1,248 Matching Results

Search Results

Advanced search parameters have been applied.

in subjects: "Stress Analysis"

open access

Structural analysis of the West Hackbery No. 6 SPR storage cavern

Four separate structural analyses of the West Hackberry No. 6 SPR storage cavern are presented. One analysis covers the creep response of the cavern beginning shortly before the time when an accidental fire occurred and proceeding through the cavern recertification pressure test. The second analysis models the surface uplife that is expected during the same pressure test. The third and fourth numerical studies investigate the structural response of West Hackberry No. 6 to slabbing and a rapid p… more

Date: August 1, 1980

Creator: Benzley, S.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

First wall/blanket/shield design and optimization system

First wall/blanket/shield design and optimization system (BSDOS) has been developed to provide a state-of-the-art design tool for fast accurate analysis. In addition, it has been designed to perform several other functions: (1) allowing comparison and evaluation studies for different concepts using the same data bases and ground rules, (2) permitting the use of any figure of merit in the evaluation studies, (3) optimizing the first wall/blanket/shield design parameters for any figure of merit u… more

Date: February 1, 1988

Creator: Gohar, Y.; Baker, C.; Attaya, H.; Cha, Y.; Majumdar, S. & Scandora, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Boundary element formulation for planar time-dependent inelastic deformation of plates with cutouts

A boundary element formulation for planar, time-dependent, inelastic deformation problems for bodies with cutouts is presented in this paper. A stress function description for these nonlinear problems leads to a nonhomogeneous biharmonic equation for the stress function rate. An integral representation of the solution uses modified kernels which guarantee that the cutout boundary is traction free for all time. This incorporation of the effect of the cutout on the stress field into the kernels l… more

Date: February 1, 1980

Creator: Mukherjee, S. & Morjaria, M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Integrity of PWR pressure vessels during overcooling accidents

The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents vessels containing high concentrations of copper and nickel, which enhance… more

Date: January 1, 1982

Creator: Cheverton, R.D.; Iskander, S.K. & Whitman, G.D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Response of a glass melter to steam explosion

As part of the safety assessment in the design of the glass melter for large-scale immobilization of high-level radioactive wastes, structural considerations of the containment shell include its dynamic responses to abnormal loading conditions such as that caused by a steam explosion. The postulated steam explosion, conservatively given an energy content equivalent to 13 pounds of TNT, is capable of exerting sudden pressures greater than 300 psi but less than 410 psi on the melter wall. By use … more

Date: January 1, 1984

Creator: Yau, W. F. & Durant, W. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

PNL technical review of pressurized thermal-shock issues. [PWR]

Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the Nuclear Regulatory Commission (NRC) should adopt regarding the ability of reactor pressure vessels to withstand the effects of pressurized thermal shock (PTS). Licensees of eight pressurized water reactors provided NRC with estimates of remaining effective full power years before corrective actions would be required to prevent an unsafe operating condition. PNL reviewed these responses and the r… more

Date: July 1, 1982

Creator: Pedersen, L. T.; Apley, W. J.; Bian, S. H.; Defferding, L. J.; Morgenstern, M. H.; Pelto, P. J. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Frequency-domain stress prediction algorithm for the LIFE2 fatigue analysis code

The LIFE2 computer code is a fatigue/fracture analysis code that is specialized to the analysis of wind turbine components. The numerical formulation of the code uses a series of cycle mount matrices to describe the cyclic stress states imposed upon the turbine. However, many structural analysis techniques yield frequency-domain stress spectra and a large body of experimental loads (stress) data is reported in the frequency domain. To permit the analysis of this class of data, a Fourier analysi… more

Date: January 1, 1992

Creator: Sutherland, H. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Boundary element analysis of time-dependent inelastic deformation of cracked plates loaded in anti-plane shear

A boundary element analysis, for determining stresses in planar cracked bodies undergoing Mode I or Mode II inelastic deformation, has been recently published by the present authors. One primary advantage of this formulation is that the effect of the crack is incorporated in the kernels of the integral equations. Thus, traction free conditions on the crack boundary are satisfied without discretization of this boundary in a numerical calculation procedure. The inelastic deformation of cracked pl… more

Date: July 1, 1980

Creator: Mukherjee, S. & Morjaria, M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Stress-related phenomena in transient radiation-induced absorption in optical fibers

The optical properties of materials can be modified by exposure to radiation and research to investigate these radiation-induced phenomena has intensified over the last several decades. The advent of optical fiber technology and the many applications of optical fiber for information transmission have sharply increased the interest in these investigations. Optical fibers present a long optical transmission path and that path may traverse different adverse environments, including radiation areas.… more

Date: January 1, 1988

Creator: Looney, L. D.; Lyons, P. B. & Kelly, R. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Design and analysis of PCRV core cavity closure

Design requirements and considerations for a core cavity closure which led to the choice of a concrete closure with a toggle hold-down as the design for the Gas-Cooled Fast Breeder Reactor (GCFR) plant are discussed. A procedure for preliminary stress analysis of the closure by means of a three-dimensional finite element method is described. A limited parametric study using this procedure indicates the adequacy of the present closure design and the significance of radial compression developed a… more

Date: May 1, 1980

Creator: Lee, T.T.; Schwartz, A.A. & Koopman, D.C.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Analysis of LOFT steam generator main feed piping loop seal modification

The stress analysis is presented for the proposed loop seal modification to the LOFT Steam Generator Main Feed Piping. THE SAP IV finite element computer program was used to analyze normal, upset, emergency, and faulted conditions. Results of the analysis indicate that the modified main feed piping system will satisfy all structural adequacy criteria specified in Subarticle NC-3650 of the ASME Boiler and Pressure Vessel Code. Results also show that the isolation snubber configuration, specified… more

Date: February 14, 1978

Creator: Nitzel, M.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Seismic Safety Margins Research Program. Phase 1. Project V. Structural sub-system response: subsystem response review. [PWR; BWR]

This project is directed toward a portion of the Seismic Safety Margins Research Program which includes one link in the seismic methodology chain. The link addressed here is the structural subsystem dynamic response which consists of those components and systems whose behavior is often determined decoupled from the major structural response. Typically the mathematical model utilized for the major structural response will include only the mass effects of the subsystem and the main model is used … more

Date: March 1, 1980

Creator: Fogelquist, J.; Kaul, M.K.; Koppe, R.; Tagart, S.W. Jr.; Thailer, H. & Uffer, R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Constitutive model for porous materials

A simple pressure versus porosity compaction model is developed to calculate the response of granular porous bed materials to shock impact. The model provides a scheme for calculating compaction behavior when relatively limited material data are available. While the model was developed to study porous explosives and propellants, it has been applied to a much wider range of materials. The early development of porous material models, such as that of Hermann, required empirical dynamic compaction … more

Date: January 1, 1982

Creator: Weston, A. M. & Lee, E. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermal-stress analysis of a Fort St. Vrain core-support block under accident conditions

A thermoelastic stress analysis of a graphite core support block in the Fort St. Vrain High Temperature Gas Cooled Reactor is described. The support block is subjected to thermal stresses caused by a loss of forced circulation accident of the reactor system. Two- and three-dimensional finite element models of the core support block are analyzed using the ADINAT and ADINA codes, and results are given that verify the integrity of this structural component under the given accident condition.

Date: January 1, 1982

Creator: Carruthers, L. M.; Butler, T. A. & Anderson, C. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Seismic analysis of reactor exhaust air filter compartment

The Filter Compartment (FC) in this analysis is a generic reactor airborne activity confinement filter compartment which possesses all the essential physical and mechanical properties of the Savannah River Site (SRS) confinement filters of Reactor Buildings K, L, and P. The filters belong to the Airborne Activity Confinement System (AACS). These filters absorb a significant amount of radioactive effluents from the exhausting air. The seismic excitation is input indirectly from the output of the… more

Date: September 24, 1990

Creator: Gong, Chung; Funderburk, E.L. & Jerrell, J.W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Quality-assurance study of the special - purpose finite-element program - SPECTROM: I. Thermal, thermoelastic, and viscoelastic problems. [Comparison with MARC-CDC]

This comparison study involves a preliminary verification of finite element calculations. The methodology of the comparison study consists of solving four example problems with both the SPECTROM finite element program and the MARC-CDC general purpose finite element program. The results show close agreement for all example problems.

Date: December 1, 1980

Creator: Wagner, R. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Borehole-inclusion stressmeter measurements in bedded salt

Sandia purchased borehole-inclusion stressmeters from a commercial supplier to measure in situ stress changes in bedded salt. However, the supplied stressmeters were difficult to set in place and gave erratic results in bedded salt. These problems were overcome with a new extended platen design. Also a straingaged transducer was designed which can be read with a conventional data logger. Due to the nonlinear behavior of bedded salt under uniaxial loading, a new empirical calibration scheme was … more

Date: July 1, 1980

Creator: Cook, C.W. & Ames, E.S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Force analysis of the advanced neutron source control rod drive latch mechanism

The Advanced Neutron Source reactor (ANS), a proposed Department of Energy research reactor currently undergoing conceptual design at the Oak Ridge National Laboratory (ORNL), will generate a thermal neutron flux approximating 10{sup 30} M{sup {minus}2}{emdash}S{sup {minus}1}. The compact core necessary to produce this flux provides little space for the shim safety control rods, which are located in the central annulus of the core. Without proper control rod drive design, the control rod drive … more

Date: January 1, 1989

Creator: Damiano, B.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Ocean thermal energy conversion (OTEC) power system development. Preliminary design report, Appendices, Part 1 (Final)

The objective of this project is the development of a preliminary design for a full-sized, closed cycle, ammonia power system module for the 100 MWe OTEC demonstration plant. In turn, this demonstration plant is to demonstrate, by 1984, the operation and performance of an Ocean Thermal Power Plant having sufficiently advanced heat exchanger design to project economic viability for commercial utilization in the late 1980's and beyond. Included in this power system development are the preliminary… more

Date: December 4, 1978

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

End effects on elbows subjected to moment loadings. [PWR; BWR]

So-called end effects for moment loadings on short-radius and long-radius butt welding elbows of various arc lengths are investigated with a view toward providing more accurate design formulas for critical piping systems. Data developed in this study, along with published information, were used to develop relatively simple design equations for elbows attached at both ends to long sections of straight pipe. These formulas are the basis for an alternate ASME Code procedure for evaluating the bend… more

Date: January 1, 1982

Creator: Rodabaugh, E. C. & Moore, S. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Stress and strain effects on the properties of composite superconductors

Practical superconductors for use in the production of high magnetic fields are generally in the form of composites of filaments of superconducting material embedded in a matrix of normally conducting material. Lorentz forces which arise during magnet operation are examples of sources of external stress, while internal stresses can arise during the fabrication of the composite superconductor, primarily due to differential thermal contraction between different materials in the composite. The pro… more

Date: January 1, 1982

Creator: Welch, D.O.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Smoothly waning, symmetrically expanding, cavity-pressure loads in earth materials

An approximate solution for the pressure loading required to expand a spherical cavity in rock and soil targets is derived. A dual characterization of fracture and flow material model is used. Frictional resistance to flow is also included. Non-linear volumetric strain hardening is modeled with bi-linear curves and unloading is assumed to be non-dilative. Applications of this solution form to the prediction of pressure loading on slender, convex-nosed earth penetrators and on spherically-nosed … more

Date: January 1, 1982

Creator: Priddy, T.G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 9. PRAISE computer code user's manual. Load Combination Program Project I final report

The PRAISE (Piping Reliability Analysis Including Seismic Events) computer code estimates the influence of earthquakes on the probability of failure at a weld joint in the primary coolant system of a pressurized water reactor. Failure, either a through-wall defect (leak) or a complete pipe severance (a large-LOCA), is assumed to be caused by fatigue crack growth of an as-fabricated interior surface circumferential defect. These defects are assumed to be two-dimensional and semi-elliptical in sh… more

Date: June 1, 1981

Creator: Lim, E.Y.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Eulerian algorithm for analyzing fluid-structure interaction in the fast reactor containment

The Eulerian algorithm described is capable of analyzing two-dimensionally the fluid-structure interaction in a typical LMFBR containment consisting of various structure components. The algorithm has several special features. First, it employs the Eulerian coordinates in the formulation and enables the technique to be applicable to excursions involving large material distortions. Second, it provides rigorous hydrodynamic analyses at the fluid-structure interface and at the geometrical discontin… more

Date: January 1, 1977

Creator: Wang, C. Y.; Chang, Y. W. & Fistedis, S. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department