THE EFFECT OF A SCRAM ON THE LEVEL OF HEAVY WATER IN THE PRESSURIZER OF THE PRTR
Technical Report
·
OSTI ID:4303477
The primary coolant loop of the PRTR facility is a heavy water circulating system which is pressurized by helium. The helium gas maintains a constant pressure on the system and prevents boiling of the coolant. On a complete scram, the coolant will drop in temperatare and approach the temperatare of the steam generator. This reduction in temperature will cause a contraction of the coolant volume and a corresponding drop in level in the pressurizer vessel. The change, and the rate of change of level of D/sub 2/O in the pressurizer are examined. (auth)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-13-004241
- OSTI ID:
- 4303477
- Report Number(s):
- HW-57424
- Country of Publication:
- United States
- Language:
- English
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