シビアアクシデントに関する熱流動研究の最近の動向

Abstract

Research on severe accident for light water reactors has been initiated after the accident of Three Mile Island in 1979 and accelerated all over the world after the Chernobyl accident in 1986. For the severe accident management Nuclear Safety Commission of Japan recommended electric utilities to investigate the possible measures in 1992. In response to this they proposed accident management strategies based on their investigations in 1994 to be voluntarily implemented in several years by reflecting findings from severe accident research. Since the severe accident phenomena largely involve the thermal-hydraulic aspects, it is of great importance to evaluate the thermal-hydraulic behaviors of severe accident in order to reduce the associated uncertainties. In the present article thermal-hydraulic behaviors during severe accident are described in terms of phenomenology, severe accident management, key issues, research methodology and remaining research items. The main phenomena include core melt progression, in-vessel core melt behaviors, molten core coolant interaction, molten core concrete interaction, direct containment heating, hydrogen behaviors, and fission product behaviors.