Mechanical properties of primary circuit materials of the WWER-440 nuclear power plants
Description
An overview is given of the mechanical properties of primary circuit austenitic materials of four WWER-440 NPPs. For the fracture test of austenitic pipes, 30 specimens from the base material and 44 from the weld metal were analyzed. The data set covered both longitudinal and circumferential orientation of crack extension and a temperature range from 24 to 300 degC. Tensile results were taken into account without considering orientation. Fracture properties are relevant to circumferential crack propagation. The fracture results lead to the conclusion that ageing possibly plays a role in case of the duplex austenitic weld metal. The Czech material manufactured at the Vitkovice steel works is compared with Russian steels characterized by lower yield stress and higher fracture resistance. (Z.S.) 1 tab., 7 figs., 4 refs
Additional details
Publishing Information
- Journal Title
- Nucleon
- Journal Issue
- no.3
- Journal Page Range
- p. 20-23.
- CODEN
- NLEQEM
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 26032471
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- AUSTENITIC STEELS; FRACTURE PROPERTIES; NUCLEAR POWER PLANTS; PIPES; PRIMARY COOLANT CIRCUITS; STEEL-CR18NI10TI; STEEL-CR18NI12TI; TENSILE PROPERTIES; WWER TYPE REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEELS; THERMAL POWER PLANTS; THERMAL REACTORS; TITANIUM ADDITIONS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS