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NOTICE:
     The users are requested to cite the No.1 of the papers given below for referencing JENDL-3.3.

 
Summary of JENDL-3.3

Purpose To provide a Japanese standard library for fast breeder reactors, thermal reactors, fusion neutronics and shielding calculations, and other applications
Number of nuclides
337
Incident neutron energy range 10-5 eV to 20 MeV
Format ENDF-6 Format.
Pointwise files prepared at 0K and 300K with LINEAR, RECENT and SIGMA1 (accuracy=0.1%)

Details of JENDL-3.3
(numerical data, descriptions, figures and tables of cross sections)
Updated Data Files
  • When fatal compilation errors are found, updated data files are released.
    The updated file is available for Am-241.
Problems of JENDL-3.3
We have found following problems in JENDL-3.3:
Downloading JENDL-3.3
CD-ROM containing JENDL-3.3 original files, pointwise files, and cross-section graphs is available on request. CD-ROM
Data files and Useful Reports made from JENDL-3.3
References of JENDL-3.3
  1. K. Shibata, T. Kawano, T. Nakagawa, O. Iwamoto, J. Katakura, T. Fukahori, S. Chiba, A. Hasegawa, T. Murata,H. Matsunobu, T. Ohsawa, Y. Nakajima, T. Yoshida, A. Zukeran, M. Kawai, M. Baba, M. Ishikawa, T. Asami, T. Watanabe, Y. Watanabe, M. Igashira, N. Yamamuro, H. Kitazawa, N. Yamano and H. Takano: "Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3," J. Nucl. Sci. Technol. 39, 1125 (2002).
  2. (Eds.) T. Nakagawa, H. Kawasaki and K. Shibata: "Curves and Tables of Neutron Cross Sections in JENDL-3.3 (Part I and II)," JAERI-Data/Code 2002-020, Part I, Part II (2002).
  3. (Ed.) K. Shibata: "Descriptive Data of JENDL-3.3 (Part I and II)," JAERI-Data/Code 2002-026, Part I, Part II (2003).

Nuclear Data Center, Japan Atomic Energy Agency (JAEA)
Modified at 2014/08/28 10:15 JST

 jendl@jaea.go.jp
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