Test report for the pressure suppression development program
Technical Report
·
OSTI ID:5664404
The test results obtained from the pressure suppression development program provide conclusive evidence that the concept is practical for reactor containment. In operation, steam would be released from a rupture in the reactor pressure vessel or the primary coolant system and flow into the dry well volume; the steam is discharged from the dry well, through vent pipes, into the water pool where it is condensed. The salient features of the system are low containment pressures and the entrainment of released fission products in the water pool. As with most new concepts there are many design considerations that can be resolved only with model or prototype testing. Two major test facilities were constructed to obtain the experimental information considered necessary for the evaluation of a pressure suppression system. Pacific Gas and Electric Co. sponsored a development program that included a large condensing test facility at the Moss Landing Power Plant of Pacific Gas and Electric Co., and a scale model transient test facility at the San Jose Plant of General Electric Co. This report presents the results of tests performed at these facilities.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Atomic Power Equipment Dept.
- DOE Contract Number:
- AC02-80ET34031
- OSTI ID:
- 5664404
- Report Number(s):
- GEAP-3143; ON: DE86013993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
DESIGN
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
POWER REACTORS
PRESSURE SUPPRESSION
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH PROGRAMS
RUPTURES
TEST FACILITIES
TESTING
THERMAL POWER PLANTS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
DESIGN
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
POWER REACTORS
PRESSURE SUPPRESSION
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH PROGRAMS
RUPTURES
TEST FACILITIES
TESTING
THERMAL POWER PLANTS