Modeling Techniques for Seismic Analysis of Supported Systems
An automated seismic qualification process is presented which integrates the modeling and evaluation aspects of supported system design. Emphasis is placed on baseplate and joint design....
Analytical Solution of Cable Tray Hanger 3D Structural Interaction under Seismic Loading
Structural design of cable tray hangers is controlled by the Nuclear Regulatory Commission's stringent requirements of seismic analysis. A finite element space frame model...
A Correlation Study on the Spectrum Decomposition Method
The major elements of the Spectrum Decomposition Method (SDM) are reviewed together with its automated process for generation of in-equipment response spectra (IERS). The floor required...
Transient Fluid-Structure Interaction of a Cylindrical Tank with a Flexible Baseplate
Analytically predicted coupled natural frequencies, response functions, and transient responses are compared with measured values for a partially filled cylindrical tank subject to excitation...
Fluid Structure Interaction Analysis of a Concrete Suppression Chamber of Mark I Containment System
Recent studies have demonstrated that the interaction between a structure and fluid can have a significant influence on the response of the overall system when subjected to certain dynamic...
A Pseudo Response Spectrum Method for Mark I Loads
A pseudo base motion response spectrum method is developed to uniquely evaluate the periodic condensation oscillation and chugging drag loads that may occur on submerged structures within...
Containment Integrity of SEP Plants under Combined Loads
The containment designs analyzed consisted of three inverted light-bulb shaped drywells used in boiling water reactor (BWR) systems, and three steel-lines concrete containments and a spherical...
Determination of Containment Vessel Ultimate Capacity Using Nonlinear Finite Element Analysis
Analysis of steel containment vessels is normally performed using linear elastic solutions with allowable stresses specified by applicable design codes. This method gives little indication...
Containment Capability
Section 2. 0 of this report contains a description of analysis methods for the containment structure. Testing on containment models and sections of containments is described. Section 3....
Simplified Design of Flexible Expansion Anchored Plates for Nuclear Structures
The following two phases of the design of expansion anchored plates are discussed in this paper. a) Initial Design. b) Reassessment of as-built conditions. Initial design refers to the...
Evaluation of Non-Ductile Drilled-in Expansion Bolts
This paper provides background and justification for the design of closely spaced non-ductile drilled-in expansion bolts (bolts). It describes testing used to establish allowable design...
ACI 349 Embedments: Code Provisions and Methods of Analysis
Steel embedments form the critical link between steel and concrete structures. Appendix B of ACT 349, Code Requirements for Nuclear Safety Related Concrete Structures, specifies the ultimate...
Sodium Concrete Reaction ? Structural Considerations
An overview of the sodium concrete reaction phenomenon, with emphasis on structural considerations, is presented. Available test results for limestone, basalt, and magnetite concrete with...
Capability of LMFBR Plant Structures Beyond the Design Base
A study is presented concerning the capability of structures in a loop type Liquid Metal Fast Breeder Reactor Plant, the Clinch River Breeder Reactor Plant (CRBRP), to sustain conditions...
Reduction of Seismic Response in Breeder Plants
Thin-walled vessels to be used in the Nuclear Steam Supply Systems (NSSS) of future LMFBR's will be more sensitive to seismic excitation than their equivalents used in conventional...
A New Approach to the Design of Core Support Structures for Large LMFBR Plants
The paper describes an innovative design concept for a LMFBR Core Support Structure. A hanging Core Support Structure is described and analyzed. The design offers inherent safety features,...
A Computer Integrated Engineering System for Nuclear Plant Design
The design, construction, and licensing of nuclear power facilities is a long and complicated process which can span a time period of over ten years. This tremendous lead time to plant...
Experimental Determination of Fluid-Coupling Coefficients in an Array of Hexagonal Prisms
The problem is related to the seismic analysis of fast breeder reactor cores, where the fluid trapped between the subassemblies is known to have a considerable influence on the core response....
An Estimate and Evaluation of Design Error Effects on Nuclear Power Plant Design Adequacy
An estimate by the author is found of typical error levels contained in Structural-Mechanical-Civil Design and Stress Reports. Based on the original analysis performed to demonstrate design...
Update on Impact Effects in Nuclear Plants Part II?Review of Pipe Whip Impact
Current regulations require that pipe breaks be postulated in high-energy lines and measures be taken to prevent consequent damage to essential structures and systems. The paper addressed...
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