[[abstract]]Reports on a series of small-break LOCA analyses for a typical Westinghouse 3-loop PWR, with a large, dry containment, using the MAAP 3.0 code. Calculations include a presumed base case study, sensitivity studies, and operator actions for S2DJ and S2WH accidents. The analyses cover both primary-system and containment responses. The calculated results show that in certain cases, containment spray (after reactor vessel failure) would result in the early occurrence of global burns. An early containment spray (before vessel failure) would cause an earlier vessel failure time in the S2WH accident. In some S2DJ cases, a small LOCA break area may mean an earlier vessel failure time compared with that in the cases with large LOCA breaks...
In the case of total failure of the high pressure injection (HPI) system following small break loss ...
The consequences of sever reactor accident depend greatly on containment safety features and contain...
The consequences of sever reactor accident depend greatly on containment safety features and contain...
[[abstract]]This paper reports on a small-break loss-of-coolant accident (LOCA) analysis for Taipowe...
[[abstract]]Responses of a large, dry pressurized water reactor (PWR) containment in a station black...
[[abstract]]Using a typical Westinghouse 3-loop PWR plant (with a large, dry containment) as the obj...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
[[abstract]]According to Maanshan Unit 1 plant probabilistic risk assessment (PRA), the small loss-o...
[[abstract]]The long-term responses of the reactor coolant system and the containment of a boiling w...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
Small-Break loss of coolant issue was highlighted in 1979, after the Three Mile Island accident. The...
Small-Break loss of coolant issue was highlighted in 1979, after the Three Mile Island accident. The...
Small-Break loss of coolant issue was highlighted in 1979, after the Three Mile Island accident. The...
A postulated double-ended guillotine break of a direct-vessel-injection line in an AP600 plant has b...
International audienceThe safety analysis of the PWR plants requires to assess the consequences of a...
In the case of total failure of the high pressure injection (HPI) system following small break loss ...
The consequences of sever reactor accident depend greatly on containment safety features and contain...
The consequences of sever reactor accident depend greatly on containment safety features and contain...
[[abstract]]This paper reports on a small-break loss-of-coolant accident (LOCA) analysis for Taipowe...
[[abstract]]Responses of a large, dry pressurized water reactor (PWR) containment in a station black...
[[abstract]]Using a typical Westinghouse 3-loop PWR plant (with a large, dry containment) as the obj...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
[[abstract]]According to Maanshan Unit 1 plant probabilistic risk assessment (PRA), the small loss-o...
[[abstract]]The long-term responses of the reactor coolant system and the containment of a boiling w...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
Small-Break loss of coolant issue was highlighted in 1979, after the Three Mile Island accident. The...
Small-Break loss of coolant issue was highlighted in 1979, after the Three Mile Island accident. The...
Small-Break loss of coolant issue was highlighted in 1979, after the Three Mile Island accident. The...
A postulated double-ended guillotine break of a direct-vessel-injection line in an AP600 plant has b...
International audienceThe safety analysis of the PWR plants requires to assess the consequences of a...
In the case of total failure of the high pressure injection (HPI) system following small break loss ...
The consequences of sever reactor accident depend greatly on containment safety features and contain...
The consequences of sever reactor accident depend greatly on containment safety features and contain...