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Computer-Aided Load Monitoring System for Nuclear Power Plant Steel Framing Structures
The design of nuclear power plant steel framing structures is a long and involved process. It is often complicated by numerous changes in design loads as a result of additions, deletions...

Reliability Assessment of Indian Point Unit 3 Containment Structure Under Combined Loads
In the current design criteria, the load combinations specified for design of concrete containment structures are in the deterministic format. However, by applying the probability-based...

Sensitivity of Peak Dynamic Responses to Input Factors
Responses have been calculated for the Zion Unit 1 plant, using the SSMRP computer code SMACS, as part of the seismic probabilistic risk assessment performed by the Seismic Safety Margins...

Treatment of Design and Construction Errors in PRA
The risk estimates developed in a PRA should allow for potential design and construction errors. These errors generally modify the component responses and fragilities. Since most design...

Coupled Vertical-Rocking Response of Base-Isolated Structures
A base-isolated building can have a small horizontal eccentricity between the center of mass of the superstructure and the center of rigidity of the supporting bearings. The structure...

Enhancing Quality of Construction on Nuclear Facilities
From the author's viewpoint and the viewpoint of others, the quality of construction on both nuclear projects and many other non-nuclear projects has decreased. The trend...

Techniques for Automating the Process of As-Built Reconciliation
The approach utilizes an electronic digital 'ruler' capable of measuring distances to 100 feet with a resolution of 1/100 of a foot. This ruler interfaces to...

Desin Control for Nuclear Power Plant Modifications
Modifications to operating nuclar power plants which impact structural components must be performed in a manner that is consistent with the licensing basis and technical specifications...

Microcomputer Applications for NSSS Data Package Review
Associated with each component of a Nuclear Steam Supply System are the necessary supporting documents which demonstrate compliance with applicable codes, specifications and design criteria....

New Developments in Seismic Analysis of Primary and Secondary Systems
This paper presents recent advances made at NCSU in the seismic analysis of these systems. Algorithms are presented by which coupled mode shapes and frequencies can be evaluated without...

A Study of the Correlation of the Components of Instructure Motions During Earthquakes
Thirty-two buildings are selected that have all three components of motion recorded in the basement, midheight and top of the structure. The correlation coefficients of these motions,...

Major Considerations in Scale Modeling of Reinforced Concrete Containment Structures
Reinforced concrete containment structures pose unique modeling problems, especially when leakage integrity is of interest. This paper presents a general discussion of modeling considerations...

Design Verification of HVAC Duct Turning Vanes in Nuclear Power Plants
HVAC ducts in nuclear power plants utilize short radius elbow construction with turning vanes to minimize the space requirement for duct work and to reduce flow losses in the elbows. Turning...

Evaluation of the Ultimate Pressure Capacity of Rectangular HVAC Ducts for Nuclear Power Plants
Structural design criteria are presently based on the AISI Code which limits the duct panel width-to-thickness ratio to a maximum of 500 and the maximum height-to-thickness ratio to 200,...

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...

 

 

 

 

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