Journal of Pressure Vessel Technology: Recent submissions
Now showing items 3941-3960 of 4506
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A Procedure for the Assessment of the Structural Integrity of Nuclear Pressure Vessels
(The American Society of Mechanical Engineers (ASME), 1983)This paper presents a simple engineering procedure that the utility industry can use to assess the integrity of typical nuclear-grade pressure vessels. The procedure recognizes both brittle ... -
Thermoviscoplastic Analysis of First Walls Subjected to Fusion Power Transients
(The American Society of Mechanical Engineers (ASME), 1983)Abrupt thermal fluxes on the first walls of fusion reactors represent a loading environment that requires advanced analytical capabilities. Solutions are needed to a wide range of postulated ... -
Determination of Volume of a Partially Full Horizontal Cylindrical Tank With Conical Heads
(The American Society of Mechanical Engineers (ASME), 1983) -
Design Parameters Affecting Bolt Load in Ring-Type Gasketed Joints
(The American Society of Mechanical Engineers (ASME), 1983)A simplified formula for predicting the change in bolt load from preload to operating condition in a ring-type bolted flange connection is presented. The results clearly demonstrate the important ... -
Optimizing Cylindrical and Spherical Pressure Vessels Containing Ideally Behaving Gases and Solid Inserts
(The American Society of Mechanical Engineers (ASME), 1983)Expressions were derived for the minimum outer radii of thick-walled cylindrical and spherical pressure vessels which contain a given amount of ideally behaving gas and a solid insert. -
VCE Method of J Determination for a Pressurized Pipe Under Bending
(The American Society of Mechanical Engineers (ASME), 1983)The J values for a circumferential through crack in a 4-in. (101.6-mm) schedule 80 pipe subjected to axial and bending loads were determined. The Virtual Crack Extension (VCE) method was used ... -
The Southwell Method for Predicting Plastic Buckling Loads for Elbows
(The American Society of Mechanical Engineers (ASME), 1983)The Southwell method for the prediction of buckling loads is applied to results obtained from tests of two 16-in-dia Type 304 stainless steel elbows loaded by an in-plane closing bending moment ... -
Clamped Spherical Shell Subject to Partially Applied Hydrostatic Pressure
(The American Society of Mechanical Engineers (ASME), 1983) -
Lifetime Analysis of Fusion Reactor First Wall Components
(The American Society of Mechanical Engineers (ASME), 1983)Linear elastic fracture mechanics is used to predict the growth of a semi-elliptical surface flaw through a thin-walled actively cooled 316 stainless steel first wall in a tokamak power reactor, ... -
On the Plastic and Viscoplastic Constitutive Equations—Part II: Application of Internal Variable Concepts to the 316 Stainless Steel
(The American Society of Mechanical Engineers (ASME), 1983)The constitutive equations developed in Part I with a combination of isotropic and nonlinear kinematic hardening rules can describe the usual monotonic and cyclic behavior of metals and alloys. ... -
Estimation of Creep Deformation in Components From Short-Term Proof Test Data
(The American Society of Mechanical Engineers (ASME), 1983)The paper describes a technique for estimating creep deformation from the results of short-term proof tests. The method relies on the concept of a reference stress which is representative of ... -
Corrigendum: “On a Study of the Use of the (Ṫ) Integral in Fracture Analysis of Solids With Inelastic Rate-Constitutive Laws” (Journal of Pressure Vessel Technology, 1982, 104, pp. 331–337)
(The American Society of Mechanical Engineers (ASME), 1983) -
On the Plastic and Viscoplastic Constitutive Equations—Part I: Rules Developed With Internal Variable Concept
(The American Society of Mechanical Engineers (ASME), 1983)The description of monotonic and cyclic behavior of material is possible by generalizing the internal stress concept by means of a set of internal variables. In this paper the classical isotropic ... -
Stress Redistribution During Annealing of a Multi-Pass Butt-Welded Pipe
(The American Society of Mechanical Engineers (ASME), 1983)The reduction of welding stresses during some standard post-weld heat treatments (PWHT) is numerically determined for a multi-pass butt-welded pipe made of a micro-alloyed C-Mn steel. Most of ... -
Erratum: “Dynamic Crack Curving and Branching in Line-Pipes” (Journal of Pressure Vessel Technology, 1982, 104, pp. 317–322)
(The American Society of Mechanical Engineers (ASME), 1983) -
Seismic Analysis of Structures With Coulomb Friction
(The American Society of Mechanical Engineers (ASME), 1983)A modal superposition method for the dynamic analysis of a structure with Coulomb friction is presented. The finite element method is used to derive the equations of motion, and the nonlinearities ... -
Crack Initiation Under Low-Cycle Multiaxial Fatigue in Type 316L Stainless Steel
(The American Society of Mechanical Engineers (ASME), 1983)Low-cycle fatigue tests corresponding to fatigue life range between 103 and 105 cycles were carried out at room temperature on one heat of 316 L austenitic stainless steel. These tests included: ... -
Experimental Verification of Constitutive Equations for Creep and Plasticity Based on Overlay Models
(The American Society of Mechanical Engineers (ASME), 1983)A general description of creep and plastic deformation based on overlay models is presented. This includes the description of time effects during plastic deformation at room temperature. A ... -
Stress Intensity Factors for Radial Cracks in a Pre-Stressed, Thick-Walled Cylinder of Strain-Hardening Materials
(The American Society of Mechanical Engineers (ASME), 1983)A simple method which combines the weight function technique and finite element results is used to obtain mode I stress intensity factor solutions for radially cracked cylinders subjected to a ... -
An Analysis of Dynamic Crack Propagation and Arrest in a Nuclear Pressure Vessel Under Thermal Shock Conditions
(The American Society of Mechanical Engineers (ASME), 1983)The inner wall of a nuclear pressure vessel can become embrittled during service due to irradiation effects. As a result, a small flaw could become critical during the thermal shock that would ...