EVALUATION OF THERMAL NEUTRON CONSTANTS OF 233-U, 239-PU AND 241-PU AND THE FISSION NEUTRON YIELD OF 252-CF
The thermal neutron constants comprise the thermal neutron (2200 m.sU-1) absorption and fission cross sections, nu (total number of neutrons emitted per fission), and eta (total number of neutrons emitted per neutron captured) for the nuclides 233-U, 235-U, 239-Pu, and 241-Pu. nu for 252-Cf is included because it is widely used as a standard for the measurement of nu for neutron induced fission of the other nuclides. The importance of these data stems from the role they play in the prediction of the neutron economy in nuclear power reactors. The continued appearance of new data has prompted a continuous reevaluation of the data over the years. Owing to the correlated nature of the measurements these evaluations necessarily take the form of simultaneous least squares fits to all the data together with updating older data in terms of newer values for standard cross sections half lives etc.
Bibliographic Reference: EUROPEAN APPLIED RESEARCH REPORTS, NUCLEAR SCIENCE AND TECHNOLOGY SECTION, VOL. 5, NO. 4, PP 609-676, 1984. (EUR 8805 E)
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Record Number: 1989122064900 / Last updated on: 1987-01-01
Available languages: en