Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

DETERMINATION OF THE LEAK RATES OF REACTOR CONTAINMENT VESSELS AT LOW TEST PRESSURE (in German)

Journal Article · · Atomkernenergie (West Germany) Merged with Kerntechnik to form Atomkernenerg./Kerntech. Acta Radiol. Changed to Acta Radiol.: Oncol., Radiat. Phys.
OSTI ID:4822374

During the time of construction and operation of reactor containment vessels, several leak rate tests must be performed. This is usually achieved by pumping to that pressure within the containment which is expected after an accident. This pressure, for water-cooled power reactors, may amount to several atmospheres, making tests both expensive and lengthy. By means of an analysis of the flow of gases through possible leaks in a containment, it is demonstrated that an overpressure to the order of 0.1 atm is sufficient for the determination of the leak rate. An equation is given permitting, from the value of the leak rate measured at low pressure, a safe determination of that leak rate to be expected after an accident. Moreover it is shown that the error in the determination of the leak rate will not be substantially higher at low test pressures than at high test pressures. (auth)

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-16-001201
OSTI ID:
4822374
Journal Information:
Atomkernenergie (West Germany) Merged with Kerntechnik to form Atomkernenerg./Kerntech. Acta Radiol. Changed to Acta Radiol.: Oncol., Radiat. Phys., Journal Name: Atomkernenergie (West Germany) Merged with Kerntechnik to form Atomkernenerg./Kerntech. Acta Radiol. Changed to Acta Radiol.: Oncol., Radiat. Phys. Vol. Vol: 6; ISSN ATKEA
Country of Publication:
Country unknown/Code not available
Language:
German

Similar Records

Helium leak testing of a radioactive contaminated vessel under high pressure in a contaminated environment
Conference · Tue Oct 01 00:00:00 EDT 1996 · OSTI ID:392128
USING AN ADAPTER TO PERFORM THE CHALFANT-STYLE CONTAINMENT VESSEL PERIODIC MAINTENANCE LEAK RATE TEST
Conference · Fri Jun 03 00:00:00 EDT 2011 · OSTI ID:1016385
FFTF integrated leak rate computer system
Conference · Wed Dec 31 23:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:5358573

Related Subjects

ACCIDENTS
BOILING
COMPRESSORS
CONFERENCE
CONVECTION
ECONOMICS
EFFICIENCY
EQUATIONS
ERRORS
FABRICATION
FAILURES
FLUID FLOW
FLUIDS
GAS FLOW
HEAT TRANSFER
LEAKS
LOSSES
MAINTENANCE
MEASURED VALUES
POWER PLANTS
PRANDTL NUMBER
PRESSURE
PRESSURE VESSELS
REACTOR TECHNOLOGY
REACTORS
SHELLS
SOLIDS
TESTING
THERMAL CONDUCTIVITY
VELOCITY
VESSELS
WATER COOLANT