THE EFFECT OF HELIUM SOLUBILITY IN WATER ON AN EMERGENCY SHUTDOWN OF THE PRTR
Technical Report
·
OSTI ID:4287866
The calculations indicate that on an emergency shutdown, with loss of primary coolant circulation, the hellum solubillty will show a marked decrease between ten and fifteen minutes after the initiation of the scram. The decrease in solubillty, if equillbrium is assumed, will release 4.0 cubic feet of gas at the conditions existing in the primary coolant system. This quantity of hellum, if trapped at the high polat in the system, could establish a gas block that could not be overcome by natural convection circulation. Slowing or stopping of the circulation would cause the coolant to boil in the process tube. However, with all of the process tubes connected in parallel, it is difficult to predict accurately the conditions in a particular tube and it is recommended that farther consideration be given to this problem. A properly scheduled variation in total pressure on emergency shutdown could prevent the helium release indicated above. It is recommended that this be given consideration in planning the reactor operation. Another effect of the change of helium solubility with temperature is that in normal operation passage or primary coolant through the process tubes with attendant heating causes a reduction in the helium solubility. This amounts to a value of 7.4% void fraction at the outlet of the process tubes if equilibrium is assumed. (auth)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- NSA Number:
- NSA-13-003383
- OSTI ID:
- 4287866
- Report Number(s):
- HW-57376
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
THE EFFECT OF A SCRAM ON THE LEVEL OF HEAVY WATER IN THE PRESSURIZER OF THE PRTR
An integrated safe shutdown heat removal system for light water reactors
Control of cobalt-58 dissolution during refueling shutdowns of pressurized water reactors using a hydrogen peroxide addition
Technical Report
·
Fri Sep 12 00:00:00 EDT 1958
·
OSTI ID:4303477
An integrated safe shutdown heat removal system for light water reactors
Technical Report
·
Sat May 01 00:00:00 EDT 1976
·
OSTI ID:7306559
Control of cobalt-58 dissolution during refueling shutdowns of pressurized water reactors using a hydrogen peroxide addition
Journal Article
·
Tue Jan 31 23:00:00 EST 1978
· Nucl. Technol.; (United States)
·
OSTI ID:5190405
Related Subjects
ACCIDENTS
BOILING
CONVECTION
COOLANT LOOPS
EQUATIONS
ERRORS
EVAPORATION
FAILURES
FLUID FLOW
GASES
HEAT TRANSFER
HEATING
HELIUM
HIGH TEMPERATURE
LEAKS
NUMERICALS
PLANNING
PLUTONIUM
PRESSURE
PRESSURE VESSELS
PRTR
REACTOR CORE
REACTOR SAFETY
REACTORS
REPROCESSING
SHUTDOWN
SOLUBILITY
STABILITY
TEMPERATURE
TUBES
VOLUME
WATER
WATER COOLANT
BOILING
CONVECTION
COOLANT LOOPS
EQUATIONS
ERRORS
EVAPORATION
FAILURES
FLUID FLOW
GASES
HEAT TRANSFER
HEATING
HELIUM
HIGH TEMPERATURE
LEAKS
NUMERICALS
PLANNING
PLUTONIUM
PRESSURE
PRESSURE VESSELS
PRTR
REACTOR CORE
REACTOR SAFETY
REACTORS
REPROCESSING
SHUTDOWN
SOLUBILITY
STABILITY
TEMPERATURE
TUBES
VOLUME
WATER
WATER COOLANT