Reactivity control capability of fuel-salt processing system in a molten-salt breeder reactor.

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概要

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• An evaluation is made of the reactivity control capability of the fuel processing sys-tem (FPS) in a molten-salt breeder reactor. The principal functions required of the FPS are : (a) Isolation of 233Pa from regions of high neutron flux during its decay to 233U, and (b) the removal of fission products from the system. The FPS can very use-fully serve also to control the primary system reactivity by appropriately utilizing its function of extracting uranium and reconstituting the fuel contained in the salt. The principles of operation are quite similar to the chemical shim control system currently installed in PWR's whereby the core reactivity, affected by changes in the moderator temperature, fuel burnup and transient Xe, is adjusted by regulating the concentration of boric acid introducted in the moderator as neutron absorber. The present study ex-amines the capability of the FPS to follow transient Xe as in PWR's, and proves that the FPS should effectively serve as a system for adjusting not only long-term changes in reactivity but also short-term transient variations without any accompanying difficulties foreseen in operation.

• 一般社団法人 日本原子力学会の論文

著者

• SHIMAZU Yoichiro

  Mitsubishi Atomic Power Ind., Inc.

関連論文

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• Real Time Measurement of Large Negative Reactivities by a Modified Digital Reactivity Meter.
• Nuclear safety analysis of a molten salt breeder reactor.
• A New Method of Estimation for Moderator Temperature Coefficient Using Fourier Transform.
• Reactivity control capability of fuel-salt processing system in a molten-salt breeder reactor.

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