Universal treatment of plumes and stresses for pressurized thermal sho.
Universal treatment of plumes and stresses for pressurized thermal shock evaluations. Nucl eng des. Theo Theofanous. H. Yan. The thermal field in a reactor vessel downcomer and resulting thermal/stress response in the adjacent reactor vessel wall during high-pressure safety injection are examined, especially with regard to departures from one-dimensional behavior. The stress produced by thermal shock is much higher than that produced by pressure variation. The highest stress is situated at the joint of the injection pipe and the pressure vessel, and local plastic areas consequently occur in these places.
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The stress produced by thermal shock is much higher than that produced by pressure . Theofous T. Angelini . and Yan . Universal Treatment of Plumes and Stresses for Pressurized Thermal-Shock Evaluations.
The stress produced by thermal shock is much higher than that produced by pressure variation. The coupling effects of mechanical and thermal stresses have been analyzed and the influences of combined stress on the pressure vessel strength have been evaluated. joint pipe system pressure vessel finite element method coupling of mechanical and thermal stress.
Guidelines on pressurized thermal shock. Analysis for wwer nuclear power plants. These guidelines deal with the reactor pressure vessel (RPV) pressurized thermal shock (PTS) analysis required to justify RPV integrity for nuclear power plants with WWER type reactors. The guidelines provide advice on the individual elements of the PTS analysis, such as acceptance criteria, analysis methods, computer codes, and assumptions to be used as well as on quality assurance.
Theofanous correlated the results of the more detailed analysis using the . ANGELINI, S, and YAN, . Universal Treatment of Plumes and Stresses for Pressurized Thermal Shock Evaluations, . Nuclear Regulatory Commission, NUREG/CR-5854, June 1982.
Theofanous correlated the results of the more detailed analysis using the plume decay equations shown in Table 2. It is noted that these same dimensionless groups used in his correlation were also obtained in the present scaling analysis. Table 1. Governing equations for a forced axisymmetric plume Governing Balance Equations Volume Balance: Momentum Balance: Energy Balance: where λ is equal to bu/bg.
In this paper, treatment schemes to evaluate stress and resulting stress intensity factor for RPV with stainless steel clad are . Fracture mechanics is one of the major areas of the pressurized thermal shock (PTS) evaluation.
In this paper, treatment schemes to evaluate stress and resulting stress intensity factor for RPV with stainless steel clad are introduced. For a reference transient, the effects of clad thermal conductivity and thermal expansion coefficients on deterministic fracture mechanics analysis are examined. To evaluate the reactor pressure vessel integrity associated with PTS, PFM methodology demands precise calculation of temperature, stress, and stress intensity factor for the variety of PTS transients.
The stress intensity factor at crack tip is evaluated by mean the weight . UNIPI Methodology for PTS Analysis Two different cooling mechanisms, the plume and stripe cooling, are considered in connection with the determination o. .
UNIPI Methodology for PTS Analysis. The thermal load to be applied to the FE model for the stress analysis can be extrapolate from the CFD result considering the temperature profile at the interface between down-comer fluid model and RPV wall. This step is accomplished using suitable subroutines developed for this purpose. Two different cooling mechanisms, the plume and stripe cooling, are considered in connection with the determination of thermal loads.
vessel integrity for pressurized thermal shock .
Potential impact of enhanced fracture-toughness data on fracture mechanics assessment of PWR vessel integrity for pressurized thermal shock. Conference Dickson, . These two sets of data are enhanced because they have distinguishing characteristics that could potentially impact PWR pressure vessel integrity assessments for the pressurized-thermal shock (PTS) loading condition which is a major plant-life extension issue to be confronted in the 1990's. Rectification of ductile tearing technology deficiencies may require extending the technology to include amore more complete treatment of stress state and loading history effects.
International atomic energy agency, Pressurised thermal shock in nuclear power plants: good practices for .
International atomic energy agency, Pressurised thermal shock in nuclear power plants: good practices for assessment, IAEA, Austria, IAEA-TECDOC-1627, (2010). Nuclear Regulatory Commission, Code of Federal Regulations, Title 10, Section 50. 61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, (1984). The results show that the stress and strain in head of the tubular textile composite material during inversion is instability, where the stress is concentrative, so the head of the tubular textile composite material is easy to break. 945. Thermal Stress Simulation of the Surface Grinding.