Integral data evaluation of stainless steel, /sup 239/Pu, /sup 240/Pu, and H/sub 2/O for homogeneous plutonium systems [electronic resource].
- Columbus, Ohio : Battelle Memorial Institute, 1979. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Additional Creators:
- Battelle Memorial Institute and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Theory-experiment correlations of plutonium-fueled systems using ENDF/B cross-section data have discrepancies which could be due to cross-section data, theoretical methods, and/or interpretation of the experiment. Analyses of homogeneous plutonium critical experiments were performed to determine where cross section deficiencies may exist. New thermal cross-section data (0.3 eV) were generated for /sup 239/Pu and /sup 240/Pu capture, fission, and neutrons per fission. Two scattering kernels for hydrogen bound in water were also generated. Calculated values of k/sub eff/ using these new data were compared with corresponding values using ENDF/B-IV data. The results indicate that the /sup 240/Pu resonance data are sufficiently well known for hydrogen-moderated plutonium systems. In systems using stainless steel as structural and/or neutron control, a large fraction of the neutron absorptions occur in the stainless steel. Analyses of several systems containing stainless steel indicate that the uncertainty in calculated values of k/sub eff/ is small using current estimates of the uncertainties in the cross sections. 20 figures, 30 tables.
- Published through SciTech Connect., 08/01/1979., "nureg/cr-0965", " pnl-3071", and Jenquin, U.P.; Thompson, J.K.; Kottwitz, D.A.; Trapp, T.J.
- Funding Information:
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