Published January 2002 | Version v1
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Comparison of 235U fission cross sections in JENDL-3.3 and ENDF/B-VI

  • 1. Kyushu Univ., Fukuoka (Japan)
  • 2. National Institute of Standards and Technology (United States)
  • 3. Data Engineering, Inc., Fujisawa, Kanagawa (Japan)
  • 4. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
  • 5. Los Alamos National Laboratory, Los Alamos, NM (United States)

Description

Comparisons of evaluated fission cross sections for 235U in JENDL-3.3 and ENDF/B-VI are carried out. The comparisons are made for both the differential and integral data. The fission cross sections as well as the fission ratios are compared with the experimental data in detail. Spectrum averaged cross sections are calculated and compared with the measurements. The employed spectra are the 235U prompt fission neutron spectrum, the 252Cf spontaneous fission neutron spectrum, and the neutron spectrum produced by a 9Be(d, xn) reaction. For 235U prompt fission neutron spectrum, the ENDF/B-VI evaluation reproduces experimental averaged cross sections. For 252Cf and 9Be(d, xn) neutron spectra, the JENDL-3.3 evaluation gives better results than ENDF/B-VI. (author)

Availability note (English)

Available from INIS in electronic form; Also available from JAEA; URL: http://jolisf.tokai-sc.jaea.go.jp/pdf/res/JAERI-Research-2001-058.pdf

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Additional details

Publishing Information

Imprint Pagination
36 p.
Report number
JAERI-Research--2001-058

Optional Information

Notes
22 refs., 26 figs., 4 tabs.; This record replaces 33043377