Accurate 238U neutron capture rate determinations

Measurements and analysis for reaction rate ratio of 238 U capture to 239 Pu fission (C8/ F9) and that of 238 U capture to 235 U fission (C8/ F5), which are important as indexes of breeding behavior of a fast breeder reactor, were made at Fast Critical Assembly (FCA) of Japan Atomic Energy Research Institute. The measurements were made by a foil activation technique at two assemblies simulating metallic-fueled liquid metal fast breeder reactor and an assembly simulating a MOX-fueled one. The analysis was made based on JENDL3.2 nuclear data file. Calculation to experiment ratios of C8/ F9 and C8/ F5 were 0.99-1.02 and 1.0-1.03 respectively. Furthermore, the 238 U capture rate and the 235 U fission rate were measured in a thermal neutron standard field in Heavy Water Facility of Kyoto University Research Reactor to verify accuracy of the present foil activation technique itself and to confirm these C / E values.

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Measurements of Reaction Rate Ratios as Indexes of Breeding Performance in Mock-up Cores of FCA Simulating Metallic-fueled LMFBR and MOX-fueled LMFBR

Sakurai

Nemoto

Kobayashi

et al. 1999

Journal of Nuclear Science and Technology

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Measurement and analysis of neutron capture rate of U-238 in an alternate depleted uranium/polyethylene system

Yan¹,

Liu²,

Lü³

et al. 2012

Acta Phys. Sin.

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In order to check the conceptual design of subcritical reactor, an alternate depleted uranium/polyethylene-shell simulation device was established, to carry out uranium-238 neutron capture rate experiment using activation technique. The depleted uranium foils were activated at 90o to the incident. By measuring the 277.6 keV -ray emitted from 239Np generated by 238U (n, ) 239U reaction and correcting self-absorption of uranium experimentally, the 238U (n, ) reaction rate with an uncertainty between 3.5% and 3.7% and a total neutron capture of 2.24 0.09 of the system were obtained. The experiment was simulated using MCNP5 code with ENDF libraries. The simulations and measurements accord within 5% for the 238U (n, ) reaction rate and within 1% for the total neutron capture rate of 238U.

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Accurate 238U neutron capture rate determinations

Cited by 2 publications

References 11 publications

Measurements of Reaction Rate Ratios as Indexes of Breeding Performance in Mock-up Cores of FCA Simulating Metallic-fueled LMFBR and MOX-fueled LMFBR

Measurements of Reaction Rate Ratios as Indexes of Breeding Performance in Mock-up Cores of FCA Simulating Metallic-fueled LMFBR and MOX-fueled LMFBR

Measurement and analysis of neutron capture rate of U-238 in an alternate depleted uranium/polyethylene system

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