Effect of neutron irradiation on the delayed hydride crack velocity in CANDU pressure tube materials
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
Since the pressure tube in Pickering CANDU reactor cracks in 1974, the delayed hydride cracking (DHC) has been intensively studied. It is a stable crack growth mechanism in zirconium alloys. Hydrogen accumulates at a stress raiser. If sufficient hydrogen is present, hydrides form and, and if the stress is high enough, hydride fracture and the crack advance. DHC is the important factor to govern the safety of pressure tubes in CANDU reactor. During reactor operation the accumulation of neutron irradiation on tube effects the behaviors of DHC to be accelerate crack velocity. It is very important to understand the effect of neutron irradiation on the tube material during reactor operation to protect the tube breakage. In this study the changes in the DHCV of the tubes which arise from exposure to irradiation are reviewed
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- 1466 p.
- Journal Page Range
- p. 939-940
Conference
- Title
- 2004 autumn meeting of the KNS
- Dates
- 28-29 Oct 2004
- Place
- Yongpyong (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36102530
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; CRACKS; PRESSURE TUBES; REACTOR OPERATION; SAFETY; STRESSES; VELOCITY; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; HEAVY WATER MODERATED REACTORS; OPERATION; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUBES
Optional Information
- Notes
- 6 refs, 5 figs