Published 1991 | Version v1
Journal article Metadata-only

Individual evaluation of cracking resistance in reactor vessel materials

Creators

Description

Fracture toughness of the materials of real WWER-1000 reactor vessels was determined on the basis of calculation-experimental technique for graphical representation of temperature dependence of yield strength-cracking resistance ratio. Experimental data collection was obtained which included fracture toughness values for base metal and weld metal of WWER-1000 vessel welded joints of 25KhN3MFA, 15Kh2NMFA and 22 K steels. With the use of specimens 25 and 50 mm in thickness temperature dependences of fracture toughness within the range of 103 to 233 K were built and presented

Additional details

Additional titles

Original title (Russian)
Индивидуальная оценка трещиностойкости материалов корпусов реакторов

Publishing Information

Journal Title
Zavodskaya Laboratoriya
Journal Volume
57
Journal Issue
10
Journal Page Range
p. 29-31.
ISSN
0321-4265
CODEN
ZVDLAU

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
24000370
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
FRACTURE PROPERTIES; LOW ALLOY STEELS; MECHANICAL TESTS; REACTOR VESSELS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0065-0273 K; WELDED JOINTS; WWER TYPE REACTORS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MATERIALS TESTING; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; STEELS; TEMPERATURE RANGE; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS