Research on consequence analysis method for probabilistic safety assessment of nuclear fuel facilities (2). Basic experimental data aerosol release fraction and trial analysis in boiling event to radioactive solution

A special committee on 'Research on the analysis methods for accident consequence of nuclear fuel facilities (NFFs)' was organized by the Atomic Energy Society of Japan under the entrustment of Japan Atomic Energy Agency for research on the state-of-the-art consequence analysis method for Probabilistic Safety Assessment (PSA) of NFFs, such as fuel reprocessing and fuel fabrication facilities. The objective of this research is to obtain the basic useful information related to the establishment of the quantitative performance requirement and to risk-informed regulation through qualifying issues needed to be resolved for applying PSA to NFFs. The research activities of the committee were mainly focused on accidents with more severe consequences than design basis, such as events of criticality, explosion, fire, and boiling of radioactive solution postulated in NFFs resulting in the release of radioactive materials into the environment. The research results are summarized in this technical report about basic experimental data related to key physical and chemical phenomena postulated in a boiling event of a radioactive solution storage tank caused by the loss of the cooling function. (author)