EVALUATION OF THE THERMAL NEUTRON CONSTANTS OF 233-U, 235-U, 239-PU, AND 241-PU AND THE FISSION NEUTRON YIELD OF 252-CF
In 1982 a simultaneous least squares evaluation of the thermal neutron constants of 233-U, 235-U, 239-Pu, and 241-Pu together with the fission neutron yield from the spontaneous fission of 252-Cf was performed with, for the first time, a full covariance matrix for the input data. The input data set was limited in that measurements in Maxwellian reactor spectra were excluded. (A) Concurrently, a similar evaluation was performed at Brookhaven which included the Maxwellian data set but which did not have an input covariance matrix, although the more important correlations were handled by other methods. (B) In the present work the Maxwellian data from B has been added to A, and the differences between the input and output data for the various evaluations are discussed.
Bibliographic Reference: IAEA ADVISORY GROUP MEETING ON NUCLEAR STANDARD REFERENCE DATA, GEEL (BELGIUM), NOV. 12-16, 1984 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31885 ORA
Availability: Can be ordered online
Record Number: 1989123064200 / Last updated on: 1987-01-01
Available languages: en