FIELD: nuclear power.
SUBSTANCE: invention relates to nuclear power engineering and can be used to determine of heat carrier flow in channels or fuel assemblies of nuclear reactors in tests and operation thereof. Said result is achieved due to that reactor power is varied periodically at constant flow rate of heat carrier or heat carrier flow rate is varied at constant power with a period of variation, greater than sum of thermal time delay for reactor elements involved in heat exchange of channel and thermal detector.
EFFECT: technical result is higher accuracy and efficiency by excluding from delay time transport thermal delay time.
1 cl, 1 dwg
| Title | Year | Author | Number |
|---|---|---|---|
| METHOD OF DETERMINING HEAT CARRIER FLOW IN CHANNELS OF REACTOR CORE | 1986 |
|
SU1841231A1 |
| METHOD FOR MEASURING COOLANT FLOW IN PROCESS CHANNELS OF GRAPHITE-MODERATED WATER-COOLED REACTOR | 2003 |
|
RU2252461C2 |
| MEASURING METHOD OF HEAT CARRIER FLOW RATE OF FIRST CIRCUIT OF NUCLEAR REACTOR | 2011 |
|
RU2457558C1 |
| METHOD OF CORRELATION MEASURING OF ELECTROCONDUCTIVE LIQUID CONSUMPTION | 0 |
|
SU1078249A1 |
| METHOD OF DETERMINATION OF COOLANT FLOW RATE BY CHARACTERISTIC POINT OF POWER AND SPECTRAL DENSITY OF VOLTAGE OF MAGNET INDUCTION CONVERTER OF BALL FLOW METRE | 2010 |
|
RU2434206C9 |
| METHOD OF DETERMINATION OF COORDINATE OF POINT OF HEAT-TRANSFER MEDIUM BOILING IN HEATER CHANNEL | 0 |
|
SU1100548A1 |
| METHOD TO DIAGNOSE RESONANT PULSATIONS OF PRESSURE IN HIGH-POWER CHANNEL-TYPE REACTOR DISCHARGE CIRCUIT BY MEANS OF PRIMARY CONVERTER OF BALL FLOW METER STORM-32M | 2010 |
|
RU2448377C2 |
| MEASURING CHANNEL OF INTRAREACTOR MONITORING SYSTEM | 0 |
|
SU1328848A1 |
| WATER-COOLED NUCLEAR REACTOR | 1992 |
|
RU2032946C1 |
| SENSOR | 2008 |
|
RU2396612C1 |
