| 摘要 |
PROBLEM TO BE SOLVED: To provide a small LOCA safety evaluation method capable of evaluating a small LOCA phenomenon in a next generation reactor. SOLUTION: In this small LOCA safety evaluation method for evaluating safety at the small LOCA time by using an analytical code, which is a safety evaluation method for a pressurized water reactor wherein a primary coolant heated by the core heats a secondary coolant through heat exchanger tubes of a steam generator, the analytical code calculates a distribution of non-condensable gas in the primary system. COPYRIGHT: (C)2005,JPO&NCIPI
|
