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U.S. Department of Energy
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Measurement of the neutron capture cross sections of the actinides

Conference · · Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States)
OSTI ID:7285356

The capture cross sections of the isotopes heavier than /sup 239/Pu are of great importance for the core physics, fuel recycle, and waste management for power reactors. Since total cross sections are not sufficient, a program for the measurement of these needed capture cross sections is being carried out at ORNL. Measurements have been almost completed on /sup 240/Pu, /sup 241/Pu, and /sup 241/Am and have been planned for /sup 242/Pu and possible /sup 237/Np and /sup 243/Am. The capture gamma-ray detector used is the ''total energy detector'' which is a modification of the Moxon-Rae detector. Fission, when present, is detected with fast neutron counters. Results obtained on /sup 240/Pu, /sup 241/Pu, and /sup 241/Am will extend continuously from thermal neutron energies to 350 keV. The cross sections are normalized at thermal neutron energies and the neutron flux is measured relative to the /sup 10/B(n,..cap alpha..) cross section up to 2 keV and /sup 6/Li(n,..cap alpha..) at higher neutron energies. The accuracy of the techniques used varies with the sample but is about 8 percent. With such cross sections the long range management of the actinides produced in power reactors can be planned on a more systematic basis. 4 figures. (auth)

Research Organization:
Oak Ridge National Lab., TN
OSTI ID:
7285356
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