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- 저자 : N. Yamano (검색결과 2 건)
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Quality Management System Proposed to JENDL Evaluation Project
N. Yamano,T. Yoshida,K. Nakajima,M. Ishikawa,K. Shibata,M. Uematsu,Y. Tahara 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
A concept of the quality management system proposed for the Japanese Evaluated Nuclear Data Library (JENDL) is described. The concept is based on the process approach established as an International Standard of a quality management system (ISO 9001). In order to discuss how to guarantee the quality of JENDL, a working group focusing on a quality assurance strategy was established in the Japanese Nuclear Data Committee. After three years of discussions, the working group published a report about a quality management system for JENDL and proposed this work to the JENDL evaluation group of the Japan Atomic Energy Agency. The concept of quality management system of JENDL consists of five items: (1) Objective, (2) Organization, (3) Scope, (4) Quality Assurance, and (5) Quality Manual. The concept of the quality management system and the documented procedure have been presented.
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Status of JENDL High Energy File
Y. Watanabe,K. Kosako,S. Kunieda,S. Chiba,R. Fujimoto,H. Harada,M. Kawai,F. Maekawa,T. Murata,H. Nakashima,K. Niita,N. Shigyo,S. Shimakawa,N. Yamano,T. Fukahori 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The present status of the JENDL high-energy file is reported. The recent version (referred to as JENDL/HE-2007) contains neutron and proton cross section data for energies up to 3 GeV for 107 nuclides over the wide mass range from H to Am. The newly evaluated data for 41 nuclides have been added to the first version (JENDL/HE-2004) along with some revisions. The JENDL/HE-2007 includes neutron total cross sections, nucleon elastic scattering cross sections and angular distributions, nonelastic cross sections, production cross sections and double-differential cross sections of secondary light particles (n, p, d, t, ^3He, α, and π) and gamma-rays, isotope production cross sections, and fission cross sections in the ENDF-6 format. The evaluations were performed on the basis of experimental data, nuclear model calculations, and systematics based on measurements. The evaluated cross sections are compared with available experimental data and the other evaluations. Some results of benchmark tests with MCNPX codes are shown.
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