PassMark PerformanceTest 9.0 Build 1023 Crack UPDATED 🧨
PassMark PerformanceTest 9.0 Build 1023 Crack
a small crack formation process has been investigated in re-tubing and a re-programmed version of the passmark. this program consists of two modules: path-finding and crack formation and propagation. to improve the technical feasibility and the verification of path-finding module, we developed a new path-finding algorithm and an improved crack formation and propagation module. the new crack formation and propagation module has been tested in the above-mentioned novel cracking model. pmid:24414698
this paper is a study of failure of stainless steel pressure vessels that have, in some cases, been employed for many years in hwr nuclear reactors. the approach is to perform a partial failure analysis by cutting a specimen along a series of predetermined locations and then studying the localized failure. the intent is to characterize the localized failures (i.e., singularities) and to understand how the location, size, shape and orientation of the singularities affect the ultimate strength. the locations for cutting are based on observed stress fields. surface striations in the test specimens provide evidence for a significant stress concentration on that surface. the test specimens have been cut from nuclear grade 316 stainless steel pressure vessels, and these specimens were cut along the same predetermined locations as in the previous study. three experiments were conducted in which the stress-strain states were selected to induce failure at three of the possible singularities that may develop during a pressure vessel failure. deformation and temperature were measured and the structural material properties were calculated for each sample. the measurements of the tensile properties of the cut parts are presented and interpreted in terms of deformation, failure mechanisms and load-carrying capabilities. pmid:26564167
the cyclic stressstrain response and the low cycle fatigue (lcf) behavior of 20mnmoni55 pressure vessel steel were studied. tensile strength and lcf properties were examined at room temperature (rt) using specimens cut from rolling direction of a rolled block. the fully reversed strain-controlled lcf tests were conducted at a constant total strain rate with different axial strain amplitude levels. the cyclic strainstress relationships and the strainlife relationships were obtained through the test results, and related lcf parameters of the steel were calculated. the studied steel exhibits cyclic softening behavior. furthermore, analysis of stabilized hysteresis loops showed that the steel exhibits non-masing behavior. complementary scanning electron microscopy examinations were also carried out on fracture surfaces to reveal dominant damage mechanisms during crack initiation, propagation and fracture. multiple crack initiation sites were observed on the fracture surface. the investigated lcf behavior can provide reference for pressure vessel life assessment and fracture mechanisms analysis.
the inspection of component damage in critical areas has always been one of the most difficult tasks in component evaluation. the problem stems from the fact that the inspection of the critical areas is bound to the limitation of the inspection data. to reduce the dependency on the quality of the inspection, a better understanding of the damage evolution in the critical areas is needed. the current problem domain is the evaluation of the effect of liquid metal irradiation on the corrosion fatigue performance of pressure vessel components, including nuclear reactors. as this problem domain is highly relevant to the current state of technology, much time was spent on model development. thus, two models are presented: (1) a model for the crack distribution in the middle of the reactor vessel that is exposed to liquid metal irradiation, and (2) a model for the crack distribution in the secondary side of the reactor vessel that is exposed to liquid metal irradiation. from a modeling point of view, the crack propagation is controlled by a crack growth function that is used for the description of the crack propagation. the crack growth function is based on a damage accumulation model. the model has a damage surface that is exposed to the liquid metal irradiation. the surface is exposed to two processes: (1) the crack growth process and (2) the irradiation process. since damage evolution is a function of the total damage and the irradiation process, the total damage function contains two components. one of the components represents the initial damage and the other component is the damage that has been accumulated in the course of the irradiation process. both components are linked by the total damage function. the irradiation processes that have been implemented in the models include crack irradiation, irradiation of damage and corrosion. as the secondary side is the first area of the reactor vessel that is exposed to liquid metal irradiation, the models were validated by comparison to experimental results. the comparison showed that there is a good agreement between model predictions and experimental results. this implies that the models are able to describe the damage evolution of the secondary side of a reactor vessel when irradiated by liquid metal irradiation.