Structural integrity evaluation method for overheating rupture of FBR steam generator tube
Creators
Description
This paper describes a structural integrity evaluation method for a SG tube of FBR in case of sodium-water reaction and creep rupture tests to obtain the strength of the tube material. In the SG of FBR, if intermediate size of water/steam leak (1-2 kg s-1) would occur from a tube, it could cause overheating rupture of the multiple tubes surrounding the initially failed tube due to generated sodium-water reaction heat. In the ultra-high temperature condition, the creep strength of the material is one of the dominant factors for failure behavior. Accordingly, we tried to apply the creep failure criterion for the overheating rupture of the SG tube. The creep rupture tests have been performed at ultra-high temperature conditions ranging from 1223.2 to 1323.2 K. The test material is 'Mod.9Cr-1Mo steel' which is one of the candidate materials for the tubes of the future SG of FBR. The test results have shown that tube rupture depends on the creep strength of the material; hence, instantaneous rupture does not occur even if the stress exceeds the design value of ultimate tensile strength. The test data have been suitably expressed using the Larson-Miller Parameter, and a structural integrity evaluation method based on the sum of the use-fraction associated with the creep damage has been proposed. Based on this method, the structural integrity of the tube in the sodium-water reaction flame has been evaluated. The results show that it is important to detect the initial leak of the tube within a short period and to reduce the steam pressure more rapidly by SG blowdown
Additional details
Identifiers
- PII
- S0029549301004769;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 212
- Journal Issue
- 1-3
- Journal Page Range
- p. 183-192
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35000913
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- CREEP; FBR TYPE REACTORS; LEAK TESTING; MECHANICAL TESTS; MOLTEN METAL-WATER REACTIONS; SODIUM; STEAM GENERATORS; STEEL-CR10MO2; TUBES
- Descriptors DEC
- ALKALI METALS; ALLOYS; BOILERS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MARTENSITIC STEELS; MATERIALS TESTING; MECHANICAL PROPERTIES; METALS; MOLYBDENUM ALLOYS; REACTORS; STAINLESS STEELS; STEELS; TESTING; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS
Optional Information
- Copyright
- Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.