Integrity assessment on irradiated garter springs
- 1. Post Irradiation Examination Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
Assuring the integrity of the garter spring is a prerequisite for ensuring the safety of the coolant tube, which is verily one of the most vital components of a Pressurized Heavy Water Reactor (PHWR) system. With this aim in view, twenty one numbers of Zr-2.5% Nb-Cu garter springs (G.S.) which had undergone various Effective Full Power Years of operation (EFPYs) ranging from 1.8 to 8.5, were subjected to detailed mechanical property studies at Post Irradiation Examination Division, BARC. These G.Ss had belonged to Indian PHWRs, namely RAPS, MAPS and NAPS. A report is presented on the basis of the results generated by carrying out a few relevant mechanical tests on the irradiated G.Ss. The study indicated that these garter springs even after 8.5 EFPYs of service in the respective power reactors could exhibit good amount of strength and ductility, much more than what would be required for retaining their integrity during service. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the symposium Zirconium - 2002
- Imprint Pagination
- 690 p.
- Journal Page Range
- p. 649-652
Conference
- Title
- national symposium Zirconium - 2002
- Acronym
- ZIRC - 2002
- Dates
- 11-13 Sep 2002
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 34042489
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DUCTILITY; KALPAKKAM-1 REACTOR; KALPAKKAM-2 REACTOR; NARORA-1 REACTOR; POST-IRRADIATION EXAMINATION; RAJASTHAN-1 REACTOR; RAJASTHAN-2 REACTOR; REACTOR SAFETY; SERVICE LIFE; SPRINGS; YIELD STRENGTH; ZIRCONIUM
- Descriptors DEC
- CANDU TYPE REACTORS; ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; LIFETIME; MACHINE PARTS; MECHANICAL PROPERTIES; METALS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SAFETY; TENSILE PROPERTIES; THERMAL REACTORS; TRANSITION ELEMENTS
Optional Information
- Notes
- 2 refs., 2 tabs.