‘German leak-before-break concept’ (description of German LBB procedures, practices and applications)

Bartholome, G.

doi:10.1016/s0308-0161(96)00057-9

Cited by 9 publications

(3 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Beaudoin et al (1990) described a LBB program for high energy balance-of-plant piping in the United States using fracture mechanics analysis. Bartholomé (1997) explained the 'German Leak-before-break procedures' and presented a general outline of prerequisites and practices for break preclusion. Ramachandra Murthy, 2004, 2007;Saxena et al, 2009) carried out various experimental and analytical studies on LBB behavior for both straight pipes and piping elbows.…”

Section: Introductionmentioning

confidence: 99%

Effect of thermal aging on the leak-before-break analysis of nuclear primary pipes

Wang

et al. 2014

Nuclear Engineering and Design

View full text Add to dashboard Cite

Section: Introductionmentioning

confidence: 99%

Effect of thermal aging on the leak-before-break analysis of nuclear primary pipes

Wang

et al. 2014

Nuclear Engineering and Design

View full text Add to dashboard Cite

“…have demonstrated the LBB behaviour of coolant piping using fracture mechanics analysis and testing. The German leak‐before‐break procedures, practice and applications have been explained by Bartholome 6 . Vangderglas 7 has applied LBB approach extensively to the large diameter piping of a nuclear power plant.…”

Section: Introductionmentioning

confidence: 99%

Investigations on shell–nozzle junction of steam generator for LBB justification

Murthy

Pukazhendhi

Navin

et al. 2007

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

A B S T R A C T Steam generators are important components of a nuclear reactor. They are subjected to system pressure and force controlled bending moments. Leak before break (LBB) criteria based on a fracture mechanics approach is used to ensure the reliability of the primary heat transport system of nuclear reactors. Experimental studies were recently completed for justifying LBB for the cold end of the shell-nozzle junction of the steam generator of the 500 MWe Fast breeder reactor (FBR) under construction at Kalpakkam. The internal diameter of the main tube is 1120 mm and that of the nozzle is 386.4 mm. The thickness of the main tube is 24 mm while that of the nozzle is 18 mm. Fatigue tests were conducted on two carbon steel and two modified 9Cr1Mo steel shell-nozzle junction specimens at room temperature under constant internal pressure and cyclic in-plane bending moment. Fracture tests were conducted on these components until collapse after the fatigue test. FEM analysis was also performed to identify critical locations and factor of safety for fatigue loading and collapse. The objective of the studies was to obtain the factor of safety for crack initiation, through-wall and critical crack size, and collapse. The studies demonstrated adequate factor of safety for all the above LBB criteria.

show abstract

“…The most recent methodology developed to prevent catastrophic failure is centred on the concept of leak‐before‐break (LBB). This concept, which demonstrates through fracture mechanics that there is a negligible chance of catastrophic failure prior to leakage, has been widely used in nuclear power plants for the design of a primary heat transport system (PHTS) 1–4 …”

Section: Introductionmentioning

confidence: 99%

A probabilistic simulation of fluid leakage in multiple cracks situation

Xie

2002

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

In pressure vessels and piping the leak‐before‐break (LBB) assessment method is employed to avoid any catastrophic failure prior to a detectable leakage. One of the most important parameter, the leak rate, is investigated in the present paper by means of the Monte Carlo method. A brief review is carried out with emphasis on aspects such as crack growth, crack size with detectable leakage, crack opening area and leak rate. Issues concerning the property and behaviour of multiple cracks are also covered along with a review of the characteristics of leak rate through distributed multiple cracks using a statistical simulation method. The simulation results show that the effect of multiple cracks is quite significant to the LBB concept. Both the relationship between leak rate and crack length (or time) and the statistical characteristics of the leak rate are considerably different for different initial crack conditions.

show abstract

‘German leak-before-break concept’ (description of German LBB procedures, practices and applications)

Cited by 9 publications

References 2 publications

Effect of thermal aging on the leak-before-break analysis of nuclear primary pipes

Effect of thermal aging on the leak-before-break analysis of nuclear primary pipes

Investigations on shell–nozzle junction of steam generator for LBB justification

A probabilistic simulation of fluid leakage in multiple cracks situation

Contact Info

Product

Resources

About