The current Leak Before Break (LBB) assessment is based primarily on the monotonic fracture tearing instability. In it the maximum design accident load is compared with the fracture-tearing resistance load. The effect of cyclic loading has not been generally considered in the fracture assessment of nuclear power plant piping. It is a well-known fact that reversible cyclic loading decreases the fracture resistance of the material, which leads to increased crack growth. Indian nuclear power reactors consider Operational-Basis-Earthquake (OBE) and Safe-Shutdown-Earthquake (SSE) events in the design of various structures, systems, and components. Keeping this in view a series of cyclic tearing tests have been conducted on straight pipes, made of ASTM SA333 Gr.6 carbon steel. This is the material of primary heat transport (PHT) piping material of Indian Pressurized Heavy Water Reactors (PHWR). In this series 13 tests have been carried out circumferentially through wall cracked seamless and circumferential seam welded straight pipes under reversible cyclic bending loading. All the tests have been conducted under quasistatic, i.e., slow loading rates and dynamic inertia effects are not considered. The cyclic test results have been compared with the corresponding monotonic pipe fracture test results. These test results and its comparison with corresponding monotonic tearing clearly illustrate the need of addressing the reduction in apparent fracture toughness of material under reversible cyclic loading and the safe number of load cycles in the LBB assessment.
Skip Nav Destination
suneelkg@barc.gov.in
Article navigation
February 2007
Research Papers
Effects of Simulated Seismic Loading on LBB Assessment of High Energy Piping
Suneel K. Gupta,
suneelkg@barc.gov.in
Suneel K. Gupta
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, India
Search for other works by this author on:
Vivek Bhasin,
Vivek Bhasin
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, India
Search for other works by this author on:
K. K. Vaze,
K. K. Vaze
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, India
Search for other works by this author on:
A. K. Ghosh,
A. K. Ghosh
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, India
Search for other works by this author on:
H. S. Kushwaha
H. S. Kushwaha
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, India
Search for other works by this author on:
Suneel K. Gupta
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, Indiasuneelkg@barc.gov.in
Vivek Bhasin
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, India
K. K. Vaze
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, India
A. K. Ghosh
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, India
H. S. Kushwaha
Bhabha Atomic Research Center
, Reactor Safety Division, Hall-7, Mumbai, 400 085, IndiaJ. Pressure Vessel Technol. Feb 2007, 129(1): 28-37 (10 pages)
Published Online: March 13, 2006
Article history
Received:
August 26, 2005
Revised:
March 13, 2006
Citation
Gupta, S. K., Bhasin, V., Vaze, K. K., Ghosh, A. K., and Kushwaha, H. S. (March 13, 2006). "Effects of Simulated Seismic Loading on LBB Assessment of High Energy Piping." ASME. J. Pressure Vessel Technol. February 2007; 129(1): 28–37. https://doi.org/10.1115/1.2388998
Download citation file:
Get Email Alerts
Cited By
Study On the Residual Stress Distribution of Bi-directional Cold Expansion Process Performed On Open Holes
J. Pressure Vessel Technol
Pressure Vessel Design for High Temperature and Pressure Testing on Supercritical Carbon Dioxide
J. Pressure Vessel Technol
Research On Mechanism of Dynamic Evolution Vibration Characteristics of Horizontal 90° Elbow Flow Pattern
J. Pressure Vessel Technol
Related Articles
Guest Editorial
J. Pressure Vessel Technol (February,2004)
Japanese Activities Concerning Nuclear Codes and Standards—Part I
J. Pressure Vessel Technol (February,2006)
Experimental Investigation Into the Fracture Toughness of Polyethylene Pipe Material
J. Pressure Vessel Technol (February,2005)
Prediction of Failure Behavior for Nuclear Piping Using Curved Wide-Plate Test
J. Pressure Vessel Technol (November,2004)
Related Proceedings Papers
Related Chapters
Section XI Flaw Acceptance Criteria and Evaluation Using Code Procedures
Online Companion Guide to the ASME Boiler and Pressure Vessel Codes
Applications of Elastic-Plastic Fracture Mechanics in Section XI, ASME Code Evaluations
Online Companion Guide to the ASME Boiler and Pressure Vessel Codes
Pipe Material Selection and Fracture Control
Pipeline Transportation of Carbon Dioxide Containing Impurities