Evaluation and Testing of n + 239Pu Data for ENDF/B-VI in the KeV and MeV Energy Regions

  • P. G. Young
  • R. E. MacFarlane
Conference paper
Part of the Research Reports in Physics book series (RESREPORTS)


A new analysis of neutron-induced reactions on 239Pu above En = 20 keV was performed as part of the evaluation activity for Version VI of ENDF/B. This study merges results from a new theoretical analysis of n + 239Pu reactions with covariance analyses of experimental data for the 239Pu total and (n,f) cross sections and for the prompt fission neutron multiplicity. The results of this study are combined with a new analysis of the resolved and unresolved resonance regions of 239Pu to produce a new evaluation spanning the incident neutron energy range 10−5 eV to 20 MeV. Preliminary data testing calculations for several fast critical assemblies were performed in conjunction with the evaluation.


239Pu neutron reactions data evaluation covariance analysis benchmark data testing 


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  1. 1.
    Experimental data available from the CSISRS compilation by the National Nuclear Data Center, Brookhaven National Laboratory.Google Scholar
  2. 2.
    A. D. Carlson, W. P. Poenitz, G. M. Hale, and R. W. Peelle, in Proc. Int. Conf Nucl. Data for Basic and Applied Science, Santa Fe, N.M. (Gordon and Breach Sci. Publ., 1986) v.2, p. 1429; R. Peelle and H. Conde, in Proc. Int. Conf on Nucl. Data for Science and Tech., Mito, Japan, 30 May-3 June 1988 [Ed. S. Igarasi, Saikon Publishing. Co., Ltd., Toyko, 1988], p. 1005.Google Scholar
  3. 3.
    H. Derrien and G. de Saussure, Oak Ridge National Laboratory reports ORNL/TM-10986 (1989) and ORNL/TM-11490 (1990).Google Scholar
  4. 4.
    P. G. Young and E. D. Arthur, Proc. Int. Conf. Nuclear Data For Science and Technology, Jülich, Germany, 13-17 May 1991 (to be issued).Google Scholar
  5. 5.
    P. W. Lisowski, J. L. Ullmann, S. J. Balestrini, A. O. Carlson, O. A. Wasson, and N. W. Hill, “Neutron-Induced Fission Cross-Section Ratios for 232Th, 235,238U, 237Np, and 239pu from 1 to 400 MeV,” Proc. Int. Conf. Nucl. Data for Science and Technology, Mito, Japan, May 30-June 3, 1988 (Ed. S. Igarasi Saikon Publ. Co., Ltd., 1988) p. 97.Google Scholar
  6. 6.
    J. W. Meadows, Nucl. Sci. Eng. 85, 271 (1983); J. W. Meadows, Ann. Nucl. En. 15,421 (1988).Google Scholar
  7. 7.
    H. Alter, R. G. Kidman, R. J. LaBauve, R. Protsik, and B. A. Zolotar, “ENDF-202:Cross Section Evaluation Working Group Benchmark Specifications,” Brookhaven Nat. Lab. report BNL-19302 (ENDF-202).Google Scholar
  8. 8.
    D. MrHetrick and C. Y. Fu, “GLUCS: A Generalized Least-Squares Program for Updating Cross-Section Evaluations with Correlated Data Sets,” Oak Ridge National Laboratory report ORNL/TM-7341 (1980).Google Scholar
  9. 9.
    R. E. MacFarlane, D. W. Muir, and R. M. Boicourt, “The NJOY Nuclear Data Processing System, Volume I: User’s Manual,” Los Alamos National Laboratory report LA-9393-M, Vol. I (ENDF-324) (1982).Google Scholar

Copyright information

© Springer-Verlag Berlin Heidelberg 1992

Authors and Affiliations

  • P. G. Young
    • 1
  • R. E. MacFarlane
    • 1
  1. 1.Theoretical Division MS B243Los Alamos National LaboratoryLos AlamosUSA

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