Optimization of Ap1000 Dose Equivalent I-131 Specific Activity Operating Limit

The operating limit of primary loop dose equivalent I-131 specific activity in the technical specifications of AP1000 reactor is determined based on the accident analysis assumption, and affects the discharge of radioactive effluent. The SGTR accident offsite dose and the discharge of gaseous radioactive effluent calculated according to the primary loop dose equivalent I-131 specific activity operating limit in the original AP1000 technical specifications do not meet the requirements of Chinese Standard GB6249-2011. To solve this problem, the release mechanism of iodine spike, the actual magnification of iodine spike, the operating limits and conditions, and the treatment capacity of radioactive waste treatment system are studied respectively. Through calculation, it is concluded that the iodine spike operating limit of primary loop dose equivalent I-131 specific activity can be optimized to 1.11 × 10 6 Bq/g, which can solve this problem without restricting the operation of nuclear power plant