Fracture behaviour simulation of flawed full scale pressure vessel

1990 ◽  
Vol 41 (1) ◽  
pp. 75-101 ◽  
Author(s):  
Arja Saarenheimo ◽  
Heli Talja ◽  
Kari Ikonen ◽  
Rauno Rintamaa ◽  
Heikki Keinänen ◽  
...  
Author(s):  
John H. Underwood

Engineering mechanics analysis of cannon pressure vessels is described with special emphasis on the work of the late US Army Benet Laboratories engineer David P. Kendall. His work encompassed a broad range of design and analysis of high pressure vessels for use as cannons, including analysis of the limiting yield pressure for vessels, the autofrettage process applied to thick vessels, and the fatigue life of autofrettaged cannon vessels. Mr. Kendall’s work has become the standard approach used to analyze the structural integrity of cannon pressure vessels at the US Army Benet Laboratories. The methods used by Kendall in analysis of pressure vessels were simple and direct. He used classic results from research in engineering mechanics to develop descriptive expressions for limiting pressure, autofrettage residual stresses and fatigue life of cannon pressure vessels. Then he checked the expressions against the results of full-scale cannon pressure vessel tests in the proving grounds and the laboratory. Three types of analysis are described: [i] Yield pressure tests of cannon sections compared with a yield pressure expression, including in the comparison post-test yield strength measurements from appropriate locations of the cannon sections; [ii] Autofrettage hoop residual stress measurements by neutron diffraction in cannon sections compared with expressions, including Bauschinger corrections in the expressions to account for the reduction in compressive yield strength near the bore of an autofrettaged vessel; [iii] Fatigue life tests of cannons following proving ground firing and subsequent laboratory simulated firing compared with Paris-based fatigue life expressions that include post-test metallographic determination of the initial crack size due to firing. Procedures are proposed for Paris life calculations for bore-initiated fatigue affected by crack-face pressure and notch-initiated cracking in which notch tip stresses are significantly above the material yield strength. The expressions developed by Kendall and compared with full-scale cannon pressure vessel tests provide useful first-order design and safety checks for pressure vessels, to be followed by further engineering analysis and service simulation testing as appropriate for the application. Expressions are summarized that are intended for initial design calculations of yield pressure, autofrettage stresses and fatigue life for pressure vessels. Example calculations with these expressions are described for a hypothetical pressure vessel.


It is our purpose to review fracture characteristics of heavy-walled pressure vessels in relation to the plane-strain crack toughness known under the term, K Ic . As a starting point, suppose that direct measurement of the strength of a full-scale pressure vessel containing a specific crack is contemplated. An initial crack of approximately the desired size can be introduced in several ways, for example, by inserting a sharp groove and then vibrating that region until a fatigue crack develops. However, full-scale testing is often impractical either for reasons of expense or because the introduction of in-service damage, say by nuclear irradiation, is not feasible at the full-scale size. Furthermore, valid test results can usually be obtained at much smaller scale. Small specimen fracture tests Crack extension behaviour observed in a small specimen test can be regarded as representative of full-scale fracture behaviour so long as the stresses carried by the surrounding material into the region containing the crack receive adequate representation. Since the specimen size desired for irradiation purposes is quite limited, we consider next whether crack extension of a large part-through crack in a thick-walled pressure vessel can be modelled by testing just the slice of material indicated in figures 108 ( a ) and ( b ). The calibration and use of test specimens similar to the one shown in figure 108( b ) are described by Sullivan (1964).


2012 ◽  
Vol 134 (5) ◽  
Author(s):  
John H. Underwood ◽  
John J. Keating ◽  
Edward Troiano ◽  
Gregory N. Vigilante

Results from four groups of full-scale pressure vessel service simulation tests are described and analyzed using Paris fatigue life modeling. The objective is to determine how the vessel and initial crack configurations and applied and residual stresses control the as-tested fatigue life of the vessel. The tube inner radii are in the 40–80 mm range; wall thickness varies from 6 to 80 mm; materials are ASTM A723 pressure vessel steel and IN718 nickel-base alloy; applied internal pressure varies from 90 to 700 MPa. The Paris constant, C, and exponent, m, that describe the fatigue crack propagation rate versus stress intensity factor range for the various vessel materials, were measured as part of the investigation. Extensive, previously published fatigue life results from baseline A723 pressure vessels with well characterized autofrettage residual stresses and C and m values are used to demonstrate that a Paris fatigue life model gives a good description of the measured life. The same model is then used to determine the variables with predominant control over life in three types of pressure vessel for which less information and tests results are available. A design life for pressure vessels is calculated for a specified very low probability of fatigue failure using the log(N)-normal distribution statistics often used for fatigue of structures. The results of the work showed: (i) X-ray diffraction measurements of through-wall autofrettage residual stresses are in excellent agreement with prior neutron diffraction measurements from a baseline autofrettaged A723 pressure vessel; these verified autofrettage residual stresses then provide critical input to the baseline Paris life modeling; (ii) comparison of the various full-scale fatigue test results with results from the Paris fatigue life model shows close agreement when autofrettage residual stresses are incorporated into models; (iii) model results for A723 steel vessels with yield strength reduced from the initial 1400 MPa value and degree of autofrettage increased from the initial 40% value indicates a significantly improved resistance to brittle failure with no loss of fatigue life; (iv] comparison of model fatigue life results for IN718 nickel-base alloy vessels with their full-scale test results is improved when near-bore residual stresses measured by X-ray diffraction are included in the model calculations.


1993 ◽  
Vol 115 (2) ◽  
pp. 171-176 ◽  
Author(s):  
P. S. Huang ◽  
G. B. Zhu ◽  
R. Barron

The flat steel ribbon-wound vessel is a relatively new type of wound pressure vessel. This type of vessel consists of a thin-walled inner core and helically wound flat steel ribbons. The outstanding safety in service of this type of vessel is due, in part, to the large circumferential and axial prestresses introduced during the ribbon-winding process. This paper presents a model for determination of prestresses in such a vessel. The model considers the fabrication procedures producing the prestress in the vessel. Experimental results from tests using full-scale vessels are presented. Agreement between the theoretical model and the experimental results is excellent.


1990 ◽  
Vol 119 (2-3) ◽  
pp. 475-490
Author(s):  
S. Crutzen ◽  
H. Herkenrath ◽  
K. Kussmaul ◽  
U. Mletzko

Author(s):  
M. Bakirov ◽  
V. Potapov ◽  
N. Zabruskov ◽  
I. Vystavkin ◽  
V. Levchuk

Resource of reactor with PWR is defined, in the first instance, by foundation of integrity of the third physical barrier of safety. The third physical barrier of safety provides a reliable keeping of the coolant in the boundaries of NPP primary circuit. More than thirty year history shows, that reactor vessel is a weak spot in this barrier, the metal of the pressure vessel is subjected to intensive irradiation. The mechanism of operational damage of pressure vessel steel is represented in Fig. 1. This article describes the works, which were conducted by VNIIAES during the last years in the field of elaboration of specimen-free methods and means of inspection (control) of physical-mechanical properties of pressure vessels welds metal of NPPs with PWR. On the base of analysis of that factors, which exercise the most substantial influence on the irradiation embrittlement of pressure vessel materials and on the base of distribution of these factors by degree of significance, there were selected the most appropriate specimen-free methods of inspection: kinetic indentation and kinetic magnetising. It was presented the description of the specimen-free methods, devices and of the results of laboratory measurements, and also the description of the manufacturing procedure and the procedure of certification of the methods on full-scale slabs from WWER-1000 pressure vessel. In the article also is described the example of using of the specimen-free methodics by full-scale inspection (control) of the metal of reactor internal components and of pressure vessel of WWER-1000 of Rostov NPP Unit 1.


Sign in / Sign up

Export Citation Format

Share Document