Research on Fuel Cladding Failure Temperature Criteria and Gap Release Radioactive Aftereffect for LOCA of Ship Reactor

Aiming at the particular safety requirement of ship reactor, the research on fuel cladding failure temperature criteria for LOCA was carried out. The conservative assumption was abandoned, the reasonable fuel cladding failure temperature criteria was gained with the best estimate model, and the fraction of failure and gap release radioactive aftereffect were calculated by MELCOR code. The calculation results can give a reference for evaluating cabin dose and ensuring the safety for operators.