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Fission cross section ratios in the /sup 252/Cf neutron spectrum (/sup 235/U: /sup 238/U /sup 239/Pu: /sup 237/Np)

Conference · · Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States)
OSTI ID:7285349

In a /sup 252/Cf neutron field, ratios of spectrum-averaged fission cross sections have been measured by back-to-back counting in a double fission ionization chamber with interchangeable deposits of /sup 235/U, /sup 238/U, /sup 239/Pu, and /sup 237/Np. These ratio measurements provide integral tests for evaluated cross section data. The dominant error in the ratio measurements was the +-1.4 percent to +-2.1 percent uncertainty in the fissionable deposit masses. Redundant mass assay methods were employed for all deposit nuclides. Corrections of up to (1.4 +- 0.7) percent were necessary for inelastic scattering effects on the neutron energy distribution in the cases of /sup 238/U and /sup 237/Np. For /sup 235/U and /sup 239/Pu fission rates, a correction of (0.45 + 0.20) percent was made for the contribution of neutrons moderated and back-scattered by laboratory structures. The cross section ratios observed in the present measurements were as follows: 1.000: 0.266 +- 1.7 percent: 1.500 +- 1.6 percent: 1.105 +- 2.2 percent for /sup 235/U: /sup 238/U: /sup 239/Pu: /sup 237/Np, respectively. In comparison to the observed integral cross section ratios, the corresponding values derived from ENDF/B-IV data were 2.3 percent to 6.0 percent lower. 4 tables, 1 figure. (auth)

Research Organization:
National Bureau of Standards, Washington, DC
OSTI ID:
7285349
Journal Information:
Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States), Journal Name: Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States) Vol. 1; ISSN XNBSA
Country of Publication:
United States
Language:
English