) neutron field
Paper ID: STP15162S