Effect of coating and heat treatment on high temperature burst property of stainless steel thin-walled tube
- 1. Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing (China)
Description
In order to investigate the high temperature burst behavior and effect of coating and heat treatment on burst properties of stainless steel thin-walled tube for pressurized water reactor (PWR) and supercritical water-cooled reactor (SCWR) under the simulated LOCA (loss of coolant accident) conditions, the transient-heating burst tests of original, heat treatment and coated tube specimens were carried out under the simulated LOCA conditions by using the high temperature burst facility. The data of high temperature burst properties based on three kinds of 316L stainless steel tubes and the relationships between burst strength and total circumference elongation (TCE) with temperature were obtained under the conditions of 600-1200℃ and heating rate of 5℃/s, meanwhile, the fracture morphology and microstructure of burst test specimens were analyzed. The results of the burst test show that heat treatment temperature of coating preparation is the main reason for the decrease in burst strength, and the coating has little effect on the high temperature burst strength. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 54
- Journal Issue
- 11
- Journal Page Range
- p. 2182-2187
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55097415
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- COATINGS; ELONGATION; FRACTURES; HEAT TREATMENTS; HEATING RATE; LOSS OF COOLANT; MICROSTRUCTURE; MORPHOLOGY; PWR TYPE REACTORS; SIMULATION; STAINLESS STEEL-316L; TEMPERATURE RANGE 0400-1000 K; TRANSIENTS; TUBES; WALLS
- Descriptors DEC
- ACCIDENTS; ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; DEFORMATION; ENRICHED URANIUM REACTORS; FAILURES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3-L; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 figs., 15 refs.; http://dx.doi.org/10.7538/yzk.2020.youxian.0316