Published 2006
| Version v1
Book
Evaluation of critical crack length and fracture toughness of pressure tubes using slit burst test method
- 1. Post Irradiation Examination Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
Pressure tubes (PTs) in Pressurized Heavy Water Reactors (PHWRs) operate at high temperature and pressure and undergo progressive embrittlement with increasing EFPY of operation due to synergistic effect of neutrons and hydriding. The embrittlement is manifested in reduction of fracture toughness and thereby lowers the magnitude of critical crack length (CCL) of PT. However, to satisfy Leak Before Break (LBB) criterion for assuring safe PT operation during service, CCL needs to be higher than the specified value. The slit burst test (SBT) along with fracture toughness test using CCT specimens need to be carried out to establish the CCL of the irradiated pressure tube
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1
- Imprint Pagination
- 179 p.
- Journal Page Range
- p. 156
Conference
- Title
- international conference on advances in nuclear materials processing, performance and phenomena; MBFE 2006: satellite conference on materials behaviour- far from equilibrium
- Acronym
- ANM 2006
- Dates
- 12-16 Dec 2006
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 50064033
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; LEAK TESTING; PHWR TYPE REACTORS; PRESSURE TUBES; REACTOR OPERATION; REACTOR SAFETY
- Descriptors DEC
- HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; OPERATION; REACTOR LIFE CYCLE; REACTORS; SAFETY; TESTING; TUBES
Optional Information
- Notes
- This record replaces 50063253