FIELD: power industry.
SUBSTANCE: control method of tightness of fuel element jackets involves recording of delayed neutrons in coolant of the first circuit of a nuclear reactor by means of the first detector (1) at equal time intervals T corresponding to the time of full circulation cycle of the coolant in the first reactor circuit, measurement of intensities Ni and Ni+T of detector signals, which are proportional to neutron activity of the coolant at time moments ti and ti+T, determination of difference (Ni+T-Ni)K=ΔNK, where k - number of a subtraction procedure, comparison of difference ΔNK to value ΔNK-1. Signal of detector (1) is supplied through differential transformer (2) and amplifier (3) to discriminator (4) that provides discrimination of noises of amplifier (3), processes and converts analogue signals to standard pulses for transmission to the input of count-code converter (5). Further, signals are supplied to PC (6), where they are processed as per the specified algorithm. Fulfilment of condition ΔN≥2ΔNK-1 means depressurisation of fuel element jackets.
EFFECT: improving accuracy and reliability of control of tightness of fuel element jackets.
1 dwg
Title | Year | Author | Number |
---|---|---|---|
LEAK RESISTANCE INSPECTION APPARATUS FOR FUEL ELEMENT ENCLOSURES | 2007 |
|
RU2349976C1 |
METHOD FOR CHECKING CORE OF SHIPBOARD WATER-COOLED NUCLEAR POWER PLANT FOR CONDITION | 2006 |
|
RU2301463C1 |
METHOD FOR DETECTING DEPRESSURIZED FUEL ELEMENTS | 1994 |
|
RU2094861C1 |
METHOD FOR DETECTING LEAKY THERMAL ELEMENTS OF ASSEMBLIES OF NUCLEAR REACTOR WITH LIQUID METAL HEAT CARRIER | 2016 |
|
RU2624909C1 |
METHOD OF TIGHTNESS MONITORING AT HEAT EXCHANGE SURFACE OF STEAM GENERATOR OF REACTOR PLANT WITH HEAVY LIQUID METAL HEAT CARRIER | 2013 |
|
RU2547447C1 |
FUEL ELEMENT | 2000 |
|
RU2179751C1 |
QUICK REACTOR WITH LIQUID-METAL COOLANT | 2011 |
|
RU2456686C1 |
FUEL ELEMENT WITH COMPOSITE PROTECTIVE COATING | 2019 |
|
RU2740701C2 |
METHOD FOR DETERMINATION OF CONTENT OF BORON-10 IN HEAT CARRIER OF THE FIRST CIRCUIT OF NUCLEAR REACTOR | 1991 |
|
RU2025800C1 |
METHOD OF STEAM AND GAS GENERATORS CONTROL TIGHTNESS OF SHIP NUCLEAR ENGINE INSTALLATION WITH WATER HEAT TRANSFER MEDIUM UNDER PRESSURE | 2008 |
|
RU2352005C1 |
Authors
Dates
2015-08-20—Published
2013-09-30—Filed