CA774693A - Method and apparatus for increasing the critical heat flux for high pressure steam/water flow in nuclear reactors - Google Patents

Method and apparatus for increasing the critical heat flux for high pressure steam/water flow in nuclear reactors

Info

Publication number
CA774693A
CA774693A CA774693DA CA774693A CA 774693 A CA774693 A CA 774693A CA 774693D A CA774693D A CA 774693DA CA 774693 A CA774693 A CA 774693A
Authority
CA
Canada
Prior art keywords
increasing
high pressure
water flow
pressure steam
heat flux
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
Inventor
A. Wikhammer George
P. L. Macdonald Ian
G. Collier John
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Atomic Energy of Canada Ltd AECL
Original Assignee
Atomic Energy of Canada Ltd AECL
Publication date
Application granted granted Critical
Publication of CA774693A publication Critical patent/CA774693A/en
Expired legal-status Critical Current

Links

CA774693D Method and apparatus for increasing the critical heat flux for high pressure steam/water flow in nuclear reactors Expired CA774693A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA774693T

Publications (1)

Publication Number Publication Date
CA774693A true CA774693A (en) 1967-12-26

Family

ID=36221978

Family Applications (1)

Application Number Title Priority Date Filing Date
CA774693D Expired CA774693A (en) Method and apparatus for increasing the critical heat flux for high pressure steam/water flow in nuclear reactors

Country Status (1)

Country Link
CA (1) CA774693A (en)

Similar Documents

Publication Publication Date Title
CA918314A (en) Nuclear reactor coolant flow device
AT270014B (en) Pressure equalization device for equalizing pressure fluctuations in the primary circuit of pressurized water reactors
CA774693A (en) Method and apparatus for increasing the critical heat flux for high pressure steam/water flow in nuclear reactors
CA918315A (en) Coolant flow regulation in pressure tube nuclear reactor
CA763041A (en) Heat exchange apparatus and nuclear reactor designed for the use of said apparatus
IL30190A0 (en) Method and device for regulating the quantity of thermal energy exchanged between two separate fluids
JPS5359933A (en) Electric heater
CA785383A (en) Method and apparatus for increasing burnout heat flux in reactor pressure tubes
ATA1025572A (en) DEVICE FOR DEGASSING LOW RADIOACTIVE CONDENSATE IN NUCLEAR POWER PLANTS
Guéron The treatment of uncertainties in the thermal design of nuclear reactors
CA771475A (en) Method and apparatus for cooling and humidifying a hot gas flow
CA915833A (en) Coolant flow regulation in pressure tube nuclear reactor
CA750723A (en) Method and apparatus for transferring fluid offshore
GB1199968A (en) Water Conditioning Method and Apparatus
CA702198A (en) Nuclear reactor pressure vessel and heat exchanger supporting systems
AU409298B1 (en) Heat exchanging method and apparatus
CA730760A (en) Methods and apparatus for removing heat and water from a fuel cell
CA886244A (en) Control of pressure in primary coolant system of nuclear reactor
CA853899A (en) Apparatus and method for automatic mutual adjustment of the pressure of a liquid moderator and coolant gas flowing through a nuclear reactor
CA734731A (en) Apparatus and method for starting forced flow once-through steam generating power plant
CA812999A (en) Device for operating neutron-absorbing rods in nuclear reactors
CA641500A (en) Method and apparatus for controlling fuel and/or feedwater flow in a once-through steam generator
CA801293A (en) Device in a nuclear reactor of the boiling water type
CA656455A (en) Apparatus for detecting radiation in a fluid
CA801294A (en) Internal steam separation, pumping and flow path in boiling water reactors