Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Theoretical and experimental assessment of structural integrity of primary pipe

Chellapandi, P.; Biswas, A.; Chetal, S.C.; Bhoje, S.B. (Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India))

Abstract

This paper deals with the theoretical and experimental structural mechanics analysis carried out for the primary sodium pipes for the 500 M We Prototype Fast Breeder Reactor (PFBR) towards demonstrating its structural integrity. The analysis is carried out to determine the stresses under pressure and thermal loads including seismic forces. Based on this, an optimum layout and pipe thicknesses have been arrived at. Subsequently, creep-fatigue damage values for the imposed thermal transients, in conjunction with the assumption that the spherical header gets stuck up, are estimated. Structural integrity is ensured further by detailed fracture mechanics analysis and experimental investigations. (author)

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key words: calculation methods; creep; lmfbr type reactors; mechanical tests; pipes; primary coolant circuits; seismic effects; static loads; stress analysis; thermal fatigue; breeder reactors; epithermal reactors; fast reactors; fbr type reactors; liquid metal cooled reactors;
Reference:
Proceedings of a technical meeting held in Kalpakkam, India 13-17 January 2003
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1406, pp:57-71