Update on Impact Effects in Nuclear Plants Part III?Review of Heavy Object Drop
The consequences of an accidental drop of a heavy component from a lifting device in a nuclear power plant are required to be evaluated even though the device may have been designed using...

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...

Computer-Aided Design (Seismic Qualification) of Cable Tray Support System ? CADSTrays
A computer system for the analysis and design of cable tray hangers for nuclear power generating plants is discussed. An interactive language for the CADSTrayS was developed. Application...

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...

Seismic Evaluation of Reinforced Masonry Walls
Masonry walls in operating nuclear plants are in many cases found to be overstressed in terms of allowable stresses when evaluated using current seismic design criteria. However, experimental...

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....

State-of-the-Art of Development of Floor Spectra
Floor spectra are used as seismic inputs for the design and qualification of subsystems and equipment. Until very recently, the time history analyses with single acceleration time history...

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,...

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,...

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...

Piping Analysis: A Flexibility Approach
Design for the vertical and horizontal accelerations associated with a seismic event coupled with low allowable loads on equipment are two primary contributors to the current situation....

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...

Onsite Storage Facility for Low Level Radwaste
The Tennessee Valley Authority (TVA) has designed and constructed an onsite storage facility for low level radwaste (LLRW) at its Browns Ferry Nuclear Plant in northern Alabama. The paper...

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...

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...

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...

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...

 

 

 

 

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