The fission cross sections of /sup 230/Th, /sup 232/Th, /sup 233/U, /sup 234/U, /sup 236/U, /sup 238/U, /sup 237/Np, /sup 239/Pu and /sup 242/Pu relative /sup 235/U at 14. 74 MeV neutron energy
The measurement of the fission cross section ratios of nine isotopes relative to /sup 235/U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for /sup 235/U are: /sup 230/Th - 0.290 +- 1.9%; /sup 232/Th - 0.191 +- 1.9%; /sup 233/U - 1.132 +- 0.7%; /sup 234/U - 0.998 +- 1.0%; /sup 236/U - 0.791 +- 1.1%; /sup 238/U - 0.587 +- 1.1%; /sup 237/Np - 1.060 +- 1.4%; /sup 239/Pu - 1.152 +- 1.1%; /sup 242/Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6769505
- Report Number(s):
- ANL/NDM-97; ON: DE87005541
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Neutron induced fission cross sections for /sup 232/Th, /sup 235,238/U, /sup 237/Np and /sup 239/Pu from 1 to 400 MeV
FISSION CROSS-SECTIONS OF U$sup 238$, U$sup 235$, Pu$sup 233$, Pu$sup 239$# AND Th$sup 232$ FOR 14 Mev NEUTRONS
Related Subjects
FISSION
CROSS SECTIONS
NEUTRON REACTIONS
DATA COVARIANCES
EVALUATED DATA
EXPERIMENTAL DATA
MEV RANGE 10-100
NEPTUNIUM 237 TARGET
NUCLEAR DATA COLLECTIONS
PLUTONIUM 239 TARGET
PLUTONIUM 242 TARGET
THORIUM 230 TARGET
THORIUM 232 TARGET
URANIUM 233 TARGET
URANIUM 234 TARGET
URANIUM 235 TARGET
URANIUM 236 TARGET
URANIUM 238 TARGET
BARYON REACTIONS
DATA
ENERGY RANGE
HADRON REACTIONS
INFORMATION
MEV RANGE
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
TARGETS
652020* - Nuclear Properties & Reactions
A=220 & above
Experimental