FIELD: power engineering.
SUBSTANCE: reactor vessel steel samples are heated to temperature from 300°C, their further ageing is carried out at this temperature within certain time, subsequent tests of samples are carried out for impact bending, and test results are analysed to determine the value of the shift of critical brittleness temperature, at the same time samples of reactor vessel steel in process of ageing at the temperature of reactor vessel operation of 300-320°C are additionally exposed to neutron radiation with flux of 1011-1013 n/cm2·sec for 103 hours, after that they perform baking at the temperature of 400-450°C with duration of at least 30 hours, and assessment of extent of steel embrittlement is determined using the value of shift of critical brittleness temperature ΔTk(t) as a result of thermal ageing for the time making more than 5·105 hours, in accordance with a certain mathematical expression.
EFFECT: increased accuracy of assessment of extent of embrittlement of VVER-1000 reactor vessel embrittlement as a result of thermal ageing.
3 tbl
Title | Year | Author | Number |
---|---|---|---|
METHOD OF PREDICTING RESOURCE CAPACITY OF STEEL OF REACTOR VESSELS VVER-1000 | 2013 |
|
RU2534045C1 |
METHOD FOR PREDICTING RESOURCE CAPACITY OF STEEL FOR THE REACTOR BODIES OF THE VVER TYPE | 2017 |
|
RU2654071C1 |
METHOD TO DETERMINE SHIFT OF CRITICAL BRITTLENESS TEMPERATURE OF STEELS FOR FORECASTING EMBRITTLEMENT OF BODIES OF REACTORS OF PWR TYPE | 2017 |
|
RU2635658C1 |
METHOD OF DETERMINATION OF THE CRITICAL TEMPERATURE OF STEEL BRITTLENESS BY THE CROSS SECTION OF THE WALL OF THE OBJECT | 2017 |
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RU2651632C1 |
METHOD OF FORECASTING DEGREE OF HEAT-RESISTANT STEEL EMBRITTLEMENT | 2012 |
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RU2508532C1 |
METHOD FOR COMPLEX THERMAL PROCESSING OF LARGE-SIZED FORGED PIECES | 2003 |
|
RU2235791C1 |
WELDING WIRE FOR WELDING VESSELS OF NUCLEAR REACTORS AND OTHER PRESSURE VESSELS IN POWER MACHINE ENGINEERING | 2002 |
|
RU2217284C1 |
METHOD FOR MANUFACTURING PRESSURIZED-WATER REACTOR VESSEL | 1990 |
|
RU2069900C1 |
METHOD FOR RECOVERING PROPERTIES OF MATERIAL OF POWER REACTOR CASINGS | 1993 |
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RU2081187C1 |
METHOD OF ENHANCING RESISTANCE TO CRACK PROPAGATION IN CONSTRUCTION | 1992 |
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RU2041418C1 |
Authors
Dates
2014-10-20—Published
2013-03-22—Filed