Recent status and prospects of Russian surplus weapons plutonium disposition

Kawata, Norio; Yano, Soichiro

Russian Surplus W-Pu was produced by byproducts of disarmament of nuclear weapon and recognized as a serious threat of nuclear proliferation. US and RF concluded an agreement to dispose of no less than 34 ton-Pu each in 2000. G7 countries including Japan jointed to collaborative investigation to dispose of Russian W-Pu. Relative countries have been discussing the scenario of Pu disposition mainly by burning in LWR (VVER1000) with MOX pellet fuel and FR (BN600) with MOX vipac fuel, however actual disposition work faced dead lock since estimated necessary cost is more than 3 times of pledged finance by G7 countries. JAEA has conducted to realize BN600 vipac fuel option, which is MOX vipac fuel made with W-Pu is burned in BN600 reactor, based on experiences of Pu utilization and fast reactor technology in a decade years. Technical feasibility is established through several cooperative studies with Russian Institutes. Since this option is confirmed as a low-cost and early disposition method, recently, US and RF seek to accelerate this option prior to VVER1000 option. This paper will provide a description of progress on BN600 vipac fuel option and future prospects of whole plan of Russian Surplus W-Pu disposition of 34 ton.