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受動的安全性を強化した大型FBRプラント

A Design study on a large FBR plant enhancing passive safety

林 秀行; 一宮 正和; 永沼 正行 

Hayashi, Hideyuki; not registered; not registered

水素化ジルコニウム添加によりドップラー係数を強化したスペクトル調整窒化物燃料炉心を採用した130万kWe級大型FBRプラント概念を構築した。炉心設計においては、水素化ジルコニウムの添加割合を最適化することにより、径ブランケット層数1層の条件で増殖比1.2を満足できた。また、炉心径の縮小により原子炉構造設計への負担が軽減された。炉心安全性については、流量喪失スクラム失敗事象(ULOF)及び過出力スクラム失敗事象(UTOP)に対しても炉心固有の反応度特性のみで冷却材沸騰を防止できており、固有安全炉心と呼べるレベルにまで安全性が向上されている。また、ヘッドアクセスループ型炉に特有の部位についての過渡時熱応力、地震時変位及び流量急減時の炉心支持板変位等を評価してプラントの健全性を総合的に確認した。主要設備物量から建設コストの予測を行った結果、同じ出力の軽水炉を100とした時に、本大型FBRプラントの建設コストは130$$sim$$140であることが示された。

A conceptual design study on a 1300MWe large FBR plant was performed with focusing on enhancing passive safety and capital cost reduction. Spectrum-adjusted mixed nitride fueled core in which zirconium hydride was added, was applied to enlarge Doppler reactivity coefficient. Breeding ratio of 1.2 was obtained only with one layer of radial blanket subassemblies by optimizing the content of the zirconium hydride. The optimization also lightened the burden to the reactor structure through the reduction of the core diameter. Reactor passive shutdown were performed in the ATWS events of ULOF and ULOHS, and UTOP caused by one control rod full runout was endurable under the criterion of the prevention of coolant boiling. The safety feature can be called as inherent safety, because the feature comes only from the reactivity characteristics of the core. The integrities of the reactor structures which characterize head-access loop type reactor were evaluated on the transient thermal stress at the loss of flow accident and on seismic strain. Vertical strain of core support plate at loss of flow condition was also evaluated on the passive shutdown at ULOF. The capital cost of the large FBR plant was estimated 1.3 to 1.4 times as high as that of the same scale LWR based on the weight of major components.

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