Fast Reactors and Accelerator Driven Systems Knowledge Base
Conference Article: Thermal hydraulics and thermomechanical analysis of thermal striping in a mixing tee-junction of secondary sodium circuit of Phenix reactor
Chellapandi, P.; Velusamy, K.; Biswas, A.; Rama, R.; Bhoje, S.B.; Vaidyanathan, G.; Chetal, S.C. (Indira Gandhi Centre for Atomic Research (IGCAR) (India))Abstract
The investigation of thermal striping risks calls for determination of (i) temperature fluctuations which can be in the form of random response or a set of sinusoidal functions, (ii) associated thermal stress oscillations to estimate the life cycles for initiating cracks, and (iii) crack propagation details. This report deals with the results of thermal hydraulics and thermomechanical investigations carried out by IGCAR.
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key words: benchmarks; crack propagation; fluid mechanics; mechanical properties; phenix reactor; pipe joints; pipes; secondary coolant circuits; sodium; thermal analysis; thermal stresses
- Reference:
- Final report of a co-ordinated research project 1996-1999
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TECDOC--1318, pp:63-88
- International Atomic Energy Agency, Vienna (Austria)