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The relationship between integral experimental data and nuclear fission parameters [electronic resource].

Published
Argonne, Ill. : Argonne National Laboratory, 1989.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 32 : digital, PDF file
Additional Creators
Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
High sensitivities of critical assembly and reactor design parameters to the fission cross sections, prompt and delayed neutron yields, and fission spectra parameters have resulted in an important role of experimental integral data for the testing and verification of differential data and computational methods. The higher accuracy of the experimental integral data compared with the uncertainties of reactor parameters which result from the uncertainties of the differential data has led to their utilization in data adjustment procedures. Improvements of up to a factor of ten are obtained for reactor parameters, however, the uncertainties of the basic data are reduced by smaller amounts. Other integral data like the fission spectra averaged cross sections are used for the evaluation of cross sections and fission spectra. 33 refs., 4 figs., 4 tabs.
Report Numbers
E 1.99:conf-890406-17
conf-890406-17
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
01/01/1989.
"conf-890406-17"
"DE89012394"
Fifty years with nuclear fission conference, Gaithersburg, MD, USA, 25 Apr 1989.
Poenitz, W.P.
Funding Information
W-31109-ENG-38
View MARC record | catkey: 14369458