scholarly journals Overview of activities in the U.S. related to continued service of nuclear power plant concrete structures

2011 ◽  
Vol 12 ◽  
pp. 01001 ◽  
Author(s):  
D.J. Naus
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Concrete Structures ◽  
The U.S

Critical Section Selection Methodology for the U.S. EPR™ Standard Nuclear Power Plant

2010 ◽  
Author(s):  
Se-Kwon Jung ◽  
Adam Goodman ◽  
Joe Harrold ◽  
Nawar Alchaar
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Structural Design ◽  
Nuclear Power ◽  
Structural Integrity ◽  
Safety Evaluation ◽  
Critical Section ◽  
Selection Methodology ◽  
Critical Sections ◽  
The U.S

This paper presents a three-tier, critical section selection methodology that is used to identify critical sections for the U.S. EPR™ Standard Nuclear Power Plant (NPP). The critical section selection methodology includes three complementary approaches: qualitative, quantitative, and supplementary. These three approaches are applied to Seismic Category I structures in a complementary fashion to identify the most critical portions of the building whose structural integrity needs to be maintained for postulated design basis events and conditions. Once the design of critical sections for a particular Seismic Category I structure is complete, the design for that structure is essentially complete for safety evaluation purposes. Critical sections, taken as a whole, are analytically representative of an “essentially complete” U.S. EPR™ design; their structural design adequacy provides reasonable assurance of overall U.S. EPR™ structural design adequacy.

Validation and Benchmarking of Comprehensive Vibration Assessment Program for Prototype Reactor Internals

2012 ◽  
Author(s):  
Jianfeng Yang ◽  
Lixin Yu ◽  
Byounghoan Choi
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Boiling Water ◽  
Pressurized Water ◽  
Water Reactor ◽  
Assessment Program ◽  
Water Reactors ◽  
The U.S ◽  
Reactor Internals

Reactor internals important to nuclear power plant safety shall be designed to accommodate steady-state and transient vibratory loads throughout the service life of the reactor. Operating experience has revealed failures of reactor internals in both pressurized water reactors (PWRs) and boiling water reactors (BWRs) due to flow-induced vibrations (FIVs). U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.20 presents a Comprehensive Vibration Assessment Program (CVAP) that the NRC staff considers acceptable for use in verifying the structural integrity of reactor internals for FIV prior to commercial operation. A CVAP supports the NRC reviews of applications for new nuclear reactor construction permits or operating licenses under 10 CFR Part 50, as well as design certifications and combined licenses that do not reference a standard design under 10 CFR Part 52. The overall CVAP should be implemented in conjunction with preoperational and initial startup testing. For prototype reactor internals, the comprehensive program should consist of a vibration and fatigue analysis, a vibration measurement program, an inspection program, and a correlation of their results. Validation and benchmarking processes should be integrated into the CVAP throughout each individual program. Based on the authors’ experiences in Advanced Boiling Water Reactor and AP1000® CVAPs and based on detailed reviews of the U.S. Evolutionary Power Reactor and the U.S. Advanced Pressurized Water Reactor CVAPs, this article summarizes the essential CVAP validation and benchmarking processes with proper consideration of bias errors and random uncertainties. This article provides guidance to a successful CVAP that satisfies the NRC requirements and ensures the reliability of the evaluation of potential adverse flow effects on nuclear power plant components.

Application of a Large-Scale Database System for the Analysis and Design of the US EPR™ Standard Nuclear Power Plant

2012 ◽  
Author(s):  
Se-Kwon Jung ◽  
Joseph Harrold ◽  
Nawar Alchaar
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Database System ◽  
Database Management System ◽  
Plane Shear ◽  
Analysis And Design ◽  
Shear Design ◽  
The U.S

Due to the increased size and complexity of large-scale commercial and industrial structures, it is increasingly challenging to manage key engineering data including analysis and design results of these structures. This paper presents a novel approach of using large-scale database systems as a means to gather, organize and manage key analysis and design results of a large-scale structure. Specifically, this paper describes in detail the development process of the backend database management system (DBMS) for the U.S. EPR™ Standard Nuclear Power Plant (NPP) Nuclear Island (NI) structures. The database system consists of three parent database tables to represent three representative groups of load combinations applicable to the U.S. EPR™ Standard NPP. Inheriting all characteristics of an applicable parent table, a primary child table in the database system represents a particular U.S. EPR™ NI Safety-Related structure in its entirety while a secondary child table a group of slabs or walls of the structure. Each secondary table is comprised of database fields that are representative of various structural demands, section capacities, reinforcing ratios, and demand-to-capacity ratios for three reinforced concrete design conditions (i.e., combined axial force and bending design, in-plane shear design, and out-of-plane shear design). The complete database system with fully populated tables is a central repository where all analysis and design results for the U.S. EPR™ NI Common Basemat structures are stored and sorted. To facilitate data queries from the developed backend database system, this paper introduces a user-friendly frontend interface program developed using Visual Basic Application (VBA) with Excel. Potential benefits of the developed database system are demonstrated with simple application examples involving simple data queries only followed by complex engineering tasks that require a more advanced form of data queries.

Summary and conclusions of a program addressing aging of nuclear power plant concrete structures

1999 ◽  
Vol 194 (1) ◽  
pp. 73-96 ◽  
Author(s):  
D.J. Naus ◽  
C.B. Oland ◽  
B.R. Ellingwood ◽  
C.J. Hookham ◽  
H.L. Graves III
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Concrete Structures

Critical Section Selection Methodology for the U.S. EPRTM Standard Nuclear Power Plant

2013 ◽  
Vol 135 (4) ◽  
Author(s):  
Se-Kwon Jung ◽  
Adam Goodman ◽  
Joseph Harrold ◽  
Nawar Alchaar
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Structural Design ◽  
Nuclear Power ◽  
Structural Integrity ◽  
Safety Evaluation ◽  
Critical Section ◽  
Selection Methodology ◽  
Critical Sections ◽  
The U.S

A three-tier critical section selection methodology that is used to identify critical sections for the U.S. EPRTM standard nuclear power plant (NPP) is presented. The critical section selection methodology includes three complementary approaches: qualitative, quantitative, and supplementary. These three approaches are applied to Seismic Category I structures in a complementary fashion to identify the most critical portions of the building whose structural integrity needs to be maintained for postulated design basis events and conditions. Once the design of critical sections for a particular Seismic Category I structure is complete, the design for that structure is essentially complete for safety evaluation purposes. Critical sections, taken as a whole, are analytically representative of an “essentially complete” U.S. EPRTM design; their structural design adequacy provides reasonable assurance of overall U.S. EPRTM structural design adequacy.

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