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Fundamental integral cross section ratio measurements in the thermal-neutron-induced uranium-235 fission neutron spectrum

Conference · · Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States)
OSTI ID:7194756
High-accuracy integral cross section ratio measurements have been performed in the thermal-neutron-induced uranium-235 fission neutron spectrum. This involves the basic fission reactions /sup 235/U(n,f), /sup 239/Pu(n,f), /sup 238/U(n,f) and /sup 237/Np(n,f); and the gold capture and /sup 115/In(n,n')/sup 115m/In dosimetry reactions. The uranium-235 fission neutron spectrum is generated at the center of a one meter diameter spherical cavity within a graphite thermal column. Simple and variable geometrical arrangements were used and evaluated for neutron field purity. The fission rates were determined with the NBS double fission chamber as well as with others of different size and design. All fission detectors were validated within a parallel program of interlaboratory comparisons in the MOL-..sigma sigma.. Standard Neutron Field. The activation rates have been measured with calibrated gamma-ray spectrometers. The resulting integral cross section ratios relative to the /sup 238/U(n,f) reaction are, for /sup 235/U(n,f): 3.94 +- 0.08; /sup 239/Pu(n,f): 5.93 +- 0.13; /sup 237/Np(n,f): 4.35 +- 0.13; /sup 115/In(n,n')/sup 115m/In; 0.620 +- 0.019 and; /sup 197/Au(n,..gamma..)/sup 198/Au: 0.287 +- 0.014. 5 tables, 2 figures. (auth)
OSTI ID:
7194756
Conference Information:
Journal Name: Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States) Journal Volume: 1
Country of Publication:
United States
Language:
English