Reactor component integrity: leak-before-break verification, modification of design rules and safety assessment
Creators
- 1. Bhabha Atomic Research Centre, Mumbai (India)
Description
The aim of this programme was direct verification of Leak-Before-Break (LBB) applicability to Indian reactors, modification of component design rules to achieve rationalized design rules and overall safety assessment of Nuclear Power Plants (NPPs). One of the unique features of this programme was that components of actual or near actual size were tested under different loading conditions and load combinations for direct verification and realistic quantification of safety margins. In addition the data has helped in benchmarking of existing analytical methods used in design and develop modifications to improve prediction of different modes of failure. In this programme thrust was also given to quantify the life limiting mechanisms and identify measures and technologies to enhance the operating life of the components. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of international conference on peaceful uses of atomic energy - 2009. V. 1
- Imprint Pagination
- 408 p.
- Journal Page Range
- p. 190-191
Conference
- Title
- International conference on peaceful uses of atomic energy - 2009
- Dates
- 29 Sep - 1 Oct 2009
- Place
- New Delhi (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 40105694
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; LEAK TESTING; NUCLEAR POWER PLANTS; SAFETY ANALYSIS; SPECIFICATIONS; VERIFICATION; WELDING
- Descriptors DEC
- FABRICATION; JOINING; NUCLEAR FACILITIES; POWER PLANTS; TESTING; THERMAL POWER PLANTS
Optional Information
- Notes
- 5 figs.