JAERI 1344

ENDL Dosimetry File 99 (JENDL/D-99)

K. Kobayashi, T. Iguchi, S. Iwasaki, T. Aoyama, S. Shimakawa, Y. Ikeda, N. Odano, K. Sakurai, K. Shibata, T. Nakagawa and M. Nakazawa

Department of Nuclear Energy System
Tokai Research establishment
Japan Atomic Energy Research Institute
Tokai-mura, Naka-gun, Ibaraki-ken

The JENDL Dosimetry File 99 (JENDL/D-99), which is a revised version of the JENDL Dosimetry File 91 (JENDL/D-91), has been compiled and released for the determination of neutron flux and energy spectra. This work was undertaken to remove the inconsistency between the cross sections and their covariances in JENDL/D-91 since the covariances were mainly taken from IRDF-85 although the cross sections were based on JENDL-3. Dosimetry cross sections has been evaluated for 67 reactions on 47 nuclides together with covariances. The cross sections for 34 major reactions and their covariances were simultaneously generated, and the remaining 33 reaction data were mainly taken from JENDL/D-91. Latest measurements were taken into account in the evaluation. The resultant evaluated data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-6 format. In order to confirm the reliability of the evaluated data, several integral tests have been carried out: comparisons with average cross sections measured in fission neutron fields, fast/thermal reactor spectra, DT neutron fields and Li(d,n) neutron fields. It was found from the comparisons that the cross sections calculated from JENDL/D-99 are generally in good agreement with the measured data. The contents of JENDL/D-99 and the results of the integral tests are described in this report. All of the dosimetry cross section are shown in a graphical form in the Appendix.

Contents

1. Introduction
2. Compilation of JENDL Dosimetry File 99
  2.1 Activities of Dosimetry File Integral Test Working Group
    2.1.1 General Description of the Working Group
    2.1.2 Selection of Dosimetry Reactions
    2.1.3 Scenario of the Integral Test
  2.2 Contents of JENDL Dosimetry File 99
  2.3 Format of JENDL Dosimetry File 99
3. Integral Tests for Fission Reactors
  3.1 Comparison with IRDF-90V2
    3.1.1 Resonance Integral
    3.1.2 Average Cross Sections in Fission Neutron Fields
  3.2 Integral Test with Fission Neutron Fields
    3.2.1 Standard Neutron Fields
    3.2.2 Measured Average Cross Sections
    3.2.3 Comparison of Average Cross Section Data
  3.3 Integral Test with Reactor Neutron Fields
    3.3.1 Reactor Neutron Fields
    3.3.2 ISNF
    3.3.3 CFRMF
    3.3.4 "SigmaSigma"
    3.3.5 YAYOI
    3.3.6 JOYO
    3.3.7 JMTR
    3.3.8 Results and Discussion
4. Integral Tests for Fusion Reactors
  4.1 Integral Test in D-T Fusion Neutron Environment
    4.1.1 Neutron Fields Used in the Tests
    4.1.2 Criteria of the Test
    4.1.3 Results of the Integral Test
    4.1.4 Summary
  4.2 Integral Test Using Thick Li(d,n) Neutron Field
    4.2.1 Characteristics of Neutron Field
    4.2.2 Benchmark Experiment
    4.2.3 Average Cross Sections
    4.2.4 Results of the Integral Test
    4.2.5 Summary
5. Summary Discussion on the Integral Tests
  5.1 Integral Tests of the Dosimetry Cross Sections for Fission Reactors
  5.2 Integral Tests of the Threshold Reaction Cross Sections for Fusion Reactors
  5.3 Comparison with LOWELL Measurements
  5.4 Comparison with Decay Heat Calculations Using JNDC-V2 Library
6. Conclusion
Acknowledgements
References
Appendix: Graphs of Dosimetry Cross Sections