Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

N. Mani; G. Thanigaiyarasu; P. Chellapandi

doi:10.1115/1.4005385

Journal of Pressure Vessel Technology | Volume 134 | Issue 2 | Research Paper

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Research Papers: Design and Analysis

Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

N. Mani, G. Thanigaiyarasu and P. Chellapandi

[+] Author and Article Information

N. Mani, G. Thanigaiyarasu

Anna University, Chennai-600 025, India

P. Chellapandi

Scientist Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India

J. Pressure Vessel Technol 134(2), 021211 (Jan 25, 2012) (8 pages) doi:10.1115/1.4005385 History: Received March 15, 2010; Accepted February 11, 2011; Published January 25, 2012; Online January 25, 2012

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Abstract

The steam generators (SG) control the capacity factor of sodium cooled fast reactor plants and hence they are designed with high reliability. One of the strategies to enhance the reliability is to demonstrate leak before break (LBB) justification. LBB analysis is reported for 500 MWe sodium cooled fast reactor (SFR) in this paper. The material of construction is modified 9 Cr-1 Mo and the critical location is the shell nozzle junction. The initial surface crack is postulated at the critical locations at the shell nozzle junction. The critical crack length is computed by adopting the philosophy of CEGB-R6 procedure, for which Jintegral is computed by finite element method. For determining the detectable through-wall crack length, the crack opening area is also determined by finite element method. Finally, it is demonstrated that it is possible to justify leak before break argument for SFR SG with adequate margins. The required material properties are extracted from French Design Code RCC-MR-2002 and validated with tests on plates.

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References

Milne, I., Ainsworth, R. A., Dowling, A. R., and Stewart, A. R., 1986, “Assessment of Structures Containing Defects,” CEGB Report R/H/R6, Revision 3, Central Electricity Generating Board, UK.A16, 1995, “Guide for Defect Assessment and Leak Before Break,” Rapport DMT 95/659, third draft.

RCC-MR: Design and Construction Rules for Mechanical Components for FBR Nuclear Islands, Section I, Subsection B, Class 1 Components, AFCEN, 2002.

ASME, Section III, 2001, Div 1, Subsection NH, Class 1 Components in elevated temperature service.

ASME, Sec-XI, 1989, Rules for Inspection and Testing of Components of Liquid-Metal Cooled Plants.

Gruter, L., Zeibig, H., Percie du Sert, B., Bhandari, S., 1986, “Leak-Before-Break Considerations for LMFBR Structures,” Int. J. Pressure Vessels Piping, 24 , pp. 337–346. [CrossRef]

Turbat, A., Deschanels, H., Sperandio, M., and Faidy, C., 1995, “The Use of LBB concept in French Fast Reactors: Application to SPX Plant,” LBB 95, Lyon, Oct 9–11.

Nakai, Y., Mochizulei, T., and Kawashima, K., 1982, “Safety aspects in the design of MONJU,” Lyon-Ecully, France, July 19–23, Vol. 1 , pp. 105–114.

RCC-MR: Appendix A16: Guide for Leak Before Break Analysis and Defect Assessment, AFCEN, 2002.

Beaudoin, B. F., Quiñonesand, D. F., and Hardin, T. C., 1990, “LBB Application in US Light Water Reactor Balance-of-Pipings,” Int. J. Pressure Vessels Piping, 43 , pp. 67–83. [CrossRef]

Koi, M., Aoto, K., Wada, Y., and Ueno, F., 1993, “Fracture Toughness and Criterion of Unstable Ductile Fracture of 9Cr-1Mo Steel and Weldment,” "Post Conference Seminar on Inelastic Analysis, Fatigue, Fracture and Life Prediction, SMiRT-12", Aug. 23–24, pp. 36–52.

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Figure 1

Schematic sketch of SFR-SG

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Figure 2

Geometrical and loading details

Schematics of idealized geometries and associated boundary conditions

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Figure 3

Schematics of idealized geometries and associated boundary conditions

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Figure 4

Stress distribution

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Figure 7

ML versus c

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Figure 5

Stress concentration around crack tip

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Figure 6

Estimation of limit load

Demonstration of LBB Justification for SG

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Figure 8

Demonstration of LBB Justification for SG

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Figure 10

Crack propagation in G91 plate

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Figure 9

Generation of P-δ Curves for ORNL plate

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Mani NN, Thanigaiyarasu GG, Chellapandi PP. Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor. ASME. J. Pressure Vessel Technol. 2012;134(2):021211-021211-8. doi:10.1115/1.4005385.

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Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

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