5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P1.001 Comparative study between code and analytical stress intensification factor in ITER cooling system piping

5 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 1
Poster A. Experimental Fusion Devices and Supporting Facilities P1 Poster session

Speaker

Aditya Singh (Cooling Water System)

Description

A tee or an elbow behaves very differently from a straight pipe in resisting bending moment. When a straight pipe is bent, its cross section remains circular and the stresses increase linearly with distance from the neutral axis. However, when an elbow or a tee is bent, its cross section gets deformed into an oval shape. This geometrical deformity results in increased stresses, which are accounted for by using a factor called Stress Intensification Factor (SIF). The SIFs are specified in applicable Codes and Standards and they can be used with some limitations. ASME B31.3 Appendix D provides SIFs obtained from tests on full size branch connections for tees. But in applications where the branch size is much smaller than the main run pipe (diameter ratio d/D < 0.5), use of stress intensification factor from codes is too conservative. This can cause overestimation of stresses and unnecessary design modifications in piping systems. In such cases, an improved and reduced SIF can be used, if more applicable data available. ITER secondary cooling systems (Component Cooling Water System, Chilled Water System and Heat Rejection System) have numerous interfaces with client components located in Tokamak Complex and other auxiliary buildings across the site. These systems include large amount of piping with diameters ranging from 0.15 to 2m and countless intersections. Precise SIF values need to be used for stress analysis of these piping under service levels C&D considering the huge amount of static and dynamic loads to arrive at an optimized design and layout. In this paper, a finite element approach has been adopted to find out SIF values for branch-offs as well as header pipes at intersections with varying branch sizes to compare them with the code specified values and their advantages in stress analyses of ITER CCWS, CHWS and HRS piping.

Co-authors

A. G. Ajith Kumar (Cooling Water System , ITER-India Institute for Plasma Research, GANDHINAGAR, India) Aditya Singh (Cooling Water System , ITER-India Institute for Plasma Research, GANDHINAGAR, India) D. K. Gupta (Cooling Water System , ITER-India Institute for Plasma Research, GANDHINAGAR, India) K. S. Bhatt (Cooling Water System , ITER-India Institute for Plasma Research, GANDHINAGAR, India) L. K. Sharma (Cooling Water System , ITER-India Institute for Plasma Research, GANDHINAGAR, India) M. Jadhav (Cooling Water System , ITER-India Institute for Plasma Research, GANDHINAGAR, India)

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