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AbstractAbstract
[en] New dosimetry cross-section evaluations have been made available to the reactor community. Most dosimetry-quality evaluations include a section (File 33) that defines the uncertainty and covariance matrix for the dosimetry reaction cross section. This paper compares the latest computed cross-section activities for benchmark neutron fields with experimental data. Uncertainty data is usually reported with experimental measurements. This work also presents uncertainty data for the calculated activities. The calculated uncertainty values include a full uncertainty propagation using the cross-section evaluation, energy-dependent covariance data as well as the uncertainty attributed to the knowledge of the neutron spectrum
Secondary Subject
Source
1997; 9 p; 9. international symposium on reactor dosimetry; Prague (Czech Republic); 2-6 Sep 1996; CONF-9609243--8; CONTRACT AC04-94AL85000; Also available from OSTI as DE97002466; NTIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference; Numerical Data
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INIS VolumeINIS Volume
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