Showing papers in "Nuclear Engineering and Design in 1971"

TL;DR: In this article, the authors summarized progress in the development of finite element methods for three-dimensional elastic-plastic stress analysis in fracture mechanics, focusing on the study of stress states near flaws such as a part-through crack in a pressure vessel wall.

TL;DR: In this article, the relationship between chemical structure and engineering properties and applications of common plastics and elastomers is discussed with an emphasis on the relation between chemical structures and applications and the interaction of radiation with organic materials.

TL;DR: In this article, a linear elastic fracture mechanics type formulation for predicting maximum load to fracture at any temperature was proposed, which requires a knowledge of the fracture toughness parameter K I cd and the corresponding volumetric energy ratio.

TL;DR: In this article, the Boltzmann equation for neutron transport is discussed in both integro-differential and integral form and Monte Carlo simulations of the forward and adjoint equations are discussed.

TL;DR: In this article, the failure was caused by a significant depletion in the chromium content in the weld metal, and the lack in the compositional balance was found to have originated at the overlaying of the first layer on the dissimilar base metal.

TL;DR: In this article, the fracture potential of reactor pressure vessel materials can be evaluated in terms of critical fracture load-flaw size relationships by determining the linear elastic fracture mechanics K I c toughness properties.

TL;DR: In this article, the authors measured the crack arrest toughness of A533 grade A steel and HSS plate 02 at temperatures ranging from −70°F to above 100°F and found that at low temperatures the initiation and arrest toughness were nearly equal; at higher temperatures the arrest toughness was significantly lower than the initiation toughness.

TL;DR: In this paper, the temperature and membrane stress distribution in a finite rectangular plate with an insulated circular hole was investigated, and the numerical results for temperature distribution and membrane stresses were presented.

TL;DR: In this article, the use of the discrete ordinates computer code ANISN to obtain solutions to the adjoint Boltzmann equation is discussed, which allow the calculation of transmission factors which give the tissue dose equivalent from particles transmitted through a concrete slab due to an incident source particle in a given energy-angle bin.

TL;DR: In this paper, the authors evaluated the forces and deformations of lineline plate anchors in containment structures and found that an increase in yield stress, of an amount often encountered in practice, causes a large increase in anchor force and deformation.

TL;DR: In this paper, the preparation and fabrication of actinide compounds in the pnictide and chalcoginide classes is discussed, and the properties of these compounds which would be of interest for nuclear applications are measured, and reported.

TL;DR: In this article, three welding processes are employed in the fabrication of the pressure vessels: the submerged arc (subarc) process, the shielded metal-arc process, and the electroslag process.

TL;DR: In this article, a single-bubble model for expulsion of sodium from a reactor coolant channel due to flow blockage or loss of flow transients has been developed, where the governing energy and momentum equations are numerically coupled throughout the voiding process.

TL;DR: In this paper, fast neutron induced changes in mechanical properties of a 12-in. thick manganese-molybdenum-nickel steel plate and matching submerged arc and electroslag weldments are presented.

TL;DR: In this article, general incremental forms of the equations of motion of both compressible and incompressible finite elements subjected to finite deformations are presented and applied to large deformations of viscoelastic materials in which increments in the histories of deformation gradients are used.

TL;DR: In this paper, a new mathematical model for the solution of the problem of free convection heat transfer between vertical parallel flat isothermal plates under isothermal boundary conditions, has been presented, where boundary layer equations used in the model are transformed to nonlinear coupled differential equations by similarity type variables as obtained by Ostrach for vertical flat plates in an infinite fluid medium.

TL;DR: In this paper, a cooling concept for the radial blanket region of a Fast Breeder reactor is presented which utilizes perforated ducts surrounding the blanket fuel assemblies, which generates a flow pattern which matches the sharp heat radial flux variation in the radial blankets effectively and therefore reduces coolant temperature gradients.

TL;DR: In this paper, Gross strain is defined as the axial strain at the crack location, normal to the crack plane, that would exist if the crack were not there, and the critical gross strain and critical crack opening displacement have been made for A533-B pressure vessel steel.

TL;DR: In this paper, the influence of the test loop on parallel-flow-induced vibration of fuel pins of the Na 1 fast reactor design was investigated with the same subassembly mock-up, mounted in the test section of four different flow loops with several modification.

TL;DR: In this article, the performance characteristics of sensors considered for use in protection systems of liquid metal fast breeder reactors are analyzed. And preliminary experimental data regarding vapor bubble collapse are presented, showing reasonable agreement with analytical predictions.

TL;DR: In this paper, the authors used linear elastic fracture mechanics (LEFM) data obtained with thin sections and extrapolated to project thick section fracture behavior have raised concern that this transition to high ductility may be severely depressed or eliminated near reactor operating temperatures.

TL;DR: The performance of materials containing lanthanons are reviewed with regard to chemical and metallurgical stability, irradiation damage resistance, retention of nuclear worth, and resistance to deterioration of mechanical properties.

TL;DR: In this article, the authors used the ductile-to-brittle transition temperature of the steel and how it is affected by irradiation to assess the effects of irradiation on steel pressure vessels.