Analysis of Mixed Oxide Fuel Loaded Cores in the Heavy Water Reactor FUGEN

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概要

• 論文の詳細を見る

• Uranium-plutonium mixed oxide (MOX) fuel cores in the heavy water reactor, FUGEN, were analyzed using the Advanced Thermal Reactor (ATR) type core design code system WIMS-ATR/POLESTAR and the accuracy of this code system also has been evaluated by means of operational data through the 34 burnup cycles and on-site γ-scanning data. The root mean square errors of calculated thermal neutron flux distributions were less than 5% compared with the power calibration monitor traverse data. The root mean square error of calculated power distributions was less than 4% compared with the γ-scanning data. The root mean square error of calculated burnup distributions was less than 3% compared with the γ-scanning data. The averaged effective multiplication factor was 1.000 and its standard deviation was 0.002. The calculation accuracy of void reactivity coefficient was ±3×10−5 Δk⁄k⁄%void for the equilibrium cores. The calculation accuracy of power coefficient was ±1.5×10−5Δk⁄k⁄%power. The accuracy of ATR type core design code system was enough for the core management in the Fugen Nuclear Power Station.

• 一般社団法人 日本原子力学会の論文
• 2003-11-25

著者

• Iijima Takashi

  Fugen Nuclear Power Station Japan Nuclear Cycle Development Institute

• Iijima T

  Japan Nuclear Cycle Dev. Inst. (jnc) Fukui

• OHTANI Tsukasa

  Fugen Nuclear Power Station, Tsuruga Head Office, Japan Nuclear Cycle Development Institute

• SHIRATORI Yoshitake

  Tokyo Office, Japan Nuclear Cycle Development Institute

• Ohtani Tsukasa

  Fugen Nuclear Power Station Tsuruga Head Office Japan Nuclear Cycle Development Institute

• Shiratori Yoshitake

  Tokyo Office Japan Nuclear Cycle Development Institute

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• Analysis of Mixed Oxide Fuel Loaded Cores in the Heavy Water Reactor FUGEN

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