Fracture toughness behaviour using small CCT specimen of Zr-2.5Nb pressure tube materials
Description
Fracture toughness of Zr-2.5Nb pressure tube is the essential data to estimate the CCL(critical crack length) for the concept of LBB(Leak-Before-Break) in PHWR. Zr-2.5Nb pressure tubes could be degraded due to the absorption of hydrogen from coolant and the irradiation. To investigate the fracture toughness behaviour such as J-resistance curves, dJ/da, and CCL of some Zr-alloys (CANDU-double, -quad, CW-E125, TMT-E125, E-635), the transverse tensile test and the fracture toughness test of small CCT (Curved Compact Tension) specimen with 17 mm width were carried out with the variation of testing temperature at different testing condition. To define the fracture mechanism of degradation, the fractographic comparison of fracture surface was performed using the stereoscope and SEM. In addition, the effect of non-uniformed pre-fatigue crack was also studied. In conclusion, CANDU double-melted was less tougher than CANDU quad-melted and the hydrogen embrittlement was found at room temperature. Finally, while the effect of non-uniformed pre-fatigue crack was considerable at room temperature, this effect was disappeared at 250-300 .deg. C
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Additional details
Publishing Information
- Imprint Pagination
- 80 p.
- Report number
- KAERI/TR--1777/2001
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33066837
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- CANDU TYPE REACTORS; CRACKS; FRACTOGRAPHY; FRACTURE PROPERTIES; HYDROGEN EMBRITTLEMENT; IRRADIATION; LEAKS; PRESSURE TUBES; TENSILE PROPERTIES; VARIATIONS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; EMBRITTLEMENT; HEAVY WATER MODERATED REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUBES
Optional Information
- Notes
- 57 refs, 65 figs, 105 tabs