METHOD FOR EVALUATING SERVICE LIFE OF PRESSURIZED-TUBE REACTOR GRAPHITE STACK Russian patent published in 2005 - IPC

Abstract RU 2266576 C1

FIELD: nuclear power engineering; evaluating service life of pressurized-tube reactor and its graphite stack.

SUBSTANCE: proposed method for evaluating service life of pressurized-tube reactor graphite stack includes step-by-step selective accelerated irradiation of graphite blocks, evaluation of limiting value of fluence as soon as graphite has acquired ultimate strength, and its comparison with fluence of graphite blocks of other reactor subchannels. Graphite blocks are subjected to step-by-step irradiation on running reactor in subchannels with power generation amounting to 90 - 100% of current maximum value attained for reactor; mean power level higher than average for reactor by 20 - 30%, but not higher than maximal admissible level, is maintained in them. Upon termination of each irradiation step strength of graphite blocks of selected subchannels is measured, service life of reactor graphite stack is evaluated as soon as they have reached permissible ultimate strength through margin of fluence by difference between maximum value of graphite block fluence in chosen subchannels measured for graphite brought to ultimate strength and fluence of graphite blocks in remaining subchannels of reactor.

EFFECT: enhanced reliability of evaluating graphite stack life and its extension ensuring desired safety in reactor operation.

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RU 2 266 576 C1

Authors

Lebedev V.I.

Chernikov O.G.

Shmakov L.V.

Kovalev S.M.

Kudrjavtsev K.G.

Zakharzhevskij Ju.O.

Rogozin V.N.

Anan'Ev A.N.

Baldin V.D.

Dates

2005-12-20Published

2004-04-07Filed