STEAM SEPARATION TECHNOLOGY UNDER THE EURATOM PROGRAM. Quarterly Progress Report, January 1, 1963-March 31, 1963

Technical Report · Wed Apr 10 04:00:00 EST 1963

DOI:https://doi.org/10.2172/4690174· OSTI ID:4690174

For purposes of analysis and experiment the centrifugal type downflow separator was divided into the inlet nozzle, separating zone, and outlet nozzle. The analysis and experiments have resulted in a new outlet design, a method of determining separating length, and a more effective inlet nozzle. The results have caused a reduction in pressure loss from 5 ft of water for the reference design to 1.5 ft of water for the new design at a flow rate of 1400 gpm. A reactor core riser and downcomer region was mocked-up in the large air-water tank. Void fraction in the downcomer region was measured as a function of water velocity, water temperature, inlet gas flow rate, and riser geometry. Results show that the void fraction in the downcomer is essentially zero until a threshold downcomer velocity is reached. The void fraction then rises rapidly with increasing water velocity to approximately l1% and then appears to remain constant. Test data from this experiment are being correlated using a dimensional analysis technique. An initial prediction equation was developed. (auth)

• Research Organization: Allis-Chalmers Mfg. Co. Atomic Energy Div., Milwaukee
• NSA Number: NSA-17-023457
• OSTI ID: 4690174
• Report Number(s): ACNP-63013; EURAEC-624
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

AIR
ENGINEERING AND EQUIPMENT
EQUATIONS
EURATOM
GAS FLOW
LOSSES
MOCKUP
PLANNING
PRESSURE
REACTOR CORE
STEAM
TESTING
VELOCITY
VESSELS
WATER