Pressure-tube blockage analysis of N Reactor
Technical Report
·
OSTI ID:719910
A 100% blockage of a pressure tube connector with the reactor at full power was analyzed. The blockage leads to fuel heatup, melting of the fuel and subsequent failure of the pressure tube. Two cases were studied, one with the connector remaining blocked throughout the transient, and one with the blockage clearing when the pressure tube fails. The analysis showed that the reactor scrams normally due to low pressure tube flow. The coolant from the break is released into the reactor graphite moderator where the reactor gas vent system directs the released coolant into the confinement. The Emergency Core Cooling System (ECCS) does not actuate. There is no danger to the biological shield. 11 refs., 40 figs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States); Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 719910
- Report Number(s):
- WHC-SP--0260; ON: TI89021302
- Country of Publication:
- United States
- Language:
- English
Similar Records
In-core pressure tube rupture at N Reactor
Small break LOCA [Loss-of-Coolant Accidents] analysis for the N Reactor
Blocked tube transient and failure analysis
Technical Report
·
Sat Jul 01 00:00:00 EDT 1989
·
OSTI ID:719915
Small break LOCA [Loss-of-Coolant Accidents] analysis for the N Reactor
Technical Report
·
Thu Jun 01 00:00:00 EDT 1989
·
OSTI ID:719908
Blocked tube transient and failure analysis
Technical Report
·
Tue Sep 12 00:00:00 EDT 1978
·
OSTI ID:6563192