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Report No.
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Analysis of reduced sodium void reactivity core and improved Doppler reactivity core by utilizing the threshold reaction

not registered; Kawashima, Masatoshi*; not registered; Yamaoka, Mitsuaki*; Fujita, Reiko*

In the first reactor, sodium void reactivity and and sodium coolant temperature reavtivity are increased, and Doppler coefficient is decreased when MA is recycled. It is important to improve these reactivities in terms of safety features. In the study, Analysis was conducted of the effect on the sodium void reduction without deteriorating the core performance by mixing nuclides that give large absorption reactions in the higher energy region, where neutrons are increased at the neutron spectrum is hardened. Effect of higher Pu isotopes was also analyzed with parameters for improving Doppler coefficient. In the analysis of reduced sodium void reactivity core usig the threshold reaction, dominant energy region was identified for the sodium void reactivity by analyzing the core neutron spectra with parameters of MA mixing and core size. Furthermore, effect on reducing void reactivity was analyzed with parameters of inventory amounts and kinds of absorber nuclides. As a result, it was found that the sodium void reactivity of the MOX core with oxide-17 was about half of that of the core with natural oxide. In the analysis of reduced Doppler reactivity core, effect of improving the Doppler effect was analyzed for the nitride fuel core with higher Pu isotopes and resonance absorbers. Applicability and properties required for core analysis were also examined for candidates of base inert material, and the properties of fuel with those materials were preliminary surveyed. As a result, it was found that characteristics including Doppler coefficients can be improved with nuclides of structure material as metal form.

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