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超臨界圧軽水冷却高速炉の大出力化の検討

A Design study of high electric power for fast reactor cooled by super critical light water

越塚 誠一*

Koshizuka, Seiichi*

超臨界圧軽水冷却高速炉の大出力化の可能性を検討するため、大型の高温超臨界圧軽水冷却高速炉(SCFR-H)の設計研究を行った。臨界圧軽水冷却炉は現在の火力ボイラーの主流である貫流型直接サイクルを採用し、超臨界水を冷却材とすることで、現行の軽水炉と比較してシステムの大幅な簡素化、コンパクト化および熱効率の向上が可能になる概念である。本検討にて、ブランケット上昇流冷却型SCFR-H、ブランケット下降流型SCFR-H及び高出力型SCFR-Hの3種類の炉心を設計した。いずれも熱効率が43%を超え、冷却材密度係数を正に保ちつつ電気出力1600MWを上回る概念である。熱中性子炉であるSCLWR-H(電気出力1212MW)と、同一の原子炉圧力容器内径の条件の下に比較検討し、電気出力で最大約1.7倍増加できることが示された。出力増大という観点からは、燃料配置を稠密にできる高速炉の方が、十分な減速材領域を必要とする熱中性子炉よりも出力密度を高めることができるため有利である。すなわち、超臨界圧軽水冷却炉では、高出力を目指した高速炉にすればさらに経済性が向上すると結論できる。

In order to evaluate the possibility to achieve high electric power by a fast reactor with supercritical light water, the design study was carried out on a large fast reactor core with high coolant outlet temperature (SCFR-H). Since the reactor coolant circuit uses once-through direct cycle where all feedwater flows through the core to the turbine at supercritical pressure, it is possible to design much simpler and more compact reactor systems and to achieve higher thermal efficiency than those of current light water reactors. The once-through direct cycle system is employed in current fossil-fired power plants. In the present study, three types of core were designed. The first is SCFR-H with blankets cooled by ascending flow, the second is SCFR-H with blankets cooled by descending flow and the third is SCFR-H with high thermal power. Every core was designed to achieve the thermal efficiency over 43%, positive coolant density reactivity coefficient and electric power over 1600MW. Core characteristics of SCFR-Hs were compared with those of SCLWR-H (electric power: 1212MW), which is a thermal neutron spectrum reactor cooled and moderated by supercritical light water, with the same diameter of the reactor pressure vessel. It was shown that SCFR-H could increase the electric power about l.7 times maximally. From the standpoint of the increase of a reactor thermal power, a fast reactor has advantages as compared with a thermal neutron reactor, because it can increase the power density by adopting tight fuel lattices and eliminating the moderator region. Thus, it was concluded that a reactor cooled by supercritical light water could further improve the cost competitiveness by using a fast neutron spectrum and achieving a higher thermal power.

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