Stress intensity factor calculation for surface and subsurface semi-elliptical cracks in the outlet branch pipe zone of the WWER-440 reactor pressure vessel

Korinets, A.R.; Chernysh, T.A.; Maksimov, Yu.M.; Semishkin, V.P.

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Stress intensity factor calculation for surface and subsurface semi-elliptical cracks in the outlet branch pipe zone of the WWER-440 reactor pressure vessel

Korinets, A.R.; Chernysh, T.A.; Maksimov, Yu.M.; Semishkin, V.P.1992

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AbstractAbstract

[en] Calculation of stress intensity factor for subfused and surface semi-elliptical cracks in the zone of branch pipe joining with the WWER-440 vessel under conditions of maximum credible accident is discussed. The coefficient obtained by the method of crack virtual growth and asymptotic displacement method is compared with that determined on the bases of the influence functions for subfused and surface cracks in a plate

Original Title

Raschet koehffitsienta intensivnosti napryazhenij dlya poluehllipticheskikh treshchin mezhdu patrubkom i korpusom reaktora

Primary Subject

SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS (E3200)

Record Type

Journal Article

Journal

Atomnaya Ehnergiya; ISSN 0004-7163;

; CODEN AENGAB; v. 73(2); p. 87-91

Country of publication

Russian Federation

Descriptors (DEI)

CRACK PROPAGATION, DIAGRAMS, ECCS, FINITE ELEMENT METHOD, MAXIMUM CREDIBLE ACCIDENT, PIPE JOINTS, REACTOR VESSELS, STRESS ANALYSIS, STRESS INTENSITY FACTORS, TEMPERATURE DISTRIBUTION, WELDED JOINTS, WWER TYPE REACTORS

Descriptors (DEC)

ACCIDENTS, CALCULATION METHODS, CONTAINERS, DESIGN BASIS ACCIDENTS, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, INFORMATION, JOINTS, NUMERICAL SOLUTION, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR PROTECTION SYSTEMS, REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS

LanguageLanguage

Russian

Reference NumberReference Number

25070056

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