Evaluating Heuristics for Planning Effective and Efficient Inspections

Science.gov (United States)

Shull, Forrest J.; Seaman, Carolyn B.; Diep, Madeline M.; Feldmann, Raimund L.; Godfrey, Sara H.; Regardie, Myrna

2010-01-01

A significant body of knowledge concerning software inspection practice indicates that the value of inspections varies widely both within and across organizations. Inspection effectiveness and efficiency can be measured in numerous ways, and may be affected by a variety of factors such as Inspection planning, the type of software, the developing organization, and many others. In the early 1990's, NASA formulated heuristics for inspection planning based on best practices and early NASA inspection data. Over the intervening years, the body of data from NASA inspections has grown. This paper describes a multi-faceted exploratory analysis performed on this · data to elicit lessons learned in general about conducting inspections and to recommend improvements to the existing heuristics. The contributions of our results include support for modifying some of the original inspection heuristics (e.g. Increasing the recommended page rate), evidence that Inspection planners must choose between efficiency and effectiveness, as a good tradeoff between them may not exist, and Identification of small subsets of inspections for which new inspection heuristics are needed. Most Importantly, this work illustrates the value of collecting rich data on software Inspections, and using it to gain insight into, and Improve, inspection practice.

Discussion of in-service inspection planning for nuclear power plants

International Nuclear Information System (INIS)

Aoki, Takayuki; Takagi, Toshiyuki

2012-01-01

For creating an inspection plan for industrial plants like nuclear power plants, it is necessary to have a well-grounded basis. Therefore, this paper proposes a method for determining the following three elements of such a plan: the equipment to be inspected, the inspection method to be adopted, and the timing of its implementation using a scientific approach. The key idea is to analyze the components of the plan by employing the understanding of cancer detection and diagnosis in medical science and also to take an approach of creating a plan based on the characteristic features of the component and its aging degradation mode, the performance of the inspection method, and the relationship between the two. Taking all the above into account, the factors to be considered and the best way for inspecting the plants are presented in this paper. (author)

Use of knowledge based systems for rational reliability analysis based inspection and maintenance planning for offshore structures

International Nuclear Information System (INIS)

Tang, M.X.; Dharmavasan, S.; Peers, S.M.C.

1994-01-01

The structural integrity of fixed offshore platforms is ensured by periodic inspections. In the past, decisions made as to when, where and how to inspect have been made by engineers using rules-of-thumb and general planning heuristics. It is now hoped that more rational inspection and maintenance scheduling may be carried out by applying recently developed techniques based on structural reliability methods. However, one of the problems associated with a theoretical approach is that it is not always possible to incorporate all the constraints that are present in a practical situation. These constraints modify the decisions made for analysis data input and the interpretation of the analysis results. Knowledge based systems provide a mean of encapsulating several different forms of information and knowledge within a computer system and hence can overcome this problem. In this paper, a prototype system being developed for integrating reliability based analysis with other constraints for inspection scheduling will be described. In addition, the scheduling model and the algorithms to carry out the scheduling will be explained. Furthermore, implementation details are also given

Generic Inspection Planning for Steel Structures

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Faber, Michael H.

2002-01-01

This paper presents a simplified and practically applicable approach for risk based inspection planning of fatigue sensitive structural details in steel structures. The basic idea is that the fatigue sensitive details are categorized according to their Fatigue Design Factor (FDF) and SN curve. When...

Statistical methods for the planning of inspections

International Nuclear Information System (INIS)

Hough, C.G.; Beetle, T.M.

1976-01-01

Inspection plans are designed to detect diversions of M kilograms of nuclear material with a high degree of confidence. Attribute sample plans were first developed and applied at a zero-energy fast reactor in the United Kingdom in co-operation with the Agency. Battelle-Northwest in the United States of America proposed a variables sample plan based on decision theory. The Karlsruhe Research Center in the Federal Republic of Germany developed the strategic points concept and sample plans based on game theory considerations. All these approaches were combined into a common approach which is summarized in this report. (author)

Image formation simulation for computer-aided inspection planning of machine vision systems

Science.gov (United States)

Irgenfried, Stephan; Bergmann, Stephan; Mohammadikaji, Mahsa; Beyerer, Jürgen; Dachsbacher, Carsten; Wörn, Heinz

2017-06-01

In this work, a simulation toolset for Computer Aided Inspection Planning (CAIP) of systems for automated optical inspection (AOI) is presented along with a versatile two-robot-setup for verification of simulation and system planning results. The toolset helps to narrow down the large design space of optical inspection systems in interaction with a system expert. The image formation taking place in optical inspection systems is simulated using GPU-based real time graphics and high quality off-line-rendering. The simulation pipeline allows a stepwise optimization of the system, from fast evaluation of surface patch visibility based on real time graphics up to evaluation of image processing results based on off-line global illumination calculation. A focus of this work is on the dependency of simulation quality on measuring, modeling and parameterizing the optical surface properties of the object to be inspected. The applicability to real world problems is demonstrated by taking the example of planning a 3D laser scanner application. Qualitative and quantitative comparison results of synthetic and real images are presented.

Computational framework for risk-based planning of inspections, maintenance, and condition monitoring using discrete Bayesian networks

DEFF Research Database (Denmark)

Nielsen, Jannie Sønderkær; Sørensen, John Dalsgaard

2018-01-01

This paper presents a computational framework for risk-based planning of inspections and repairs for deteriorating components. Two distinct types of decision rules are used to model decisions: simple decision rules that depend on constants or observed variables (e.g. inspection outcome...... expecte d life-cycle costs. For advanced decision rules, simulations are performed to estimate the expected costs, and dBNs are used within the simulations for decision-making. Information from inspections and condition monitoring are included if available. An example in the paper demonstrates...... the framework and the implemented strategies and decision rules, including various types of condition-based maintenance. The strategies using advanced decision rules lead to reduced costs compared to the simple decision rules when condition monitoring is applied, and the value of condition monitoring...

Inspection of licensee activities in emergency planning

International Nuclear Information System (INIS)

Van Binnebeek, J.J.; Gutierrez Ruiz, Luis Miguel; Bouvrie, E. des; Aro, Ilari; Gil, J.; Balloffet, Yves; Forsberg, Staffan; Klonk, H.; Lang, Hans-Guenter; Fichtinger, G.; Warren, T.; Manzella, P.; Gallo, R.; Koizumi, Hiroyoshi; Johnson, M.; Pittermann, P.

1998-01-01

The CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries Following discussions at several meetings on the topic of what is expected by the regulatory body regarding inspection criteria, WGIP proposed putting together a compilation of Member countries practices on regulatory inspection practices with respect to licensee emergency planning. CNRA approved this task and this report. Information was collected from a questionnaire which was issued in 1996. The report presents information on regulatory inspection activities with respect to emergency planning in NEA Member countries. The focus of the report is on the third section. It reviews the similarities and differences in inspection practices to evaluate compliance with the requirements over which the regulatory body (RB) has jurisdiction

Hanford site post-NPH building inspection plan

International Nuclear Information System (INIS)

Wagenblast, G.R. Westinghouse Hanford

1996-01-01

This plan establishes consistent post-NPH building inspection procedures and defines a procedure for prioritization of buildings for inspection to ensure the safety of facilities prior to reentry. Qualification of systems for restart of operation is not included. This plan takes advantage, where possible, of existing national procedures for post-NPH inspection of buildings, of existing structural design and evaluation documentation of Hanford facilities, and current and proposed seismic instrumentation located throughout the Hanford site. A list of buildings, prioritized according to current building safety function and building vulnerability (without regard for or information about a damaging natural forces event) is provided

29 CFR 1956.84 - Location of plan for inspection and copying.

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Location of plan for inspection and copying. 1956.84... PLANS Illinois § 1956.84 Location of plan for inspection and copying. A copy of the plan may be inspected and copied during normal business hours at the following locations: Office of State Programs, U.S...

29 CFR 1956.64 - Location of plan for inspection and copying.

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Location of plan for inspection and copying. 1956.64... PLANS New Jersey § 1956.64 Location of plan for inspection and copying. A copy of the plan may be inspected and copied during normal business hours at the following locations: Office of State Programs, U.S...

Inspection logistics planning for multi-stage production systems with applications to semiconductor fabrication lines

Science.gov (United States)

Chen, Kyle Dakai

Since the market for semiconductor products has become more lucrative and competitive, research into improving yields for semiconductor fabrication lines has lately received a tremendous amount of attention. One of the most critical tasks in achieving such yield improvements is to plan the in-line inspection sampling efficiently so that any potential yield problems can be detected early and eliminated quickly. We formulate a multi-stage inspection planning model based on configurations in actual semiconductor fabrication lines, specifically taking into account both the capacity constraint and the congestion effects at the inspection station. We propose a new mixed First-Come-First-Serve (FCFS) and Last-Come-First-Serve (LCFS) discipline for serving the inspection samples to expedite the detection of potential yield problems. Employing this mixed FCFS and LCFS discipline, we derive approximate expressions for the queueing delays in yield problem detection time and develop near-optimal algorithms to obtain the inspection logistics planning policies. We also investigate the queueing performance with this mixed type of service discipline under different assumptions and configurations. In addition, we conduct numerical tests and generate managerial insights based on input data from actual semiconductor fabrication lines. To the best of our knowledge, this research is novel in developing, for the first time in the literature, near-optimal results for inspection logistics planning in multi-stage production systems with congestion effects explicitly considered.

Hanford Facility Resource Conservation and Recovery Act Permit General Inspection Plan

International Nuclear Information System (INIS)

Beagles, D.S.

1995-02-01

This inspection plan describes the activities that shall be conducted for a general inspection of the Hanford Facility. RCRA includes a requirement that general facility inspections be conducted of the 100, 200 East, 200 West, 300, 400, and 1100 areas and the banks of the Columbia River. This plan meets the RCRA requirements and also provides for scheduling of inspections and defines general and specific items to be noted during the inspections

Designing a two-rank acceptance sampling plan for quality inspection of geospatial data products

Science.gov (United States)

Tong, Xiaohua; Wang, Zhenhua; Xie, Huan; Liang, Dan; Jiang, Zuoqin; Li, Jinchao; Li, Jun

2011-10-01

To address the disadvantages of classical sampling plans designed for traditional industrial products, we originally propose a two-rank acceptance sampling plan (TRASP) for the inspection of geospatial data outputs based on the acceptance quality level (AQL). The first rank sampling plan is to inspect the lot consisting of map sheets, and the second is to inspect the lot consisting of features in an individual map sheet. The TRASP design is formulated as an optimization problem with respect to sample size and acceptance number, which covers two lot size cases. The first case is for a small lot size with nonconformities being modeled by a hypergeometric distribution function, and the second is for a larger lot size with nonconformities being modeled by a Poisson distribution function. The proposed TRASP is illustrated through two empirical case studies. Our analysis demonstrates that: (1) the proposed TRASP provides a general approach for quality inspection of geospatial data outputs consisting of non-uniform items and (2) the proposed acceptance sampling plan based on TRASP performs better than other classical sampling plans. It overcomes the drawbacks of percent sampling, i.e., "strictness for large lot size, toleration for small lot size," and those of a national standard used specifically for industrial outputs, i.e., "lots with different sizes corresponding to the same sampling plan."

Optimal, Generic Planning of Maintenance and Inspection of Steel Bridges

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Faber, Michael Havbro

2002-01-01

Fatigue damage is an important deterioration mechanism for steel bridges. This paper describes a simplified and generic approach for reliability and risk based inspection planning of fatigue sensitive structural details. Fatigue sensitive details are categorized according to their loading charact...

Acceptance inspection plan 105KE Facility modifications for fuel retrieval subproject

International Nuclear Information System (INIS)

Shen, E.J.

1998-01-01

The acceptance inspection of construction by Fluor Daniel Hanford (FDH) is performed to provide assurance that fabrication, construction, and installation are in accordance with approved contract documents. Approved contract documents used to perform inspections may include specifications, drawings, and contractor submittals such as fabrication drawings, procedures, etc. The amount or degree of inspection activity is tailored to the project as determined by the project team so that the effort and cost expended are commensurate with the importance of the facility in terms of function and safety. Inspections are documented to provide verification of the acceptability of the work performed. This document identifies the inspections and documentation forms to be provided. It is prepared and implemented with the understanding that the construction contractor is fully responsible for compliance with contract documents and for the quality of work performed. Inspections performed are in accordance with approved procedures. The Manager of Acceptance Inspection is responsible for the implementation of this plan and assignment of personnel for the work. Inspections are conducted by personnel who are qualified and certified, to perform their assigned task. The Acceptance Inspection Plan is organized in the Construction Specification Institute (CSI) format to cross reference design specification sections with sections of the AI Plan. In each AI Plan section the applicable specification section subject will be identified followed by the appropriate inspection requirements. General surveillances will be listed when applicable. Acceptance Inspection Reports are provided to document inspections not documented on a test report (i.e., Soil Test Data, Concrete Test Report, NDE/Weld Record, Leak/Pressure Test Certification, Backflow Device Test Report, Nonconformance Report, Deficiency Report, and/or Contractors testing forms)

Acceptance inspection plan 105KW Facility modifications for fuel retrieval subproject

International Nuclear Information System (INIS)

Shen, E.J.

1998-01-01

The acceptance inspection of construction by Fluor Daniel Hanford (FDH) is performed to provide assurance that fabrication, construction, and installation are in accordance with approved contract documents. Approved contract documents used to perform inspections may include specifications, drawings, and contractor submittals such as fabrication drawings, procedures, etc. The amount or degree of inspection activity is tailored to the project as determined by the project team so that the effort and cost expended are commensurate with the importance of the facility in terms of function and safety. Inspections are documented to provide verification of the acceptability of the work performed. This document identifies the inspections and documentation forms to be provided. It is prepared and implemented with the understanding that the construction contractor is fully responsible for compliance with contract documents and for the quality of.work performed. Inspections performed are in accordance with approved procedures. The Manager of Acceptance Inspection is responsible for the implementation of this plan and assignment of personnel for the work. Inspections are conducted by personnel who are qualified and certified to perform their assigned task. The Acceptance Inspection Plan is organized in the Construction Specification Institute (CSI) format to cross reference design specification sections with sections of the AI Plan. In each AI Plan section the applicable specification section subject will be identified followed by the appropriate inspection requirements. General surveillances will be listed when applicable. Acceptance Inspection Reports are provided to document inspections not documented on a test report (i.e., Soil Test Data, Concrete Test Report, NDE/Weld Record, Leak/Pressure Test Certification, Backflow Device Test Report, Nonconformance Report, Deficiency Report, and/or Contractors testing forms)

B Plant Complex generator dangerous waste storage areas inspection plan: Revision 1

International Nuclear Information System (INIS)

Beam, T.G.

1994-01-01

This document contains the inspection plan for the <90 day dangerous/mixed waste storage areas and satellite accumulation areas at B Plant Complex. This inspection plan is designed to comply with all applicable federal, state and US Department of Energy-Richland Operations Office training requirements. In particular, the requirements of WAC 173-303 ''Dangerous Waste Regulations'' are met by this inspection plan. This inspection plan is designed to provide B Plant Complex with the records and documentation showing that the waste storage and handling program is in compliance with applicable regulations. The plan also includes the requirements for becoming a qualified inspector of waste storage areas and the responsibilities of various individuals and groups at B Plant Complex

B Plant treatment, storage, and disposal (TSD) units inspection plan

International Nuclear Information System (INIS)

Beam, T.G.

1996-01-01

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ''Dangerous Waste Regulations'' (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements

Trajectory planning of tokamak flexible in-vessel inspection robot

Energy Technology Data Exchange (ETDEWEB)

Wang, Hesheng [Department of Automation, Shanghai Jiao Tong University, 200240 Shanghai (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China, 200240 Shanghai (China); Chen, Weidong, E-mail: wdchen@sjtu.edu.cn [Department of Automation, Shanghai Jiao Tong University, 200240 Shanghai (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China, 200240 Shanghai (China); Lai, Yinping; He, Tao [Department of Automation, Shanghai Jiao Tong University, 200240 Shanghai (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China, 200240 Shanghai (China)

2015-10-15

Highlights: • A tokamak flexible in-vessel inspection robot is designed. • Two trajectory planning methods are used to ensure the full coverage of the first wall scanning. • The method is tested on a simulated platform of EAST with the flexible in-vessel inspection robot. • Experimental results show the effectiveness of the proposed algorithm. - Abstract: Tokamak flexible in-vessel inspection robot is mainly designed to carry a camera for close observation of the first wall of the vacuum vessel, which is essential for the maintenance of the future tokamak reactor without breaking the working condition of the vacuum vessel. A tokamak flexible in-vessel inspection robot is designed. In order to improve efficiency of the remote maintenance, it is necessary to design a corresponding trajectory planning algorithm to complete the automatic full coverage scanning of the complex tokamak cavity. Two different trajectory planning methods, RS (rough scanning) and FS (fine scanning), according to different demands of the task, are used to ensure the full coverage of the first wall scanning. To quickly locate the damage position, the first trajectory planning method is targeted for quick and wide-ranging scan of the tokamak D-shaped section, and the second one is for careful observation. Furthermore, both of the two different trajectory planning methods can ensure the full coverage of the first wall scanning with an optimal end posture. The method is tested on a simulated platform of EAST (Experimental Advanced Superconducting Tokamak) with the flexible in-vessel inspection robot, and the results show the effectiveness of the proposed algorithm.

Trajectory planning of tokamak flexible in-vessel inspection robot

International Nuclear Information System (INIS)

Wang, Hesheng; Chen, Weidong; Lai, Yinping; He, Tao

2015-01-01

Highlights: • A tokamak flexible in-vessel inspection robot is designed. • Two trajectory planning methods are used to ensure the full coverage of the first wall scanning. • The method is tested on a simulated platform of EAST with the flexible in-vessel inspection robot. • Experimental results show the effectiveness of the proposed algorithm. - Abstract: Tokamak flexible in-vessel inspection robot is mainly designed to carry a camera for close observation of the first wall of the vacuum vessel, which is essential for the maintenance of the future tokamak reactor without breaking the working condition of the vacuum vessel. A tokamak flexible in-vessel inspection robot is designed. In order to improve efficiency of the remote maintenance, it is necessary to design a corresponding trajectory planning algorithm to complete the automatic full coverage scanning of the complex tokamak cavity. Two different trajectory planning methods, RS (rough scanning) and FS (fine scanning), according to different demands of the task, are used to ensure the full coverage of the first wall scanning. To quickly locate the damage position, the first trajectory planning method is targeted for quick and wide-ranging scan of the tokamak D-shaped section, and the second one is for careful observation. Furthermore, both of the two different trajectory planning methods can ensure the full coverage of the first wall scanning with an optimal end posture. The method is tested on a simulated platform of EAST (Experimental Advanced Superconducting Tokamak) with the flexible in-vessel inspection robot, and the results show the effectiveness of the proposed algorithm.

29 CFR 1952.156 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... inspected and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.156 Section 1952.156..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS North Carolina § 1952...

29 CFR 1952.96 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... inspected and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.96 Section 1952.96..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS South Carolina § 1952...

29 CFR 1952.381 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... inspected and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.381 Section 1952.381..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Puerto Rico § 1952...

Study of a risk-based piping inspection guideline system.

Science.gov (United States)

Tien, Shiaw-Wen; Hwang, Wen-Tsung; Tsai, Chih-Hung

2007-02-01

A risk-based inspection system and a piping inspection guideline model were developed in this study. The research procedure consists of two parts--the building of a risk-based inspection model for piping and the construction of a risk-based piping inspection guideline model. Field visits at the plant were conducted to develop the risk-based inspection and strategic analysis system. A knowledge-based model had been built in accordance with international standards and local government regulations, and the rational unified process was applied for reducing the discrepancy in the development of the models. The models had been designed to analyze damage factors, damage models, and potential damage positions of piping in the petrochemical plants. The purpose of this study was to provide inspection-related personnel with the optimal planning tools for piping inspections, hence, to enable effective predictions of potential piping risks and to enhance the better degree of safety in plant operations that the petrochemical industries can be expected to achieve. A risk analysis was conducted on the piping system of a petrochemical plant. The outcome indicated that most of the risks resulted from a small number of pipelines.

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

2002-05-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

1999-09-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

Reliability Assessment and Reliability-Based Inspection and Maintenance of Offshore Wind Turbines

DEFF Research Database (Denmark)

Ramírez, José G. Rangel; Sørensen, John Dalsgaard

2009-01-01

Probabilistic methodologies represent an important tool to identify the suitable strategy to inspect and deal with the deterioration in structures such as offshore wind turbines (OWT). Reliability based methods such as Risk Based Inspection (RBI) planning may represent a proper methodology to opt...

Risk-based inspection in the context of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G., E-mail: soaresw@cdtn.br, E-mail: vasconv@cdtn.br, E-mail: egr@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

Risk-based inspection in the context of nuclear power plants

International Nuclear Information System (INIS)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G.

2015-01-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

Risk-based priorities for inspection of nuclear pressure boundary components at selected LWRs

International Nuclear Information System (INIS)

Vo, T.V.; Simonen, F.A.; Gore, B.F.; Doctor, S.R.; Smith, B.W.

1990-01-01

Data from existing probabilistic risk assessments for eight representative nuclear power plants were used to identify and prioritize the most relevant systems to plant safety. The objective of this paper is to assess current in-service inspection requirements for pressure boundary systems and components, and to develop recommendations for improvements. This study demonstrates the feasibility of using risk-based methods to develop plant-specific inspection plans. Results for the eight representative plants also indicate generic trends that suggest improvements in current inspection plans now based on priorities set in accordance with code definitions of Class 1, 2, and 3 systems

Risk-based priorities for inspection of nuclear pressure boundary components at selected LWRs

International Nuclear Information System (INIS)

Vo, T.V.; Simonen, F.A.; Gore, B.F.; Doctor, S.R.; Smith, B.W.

1990-03-01

Data from existing probabilistic risk assessments for eight representative nuclear power plants were used to identify and prioritize the most relevant systems to plant safety. The objective was to assess current in-service inspection requirements for pressure boundary systems and components, and to develop recommendations for improvements. This study demonstrates the feasibility of using risk-based methods to develop plant-specific inspection plans. Results for the eight representative plants also indicate generic trends that suggest improvements in current inspection plans now based on priorities set in accordance with code definitions of Class 1, 2, and 3 systems. 2 refs., 4 figs., 5 tabs

Hanford Facility resource conservation and recovery act permit general inspection plan

International Nuclear Information System (INIS)

Beagles, D.B.

1995-12-01

The Hanford Facility Resource Conservation and Recovery Act Permit, General Inspection Requirements, includes a requirement that general facility inspections be conducted of the 100, 200 East, 200 West, 300, 400, and 1100 Areas and the banks of the Columbia River. This inspection plan describes the activities that shall be conducted for a general inspection of the Hanford Facility

Double-shell tank ultrasonic inspection plan. Revision 1

International Nuclear Information System (INIS)

Pfluger, D.C.

1994-01-01

The waste tank systems managed by the Tank Waste Remediation System Division of Westinghouse Hanford Company includes 28 large underground double-shell tanks (DST) used for storing hazardous radioactive waste. The ultrasonic (UT) inspection of these tanks is part of their required integrity assessment (WAC 1993) as described in the tank systems integrity assessment program plan (IAPP) (Pfluger 1994a) submitted to the Ecology Department of the State of Washington. Because these tanks hold radioactive waste and are located underground examinations and inspections must be done remotely from the tank annuli with specially designed equipment. This document describes the UT inspection system (DSTI system), the qualification of the equipment and procedures, field inspection readiness, DST inspections, and post-inspection activities. Although some of the equipment required development, the UT inspection technology itself is the commercially proven and available projection image scanning technique (P-scan). The final design verification of the DSTI system will be a performance test in the Hanford DST annulus mockup that includes the demonstration of detecting and sizing corrosion-induced flaws

Risk Based Inspection of Gas-Cooling Heat Exchanger

Directory of Open Access Journals (Sweden)

Dwi Priyanta

2017-09-01

Full Text Available On October 2013, Pertamina Hulu Energi Offshore North West Java (PHE – ONWJ platform personnel found 93 leaking tubes locations in the finfan coolers/ gas-cooling heat exchanger. After analysis had been performed, the crack in the tube strongly indicate that stress corrosion cracking was occurred by chloride. Chloride stress corrosion cracking (CLSCC is the cracking occurred by the combined influence of tensile stress and a corrosive environment. CLSCC is the one of the most common reasons why austenitic stainless steel pipework or tube and vessels deteriorate in the chemical processing, petrochemical industries and maritime industries. In this thesis purpose to determine the appropriate inspection planning for two main items (tubes and header box in the gas-cooling heat exchanger using risk based inspection (RBI method. The result, inspection of the tubes must be performed on July 6, 2024 and for the header box inspection must be performed on July 6, 2025. In the end, RBI method can be applicated to gas-cooling heat exchanger. Because, risk on the tubes can be reduced from 4.537 m2/year to 0.453 m2/year. And inspection planning for header box can be reduced from 4.528 m2/year to 0.563 m2/year.

GASVOL 18'' gas pipeline - risk based inspection study

Energy Technology Data Exchange (ETDEWEB)

Bjoernoey, Ola H.; Etterdal, Birger A. [Det Norske Veritas (DNV), Oslo (Norway); Guarize, Rosimar; Oliveira, Luiz F.S. [Det Norske Veritas (DNV) (Brazil); Faertes, Denise; Dias, Ricardo [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil)

2003-07-01

This paper describes a risk based approach and inspection planning as part of the Pipeline Integrity Management (PIM) system for the 95.5 km long 18'' GASVOL gas pipeline in the South eastern region of Brazil transporting circa 5 000 000 m3 dry gas per day. Pipeline systems can be subject to several degradation mechanisms and inspection and monitoring are used to ensure system integrity. Modern pipeline regulations and codes are normally based on a core safety or risk philosophy. The detailed design requirements presented in design codes are practical interpretations established so as to fulfill these core objectives. A given pipeline, designed, constructed and installed according to a pipeline code is therefore the realization of a structure, which, along its whole length, meets the applicable safety objectives of that code. The main objective of Pipeline Integrity Management (PIM) is to control and document the integrity of the pipeline for its whole service life, and to do this in a cost-effective manner. DNV has a specific approach to RBI planning, starting with an initial qualitative assessment where pipelines and damage type are ranked according to risk and potential risk reduction by an inspection and then carried forward to a quantitative detailed assessment where the level of complexity and accuracy can vary based on availability of information and owner needs. Detailed assessment requires significant effort in data gathering. The findings are dependent upon the accuracy of the inspection data, and on DNV's interpretation of the pipeline reference system and simplifications in the inspection data reported. The following specific failure mechanisms were investigated: internal corrosion, external corrosion, third party interference, landslides and black powder. RBI planning, in general words, is a 'living process'. In order to optimize future inspections, it is essential that the analyses utilize the most recent information regarding

A Novel Method of Autonomous Inspection for Transmission Line based on Cable Inspection Robot LiDAR Data

Directory of Open Access Journals (Sweden)

Xinyan Qin

2018-02-01

Full Text Available With the growth of the national economy, there is increasing demand for electricity, which forces transmission line corridors to become structurally complicated and extend to complex environments (e.g., mountains, forests. It is a great challenge to inspect transmission line in these regions. To address these difficulties, a novel method of autonomous inspection for transmission line is proposed based on cable inspection robot (CIR LiDAR data, which mainly includes two steps: preliminary inspection and autonomous inspection. In preliminary inspection, the position and orientation system (POS data is used for original point cloud dividing, ground point filtering, and structured partition. A hierarchical classification strategy is established to identify the classes and positions of the abnormal points. In autonomous inspection, CIR can autonomously reach the specified points through inspection planning. These inspection targets are imaged with PTZ (pan, tilt, zoom cameras by coordinate transformation. The feasibility and effectiveness of the proposed method are verified by test site experiments and actual line experiments, respectively. The proposed method greatly reduces manpower and improves inspection accuracy, providing a theoretical basis for intelligent inspection of transmission lines in the future.

Standard Ship Test and Inspection Plan, Procedures and Database

National Research Council Canada - National Science Library

1999-01-01

... construction schedules and increased cost is the area of test and inspection. This project investigates existing rules and regulations for testing and inspection of commercial ships and identifies differences and similarities within the requirements. The results include comparison matrices, a standard test plan, a set of standard test procedures, and a sample test database developed for a typical commercial ship.

INSPTRAX - The Inspection Targeting, Planning and Tracking Database

Data.gov (United States)

U.S. Environmental Protection Agency — The INSPTRAX System tracks Air, RCRA, and Water inspection targeting, planning and tracking information. It is used by the the Air, RCRA, and Water programs to input...

Monitoring well inspection and maintenance plan Y-12 Plant, Oak Ridge, Tennessee (revised)

International Nuclear Information System (INIS)

1996-09-01

Inspection and maintenance of groundwater monitoring wells is a primary element of the Oak Ridge Y-12 Plant Groundwater Protection Program (GWPP). This document is the revised groundwater monitoring well inspection and maintenance plan for the U.S. Department of Energy (DOE) Y-12 Plant in Oak Ridge, Tennessee. The plan provides a systematic program for: (1) inspecting the physical condition of monitoring wells at the Y-12 Plant and (2) identifying maintenance needs that will extend the life of each well and ensure that representative groundwater quality samples and hydrologic data are collected from the wells. Original documentation for the Y-12 Plant GWPP monitoring well inspection and maintenance program was provided in HSW, Inc. 1991a. The original revision of the plan specified that only a Monitoring Well Inspection/Maintenance Summary need be updated and reissued each year. Rapid growth of the monitoring well network and changing regulatory requirements have resulted in constant changes to the status of wells (active or inactive) listed on the Monitoring Well Inspection/Maintenance Summary. As a result, a new mechanism to track the status of monitoring wells has been developed and the plan revised to formalize the new business practices. These changes are detailed in Sections 2.4 and 2.5

Comparative Study on Urban Planning Inspection System in the UK and China

Institute of Scientific and Technical Information of China (English)

2012-01-01

The urban-rural planning inspector system of China is hierarchical supervision over local governments from the Central Government in respect of town and country development. The comparative analysis on planning inspection system of the UK may provide experience in seeking solutions to the problems occurring in the system of China. The planning inspector system of China can be improved in six aspects such as establishing the legal status, setting up the planning inspection agency, completing the personnel management system, enhancing the legal binding force, building the internal and external supervision channel, supplementing the relieve function, and establishing the coordination mechanism of various internal supervisions.

Preliminary inspection of secondary cooling system piping for maintenance plan in JMTR

International Nuclear Information System (INIS)

Hanakawa, Hiroki; Hanawa, Yoshio; Izumo, Hironobu; Fukasaku, Akitomi; Nagao, Yoshiharu; Miyazawa, Masataka; Niimi, Motoji

2008-01-01

The JMTR is under the refurbishment and will start on FY 2011. The JMTR will operate for about 20 years from 2011. Before this JMTR operation, preliminary inspection of secondary cooling system piping was carried out in order to make a maintenance plan. As the results of this inspection, it was confirmed that the corrosion was reached by piping ingot, or decrease of piping thickness could hardly be observed. Therefore, it was confirmed that the strength or the functionality of the piping had been maintained by usual operation and maintenance. According to the results of this inspection, the basic date for maintenances are confirmed and it is clear to be able to make the maintenances plan in future. (author)

29 CFR 1952.356 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.356 Section 1952.356..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Arizona § 1952.356...

29 CFR 1952.206 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.206 Section 1952.206..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Minnesota § 1952.206...

29 CFR 1952.216 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.216 Section 1952.216..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Maryland § 1952.216...

29 CFR 1952.236 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.236 Section 1952.236..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Kentucky § 1952.236...

29 CFR 1952.296 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.296 Section 1952.296..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Nevada § 1952.296...

29 CFR 1952.226 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.226 Section 1952.226..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Tennessee § 1952.226...

29 CFR 1952.346 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.346 Section 1952.346..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Wyoming § 1952.346...

29 CFR 1952.266 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.266 Section 1952.266..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Michigan § 1952.266...

29 CFR 1952.315 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.315 Section 1952.315..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Hawaii § 1952.315...

29 CFR 1952.245 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.245 Section 1952.245..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Alaska § 1952.245...

29 CFR 1952.171 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.171 Section 1952.171..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS California § 1952.171...

29 CFR 1952.376 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.376 Section 1952.376..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Virginia § 1952.376...

29 CFR 1952.326 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.326 Section 1952.326..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Indiana § 1952.326...

29 CFR 1952.271 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.271 Section 1952.271..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Vermont § 1952.271...

29 CFR 1952.106 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.106 Section 1952.106..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Oregon § 1952.106...

29 CFR 1952.121 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.121 Section 1952.121..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Washington § 1952.121...

29 CFR 1952.366 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... and copied during normal business hours at the following locations: Office of State Programs... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.366 Section 1952.366..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS New Mexico § 1952.366...

29 CFR 1956.41 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... business hours at the following locations: Office of State programs, 2100 M Street NW, Room 149, Washington... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1956.41 Section 1956.41..., DEPARTMENT OF LABOR (CONTINUED) STATE PLANS FOR THE DEVELOPMENT AND ENFORCEMENT OF STATE STANDARDS APPLICABLE...

29 CFR 1952.116 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... copied during normal business hours at the following locations: Office of State Programs, Occupational... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.116 Section 1952.116..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Utah § 1952.116 Where...

29 CFR 1952.166 - Where the plan may be inspected.

Science.gov (United States)

2010-07-01

... copied during normal business hours at the following locations: Office of State Programs, Occupational... 29 Labor 9 2010-07-01 2010-07-01 false Where the plan may be inspected. 1952.166 Section 1952.166..., DEPARTMENT OF LABOR (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS Iowa § 1952.166 Where...

Calculation of parameters for inspection planning and evaluation: mixed-oxide fuel fabrication facilities

International Nuclear Information System (INIS)

Reardon, P.T.; Mullen, M.F.

1982-08-01

As part of Task C.35 (Calculation of Parameters for Inspection Planning and Evaluation) of the US Program of Technical Assistance to IAEA Safeguards, Pacific Northwest Laboratory has performed some quantitative analyses of IAEA inspection activities for mixed-oxide fuel fabrication facilities. There were four distinct efforts involved in this task. These were as follows: show the effect on a material balance verification of using two variables measurement methods in some strata; perform additional calculations for the reference facility described in STR-89; modify the INSPECT computer programs to be used as an after-inspection analysis tool, as well as a preinspection planning tool; provide written comments and explantations of text and graphs of the first draft of STR-89, Safeguards Considerations for Mixed-Oxide Fuel Element Fabrication Facilities, by W. Bahm, T. Shea, and D. Tolchenkov, System Studies Section, IAEA

Performance-based inspection and maintenance strategies

International Nuclear Information System (INIS)

Vesely, W.E.

1995-01-01

Performance-based inspection and maintenance strategies utilize measures of equipment performance to help guide inspection and maintenance activities. A relevant measure of performance for safety system components is component unavailability. The component unavailability can also be input into a plant risk model such as a Probabilistic Risk Assessment (PRA) to determine the associated plant risk performance. Based on the present and projected unavailability performance, or the present and projected risk performance, the effectiveness of current maintenance activities can be evaluated and this information can be used to plan future maintenance activities. A significant amount of information other than downtimes or failure times is collected or can be collected when an inspection or maintenance is conducted which can be used to estimate the component unavailability. This information generally involves observations on the condition or state of the component or component piecepart. The information can be detailed such as the amount of corrosion buildup or can be general such as the general state of the component described as ' high degradation', ' moderate degradation', or ' low degradation'. Much of the information collected in maintenance logs is qualitative and fuzzy. As part of an NRC Research program on performance-based engineering modeling, approaches have been developed to apply Fuzzy Set Theory to information collected on the state of the component to determine the implied component or component piecepart unavailability. Demonstrations of the applications of Fuzzy Set Theory are presented utilizing information from plant maintenance logs. The demonstrations show the power of Fuzzy Set Theory in translating engineering information to reliability and risk implications

Optimal inspection planning for onshore pipelines subject to external corrosion

International Nuclear Information System (INIS)

Gomes, Wellison J.S.; Beck, André T.; Haukaas, Terje

2013-01-01

Continuous operation of pipeline systems involves significant expenditures in inspection and maintenance activities. The cost-effective safety management of such systems involves allocating the optimal amount of resources to inspection and maintenance activities, in order to control risks (expected costs of failure). In this context, this article addresses the optimal inspection planning for onshore pipelines subject to external corrosion. The investigation addresses a challenging problem of practical relevance, and strives for using the best available models to describe random corrosion growth and the relevant limit state functions. A single pipeline segment is considered in this paper. Expected numbers of failures and repairs are evaluated by Monte Carlo sampling, and a novel procedure is employed to evaluate sensitivities of the objective function with respect to design parameters. This procedure is shown to be accurate and more efficient than finite differences. The optimum inspection interval is found for an example problem, and the robustness of this optimum to the assumed inspection and failure costs is investigated. It is shown that optimum total expected costs found herein are not highly sensitive to the assumed costs of inspection and failure. -- Highlights: • Inspection, repair and failure costs of pipeline systems considered. • Optimum inspection schedule (OIS) obtained by minimizing total expected life-cycle costs. • Robustness of OIS evaluated w.r.t. estimated costs of inspection and failure. • Accurate non-conservative models of corrosion growth employed

Prospects offered by the departmental plans inspection; Les perspectives offertes par la revision des plans departementaux

Energy Technology Data Exchange (ETDEWEB)

Thauvin, Ph.

2000-07-01

In the framework of the departmental plans inspection, a detailed document is presented on the domestic and industrial wastes management. These plans forecast an increase of the recycling facing the incineration, a mastership of the costs, a better application of the regulations and a campaign of public information. The indicators of control and the main points of these plans are discussed, supported by tables and definitions. (A.L.B.)

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

International Nuclear Information System (INIS)

Van Binnebeek, J.J.; Aubrey, Richard; Grandame, Melvyn; Aro, Ilari; Balloffet, Yves; Klonk, Hartmut; Manzella, Pietro; Koizumi, Hiroyoshi; Bouvrie, E.C. des; Forsberg, Staffan; Lang, Hans-Guenter; Mehew, Robert; Warren, Thomas; Woodhouse, Paul; Gallo, Robert M.; Campbell, Rob; )

1997-01-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

Energy Technology Data Exchange (ETDEWEB)

Van Binnebeek, J. J. [AIB-Vincotte Nuclear - AVN, Avenue du Roi, 157, B-1060 Brussels (Belgium); Aubrey, Richard; Grandame, Melvyn [Atomic Energy Control Board - AECB, P.O. Box 1046, Station B, 280 Slater Street, Ottawa, Ontario K1P 5S9 (Canada); Aro, Ilari [Finnish Centre for Radiation and Nuclear Safety - STUK, P.O. Box 14, FIN-00881 Helsinki (Finland); Balloffet, Yves [DRIRE Rhone Alpes, 146, rue Pierre Corneille, 69426 Lyon CEDEX 03 (France); Klonk, Hartmut [Bundesamt fuer Strahlenschutz - BfS, Federal Office for Radiation Protection, Postbox 10 01 49, 38201 Salzgitter 1 (Germany); Manzella, Pietro [A.N.P.A., Via V. Brancati, 48, 1-00144 Roma EUR (Italy); Koizumi, Hiroyoshi [Tech. Stan. Dept. - JAPEIC, Shin-Toranomon Bldg., 1-5-11, Akasaka, Minato-ku, Tokyo 107 (Japan); Bouvrie, E.C. des [Ministry of Social Affairs and Employment, Nuclear Safety Dept. KFD, P.O. Box 90804, 2509 LV The Hague (Netherlands); Forsberg, Staffan [Swedish Nuclear Power Inspectorate - SKI, Klarabergsviadukten 90, S-10658 Stockholm (Sweden); Lang, Hans-Guenter [Section Plant Coordination and Inspection, Swiss Federal Nuclear Safety Inspectorate - HSK, CH-5232 Villigen-HSK (Switzerland); Mehew, Robert; Warren, Thomas; Woodhouse, Paul [Health and Safety Executive - NII, St. Peter' s House, Balliol Road, Bootle, Merseyside L20 3LZ (United Kingdom); Gallo, Robert M. [Special Inspection Branch, US Nuclear Regulatory Commission - US NRC, Mail Stop 0-9A1, Washington, DC 20555 (United States); Campbell, Rob [International Atomic Energy Agency - IAEA, P.O. Box 100, A-1400 Vienna (International Atomic Energy Agency (IAEA))

1997-07-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities.

Activities for turbine maintenance: planning, implementation and evaluation of inspection results

International Nuclear Information System (INIS)

Azcue, J.; Sanchez, M. A.; Alvaro, M.

2014-01-01

The article will cover the most significant aspects of how Tecnatom carry out the turbine maintenance work, both from the point of view of the inspection itself as the pre-and post tasks associated. Thus, the issues that will be part of the article are the Manual Inspection Service (MISI) and the inspection database, ISI WEB. These tools are essential for planning field work and serve as a guide to run later turbine inspections in different plants. Following this introduction the inspection teams and the techniques used by Tecnatom will be described. finally, the article will contain a small mention about management studies of life and integrity analysis of the turbine that can be performed, as well as involvement in its safe operation that is derived from them. Ultimately, the intention is to provide a comprehensive approach to the issue in question, the turbine maintenance work, so that the reader can get an ideal of the whole process. (Author)

Application of risk-based methods for inspection of nuclear power plant components

International Nuclear Information System (INIS)

Balkey, K.R.

1992-01-01

In-service inspections (ISIs) can play a significant role in minimizing equipment and structural failures. All aspects of inspections, i.e., objectives, method, timing, and the acceptance criteria for detected flaws can affect the probability of component failure. Where ISI programs exist, they are primarily based on prior experience and engineering judgment. At best, some include an implicit consideration of risk (probability of failure multiplied by consequence). Since late 1988, a multidisciplined American Society of Mechanical Engineers (ASME) Research Task Force on Risk-Based Inspection Guidelines has been addressing the general question of how to formally incorporate risk considerations into plans and requirements for the ISI of components and structural systems. The task force and steering committee that guided the project have concluded that appropriate analytical methods exist for evaluating and quantifying risks associated with pressure boundary and structural failures. With the support of about a dozen industry and government organizations, the research group has recommended a general methodology for establishing a risk-based inspection program that could be applied to any nuclear system or structural system

Risk-based inspection and maintenance systems for steam turbines

International Nuclear Information System (INIS)

Fujiyama, Kazunari; Nagai, Satoshi; Akikuni, Yasunari; Fujiwara, Toshihiro; Furuya, Kenichiro; Matsumoto, Shigeru; Takagi, Kentaro; Kawabata, Taro

2004-01-01

The risk-based maintenance (RBM) system has been developed for steam turbine plants coupled with the quick inspection systems. The RBM system utilizes the field failure and inspection database accumulated over 30 years. The failure modes are determined for each component of steam turbines and the failure scenarios are described as event trees. The probability of failure is expressed in the form of unreliability functions of operation hours or start-up cycles through the cumulative hazard function method. The posterior unreliability is derived from the field data analysis according to the inspection information. Quick inspection can be conducted using air-cooled borescope and heat resistant ultrasonic sensors even if the turbine is not cooled down sufficiently. Another inspection information comes from degradation and damage measurement. The probabilistic life assessment using structural analysis and statistical material properties, the latter is estimated from hardness measurement, replica observation and embrittlement measurement. The risk function is calculated as the sum product of unreliability functions and expected monetary loss as the consequence of failure along event trees. The optimum maintenance plan is determined among simulated scenarios described through component breakdown trees, life cycle event trees and risk functions. Those methods are effective for total condition assessment and economical maintenance for operating plants

Reliability Assessment and Reliability-Based Inspection and Maintenance of Offshore Wind Turbines

DEFF Research Database (Denmark)

Ramirez, José Rangel

actions are the most relevant and effective means of control of deterioration. The risk-based inspection planning methodology, based on Bayesian decision theory, represents an important tool to identify the suitable strategy to inspect and control the deterioration in structures such as offshore wind...... performance during the life cycle. The deterioration processes, such as fatigue and corrosion, are typically affecting offshore structural systems. This damage decreases the system performance and increases the risk of failure, thus not fulfilling the established safety criteria. Inspection and maintenance...... to their offshore location, no pollution risks and low human risks since they are unmanned. This allows the allocation of lower reliability level compared to e.g. oil & gas installations. With the incursion to water depths between 20 and 50 meters, the use of jacket and tripod structures represents a feasible...

Sensitivity of Risk-Based Maintenance Planning of Offshore Wind Turbine Farms

DEFF Research Database (Denmark)

Ambühl, Simon; Sørensen, John Dalsgaard

2017-01-01

Inspection and maintenance expenses cover a considerable part of the cost of energy from offshore wind turbines. Risk-based maintenance planning approaches are a powerful tool to optimize maintenance and inspection actions and decrease the total maintenance expenses. Risk-based planning is based...... on many input parameters, which are in reality often not completely known. This paper will assess the cost impact of this incomplete knowledge based on a case study following risk-based maintenance planning. The sensitivity study focuses on weather forecast uncertainties, incomplete knowledge about...... the needed repair time on the site as well as uncertainties about the operational range of the boat and helicopter used to access the broken wind turbine. The cost saving potential is estimated by running Crude Monte Carlo simulations. Furthermore, corrective and preventive (scheduled and condition...

A High-Speed Train Operation Plan Inspection Simulation Model

Directory of Open Access Journals (Sweden)

Yang Rui

2018-01-01

Full Text Available We developed a train operation simulation tool to inspect a train operation plan. In applying an improved Petri Net, the train was regarded as a token, and the line and station were regarded as places, respectively, in accordance with the high-speed train operation characteristics and network function. Location change and running information transfer of the high-speed train were realized by customizing a variety of transitions. The model was built based on the concept of component combination, considering the random disturbance in the process of train running. The simulation framework can be generated quickly and the system operation can be completed according to the different test requirements and the required network data. We tested the simulation tool when used for the real-world Wuhan to Guangzhou high-speed line. The results showed that the proposed model can be developed, the simulation results basically coincide with the objective reality, and it can not only test the feasibility of the high-speed train operation plan, but also be used as a support model to develop the simulation platform with more capabilities.

Risk-based inspection of nuclear power plants

International Nuclear Information System (INIS)

Masopust, R.

1995-01-01

A multidiscipline research programme was developed in the USA to establish risk-based inspections for NPP structures and equipment components. Based on this US research effort, the risk-based procedure for developing inspection guidelines for NPPs is described. The procedure includes the definition of systems, qualitative risk assessment, qualitative risk analysis and development of the inspection programme. The method, when adopted and modified, is recommended also for risk-based inspections of structures and equipment of WWER-type NPPs. A pilot application of the method to unit 1 of the Surry NPP is summarized. (Z.S.) 1 tab., 1 fig., 5 refs

Rail inspection system based on iGPS

Science.gov (United States)

Fu, Xiaoyan; Wang, Mulan; Wen, Xiuping

2018-05-01

Track parameters include gauge, super elevation, cross level and so on, which could be calculated through the three-dimensional coordinates of the track. The rail inspection system based on iGPS (indoor/infrared GPS) was composed of base station, receiver, rail inspection frame, wireless communication unit, display and control unit and data processing unit. With the continuous movement of the inspection frame, the system could accurately inspect the coordinates of rail; realize the intelligent detection and precision measurement. According to principle of angle intersection measurement, the inspection model was structured, and detection process was given.

Evaluation of sampling plans for in-service inspection of steam generator tubes

International Nuclear Information System (INIS)

Kurtz, R.J.; Heasler, P.G.; Baird, D.B.

1994-02-01

This report summarizes the results of three previous studies to evaluate and compare the effectiveness of sampling plans for steam generator tube inspections. An analytical evaluation and Monte Carlo simulation techniques were the methods used to evaluate sampling plan performance. To test the performance of candidate sampling plans under a variety of conditions, ranges of inspection system reliability were considered along with different distributions of tube degradation. Results from the eddy current reliability studies performed with the retired-from-service Surry 2A steam generator were utilized to guide the selection of appropriate probability of detection and flaw sizing models for use in the analysis. Different distributions of tube degradation were selected to span the range of conditions that might exist in operating steam generators. The principal means of evaluating sampling performance was to determine the effectiveness of the sampling plan for detecting and plugging defective tubes. A summary of key results from the eddy current reliability studies is presented. The analytical and Monte Carlo simulation analyses are discussed along with a synopsis of key results and conclusions

Risk-based methodology for USNRC inspections

International Nuclear Information System (INIS)

Wong, S.M.; Holahan, G.M.; Chung, J.W.; Johnson, M.R.

1995-01-01

This paper describes the development and trial applications of a risk-based methodology to enhance the inspection processes for US nuclear power plants. Objectives of risk-based methods to complement prescriptive engineering approaches in US Nuclear Regulatory Commission (USNRC) inspection programs are presented. Insights from time-dependent risk profiles of plant configurational from Individual Plant Evaluation (IPE) studies were integrated to develop a framework for optimizing inspection efforts in NRC regulatory initiatives. Lessons learned from NRC pilot applications of the risk-based methodology for evaluation of the effectiveness of operational risk management programs at US nuclear power plant sites are also discussed

Tank waste remediation system nuclear criticality safety inspection and assessment plan

International Nuclear Information System (INIS)

VAIL, T.S.

1999-01-01

This plan provides a management approved procedure for inspections and assessments of sufficient depth to validate that the Tank Waste Remediation System (TWRS) facility complies with the requirements of the Project Hanford criticality safety program, NHF-PRO-334, ''Criticality Safety General, Requirements''

Development of in-service inspection plans for nuclear components at the Surry 1 nuclear power station

International Nuclear Information System (INIS)

Vo, T.V.; Simonen, F.A.; Doctor, S.R.; Smith, B.W.; Gore, B.F.

1993-01-01

As part of the nondestructive evaluation reliability program sponsored by the US Nuclear Regulatory Commission at Pacific Northwest Laboratory, a methodology has been developed for establishing in-service inspection priorities of nuclear power plant components. The method uses results of probabilistic risk assessment in conjunction with the techniques of failure modes and effects analysis to identify and prioritize the most risk-important systems and components for inspection at nuclear power plants. Surry nuclear power station unit 1 was selected for demonstrating the methodology. The specific systems selected for analysis were the reactor pressure vessel, the reactor coolant, the low pressure injection including the accumulators, and the auxiliary feedwater. The results provide a risk-based ranking of components that can be used to establish a prioritization of the components and a basis for developing improved in-service inspection plans at nuclear power plants

An analysis of OSHA inspections assessing contaminant exposures in general medical and surgical hospitals.

Science.gov (United States)

Knight, Jordan L; Sleeth, Darrah K; Larson, Rodney R; Pahler, Leon F

2013-04-01

This study analyzed data from the Occupational Safety and Health Administration's (OSHA) Chemical Exposure Health Database to assess contaminant exposures in general medical and surgical hospitals. Seventy-five inspections conducted in these hospitals from 2005 through 2009 were identified. Five categories of inspections were conducted, the three most common being complaint-based, planned, and referral-based inspections. Complaint-based inspections comprised the majority of inspections-55 (73%) of the 75 conducted. The overall violation rate for all inspection types was 68%. This finding was compared to the violation rates of planned inspections (100%), referral-based inspections (83%), and complaint-based inspections (62%). Asbestos was the hazardous substance most commonly sampled and cited by OSHA in hospitals, with 127 samples collected during 24 inspections; 31% of the total 75 inspections resulting in one or more violations were due to asbestos. Copyright 2013, SLACK Incorporated.

Analisis Kepatuhan Supervisor Terhadap Implementasi Program Occupational Health & Safety (Ohs) Planned Inspection Di PT. Ccai

OpenAIRE

Sarah, Dewi; Ekawati, Ekawati; Widjasena, Baju

2015-01-01

The Government has issued Regulation Legislation No. 50 Year 2012 on Health and Safety Management System (SMK3). CCAI is a company that has implemented SMK3. The application of the CCAI SMK3 supported by K3 program one of them is OHS Planned Inspection. This study aimed to analyze the implementation of Occupational Health & Safety (OHS) program Planned Inspection in CCAI. The subjects of this study amounted to five people as the main informants and 2 as an informant triangulation. The res...

A study on in-pipe inspection mobile robots, 3

International Nuclear Information System (INIS)

Fukuda, Toshio; Hosokai, Hidemi; Uemura, Masahiro.

1990-01-01

This paper deals with inspection path planning for in-pipe inspection mobile robots which have the capability of moving through complicated pipeline networks. It is imperative that the robot systems have an inspection path planning system for such networks for their reasonable and rational operation, controlled by themselves or by the operators. The planning mainly requires two projects: the selection of the place to put the robot in or out, and the generation of the paths in the networks. This system provides the for complicated problems with plural inspection points using a basic strategy of systematically producing patterns and dividing partial problems of simple searches based on rules. (author)

Reliability-based design and planning of inspection and monitoring of offshore wind turbines

DEFF Research Database (Denmark)

Dominguez, Sergio Marquez

When the wind is blowing fiercely, wind turbines must resist. Wind turbines have to withstand the rough environmental conditions in the most reliable manner and start to produce renewable energy when the wind becomes friendly again. Never give up ‘wind turbine’ face the winds and be proud of cont...... of probability and statistics for application in structural reliability-based risk inspections....

Evaluation of piping reliability and failure data for use in risk-based inspections of nuclear power plants

International Nuclear Information System (INIS)

Vasconcelos, V. de; Soares, W.A.; Costa, A.C.L. da; Rabello, E.G.; Marques, R.O.

2016-01-01

During operation of industrial facilities, components and systems can deteriorate over time, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) involves inspection planning based on information about risks, through assessing of probability and consequence of failures. In-service inspections are used in nuclear power plants, in order to ensure reliable and safe operation. Traditional deterministic inspection approaches investigate generic degradation mechanisms on all systems. However, operating experience indicates that degradation occurs where there are favorable conditions for developing a specific mechanism. Inspections should be prioritized at these places. Risk-Informed In-service Inspections (RI-ISI) are types of RBI that use Probabilistic Safety Assessment results, increasing reliability and plant safety, and reducing radiation exposure. These assessments use both available generic reliability and failure data, as well as plant specific information. This paper proposes a method for evaluating piping reliability and failure data important for RI-ISI programs, as well as the techniques involved. (author)

Evaluation of piping reliability and failure data for use in risk-based inspections of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Vasconcelos, V. de; Soares, W.A.; Costa, A.C.L. da; Rabello, E.G.; Marques, R.O., E-mail: vasconv@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2016-07-01

During operation of industrial facilities, components and systems can deteriorate over time, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) involves inspection planning based on information about risks, through assessing of probability and consequence of failures. In-service inspections are used in nuclear power plants, in order to ensure reliable and safe operation. Traditional deterministic inspection approaches investigate generic degradation mechanisms on all systems. However, operating experience indicates that degradation occurs where there are favorable conditions for developing a specific mechanism. Inspections should be prioritized at these places. Risk-Informed In-service Inspections (RI-ISI) are types of RBI that use Probabilistic Safety Assessment results, increasing reliability and plant safety, and reducing radiation exposure. These assessments use both available generic reliability and failure data, as well as plant specific information. This paper proposes a method for evaluating piping reliability and failure data important for RI-ISI programs, as well as the techniques involved. (author)

First fuel re-load of Angra-1 reactor - Inspection and hearing plan

International Nuclear Information System (INIS)

Pollis, W.; Alvarenga, M.A.B.; Meldonian, N.L.; Paiva, R.L.C. de; Pollis, R.

1985-01-01

The plan of inspection and hearing of the first fuel reload of Angra-1 nuclear reactor is detailed. It consists in five steps: receiving and storage of the fuel; reload preparation; activities during; post-reload activities, and preliminary activities. (M.I.)

Technology Assessment of the Inspection Readiness Plan in Chemical Weapons Convention Challenge Inspections

National Research Council Canada - National Science Library

Woodley, Anthony

1998-01-01

...) Challenge Inspections. The CWC is an intrusive inspection. The Challenge Inspection allows for a team of international inspectors to inspect on very short notice a naval facility suspected of violating the CWC...

Process Improvement to the Inspection Readiness Plan in Chemical Weapons Convention Challenge Inspections

National Research Council Canada - National Science Library

Triplett, William

1997-01-01

...) Challenge Inspection. The CWC is an intensive inspection. The Challenge Inspection allows for a team of international inspectors to inspect a naval facility suspected of violating the CWC on very short notice...

Application of risk based inspection as a part of life management of nuclear power plants

International Nuclear Information System (INIS)

Vinod, Gopika; Babar, A.K.; Saraf, R.K.; Kushwaha, H.S.; Venkat Raj, V.

2002-01-01

Full text: Risk Informed approach is a systematic effort to improve plant safety in a more efficient manner by distributing the available safety resources depending on the importance to plant safety. This approach has found immense application in various aspects associated with Nuclear Power Plants, including design, manufacturing, operation and regulation. Typical applications of Risk Informed approach are in Technical Specification, In-Service Inspection (ISI) requirements, Motor Operated Valve testing, Configuration Control etc. In order to cater to such variety of Probabilistic Safety Assessment (PSA) based Risk Informed requirements, a software package, 'Risk Monitor' has been developed by the authors. An important application of Risk informed approach that has been undertaken for Indian Pressurised Heavy Water Reactor (IPHWR) is towards Risk Informed In-Service Inspection (RI-ISI). Studies are being conducted to evolve an inspection plan that is optimised to provide effective inspections at the right location with a proper inspection frequency. Using risk informed approach, the identification of system / component for inspection resource allocation is based on the results from Level 1 PSA of a NPP. Even though this methodology can be employed on any of the nuclear components/systems such as mechanical systems, instrumentation, etc., as a starting point, piping has been considered for employing Risk Informed Inspection. Plant risk assessment is modelled through the analysis of Core Damage Frequency (CDF) using PSA models. Risk Informed Inspection program of piping involves the estimation of failure probability or frequency of a piping segment and estimation of consequences of piping failures. ISI program changes could affect the failure probability values of piping and can introduce a change in CDF. These effects can be brought out through the implementation of Risk Informed inspection strategy. Various importance measures like Fussel-Vesely, Birnbaum

Risk-based inspection--Development of guidelines

International Nuclear Information System (INIS)

1993-07-01

Effective inservice inspection programs can play a significant role in minimizing equipment and structural failures. Most of the current inservice inspection programs for light water reactor (LWR) nuclear power plant components are based on experience and engineers' qualitative judgment. These programs include only an implicit consideration of risk, which combines the probability of failure of a component under its operation and loading conditions and the consequences of such failure, if it occurs. This document recommends appropriate methods for establishing a risk-based inspection program for LWR nuclear power plant components. The process has been built from a general methodology (Volume 1) and has been expanded to involve five major steps: defining the system; evaluating qualitative risk assessment results; using this and information from plant probabilistic risk assessments to perform a quantitative risk analysis; selecting target failure probabilities; and developing an inspection program for components using economic decision analysis and structural reliability assessment methods

A preventive maintenance model with a two-level inspection policy based on a three-stage failure process

International Nuclear Information System (INIS)

Wang, Wenbin; Zhao, Fei; Peng, Rui

2014-01-01

Inspection is always an important preventive maintenance (PM) activity and can have different depths and cover all or part of plant systems. This paper introduces a two-level inspection policy model for a single component plant system based on a three-stage failure process. Such a failure process divides the system′s life into three stages: good, minor defective and severe defective stages. The first level of inspection, the minor inspection, can only identify the minor defective stage with a certain probability, but can always reveal the severe defective stage. The major inspection can however identify both defective stages perfectly. Once the system is found to be in the minor defective stage, a shortened inspection interval is adopted. If however the system is found to be in the severe defective stage, we may delay the maintenance action if the time to the next planned PM window is less than a threshold level, but otherwise, replace immediately. This corresponds to the well adopted maintenance policy in practice such as periodic inspections with planned PMs. A numerical example is presented to demonstrate the proposed model by comparing with other models. - Highlights: • The system′s deterioration goes through a three-stage process, namely, normal, minor defective and severe defective. • Two levels of inspections are proposed, e.g., minor and major inspections. • Once the minor defective stage is found, instead of taking a maintenance action, a shortened inspection interval is recommended. • When the severe defective stage is found, we delay the maintenance according to the threshold to the next PM. • The decision variables are the inspection intervals and the threshold to PM

Ergodicity of forward times of the renewal process in a block-based inspection model using the delay time concept

International Nuclear Information System (INIS)

Wang Wenbin; Banjevic, Dragan

2012-01-01

The delay time concept and the techniques developed for modelling and optimising plant inspection practice have been reported in many papers and case studies. For a system subject to a few major failure modes, component based delay time models have been developed under the assumptions of an age-based inspection policy. An age-based inspection assumes that an inspection is scheduled according to the age of the component, and if there is a failure renewal, the next inspection is always, say τ times, from the time of the failure renewal. This applies to certain cases, particularly important plant items where the time since the last renewal or inspection is a key to schedule the next inspection service. However, in most cases, the inspection service is not scheduled according to the need of a particular component, rather it is scheduled according to a fixed calendar time regardless whether the component being inspected was just renewed or not. This policy is called a block-based inspection which has the advantage of easy planning and is particularly useful for plant items which are part of a larger system to be inspected. If a block-based inspection policy is used, the time to failure since the last inspection prior to the failure for a particular item is a random variable. This time is called the forward time in this paper. To optimise the inspection interval for block-based inspections, the usual criterion functions such as expected cost or down time per unit time depend on the distribution of this forward time. We report in this paper the development of a theoretical proof that a limiting distribution for such a forward time exists if certain conditions are met. We also propose a recursive algorithm for determining such a limiting distribution. A numerical example is presented to demonstrate the existence of the limiting distribution.

Reliability-based inspection of prestressed concrete containment structures

International Nuclear Information System (INIS)

Pandey, M.D.

1996-03-01

A study was undertaken to develop a reliability-based approach to the planning of inspection programs for prestressed concrete containment structures. The main function of the prestressing system is to ensure the leak integrity of the containment by maintaining a compressive state of stress under the tensile forces which arise in a hypothesized loss of coolant accident. Prestressing force losses (due to creep and shrinkage, stress relaxation or tendon corrosion) can lead to tensile stresses under accident pressure, resulting in loss of containment leak integrity due to concrete cracking and tensile yielding of the non-prestressed reinforcement. Therefore, the evaluation of prestressing inspection programs was based on their effectiveness in maintaining an acceptable reliability level with respect to a limit state representing yeilding of non-prestressed reinforcement. An annual target reliability of 10 -4 was used for this limit state. As specified in CSA-N287.7, the evaluation of prestressing systems for containment structures is based on the results of lift-off tests to determine the prestressing force. For unbonded systems the tests are carried out on a randomly selected sample from each tendon group in the structure. For bonded systems, the test is carried out on an unbonded test beam that matches the section geometry and material properties of the containment structure. It was found that flexural testing is useful in updating the probability of concrete cracking under accident pressure. For unbonded systems, the analysis indicated that the sample size recommended by the CSA Standard (4% of the tendon population) is adequate. The CSA recommendation for a five year inspection interval is conservative unless severe degradation of the prestressing system, characterized by a high prestressing loss rate (>3%) and a large coefficient of variation of the measured prestressing force (>15%), is observed

Engineering Task Plan for the Ultrasonic Inspection of Hanford Double Shell Tanks (DST) FY2000

International Nuclear Information System (INIS)

JENSEN, C.E.

2000-01-01

This document facilitates the ultrasonic examination of Hanford double-shell tanks. Included are a plan for engineering activities (individual responsibilities), plan for performance demonstration testing, and a plan for field activities (tank inspection). Also included are a Statement of Work for contractor performance of the work and a protocol to be followed should tank flaws that exceed the acceptance criteria be discovered

Design and implementation of motion planning of inspection and maintenance robot for ITER-like vessel

Energy Technology Data Exchange (ETDEWEB)

Wang, Hesheng; Lai, Yinping [Department of Automation, Shanghai Jiao Tong University, Shanghai 200240 (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China); Chen, Weidong, E-mail: wdchen@sjtu.edu.cn [Department of Automation, Shanghai Jiao Tong University, Shanghai 200240 (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China); Cao, Qixin [Institute of Robotics, Shanghai Jiao Tong University, Shanghai 200240 (China)

2015-12-15

Robot motion planning is a fundamental problem to ensure the robot executing the task without clashes, fast and accurately in a special environment. In this paper, a motion planning of a 12 DOFs remote handling robot used for inspecting the working state of the ITER-like vessel and maintaining key device components is proposed and implemented. Firstly, the forward and inverse kinematics are given by analytic method. The work space and posture space of this manipulator are both considered. Then the motion planning is divided into three stages: coming out of the cassette mover, moving along the in-vessel center line, and inspecting the D-shape section. Lastly, the result of experiments verified the performance of the motion design method. In addition, the task of unscrewing/screwing the screw demonstrated the feasibility of system in function.

Auxiliary feedwater system risk-based inspection guide for the North Anna nuclear power plants

International Nuclear Information System (INIS)

Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

1992-10-01

In a study sponsored by the US Nuclear regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. North Anna was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the North Anna plant

Auxiliary feedwater system risk-based inspection guide for the Ginna Nuclear Power Plant

International Nuclear Information System (INIS)

Pugh, R.; Gore, B.F.; Vo, T.V.; Moffitt, N.E.

1991-09-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Ginna was selected as the eighth plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Ginna plant. 23 refs., 1 fig., 1 tab

26 CFR 301.6104(a)-2 - Public inspection of material relating to pension and other plans.

Science.gov (United States)

2010-04-01

... pension and other plans. 301.6104(a)-2 Section 301.6104(a)-2 Internal Revenue INTERNAL REVENUE SERVICE... and Returns Returns and Records § 301.6104(a)-2 Public inspection of material relating to pension and...— (i) A pension, profit-sharing, or stock bonus plan under section 401(a), (ii) An annuity plan under...

Vision Based Autonomous Robotic Control for Advanced Inspection and Repair

Science.gov (United States)

Wehner, Walter S.

2014-01-01

The advanced inspection system is an autonomous control and analysis system that improves the inspection and remediation operations for ground and surface systems. It uses optical imaging technology with intelligent computer vision algorithms to analyze physical features of the real-world environment to make decisions and learn from experience. The advanced inspection system plans to control a robotic manipulator arm, an unmanned ground vehicle and cameras remotely, automatically and autonomously. There are many computer vision, image processing and machine learning techniques available as open source for using vision as a sensory feedback in decision-making and autonomous robotic movement. My responsibilities for the advanced inspection system are to create a software architecture that integrates and provides a framework for all the different subsystem components; identify open-source algorithms and techniques; and integrate robot hardware.

A pilot application of risk-based methods to establish in-service inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station

International Nuclear Information System (INIS)

Vo, T.; Gore, B.; Simonen, F.; Doctor, S.

1994-08-01

As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory Commission, the Pacific Northwest Laboratory is developing a method that uses risk-based approaches to establish in-service inspection plans for nuclear power plant components. This method uses probabilistic risk assessment (PRA) results and Failure Modes and Effects Analysis (FEMA) techniques to identify and prioritize the most risk-important systems and components for inspection. The Surry Nuclear Power Station Unit 1 was selected for pilot applications of this method. The specific systems addressed in this report are the reactor pressure vessel, the reactor coolant, the low-pressure injection, and the auxiliary feedwater. The results provide a risk-based ranking of components within these systems and relate the target risk to target failure probability values for individual components. These results will be used to guide the development of improved inspection plans for nuclear power plants. To develop inspection plans, the acceptable level of risk from structural failure for important systems and components will be apportioned as a small fraction (i.e., 5%) of the total PRA-estimated risk for core damage. This process will determine target (acceptable) risk and target failure probability values for individual components. Inspection requirements will be set at levels to assure that acceptable failure probabilistics are maintained

Generalizing Perspective-based Inspection to handle Object-Oriented Development Artifacts

OpenAIRE

Laitenberger, O.; Atkinson, C.

1998-01-01

The value of software inspection for uncovering defects early in the development lifecycle has been well documented. Of the various types of inspection methods published to date, experiments have shown perspective-based inspection to be one of the most effective, because of its enhanced coverage of the defect space. However, inspections in general, and perspective-based inspections in particular, have so far been applied predominantly in the context of conventional structured development meth...

Feature-based tolerancing for intelligent inspection process definition

International Nuclear Information System (INIS)

Brown, C.W.

1993-07-01

This paper describes a feature-based tolerancing capability that complements a geometric solid model with an explicit representation of conventional and geometric tolerances. This capability is focused on supporting an intelligent inspection process definition system. The feature-based tolerance model's benefits include advancing complete product definition initiatives (e.g., STEP -- Standard for Exchange of Product model dam), suppling computer-integrated manufacturing applications (e.g., generative process planning and automated part programming) with product definition information, and assisting in the solution of measurement performance issues. A feature-based tolerance information model was developed based upon the notion of a feature's toleranceable aspects and describes an object-oriented scheme for representing and relating tolerance features, tolerances, and datum reference frames. For easy incorporation, the tolerance feature entities are interconnected with STEP solid model entities. This schema will explicitly represent the tolerance specification for mechanical products, support advanced dimensional measurement applications, and assist in tolerance-related methods divergence issues

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2011

International Nuclear Information System (INIS)

2010-07-01

The objective of this report is to provide an overview of inspection activities of the Radiological Protection Institute of Ireland, to examine the evolution in licensee numbers and to outline the rationale in developing annual inspection programmes. All inspection activities are now carried out within the framework of a quality management system including: inspection planning, the training of inspectors, the conduct of inspections as well as inspection follow up and review. The report also provides an overview of the main features of the quality system

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2013

International Nuclear Information System (INIS)

2013-04-01

The objective of this report is to provide an overview of inspection activities of the Radiological Protection Institute of Ireland RPII, to examine the evolution in licensee numbers and to outline the rationale in developing annual inspection programmes. All inspection activities are now carried out within the framework of a quality management system including inspection planning, the training of inspectors, the conduct of inspections as well as post inspection follow up and review. This report also provides an overview of the main features of the quality system

Condition Indicators for Inspection Planning of Concrete Structures

DEFF Research Database (Denmark)

Faber, Michael Havbro; Sørensen, John Dalsgaard

2002-01-01

Based on previous work by the authors a Bayesian formulation of condition indicators is developed further whereby in conjunction with a systems modelling of concrete structures the experience and expertise of the inspection personnel may be fully utilized. It is shown how the predicted evolution ...

Auxiliary feedwater system risk-based inspection guide for the Palo Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Bumgardner, J.D.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Sloan, J.A.

1993-02-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Palo Verde was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Palo Verde plants

Auxiliary feedwater system risk-based inspection guide for the McGuire nuclear power plant

International Nuclear Information System (INIS)

Bumgardner, J.D.; Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

1994-05-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. McGuire was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the McGuire plant

Auxiliary feedwater system risk-based inspection guide for the Maine Yankee Nuclear Power Plant

International Nuclear Information System (INIS)

Gore, B.F.; Vo, T.V.; Moffitt, N.E.; Bumgardner, J.D.

1992-10-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. The information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Maine Yankee was selected as one of a series of plants for study. ne product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Maine Yankee plant

Auxiliary feedwater system risk-based inspection guide for the Point Beach nuclear power plant

International Nuclear Information System (INIS)

Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Vehec, T.A.

1993-02-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Point Beach was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Point Beach plant

OSE inspection of materials control and accountability: Review

International Nuclear Information System (INIS)

Coady, K.J.

1987-01-01

As part of its task to confirm that Department of Energy (DOE) field offices provide levels of security and safeguards commensurate with defined threats, the DOE Office of Security Evaluations (OSE) conducts inspections of the nuclear materials control and accountability (MC and A) systems at DOE facilities throughout the United States. Inspections are based on the DOE Safeguards and Security Standards and Criteria, tailored to the specific aspects at and threats to each individual site. This paper reviews the process of inspecting MC and A systems during the planning, preinspection, and inspection/reporting phases

The Use of Explosion Aftershock Probabilities for Planning and Deployment of Seismic Aftershock Monitoring System for an On-site Inspection

Science.gov (United States)

Labak, P.; Ford, S. R.; Sweeney, J. J.; Smith, A. T.; Spivak, A.

2011-12-01

One of four elements of CTBT verification regime is On-site inspection (OSI). Since the sole purpose of an OSI shall be to clarify whether a nuclear weapon test explosion or any other nuclear explosion has been carried out, inspection activities can be conducted and techniques used in order to collect facts to support findings provided in inspection reports. Passive seismological monitoring, realized by the seismic aftershock monitoring (SAMS) is one of the treaty allowed techniques during an OSI. Effective planning and deployment of SAMS during the early stages of an OSI is required due to the nature of possible events recorded and due to the treaty related constrains on size of inspection area, size of inspection team and length of an inspection. A method, which may help in planning the SAMS deployment is presented. An estimate of aftershock activity due to a theoretical underground nuclear explosion is produced using a simple aftershock rate model (Ford and Walter, 2010). The model is developed with data from the Nevada Test Site and Semipalatinsk Test Site, which we take to represent soft- and hard-rock testing environments, respectively. Estimates of expected magnitude and number of aftershocks are calculated using the models for different testing and inspection scenarios. These estimates can help to plan the SAMS deployment for an OSI by giving a probabilistic assessment of potential aftershocks in the Inspection Area (IA). The aftershock assessment combined with an estimate of the background seismicity in the IA and an empirically-derived map of threshold magnitude for the SAMS network could aid the OSI team in reporting. We tested the hard-rock model to a scenario similar to the 2008 Integrated Field Exercise 2008 deployment in Kazakhstan and produce an estimate of possible recorded aftershock activity.

Risk based inspection experience from the European chemical- and petrochemical industries

International Nuclear Information System (INIS)

Kristensen, Hans; Jeppesen, Leif; Larsen, Bjarne; Kim, Na Yon

2001-01-01

As an inspection vendor with 60 years of experience and with more than 25 years of experience as manufacturer of the Automated Ultrasonic NDT systems, the P-scan systems, FORCE Institute is continuously analysing the market for NDT. This is done to assure that both the equipment product line and the service mix provided by FORCE Institute are meeting the requirements from the industry today and in the future. The concept of Risk Based Inspection Programmes were adopted early by the offshore industry and has in the recent years been adopted by many other industries as a reliable and cost efficient way of maintaining a production facility. A Risk/Reliability Based Inspection Programme is a 'living organism' that constantly needs information if it shall be of any value and NDT information is only one type of information that is required. The NDT information required is normally related to corrosion/base material information and weld integrity information. NDT as an integrated part of a plants maintenance system is, in Europe, currently influenced by the following tendencies which all are related to 'Risk Based Inspection': · Increased use of Base-Line Inspections · Reduction in the use of repeated inspections(qualitative- instead of quantitative Inspections). · Inspection results are fed directly into the plant maintenance system. · Fitness-for-Purpose acceptance criteria instead of conventional acceptance criteria. As repeatability and accuracy is a key issue for the data, automated ultrasonic inspection is increasingly used as an alternative to manual ultrasonic inspection, but due to the physical size of most automated ultrasonic inspection systems the gain in productivity has not been as significant as the gain in repeatability and accuracy. In this paper some of FORCE Institute's practical experiences with examinations carried out in connection with Risk Based Inspection is used to illustrate the above described tendencies. Not only examples using automated

The time optimal trajectory planning with limitation of operating task for the Tokamak inspecting manipulator

Energy Technology Data Exchange (ETDEWEB)

Wang, Hesheng; Lai, Yinping [Department of Automation,Shanghai Jiao Tong University, Shanghai (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China); Chen, Weidong, E-mail: wdchen@sjtu.edu.cn [Department of Automation,Shanghai Jiao Tong University, Shanghai (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China)

2016-12-15

In this paper, a new optimization model of time optimal trajectory planning with limitation of operating task for the Tokamak inspecting manipulator is designed. The task of this manipulator is to inspect the components of Tokamak, the inspecting velocity of manipulator must be limited in the operating space in order to get the clear pictures. With the limitation of joint velocity, acceleration and jerk, this optimization model can not only get the minimum working time along a specific path, but also ensure the imaging quality of camera through the constraint of inspecting velocity. The upper bound of the scanning speed is not a constant but changes according to the observation distance of camera in real time. The relation between scanning velocity and observation distance is estimated by curve-fitting. Experiment has been carried out to verify the feasibility of optimization model, moreover, the Laplace image sharpness evaluation method is adopted to evaluate the quality of images obtained by the proposed method.

The time optimal trajectory planning with limitation of operating task for the Tokamak inspecting manipulator

International Nuclear Information System (INIS)

Wang, Hesheng; Lai, Yinping; Chen, Weidong

2016-01-01

In this paper, a new optimization model of time optimal trajectory planning with limitation of operating task for the Tokamak inspecting manipulator is designed. The task of this manipulator is to inspect the components of Tokamak, the inspecting velocity of manipulator must be limited in the operating space in order to get the clear pictures. With the limitation of joint velocity, acceleration and jerk, this optimization model can not only get the minimum working time along a specific path, but also ensure the imaging quality of camera through the constraint of inspecting velocity. The upper bound of the scanning speed is not a constant but changes according to the observation distance of camera in real time. The relation between scanning velocity and observation distance is estimated by curve-fitting. Experiment has been carried out to verify the feasibility of optimization model, moreover, the Laplace image sharpness evaluation method is adopted to evaluate the quality of images obtained by the proposed method.

Inspection maintenance and planning of shutdown in thermal electric generating plants

International Nuclear Information System (INIS)

Dezordi, W.L.; Correa, D.A.; Kina, M.

1984-01-01

The schedule shutdown of an industrial plant and, more specifically, of an electrical generating station, is becoming increasingly important. The major parameters to be taken into account for the planning of such a shutdown are basically of economic-financial nature such as costs of the related services (materials, equipment, manpower, etc), loss of revenue caused by the station's shutdown as well as by the station availability, and other requirements expected from it by the Load Dispatch and consumers. Improving the equipment's performances and the station's availability are the fundamental objectives to be strived for. The authors present in this paper, in an abridged form, the planning tools used for thermal electric generating plants shutdowns for inspections, maintenance and design changes implementation. (Author) [pt

Auxiliary feedwater system risk-based inspection guide for the South Texas Project nuclear power plant

International Nuclear Information System (INIS)

Bumgardner, J.D.; Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

1993-12-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. South Texas Project was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the South Texas Project plant

Auxiliary feedwater system risk-based inspection guide for the Byron and Braidwood nuclear power plants

International Nuclear Information System (INIS)

Moffitt, N.E.; Gore, B.F.; Vo, T.V.

1991-07-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Byron and Braidwood were selected for the fourth study in this program. The produce of this effort is a prioritized listing of AFW failures which have occurred at the plants and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Byron/Braidwood plants. 23 refs., 1 fig., 1 tab

Auxiliary feedwater system risk-based inspection guide for the H. B. Robinson nuclear power plant

International Nuclear Information System (INIS)

Moffitt, N.E.; Lloyd, R.C.; Gore, B.F.; Vo, T.V.; Garner, L.W.

1993-08-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. H. B. Robinson was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the H. B. Robinson plant

Auxiliary feedwater system risk-based inspection guide for the J.M. Farley Nuclear Power Plant

International Nuclear Information System (INIS)

Vo, T.V.; Pugh, R.; Gore, B.F.; Harrison, D.G.

1990-10-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment(PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. J. M. Farley was selected as the second plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important at the J. M. Farley plant. 23 refs., 1 fig., 1 tab

Future plans for performance analysis and maintenance/inspection optimization of shutoff rods based on the case study of Bruce Power Unit-3 Shutoff Rod 5 inspection

International Nuclear Information System (INIS)

Nasimi, E.; Gabbar, H.A.

2011-01-01

Shutdown System 1 (SDS1) is a preferred method for a quick shutdown of nuclear fission process in CANDU (CANada Deuterium Uranium) reactor units. Failure of a routine SDS1 safety test during Fall 2009 outage resulted in the need to develop and execute a new methodology for Shutoff Rod inspection and re-evaluate the known degradation mechanisms and failure modes. This paper describes the development of this methodology and the obtained results. It also proposes several alternative solutions for the future performance analysis and maintenance/inspection optimization for SDS1 Shutoff Rods based on the Bruce Power Unit-3 Shutoff Rod 5 case study. (author)

AWARE-P: a system-based software for urban water IAM planning

OpenAIRE

Coelho, S.T.; Vitorino, D.; Alegre, H.

2013-01-01

The AWARE-P IAM planning software offers a non-intrusive, web-based, collaborative integration environment for a wide variety of data and processes that may be relevant to the IAM decision-making process, including maps, GIS shapefiles and geodatabases; inventory records; work orders, maintenance, inspections/CCTV records; network models, performance indicators, asset valuation records, among others. The software provides an organized framework for evaluating and comparing planning alternativ...

Vibrational Based Inspection Of A Steel Mast

DEFF Research Database (Denmark)

Kirkegaard, Poul Henning; Rytter, A.

1994-01-01

The aim of this paper is to present the results from a research project concerning vibrational based inspection of a 20 meter high steel mast containing well defined damages. Introductory analyses dealing with among other things evaluation of potential damage indicators and determination of accep......The aim of this paper is to present the results from a research project concerning vibrational based inspection of a 20 meter high steel mast containing well defined damages. Introductory analyses dealing with among other things evaluation of potential damage indicators and determination...

The API methodology for risk-based inspection (RBI) analysis for the petroleum and petrochemical industry

International Nuclear Information System (INIS)

Reynolds, J.T.

1998-01-01

Twenty-one petroleum and petrochemical companies are currently sponsoring a project within the American Petroleum Institute (API) to develop risk-based inspection (RBI) methodology for application in the refining and petrochemical industry. This paper describes that particular RBI methodology and provides a summary of the three levels of RBI analysis developed by the project. Also included is a review of the first pilot project to validate the methodology by applying RBI to several existing refining units. The failure for pressure equipment in a process unit can have several undesirable effects. For the purpose of RBI analysis, the API RBI program categorizes these effects into four basic risk outcomes: flammable events, toxic releases, major environmental damage, and business interruption losses. API RBI is a strategic process, both qualitative and quantitative, for understanding and reducing these risks associated with operating pressure equipment. This paper will show how API RBI assesses the potential consequences of a failure of the pressure boundary, as well as assessing the likelihood (probability) of failure. Risk-based inspection also prioritizes risk levels in a systematic manner so that the owner-user can then plan an inspection program that focuses more resources on the higher risk equipment; while possibly saving inspection resources that are not doing an effective job of reducing risk. At the same time, if consequence of failure is a significant driving force for high risk equipment items, plant management also has the option of applying consequence mitigation steps to minimize the impact of a hazardous release, should one occur. The target audience for this paper is engineers, inspectors, and managers who want to understand what API Risk-Based Inspection is all about, what are the benefits and limitations of RBI, and how inspection practices can be changed to reduce risks and/or save costs without impacting safety risk. (Author)

Inspection Based Evaluation of a Danish Road Bridge

DEFF Research Database (Denmark)

Thoft-Christensen, Palle

In this paper it is shown how an inspection-based evaluation of a Danish road bridge may be performed using the BRIDGE1 and BRIDGE2 bridge management systems produced within the EC-supported research programme "Assessment of Performance and Optimal Strategies for Inspection and Maintenance...

Czech interim spent fuel storage facility: operation experience, inspections and future plans

International Nuclear Information System (INIS)

Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

1999-01-01

The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

Optimal Inspection Planning for Fatigue Damage of Offshore Structures

DEFF Research Database (Denmark)

Madsen, H.O.; Sørensen, John Dalsgaard; Olesen, R.

1990-01-01

A formulation of optimal design, inspection and maintenance against damage caused by fatigue crack growth is formulated. A stochastic model for fatigue crack growth based on linear elastic fracture mechanics Is applied. Failure is defined by crack growth beyond a critical crack size. The failure ...

Merge Fuzzy Visual Servoing and GPS-Based Planning to Obtain a Proper Navigation Behavior for a Small Crop-Inspection Robot.

Science.gov (United States)

Bengochea-Guevara, José M; Conesa-Muñoz, Jesus; Andújar, Dionisio; Ribeiro, Angela

2016-02-24

The concept of precision agriculture, which proposes farming management adapted to crop variability, has emerged in recent years. To effectively implement precision agriculture, data must be gathered from the field in an automated manner at minimal cost. In this study, a small autonomous field inspection vehicle was developed to minimise the impact of the scouting on the crop and soil compaction. The proposed approach integrates a camera with a GPS receiver to obtain a set of basic behaviours required of an autonomous mobile robot to inspect a crop field with full coverage. A path planner considered the field contour and the crop type to determine the best inspection route. An image-processing method capable of extracting the central crop row under uncontrolled lighting conditions in real time from images acquired with a reflex camera positioned on the front of the robot was developed. Two fuzzy controllers were also designed and developed to achieve vision-guided navigation. A method for detecting the end of a crop row using camera-acquired images was developed. In addition, manoeuvres necessary for the robot to change rows were established. These manoeuvres enabled the robot to autonomously cover the entire crop by following a previously established plan and without stepping on the crop row, which is an essential behaviour for covering crops such as maize without damaging them.

Estimation of inspection effort

International Nuclear Information System (INIS)

Mullen, M.F.; Wincek, M.A.

1979-06-01

An overview of IAEA inspection activities is presented, and the problem of evaluating the effectiveness of an inspection is discussed. Two models are described - an effort model and an effectiveness model. The effort model breaks the IAEA's inspection effort into components; the amount of effort required for each component is estimated; and the total effort is determined by summing the effort for each component. The effectiveness model quantifies the effectiveness of inspections in terms of probabilities of detection and quantities of material to be detected, if diverted over a specific period. The method is applied to a 200 metric ton per year low-enriched uranium fuel fabrication facility. A description of the model plant is presented, a safeguards approach is outlined, and sampling plans are calculated. The required inspection effort is estimated and the results are compared to IAEA estimates. Some other applications of the method are discussed briefly. Examples are presented which demonstrate how the method might be useful in formulating guidelines for inspection planning and in establishing technical criteria for safeguards implementation

New approach for risk based inspection of H2S based Process Plants

International Nuclear Information System (INIS)

Vinod, Gopika; Sharma, Pavan K.; Santosh, T.V.; Hari Prasad, M.; Vaze, K.K.

2014-01-01

Highlights: • Study looks into improving the consequence evaluation in risk based inspection. • Ways to revise the quantity factors used in qualitative approach. • New approach based on computational fluid dynamics along with probit mathematics. • Demonstrated this methodology along with a suitable case study for the said issue. - Abstract: Recent trend in risk informed and risk based approaches in life management issues have certainly put the focus on developing estimation methods for real risk. Idea of employing risk as an optimising measure for in-service inspection, termed as risk based inspection, was accepted in principle from late 80s. While applying risk based inspection, consequence of failure from each component needs to be assessed. Consequence evaluation in a Process Plant is a crucial task. It may be noted that, in general, the number of components to be considered for life management is very large and hence the consequence evaluation resulting from their failures (individually) is a laborious task. Screening of critical components is usually carried out using simplified qualitative approach, which primarily uses influence factors for categorisation. This necessitates logical formulation of influence factors and their ranges with a suitable technical basis for acceptance from regulators. This paper describes application of risk based inspection for H 2 S based Process Plant along with the approach devised for handling the influence factor related to the quantity of H 2 S released

Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection

Energy Technology Data Exchange (ETDEWEB)

Vo, T.V.; Smith, B.W.; Simonen, F.A.; Gore, B.F.

1994-08-01

The goals of the Evaluation and Improvement of Non-destructive Examination Reliability for the In-service Inspection of Light Water Reactors Program sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory (PNL) are to (1) assess current ISI techniques and requirements for all pressure boundary systems and components, (2) determine if improvements to the requirements are needed, and (3) if necessary, develop recommendations for revising the applicable ASME Codes and regulatory requirements. In evaluating approaches that could be used to provide a technical basis for improved inservice inspection plans, PNL has developed and applied a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. In the PNL program, the feasibility of generic ISI requirements is being addressed in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. The results of these evaluations will be later consolidated into requirements for comprehensive inservice inspection of nuclear power plant components that will be developed in Phase II. This report presents Phase I evaluations for eight selected plants and attempts to compare these PRA-based inspection priorities with current ASME Section XI requirements for Class 1, 2 and 3 systems. These results show that there are generic insights that can be extrapolated from the selected plants to specific classes of light water reactors.

Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection

International Nuclear Information System (INIS)

Vo, T.V.; Smith, B.W.; Simonen, F.A.; Gore, B.F.

1994-08-01

The goals of the Evaluation and Improvement of Non-destructive Examination Reliability for the In-service Inspection of Light Water Reactors Program sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory (PNL) are to (1) assess current ISI techniques and requirements for all pressure boundary systems and components, (2) determine if improvements to the requirements are needed, and (3) if necessary, develop recommendations for revising the applicable ASME Codes and regulatory requirements. In evaluating approaches that could be used to provide a technical basis for improved inservice inspection plans, PNL has developed and applied a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. In the PNL program, the feasibility of generic ISI requirements is being addressed in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. The results of these evaluations will be later consolidated into requirements for comprehensive inservice inspection of nuclear power plant components that will be developed in Phase II. This report presents Phase I evaluations for eight selected plants and attempts to compare these PRA-based inspection priorities with current ASME Section XI requirements for Class 1, 2 and 3 systems. These results show that there are generic insights that can be extrapolated from the selected plants to specific classes of light water reactors

Enhancement of the reliability of automated ultrasonic inspections using tools of quantitative NDT

International Nuclear Information System (INIS)

Kappes, W.; Baehr, W.; Kroening, M.; Schmitz, V.

1994-01-01

To achieve reliable test results from automated ultrasonic inspection of safety related components, optimization and integral consideration of the various inspection stages - inspection planning, inspection performance and evaluation of results - are indispensable. For this purpose, a large potential of methods is available: advanced measurement techniques, mathematical-numerical modelling processes, artificial intelligence tools, data bases and CAD systems. The potential inherent in these methods to enhance inspection reliability is outlined by way of different applications. (orig.) [de

SIIA: a knowledge-based assistant for the SAFT ultrasonic inspection system(a)

International Nuclear Information System (INIS)

Melton, R.B.; Doctor, S.R.; Taylor, T.T.; Badalamente, R.V.

1987-01-01

SIIA(b) is a knowledge-based system designed to assist in making the operation of the Synthetic Aperture Focussing Technique (SAFT) Ultrasonic Inspection System more reliable and efficient. This paper reports on their effort to develop a prototype version of SIIA to demonstrate the feasibility of using knowledge-based systems in nondestructive evaluation (NDE). The first section of the paper describes the structure of the problem and their conceptual design of the knowledge-based system. The next section describes the current state of the prototype SIIA system and relates some of their experiences in developing the system. The final section discusses their plans for future development of SIIA and the implications of this type of system for other NDE techniques and applications

Drone Mission Definition and Implementation for Automated Infrastructure Inspection Using Airborne Sensors.

Science.gov (United States)

Besada, Juan A; Bergesio, Luca; Campaña, Iván; Vaquero-Melchor, Diego; López-Araquistain, Jaime; Bernardos, Ana M; Casar, José R

2018-04-11

This paper describes a Mission Definition System and the automated flight process it enables to implement measurement plans for discrete infrastructure inspections using aerial platforms, and specifically multi-rotor drones. The mission definition aims at improving planning efficiency with respect to state-of-the-art waypoint-based techniques, using high-level mission definition primitives and linking them with realistic flight models to simulate the inspection in advance. It also provides flight scripts and measurement plans which can be executed by commercial drones. Its user interfaces facilitate mission definition, pre-flight 3D synthetic mission visualisation and flight evaluation. Results are delivered for a set of representative infrastructure inspection flights, showing the accuracy of the flight prediction tools in actual operations using automated flight control.

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2012

International Nuclear Information System (INIS)

2012-04-01

The purpose of this document is to promote transparency in the activities of the RPII. It explains aspects of the internal workings of the Regulation and Information Management Division of the Institute to aid understanding of the processes and decisions of that Division which may impact on licensees and other interested parties. The objective of the report is to provide an overview of inspection activities of the RPII, to examine the evolution in licensee numbers and to outline the rationale in developing annual inspection programmes. All inspection activities are now carried out within the framework of a quality management system including; inspection planning, the training of inspectors, the conduct of inspections, as well as post inspection follow up and review. This report also provides an overview of the main features of the quality system

Inspection Methods in Programming: Cliches and Plans.

Science.gov (United States)

1987-12-01

part of the definition of the data plan. 44 THE PLAN (ALCULUS old:indexed-sequence I base: index: *sequence integer bump: oneplus update: new- term A...select-in dexred- sele¢ t-in dexed- sequence- base sequence-index,!’ sSdbump:. . oneplus ’,U a ," .update: " alter-term make: alter-indexed- sequence-index

Reliability and risk-based planning of operation and maintenance of offshore wind turbines

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Florian, Mihai; Berzonskis, Arvydas

2016-01-01

costly (and safe), and it is important to include in the reliability assessment the information obtained during operation (from condition monitoring and inspections) and the maintenance performed (incl. repairs and replacements). The paper presents a risk-based approach for optimal planning of Operation...

Risk-Based Operation and Maintenance Planning for Offshore Wind Turbines

DEFF Research Database (Denmark)

Nielsen, Jannie Jessen; Sørensen, John Dalsgaard

2010-01-01

Operation and maintenance (O&M) are large contributors to the cost of energy for offshore wind turbines. Optimal planning of O&M should include use of inspections and monitoring results to make decisions that minimize the expected costs through the lifetime of the structures. For offshore...... structures it is especially important because of the dependence on weather windows for inspections and repairs to be possible. A model has been developed to estimate the expected costs to corrective and condition based maintenance for a wind turbine with a single component. The deterioration of the component...... is simulated, and the expected costs are found for different strategies. An application example shows that condition based maintenance has the potential of reducing the costs, and a risk based approach can be used to find the optimal strategy for O&M. Further the influence of failure rate and damage parameters...

ASME development of risk-based inspection guidelines for nuclear power plants

International Nuclear Information System (INIS)

Gore, B.F.; Balkey, K.R.

1992-08-01

A methodology has been developed for use in preparing guidelines for the in-service inspection of nuclear power plant pressure boundary and structural components. This methodology is a further development of a general methodology previously published by the task force for application to any industry. It is unique in that it utilizes probabilistic risk assessment (PRA) information to improve the quantification of risks associated with component ruptures. A procedure has also been recommended for using the resulting quantified risk estimates to determine target component rupture probability values to be maintained by inspection activities. Characteristics which an inspection strategy must possess in order to maintain target rupture probabilities are being determined by structural risk and reliability analysis (SRRA) calculations. The major features of this methodology are described in this paper, and example applications are briefly discussed. Plans for additional work in developing and applying the methodology are described

MRP-227 Reactor vessel internals inspection planning and initial results at the Oconee nuclear station unit 2

International Nuclear Information System (INIS)

Davidsaver, S.B.; Fyfitch, S.; Whitaker, D.E.; Doss, R.L.

2015-01-01

The U.S. PWR industry has pro-actively developed generic inspection requirements and standards for reactor vessel (RV) internals. The Electric Power Research Institute (EPRI) Pressurized Water Reactor (PWR) Materials Reliability Program (MRP) has issued MRP-227-A and MRP-228 with mandatory and needed requirements based on the Nuclear Energy Institute (NEI) document NEI 03-08. The inspection and evaluation guidelines contained in MRP-227-A consider eight age-related degradation mechanisms: stress corrosion cracking (SCC), irradiation-assisted stress corrosion cracking (IASCC), wear, fatigue, thermal aging embrittlement, irradiation embrittlement, void swelling and irradiation growth, and thermal and irradiation-enhanced stress relaxation or irradiation-enhanced creep. This paper will discuss the decision planning efforts required for implementing the MRP-227-A and MRP-228 requirements and the results of these initial inspections at the Oconee Nuclear power station (ONS) units. Duke Energy and AREVA overcame a significant technology and NDE challenge by successfully completing the first-of-a-kind MRP-227-A scope requirements at ONS-1 in one outage below the estimated dose and with zero safety issues or events. This performance was repeated at ONS-2 a year later. The remote NDE tooling and processes developed to examine the MRP-227-A scope for ONS-1 and ONS-2 are transferable to other PWRs

Calculation of parameters for inspection planning and evaluation: low enriched uranium conversion and fuel fabrication facilities

International Nuclear Information System (INIS)

Reardon, P.T.; Mullen, M.F.; Harms, N.L.

1981-02-01

As part of Task C.35 (Calculation of Parameters for Inspection Planning and Evaluation) of the US Program of Technical Assistance to IAEA Safeguards, Pacific Northwest Laboratory has performed some quantitative analyses of IAEA inspection activities at low-enriched uranium (LEU) conversion and fuel fabrication facilities. This report presents the results and conclusions of those analyses. Implementation of IAEA safeguards at LEU conversion and fuel fabrication facilities must take into account a variety of practical problems and constraints. One of the key concerns is the problem of flow verification, especially product verification. The objective of this report is to help put the problem of flow verification in perspective by presenting the results of some specific calculations of inspection effort and probability of detection for various product measurement strategies. In order to provide quantitative information about the advantages and disadvantages of the various strategies, eight specific cases were examined

Corrosion Assessment by Using Risk-Based Inspection Method for Petrochemical Plant - Practical Experience

International Nuclear Information System (INIS)

Choi, Song Chun; Song, Ki Hun

2009-01-01

Corrosion assessment has a number of uses but the use considered here is as a precursor to Risk-Based Inspection (RBI) planning. Systematic methods consisting of technical modules of RBI program were used to assess the effect of specific corrosion mechanism on the probability of failure in equipment of petrochemical plants. Especially in part of the damage and corrosion assessment, screening step involved evaluating the combinations of process conditions and construction materials for each equipment item in order to determine which damage mechanisms are potentially active. For general internal corrosion, either API 510 or API 570 was applied as the damage rate in the calculation to determine the remaining life and inspection frequency. In some cases, a measured rate of corrosion may not be available. The technical modules of RBI program employ default values for corrosion, typically derived from published data or from experience with similar processes, for use until inspection results are available. This paper describes the case study of corrosion and damage assessment by using RBI methodology in petrochemical plant. Specifically, this paper reports the methodology and the results of its application to the petrochemical units using the KGS-RBI TM program, developed by the Korea Gas Safety Corporation to suit Korean situation in conformity with API 581 Codes

Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project

International Nuclear Information System (INIS)

Wachs, G.W.

1997-11-01

The Department of Energy (DOE) Fissile Materials Disposition Materials Disposition Program (FMDP) has announced that reactor irradiation of MOX fuel is one of the preferred alternatives for disposal of surplus weapons-usable plutonium (Pu). MOX fuel has been utilized domestically in test reactors and on an experimental basis in a number of Commercial Light Water Reactors (CLWRs). Most of this experience has been with Pu derived from spent low enriched uranium (LEU) fuel, known as reactor grade (RG) Pu. The MOX fuel test will be irradiated in the ATR to provide preliminary data to demonstrate that the unique properties of surplus weapons-derived or weapons-grade (WG) plutonium (Pu) do not compromise the applicability of this MOX experience base. In addition, the test will contribute experience with irradiation of gallium-containing fuel to the data base required for resolution of generic CLWR fuel design issues (ORNL/MD/LTR-76). This Fabrication, Inspection, and Test Plan (FITP) is a level 2 document as defined in the FMDP LWR MOX Fuel Irradiation Test Project Plan (ORNL/MD/LTR-78)

Inspection of licensee - Maintenance programme and activities

International Nuclear Information System (INIS)

2013-01-01

An effective maintenance programme is critical to sustained safe and reliable operation of nuclear power plants. The Working Group on Inspection Practices (WGIP) concluded that when a licensee has an effective maintenance programme, the overall operating safety of the plant is improved and the protection of public health and safety enhanced. All Regulatory Bodies (RB) consider maintenance to be an important area for oversight. Although a variety of inspection practices are being used; RB are actively monitoring licensee performance. Specifically the following conclusions were reached and commendable practices identified: - Maintenance oversight by regulators appears to be in a stable continuous improvement state. Most regulators are executing inspection oversight based on an existing regulatory framework. - The performance of a licensee's maintenance programme is recognized as important part of maintaining nuclear safety. The result of the maintenance program assessment is included in the overall performance assessment of a license. - Maintenance inspection activities are recognized as an important part of the regulatory oversight process. Inspection activities are based on the safety significance and nature of work being performed by the licensee. - The effectiveness of the maintenance inspection activities is recognized to rely on properly qualified inspectors; who are adequately supported by specialists. Training and qualification of inspectors should be based on how the RB reviews and inspects licensee maintenance programmes. - Reporting requirements are identified to provide information on the licensees maintenance programme, and to help guide inspection activities. - Performance Indicators are recognized as a useful tool for helping focus regulatory activities. Basic PI are identified and tracked by the RB, and use of PI by the licensee is monitored. - Inspections are designed to confirm that the licensee is planning and scheduling maintenance with due

Pressure vessel inspection criteria based on fitness-for-purpose assessment

International Nuclear Information System (INIS)

Grover, J.L.; Cipolla, R.C.

1985-01-01

The paper on pressure vessel inspection investigates the methodology required to establish an inspection strategy consistent with fracture mechanics analysis, i.e. to define allowable flaw sizes based on location within the vessel. The methodology is demonstrated using a sample problem for a typical pressurised water reactor pressure vessel, and shows the impact of certain assumptions on the inspection strategy. The results indicate that the flaw size varies with the shape of the assumed residual stress field and the through-thickness location. Also in general, the fracture mechanics evaluation allows flaws much larger than are allowed by the inspection acceptance criteria. (UK)

Auxiliary feedwater system risk-based inspection guide for the Beaver Valley, Units 1 and 2 nuclear power plants

International Nuclear Information System (INIS)

Lloyd, R.C.; Vehec, T.A.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Rossbach, L.W.; Sena, P.P. III

1993-02-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Beaver Valley Units 1 and 2 were selected as two of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at Beaver Valley Units 1 and 2

Deployment Plan for Small Roving Annulus Inspection Vehicle

International Nuclear Information System (INIS)

Minichan, R.

2002-01-01

The Small Roving Annulus Inspection Vehicle (SRAIV) is a modified commercially available wall crawler designed to supplement the In-Service Inspection (ISI) of Savannah River Site (SRS) Waste tanks. The SRAIV provides an improved capability to achieve a more complete inspection of the tank walls than existing methods. The SRAIV will be deployed through annulus risers in the tank to gain access to tank walls requiring inspection. The SRAIV will be deployed using a manually operated deployment pole and will be coupled to the wall using permanent magnet wheels. Navigation will be performed from the remote console where pictorial views can be displayed from the on-board cameras. The unit will incorporate multiple UT transducers for traditional weld examination. In addition, a specially developed Tandem Synthetic Aperture Focusing Technique (TSAFT) UT scanning bridge can be attached to provide further investigation of the knuckle region while the vehicle remains on the vertical surface of the tank wall. In summary, the SRAIV will provide features that enhance and expand the capability of the SRS ISI program

Planning and programming of pre-operational and in-service inspections

International Nuclear Information System (INIS)

Udaondo, M.S.

1984-01-01

After a brief mention of the actual scope of in-service inspection work, conclusions are presented that relate to the preparations for inspections, making use of experience acquired since 1972 at 11 nuclear power plants in Spain which have commissioned such studies from one particular organization, and analyses are given of the advantages to be gained therefrom. Three different aspects of preparations for inspections are considered: (a) man-hour estimates and the duration of in-service inspections; (b) the sequence of action during a pre-operational inspection (assuming a typical functional organization) from definition of the codes of practice and standards applicable up to the issue of the final report and the schedule for distribution of the annual work load to be invested in a typical project, as a result of combining the two previous estimates, and (c) the documentary aspect of preparations for an inspection during a scheduled outage, as related to the various documents to be drawn up and their contents. Reference is made to the general training to be given to the staff in charge of inspection activities so as to provide them with information on, and a perspective of, the in-service inspection jobs required. (author)

Approaching application of risk-based inspection to ASME code section XI

International Nuclear Information System (INIS)

Hedden, Owen F.

1995-01-01

This paper will describe current efforts within the ASME Boiler and Pressure Vessel Committee's Subcommittee on Nuclear Inservice Inspection to introduce risk-based technology to optimize inservice inspection of nuclear power plants. The subcommittee is responsible for the content of ASME Boiler and Pressure Vessel Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. The paper will first provide the historical background for the inspection program currently in Section XI. It will then describe the development of new technology through the ASME Center for Research and Technology Development program. Next, the work now going on in two of the groups under the Section XI committee will be described in detail. Each of these two efforts is directed toward the application of new risk-based inspection technology to nuclear piping systems. Finally, the directions of additional research and applications of the technology will be discussed. (author)

Boresonic inspection of power plant rotors

International Nuclear Information System (INIS)

Rennie, I.S.

1990-01-01

Continental Field Machining and NEI Parsons together are able to provide an on site machining and boresonic inspection service. NEI Parsons existing boresonic equipment is described together with a summary of results obtained during the inspection of eighty rotors. A computer controlled automatic inspection system, planned to be in operation early in 1990, is also described

Artist - analytical RT inspection simulation tool

International Nuclear Information System (INIS)

Bellon, C.; Jaenisch, G.R.

2007-01-01

The computer simulation of radiography is applicable for different purposes in NDT such as for the qualification of NDT systems, the prediction of its reliability, the optimization of system parameters, feasibility analysis, model-based data interpretation, education and training of NDT/NDE personnel, and others. Within the framework of the integrated project FilmFree the radiographic testing (RT) simulation software developed by BAM is being further developed to meet practical requirements for inspection planning in digital industrial radiology. It combines analytical modelling of the RT inspection process with the CAD-orientated object description applicable to various industrial sectors such as power generation, railways and others. (authors)

Risk-Based School Inspections: Impact of Targeted Inspection Approaches on Dutch Secondary Schools

Science.gov (United States)

Ehren, Melanie C.; Shackleton, Nichola

2016-01-01

In most countries, publicly funded schools are held accountable to one inspectorate and are judged against agreed national standards. Many inspectorates of education have recently moved towards more proportional risk-based inspection models, targeting high-risk schools for visits, while schools with satisfactory student attainment levels are…

Label inspection of approximate cylinder based on adverse cylinder panorama

Science.gov (United States)

Lin, Jianping; Liao, Qingmin; He, Bei; Shi, Chenbo

2013-12-01

This paper presents a machine vision system for automated label inspection, with the goal to reduce labor cost and ensure consistent product quality. Firstly, the images captured from each single-camera are distorted, since the inspection object is approximate cylindrical. Therefore, this paper proposes an algorithm based on adverse cylinder projection, where label images are rectified by distortion compensation. Secondly, to overcome the limited field of viewing for each single-camera, our method novelly combines images of all single-cameras and build a panorama for label inspection. Thirdly, considering the shake of production lines and error of electronic signal, we design the real-time image registration to calculate offsets between the template and inspected images. Experimental results demonstrate that our system is accurate, real-time and can be applied for numerous real- time inspections of approximate cylinders.

Description of double-shell tank selection criteria for inspection

International Nuclear Information System (INIS)

Schwenk, E.B.; Scott, K.V.

1996-01-01

Technical criteria for selecting double-shelf tanks's (DST's) for inspection are presented. Inspection of DST's is planned to non-destructively determine the general condition of their inner wall and bottom knuckle. Inspection of representative tanks will provide a basis for evaluating the integrity of all the DST's and provide a basis for estimating remaining life. The selection criteria recommended are tank age based on date-of-first fluid entry, waste temperature, corrosion inhibitor levels, deviations from normal behavior - involving sludge levels, hydrogen release and waste transfers - least waste depth fluctuation, tank steel type, other chemical species that could activate stress-corrosion cracking, and waste types

Northeast Inspection Services, Inc. boresonic inspection system evaluation

International Nuclear Information System (INIS)

Nottingham, L.D.; Sabourin, P.F.; Presson, J.H.

1993-04-01

Turbine rotor reliability and remaining life assessment are continuing concerns to electric utilities. Over the years, boresonic inspection and evaluation have served as primary components in rotor remaining life assessment. Beginning with an evaluation of TREES by EPRI in 1982, a series of reports that document the detection and sizing capabilities of several boresonic systems have been made available. These studies should provide utilities with a better understanding of system performance and lead to improved reliability when predicting rotor remaining life. In 1990, the procedures followed for evaluating rotor boresonic performance capabilities were changed to transfer a greater portion of the data analysis function to the participating vendor. This change from previous policy was instituted so that the evaluation results would better reflect the ''final answer'' that a vendor would provide in a real rotor inspection and also to reduce the cost of an evaluation. Among the first vendors to participate in the new performance demonstration was Northeast Inspection Services, Inc. (NISI). The tests reported herein were conducted by NISI personnel under the guidelines of the new plan. Details of the new evaluation plan are also presented. Rotor bore blocks containing surface-connected fatigue cracks, embedded glass beads, and embedded radial-axial oriented disks were used in the evaluation. Data were collected during twenty-five independent passes through the blocks. The evaluation consisted of statistical characterization of the detection capabilities, flaw sizing and location accuracy, and repeatability of the inspection system. The results of the evaluation are included in this report

Decontamination and inspection plan for Phase 3 closure of the 300 area waste acid treatment system

International Nuclear Information System (INIS)

LUKE, S.N.

1999-01-01

This decontamination and inspection plan (DIP) describes decontamination and verification activities in support of Phase 3 closure of the 300 Area Waste Acid Treatment System (WATS). Phase 3 is the third phase of three WATS closure phases. Phase 3 attains clean closure conditions for WATS portions of the 334 and 311 Tank Farms (TF) and the 333 and 303-F Buildings. This DIP also describes designation and management of waste and debris generated during Phase 3 closure activities. Information regarding Phase 1 and Phase 2 for decontamination and verification activities closure can be found in WHC-SD-ENV-AP-001 and HNF-1784, respectively. This DIP is provided as a supplement to the closure plan (DOE/RL-90-11). This DIP provides the documentation for Ecology concurrence with Phase 3 closure methods and activities. This DIP is intended to provide greater detail than is contained in the closure plan to satisfy Ecology Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-610 requirement that closure documents describe the methods for removing, transporting, storing, and disposing of all dangerous waste at the unit. The decontamination and verification activities described in this DIP are based on the closure plan and on agreements reached between Ecology and the U.S. Department of Energy, Richland Operations Office (DOE-RL) during Phase 3 closure activity workshops and/or project manager meetings (PMMs)

Risk-based Inspection Guide for the Susquehanna Station HPCI system

International Nuclear Information System (INIS)

Travis, R.; Higgins, J.; Gunther, W.; Shier, W.

1992-11-01

The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A system Risk-based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Susquehanna Steam Electric Station (SSES) which is operated by Pennsylvania Power ampersand Light (PP ampersand L). Included in this S-RIG is a discussion of the role of HPCI in mitigating accidents and a presentation of PRA-based failure modes which could prevent proper operation of the system. The S-RIG uses industry operating experience, including plant-specific illustrative examples, to augment the basic PRA failure modes. It is designed to be used as a reference for both routine inspections and the evaluation of the significance of component failures

Supervision and inspection plans of plants activities

International Nuclear Information System (INIS)

Feijoo, J. P.

2009-01-01

Any idea of hierarchization between supervisor and supervised in inspection and supervision activities should necessarily be dismissed, and the independence of the supervisor when executing has tasks should be guaranteed. The inspection and supervision program enable the detection and resolution of materials and human problems alike. In addition, they are a solution to anticipate potential problems in the future, which results in a very significant reduction of industrial accidents and human errors, as well as better use and upkeep of equipment. With these programs we improve our management and our work, and without a doubt they help to strengthen the safety culture in Cofrentes Nuclear Power Plant. (Author)

Risk-Informed Decisions Optimization in Inspection and Maintenance

International Nuclear Information System (INIS)

Robertas Alzbutas

2002-01-01

partial case is used for the construction and research of the models related to inspections and maintenance planning of Ignalina Nuclear Power Plant (RBMK-1500) piping components. The discussed example is related to risk analysis and inspection program improvements for selected pipe systems. The new risk-informed inspection and maintenance program for selected pipe systems are compared with various alternatives. The usage of risk evaluations to optimize the selection of inspection locations, the inspection interval, and the changes in risk and cost due suggested modifications are demonstrated. The proposed integrated modeling methodic and general model of inspection process can be used as a base for other risk-informed models of inspection process control and risk monitors of complex dynamic systems. (authors)

Massively parallel E-beam inspection: enabling next-generation patterned defect inspection for wafer and mask manufacturing

Science.gov (United States)

Malloy, Matt; Thiel, Brad; Bunday, Benjamin D.; Wurm, Stefan; Mukhtar, Maseeh; Quoi, Kathy; Kemen, Thomas; Zeidler, Dirk; Eberle, Anna Lena; Garbowski, Tomasz; Dellemann, Gregor; Peters, Jan Hendrik

2015-03-01

SEMATECH aims to identify and enable disruptive technologies to meet the ever-increasing demands of semiconductor high volume manufacturing (HVM). As such, a program was initiated in 2012 focused on high-speed e-beam defect inspection as a complement, and eventual successor, to bright field optical patterned defect inspection [1]. The primary goal is to enable a new technology to overcome the key gaps that are limiting modern day inspection in the fab; primarily, throughput and sensitivity to detect ultra-small critical defects. The program specifically targets revolutionary solutions based on massively parallel e-beam technologies, as opposed to incremental improvements to existing e-beam and optical inspection platforms. Wafer inspection is the primary target, but attention is also being paid to next generation mask inspection. During the first phase of the multi-year program multiple technologies were reviewed, a down-selection was made to the top candidates, and evaluations began on proof of concept systems. A champion technology has been selected and as of late 2014 the program has begun to move into the core technology maturation phase in order to enable eventual commercialization of an HVM system. Performance data from early proof of concept systems will be shown along with roadmaps to achieving HVM performance. SEMATECH's vision for moving from early-stage development to commercialization will be shown, including plans for development with industry leading technology providers.

IEC-based neutron generator for security inspection system

International Nuclear Information System (INIS)

Miley, G.H.; Wu, L.; Kim, H.J.

2005-01-01

Use of a combined X-ray and neutron source for security inspections based on Inertial Electrostatic Confinement (IEC) fusion is discussed. Current inspection systems typically use X-ray techniques, but thermal neutron analysis (TNA) and fast neutron analysis (FNA), allow expanded detection of certain types of explosives. The integrated unit proposed here uses three separate IEC sources producing 14 and 2.45 MeV neutrons plus soft X-rays. This combination allows multiple detection methods with the composite signal analysis being done by a fuzzy logic system, significantly reducing false signals. (author)

A portable solution to enable guided ultrasonic inspection

International Nuclear Information System (INIS)

Enenkel, Laurent; Buechler, Johannes; Poirier, Jerome; Jervis David

2012-01-01

This paper describes the development and application of an innovative ultrasonic (UT) inspection system, which is 100% guided and menu-driven to reduce human error and ensure both inspection accuracy and productivity in the reliable and accurate non-destructive testing (NDT) of shafts, tubes, pipes, and other components and structures. Set-up is menu-directed with the minimum of instrument-specific training, allowing the integral operating software to calculate all the ultrasonic parameters for each task according to the inspection procedure and create an easy-to-follow inspection plan, using either phased array or conventional UT. The operator then scans the work piece, with an encoded scanner, which ensures that the inspection plan is strictly followed. Inspection data is transmitted to a review station in the industry-accepted, non-proprietary DICONDE protocol, allowing advanced analysis tools, such as real time, volume corrected imaging, to allow easier and more reliable image interpretation. By using GEs Rhythm software platform, inspection data can be reviewed and shared, reports generated and inspection results archived for traceability, tracking or further analysis.

Trends of degradation in steam generator tubes of Krsko NPP before the last planned inspection

International Nuclear Information System (INIS)

Cizelj, L.; Dvorsek, T.; Androjna, F.

1998-01-01

Full-length inspection of all active tubes in both Krsko steam generators resulted in a huge amount of inspection records. A computerized database was developed by Reactor Engineering division to accelerate the management of about 200.000 records. The database was designed to support the development and decision related to the plugging criteria for damaged tubes and is utilized to gain as much experience concerning the degradation of SG tube as possible. In this paper, two prevailing group of data are statistically analyzed: the axial cracks in expansion transitions at the top of tube sheet (TTS) and Outside Diameter Stress Corrosion Cracking at tube support plates (TSP). Especially ODSCC caused a vast majority of repaired tubes (e.g., plugs and sleeves). The influence of plant startups involving oxidizing transient on the repair rates of tubes affected by ODSCC is analyzed in some detail. The results are promising and show excellent correlation in SG 2 and reasonable fit in SG 1. Predictions of maximum expected number of tubes repaired due to ODSCC at the last planned inspection is given as 67 in SG 1 and 400 in SG 2. (author)

33 CFR 164.80 - Tests, inspections, and voyage planning.

Science.gov (United States)

2010-07-01

... searchlights. (5) Terminal gear. Visual inspection of tackle; of connections of bridle and towing pendant, if.... (2) Terminal gear. Visual inspection of tackle; of connections of bridle and towing pendant, if... under-keel and vertical clearances (air-gaps) for all bridges, ports, and berthing areas; (v) Pre...

Development of a two-stage inspection process for the assessment of deteriorating infrastructure

International Nuclear Information System (INIS)

Sheils, Emma; O'Connor, Alan; Breysse, Denys; Schoefs, Franck; Yotte, Sylvie

2010-01-01

Inspection-based maintenance strategies can provide an efficient tool for the management of ageing infrastructure subjected to deterioration. Many of these methods rely on quantitative data from inspections, rather than qualitative and subjective data. The focus of this paper is on the development of an inspection-based decision scheme, incorporating analysis on the effect of the cost and quality of NDT tools to assess the condition of infrastructure elements/networks during their lifetime. For the first time the two aspects of an inspection are considered, i.e. detection and sizing. Since each stage of an inspection is carried out for a distinct purpose, different parameters are used to represent each procedure and both have been incorporated into a maintenance management model. The separation of these procedures allows the interaction between the two inspection techniques to be studied. The inspection for detection process acts as a screening exercise to determine which defects require further inspection for sizing. A decision tool is developed that allows the owner/manager of the infrastructural element/network to choose the most cost-efficient maintenance management plan based on his/her specific requirements.

Engineering Work Plan for Development of Sludge Pickup Adapter for Fuel Cleanliness Inspections

International Nuclear Information System (INIS)

PITNER, A.L.

2000-01-01

The plan for developing an adapter to suction up sludge into a calibrated tube for fuel cleanliness inspection activities is described. A primary assessment of fuel cleanliness to be performed after processing through the Primary Cleaning Machine is whether the volume of any remaining canister sludge in or on a fuel assembly exceeds the allowable 14 cm 3 limit. It is anticipated that a general visual inspection of the sludge inventory after fuel assembly separation will usually suffice in making this assessment, but occasions may arise where there is some question as to whether or not the observed quantity of sludge exceeds this limit. Therefore a quantitative method of collecting and measuring the sludge volume is needed for these borderline situations. It is proposed to develop an adapter that fits on the end of the secondary cleaning station vacuum wand that will suction the material from the sludge collection tray into a chamber marked with the limiting volume to permit a direct go/no-go assessment of the sludge quantity

Flight route Designing and mission planning Of power line inspecting system Based On multi-sensor UAV

International Nuclear Information System (INIS)

Xiaowei, Xie; Zhengjun, Liu; Zhiquan, Zuo

2014-01-01

In order to obtain various information of power facilities such as spatial location, geometry, images data and video information in the infrared and ultraviolet band and so on, Unmanned Aerial Vehicle (UAV) power line inspecting system needs to integrate a variety of sensors for data collection. Low altitude and side-looking imaging are required for UAV flight to ensure sensors to acquire high-quality data and device security. In this paper, UAV power line inspecting system is deferent from existing ones that used in Surveying and Mapping. According to characteristics of UAV for example equipped multiple sensor, side-looking imaging, working at low altitude, complex terrain conditions and corridor type flight, this paper puts forward a UAV power line inspecting scheme which comprehensively considered of the UAV performance, sensor parameters and task requirements. The scheme is finally tested in a region of Guangdong province, and the preliminary results show that the scheme is feasible

Study on the inspection item and inspection method of HTGR fuel

International Nuclear Information System (INIS)

Na, Sang Ho; Kim, Y. K.; Jeong, K. C.; Oh, S. C.; Cho, M. S.; Kim, Y. M.; Lee, Y. W.

2006-01-01

The type of HTGR(High Temperature Gas-cooled Reactor) fuel is different according to the reactor type. Generally the HTGR fuel has two types. One is a block type, which is manufactured in Japan or America. And the other is a pebble type, which is manufactured in China. Regardless of the fuel type, the fuel manufacturing process started from the coated particle, which is consisted of fuel kernel and the 4 coating layers. Korea has a plan to fabricate a HTGR fuel in near future. The appropriate quality inspection standards are requested to produce a sound and reliable coated particle for HTGR fuel. Therefore, the inspection items and the inspection methods of HTGR fuel between Japan and China, which countries have the manufacturing process, are investigated to establish a proper inspection standards of our product characteristics

Development of the Risk-Based Inspection Techniques and Pilot Plant Activities

International Nuclear Information System (INIS)

Phillips, J.H.

1997-01-01

Risk-based techniques have been developed for commercial nuclear power plants. System boundaries and success criteria is defined using the probabilistic risk analysis or probabilistic safety analysis developed to meet the individual plant evaluation. Final ranking of components is by a plant expert panel similar to the one developed for maintenance rule. Components are identified as being high risk-significant or low-risk significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of pilot plants. Results from the first risk-based inspection pilot plant indicates that safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. The reduction in inspection reduces the person-rem exposure resulting in further increases in safety. These techniques have been documented in publication by the ASME CRTD

A survey on inspecting structures using robotic systems

Directory of Open Access Journals (Sweden)

Randa Almadhoun

2016-11-01

Full Text Available Advancements in robotics and autonomous systems are being deployed nowadays in many application domains such as search and rescue, industrial automation, domestic services and healthcare. These systems are developed to tackle tasks in some of the most challenging, labour intensive and dangerous environments. Inspecting structures (e.g. bridges, buildings, ships, wind turbines and aircrafts is considered a hard task for humans to perform and of critical importance since missing any details could affect the structure’s performance and integrity. Additionally, structure inspection is time and resource intensive and should be performed as efficiently and accurately as possible. Inspecting various structures has been reported in the literature using different robotic platforms to: inspect difficult to reach areas and detect various types of faults and anomalies. Typically, inspection missions involve performing three main tasks: coverage path planning, shape, model or surface reconstruction and the actual inspection of the structure. Coverage path planning ensures the generation of an optimized path that guarantees the complete coverage of the structure of interest in order to gather highly accurate information to be used for shape/model reconstruction. This article aims to provide an overview of the recent work and breakthroughs in the field of coverage path planning and model reconstruction, with focus on 3D reconstruction, for the purpose of robotic inspection.

Inspection of Emergency Arrangements

International Nuclear Information System (INIS)

2013-01-01

The Working Group on Inspection Practices (WGIP) was tasked by the NEA CNRA to examine and evaluate the extent to which emergency arrangements are inspected and to identify areas of importance for the development of good inspection practices. WGIP members shared their approaches to the inspection of emergency arrangements by the use of questionnaires, which were developed from the requirements set out in IAEA Safety Standards. Detailed responses to the questionnaires from WGIP member countries have been compiled and are presented in the appendix to this report. The following commendable practices have been drawn from the completed questionnaires and views provided by WGIP members: - RBs and their Inspectors have sufficient knowledge and information regarding operator's arrangements for the preparedness and response to nuclear emergencies, to enable authoritative advice to be given to the national coordinating authority, where necessary. - Inspectors check that the operator's response to a nuclear emergency is adequately integrated with relevant response organisations. - Inspectors pay attention to consider the integration of the operator's response to safety and security threats. - The efficiency of international relations is checked in depth during some exercises (e.g. early warning, assistance and technical information), especially for near-border facilities that could lead to an emergency response abroad. - RB inspection programmes consider the adequacy of arrangements for emergency preparedness and response to multi-unit accidents. - RBs assess the adequacy of arrangements to respond to accidents in other countries. - The RB's role is adequately documented and communicated to all agencies taking part in the response to a nuclear or radiological emergency. - Inspectors check that threat assessments for NPPs have been undertaken in accordance with national requirements and that up-to-date assessments have been used as the basis for developing emergency plans for

Extreme Learning Machine and Moving Least Square Regression Based Solar Panel Vision Inspection

Directory of Open Access Journals (Sweden)

Heng Liu

2017-01-01

Full Text Available In recent years, learning based machine intelligence has aroused a lot of attention across science and engineering. Particularly in the field of automatic industry inspection, the machine learning based vision inspection plays a more and more important role in defect identification and feature extraction. Through learning from image samples, many features of industry objects, such as shapes, positions, and orientations angles, can be obtained and then can be well utilized to determine whether there is defect or not. However, the robustness and the quickness are not easily achieved in such inspection way. In this work, for solar panel vision inspection, we present an extreme learning machine (ELM and moving least square regression based approach to identify solder joint defect and detect the panel position. Firstly, histogram peaks distribution (HPD and fractional calculus are applied for image preprocessing. Then an ELM-based defective solder joints identification is discussed in detail. Finally, moving least square regression (MLSR algorithm is introduced for solar panel position determination. Experimental results and comparisons show that the proposed ELM and MLSR based inspection method is efficient not only in detection accuracy but also in processing speed.

Development of outdoor luminescence imaging for drone-based PV array inspection

DEFF Research Database (Denmark)

Benatto, Gisele Alves dos Reis; Riedel, Nicholas; Thorsteinsson, Sune

2017-01-01

This work has the goal to examined experimentally PV module imaging methods under natural light conditions, that will be used in a fast, accurate and automatic drone-based inspection system for PV power plants.......This work has the goal to examined experimentally PV module imaging methods under natural light conditions, that will be used in a fast, accurate and automatic drone-based inspection system for PV power plants....

Development of innovative inspection tools for higher reliability of PHWR fuel

International Nuclear Information System (INIS)

Kamalesh Kumar, B.; Viswanathan, B.; Laxminarayana, B.; Ganguly, C.

2003-01-01

'Full text:' Advent of Computer aided manufacturing systems has led to very high rate of production with greater reliability. The conventional inspection tools and systems, which are often manual based do not complement with output of highly automated production line. In order to overcome the deficiency, a strategic plan was developed for having automated inspection facility for PHWR fuel assembly line. Laser based systems with their inherently high accuracy and quick response times are a favorite for metrology purpose. Non-contact nature of laser-based measurement ensures minimal contamination, low wear and tear and good repeatability. So far two laser-based systems viz. Pellet density measurement systems and triangulation sensors have been developed. Laser based fuel pellet inspection system and PHWR fuel bundle metric station are under development. Machine vision-based systems have been developed to overcome certain limitations when inspection has to be carried out on such a large scale manually. These deficiencies arise from limitations of resolution, accessibility, fatigue and absence of quantification ability. These problems get further compounded in inspection of fuel components because of their relatively small sizes, close tolerances required and the reflective surfaces. PC based vision system has been developed for inspecting components and fuel assemblies. The paper would touch upon the details of the various laser systems and vision systems that have been indigenously developed for PHWR Fuel Metrology and their impact on the assembly production line. (author)

Rail inspection of RCF defects

Directory of Open Access Journals (Sweden)

Z. Popović

2013-10-01

Full Text Available Rail defects due to rolling contact fatigue (RCF threaten the traffic safety around the world. That hazard is more distinct on railways without adequate maintenance strategy. Realization of interoperability of European railway network demands from every infrastructure manager to have a maintenance plan for the infrastructure subsystem. Besides that, this plan includes rail inspection and strategy against RCF defects. This paper emphasizes the importance of rail inspection and early detection of RCF because the most of RCF crack should be removed in rail grinding campaigns (preventive, cyclical and corrective activities during the whole rail service life.

Proposal for inclusion of the risk based inspection technique in Regulatory Standard NR 13; Proposta de inclusao da tecnica de inspecao baseada em risco na Norma Regulamentadora NR 13

Energy Technology Data Exchange (ETDEWEB)

Esteves, Vinicius Teixeira; Lima, Marco Aurelio Oliveira [Det Norske Veritas Ltda. (DNV), Rio de Janeiro, RJ (Brazil)

2012-07-01

In Brazil, the Regulatory Standard n. 13 (NR 13) establishes requirements for the inspection of boilers and pressure vessels which has main objective of preventing accidents with these types of equipment. Additionally, it has the Risk-Based Inspection (RBI) technique as an effective way to manage the mechanical integrity of various types of static mechanical equipment by through an inspection planning based on the risk factor. In this study, it is being proposed to include the RBI technique, in the NR 13, for the planning and definition of periods for the safety inspection of boilers and pressure vessels in order to promote an increase in the operational safety in process industries in Brazil. In this study it was carried out a critical analysis of NR 13 and RBI, and beyond that a bibliographic research of various international documents that relate the operational safety of pressurized equipment with the inspection activity, and the acceptability of RBI by governments, agencies and organizations around the world. It is considered that the inclusion and formal acceptance of RBI technique in the NR 13 must be accompanied by a rigorous control to avoid the 'trivialization' of its use and ensure the implementation rational, efficient and reliable. Finally, it was developed and suggested basic elements and minimum requirements to be inserted in the NR 13, to be attended, in order mandatory, by the companies that choose the implementation and use of the RBI technique as a tool for the planning of safety inspection of boilers and pressure vessels. It is concluded that the formal acceptance of the RBI technique in the NR 13 could aggregate much value to this standard, with regard to the prevention of accidents involving boilers or pressure vessels, and provide a technological jump to the companies that make use of RBI technique in Brazil. (author)

Risk based inspection for atmospheric storage tank

Science.gov (United States)

Nugroho, Agus; Haryadi, Gunawan Dwi; Ismail, Rifky; Kim, Seon Jin

2016-04-01

Corrosion is an attack that occurs on a metallic material as a result of environment's reaction.Thus, it causes atmospheric storage tank's leakage, material loss, environmental pollution, equipment failure and affects the age of process equipment then finally financial damage. Corrosion risk measurement becomesa vital part of Asset Management at the plant for operating any aging asset.This paper provides six case studies dealing with high speed diesel atmospheric storage tank parts at a power plant. A summary of the basic principles and procedures of corrosion risk analysis and RBI applicable to the Process Industries were discussed prior to the study. Semi quantitative method based onAPI 58I Base-Resource Document was employed. The risk associated with corrosion on the equipment in terms of its likelihood and its consequences were discussed. The corrosion risk analysis outcome used to formulate Risk Based Inspection (RBI) method that should be a part of the atmospheric storage tank operation at the plant. RBI gives more concern to inspection resources which are mostly on `High Risk' and `Medium Risk' criteria and less on `Low Risk' shell. Risk categories of the evaluated equipment were illustrated through case study analysis outcome.

Risk-based optimization of pipe inspections in large underground networks with imprecise information

International Nuclear Information System (INIS)

Mancuso, A.; Compare, M.; Salo, A.; Zio, E.; Laakso, T.

2016-01-01

In this paper, we present a novel risk-based methodology for optimizing the inspections of large underground infrastructure networks in the presence of incomplete information about the network features and parameters. The methodology employs Multi Attribute Value Theory to assess the risk of each pipe in the network, whereafter the optimal inspection campaign is built with Portfolio Decision Analysis (PDA). Specifically, Robust Portfolio Modeling (RPM) is employed to identify Pareto-optimal portfolios of pipe inspections. The proposed methodology is illustrated by reporting a real case study on the large-scale maintenance optimization of the sewerage network in Espoo, Finland. - Highlights: • Risk-based approach to optimize pipe inspections on large underground networks. • Reasonable computational effort to select efficient inspection portfolios. • Possibility to accommodate imprecise expert information. • Feasibility of the approach shown by Espoo water system case study.

International cooperation in production inspections

International Nuclear Information System (INIS)

Limousin, S.

2009-01-01

Nuclear pressure equipment, like the reactor pressure vessel or steam generators, are manufactured in many countries all around the world. As only few reactors were built in the 90's, most of the nuclear safety authorities have lost part of their know how in component manufacturing oversight. For these two reasons, vendor inspection is a key area for international cooperation. On the one hand, ASN has bilateral relationships with several countries (USA, Finland, China...) to fulfill specific purposes. On the other hand, ASN participates in international groups like the MDEP ( Multinational Design Evaluation Program). A MDEP working group dedicated to vendor inspection cooperation enables exchanges of informations (inspection program plan, inspection findings...) among the regulators. Join inspections are organized. International cooperation could lead in the long term to an harmonization of regulatory practices. (author)

An intelligent inspection and survey robot. Volume 1

International Nuclear Information System (INIS)

1995-01-01

ARIES number-sign 1 (Autonomous Robotic Inspection Experimental System), has been developed for the Department of Energy to survey and inspect drums containing low-level radioactive waste stored in warehouses at DOE facilities. The drums are typically stacked four high and arranged in rows with three-foot aisle widths. The robot will navigate through the aisles and perform an inspection operation, typically performed by a human operator, making decisions about the condition of the drums and maintaining a database of pertinent information about each drum. A new version of the Cybermotion series of mobile robots is the base mobile vehicle for ARIES. The new Model K3A consists of an improved and enhanced mobile platform and a new turret that will permit turning around in a three-foot aisle. Advanced sonar and lidar systems were added to improve navigation in the narrow drum aisles. Onboard computer enhancements include a VMEbus computer system running the VxWorks real-time operating system. A graphical offboard supervisory UNIX workstation is used for high-level planning, control, monitoring, and reporting. A camera positioning system (CPS) includes primitive instructions for the robot to use in referencing and positioning the payload. The CPS retracts to a more compact position when traveling in the open warehouse. During inspection, the CPS extends up to deploy inspection packages at different heights on the four-drum stacks of 55-, 85-, and 110-gallon drums. The vision inspection module performs a visual inspection of the waste drums. This system will locate and identify each drum, locate any unique visual features, characterize relevant surface features of interest and update a data-base containing the inspection data

An intelligent inspection and survey robot. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-15

ARIES {number_sign}1 (Autonomous Robotic Inspection Experimental System), has been developed for the Department of Energy to survey and inspect drums containing low-level radioactive waste stored in warehouses at DOE facilities. The drums are typically stacked four high and arranged in rows with three-foot aisle widths. The robot will navigate through the aisles and perform an inspection operation, typically performed by a human operator, making decisions about the condition of the drums and maintaining a database of pertinent information about each drum. A new version of the Cybermotion series of mobile robots is the base mobile vehicle for ARIES. The new Model K3A consists of an improved and enhanced mobile platform and a new turret that will permit turning around in a three-foot aisle. Advanced sonar and lidar systems were added to improve navigation in the narrow drum aisles. Onboard computer enhancements include a VMEbus computer system running the VxWorks real-time operating system. A graphical offboard supervisory UNIX workstation is used for high-level planning, control, monitoring, and reporting. A camera positioning system (CPS) includes primitive instructions for the robot to use in referencing and positioning the payload. The CPS retracts to a more compact position when traveling in the open warehouse. During inspection, the CPS extends up to deploy inspection packages at different heights on the four-drum stacks of 55-, 85-, and 110-gallon drums. The vision inspection module performs a visual inspection of the waste drums. This system will locate and identify each drum, locate any unique visual features, characterize relevant surface features of interest and update a data-base containing the inspection data.

Summary report for 1990 inservice inspection (ISI) of SRS 100-L reactor tank

International Nuclear Information System (INIS)

Morrison, J.M.; Loibl, M.W.

1991-01-01

The integrity of the SRS reactor tanks is a key factor affecting their suitability for continued service since, unlike the external piping system and components, the tanks are virtually irreplaceable. Cracking in various areas of the process water piping systems has occurred beginning in about 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. The primary objective of this inspection was to determine if the accessible welds and selected portions of base metal in the L Reactor tank wall contain any indications of IGSCC. This inspection included areas in and beyond the weld HAZ, extending out as far as two to three inches from the centerline of the welds, plus selected areas of base metal at the intersection of the main tank vertical and mid-girth welds. No evidence of such degradation was found in any of the areas examined. Further, additional inspections were conducted of areas that had been damaged and repaired during original fabrication, and on a sample of areas containing linear indications observed during the 1986 visual inspection of the tank. No evidence of IGSCC or other service induced degradation was detected in these areas, either. The inspection was initially planned to cover a minimum of 60% of the accessible welds, plus repair areas and a sample of the indications from the 1986 visual inspection. Direction was received from DOE while the inspection was in progress to expand the scope to cover 100% of the accessible weld areas, and the plan was adjusted accordingly. Initial setup of the tank, which prior to inspection contained Mark 60B target assemblies and nearly a full charge of Mark 22 fuel assemblies, began on October 15, 1990. The inspection was completed on April 12, 1991

Application of risk based inspection methodology of API 581 BRD to oil pipelines

Energy Technology Data Exchange (ETDEWEB)

Pezzi Filho, M. [Petrobras, Rio de Janeiro (Brazil); Freire, J.L.F.; Maragone, F.. [Pontifica Univ. Catolica, Rio de Janeiro (Brazil)

2004-07-01

In response to public concerns regarding the safe operation of pipelines, operators are relying on risk management to balance the demands of pipeline integrity and service competitiveness. This paper presented a procedure for calculating the probability of failure according to the API 581 BRD RB I methodology that uses data collected from 3 existing oil pipelines subject to internal corrosion. The risk exposure that the pipeline may be subjected to during its remaining operating life was evaluated. Risk is a function of the probability of failure and the consequences of that failure. Therefore, if the consequences of the failure are assumed to remain unchanged for a given equipment under specific operational conditions, then risk reduction will only be achieved by decreasing the probability of failure and through management of the inspection process. It was shown that if the confidence on the damage rate and on the inspection effectiveness is known, then it is possible to design an alternative to an existing inspection plan. This calls for pig inspections at 5 year intervals to ensure that the probability of failures for pipelines will be under a certain level of tolerable risk. 9 refs., 4 tabs., 3 figs.

Experience with the implementation of a risk-based ISI program and inspection qualification

International Nuclear Information System (INIS)

Chapman, O.J.V.

1996-01-01

Rolls Royce and Associates (RRA) are the Design Authority (DA) for Nuclear Steam Raising Plant (NSRP) used for the Royal Naval Nuclear Fleet. Over the past seven years RRA, with support from the Ministry of Defense, has developed and implemented a risk based in-service inspection (RBISI) strategy for the NSRP. Having used risk as a means of optimizing where to inspect, an inspection qualification (IQ) process has now been put in place to ensure that proposed inspections deliver the expected gains assumed. This qualification process follows very closely that currently being put forward by the European Network on Inspection Qualification (ENIQ)

Evaluation of effectiveness of inservice inspection in aging PWR plants based on PSA

Energy Technology Data Exchange (ETDEWEB)

Hanafusa, Hidemitsu; Irie, Takashi; Suyama, Takeshi [Institute of Nuclear Safety Systems Inc., Mihama, Fukui (Japan); Morota, Hidetsugu [Computer Software Development Co., Ltd., Tokyo (Japan)

2001-09-01

By making use of a probabilistic fracture mechanics (PFM) code which had been improved to be able to evaluate the influence of thermal aging embrittlement of cast stainless steel, we evaluated the fracture probability of welding parts of the piping of the pressurized water reactor plants in Japan and the core damage frequency by the fracture. In addition, we ranked the welding parts by the safety significance and evaluated the effectiveness of inservice inspection (ISI). As a result, it is seen that the risk increases about 25% for extending the plant life from 40 to 60 years without ISI. However, the influence of the risk on the plant life becomes negligible, when the ISI is performed adequately. This assessment is useful to plan efficient inspection and test programs of a plant under limited resources, because it is available to rank piping segments by the safety significance and to evaluate the effectiveness of inspection and test quantitatively. (author)

A real-time standard parts inspection based on deep learning

Science.gov (United States)

Xu, Kuan; Li, XuDong; Jiang, Hongzhi; Zhao, Huijie

2017-10-01

Since standard parts are necessary components in mechanical structure like bogie and connector. These mechanical structures will be shattered or loosen if standard parts are lost. So real-time standard parts inspection systems are essential to guarantee their safety. Researchers would like to take inspection systems based on deep learning because it works well in image with complex backgrounds which is common in standard parts inspection situation. A typical inspection detection system contains two basic components: feature extractors and object classifiers. For the object classifier, Region Proposal Network (RPN) is one of the most essential architectures in most state-of-art object detection systems. However, in the basic RPN architecture, the proposals of Region of Interest (ROI) have fixed sizes (9 anchors for each pixel), they are effective but they waste much computing resources and time. In standard parts detection situations, standard parts have given size, thus we can manually choose sizes of anchors based on the ground-truths through machine learning. The experiments prove that we could use 2 anchors to achieve almost the same accuracy and recall rate. Basically, our standard parts detection system could reach 15fps on NVIDIA GTX1080 (GPU), while achieving detection accuracy 90.01% mAP.

SmartInspect: Smart Contract Inspection Technical Report

OpenAIRE

Bragagnolo , Santiago; Rocha , Henrique ,; Denker , Marcus; Ducasse , Stéphane

2017-01-01

Smart contracts are embedded procedures stored with the data they act upon. Debugging deployed Smart Contracts is a difficult task since once deployed, the code cannot be reexecuted and inspecting a simple attribute is not easily possible because data is encoded. In this technical report, we present SmartInspect to address the lack of inspectability of a deployed contract. Our solution analyses the contract state by using decompilation techniques and a mirror-based architecture to represent t...

Fully Employing Software Inspections Data

Science.gov (United States)

Shull, Forrest; Feldmann, Raimund L.; Seaman, Carolyn; Regardie, Myrna; Godfrey, Sally

2009-01-01

Software inspections provide a proven approach to quality assurance for software products of all kinds, including requirements, design, code, test plans, among others. Common to all inspections is the aim of finding and fixing defects as early as possible, and thereby providing cost savings by minimizing the amount of rework necessary later in the lifecycle. Measurement data, such as the number and type of found defects and the effort spent by the inspection team, provide not only direct feedback about the software product to the project team but are also valuable for process improvement activities. In this paper, we discuss NASA's use of software inspections and the rich set of data that has resulted. In particular, we present results from analysis of inspection data that illustrate the benefits of fully utilizing that data for process improvement at several levels. Examining such data across multiple inspections or projects allows team members to monitor and trigger cross project improvements. Such improvements may focus on the software development processes of the whole organization as well as improvements to the applied inspection process itself.

Feature Space Dimensionality Reduction for Real-Time Vision-Based Food Inspection

Directory of Open Access Journals (Sweden)

Mai Moussa CHETIMA

2009-03-01

Full Text Available Machine vision solutions are becoming a standard for quality inspection in several manufacturing industries. In the processed-food industry where the appearance attributes of the product are essential to customer’s satisfaction, visual inspection can be reliably achieved with machine vision. But such systems often involve the extraction of a larger number of features than those actually needed to ensure proper quality control, making the process less efficient and difficult to tune. This work experiments with several feature selection techniques in order to reduce the number of attributes analyzed by a real-time vision-based food inspection system. Identifying and removing as much irrelevant and redundant information as possible reduces the dimensionality of the data and allows classification algorithms to operate faster. In some cases, accuracy on classification can even be improved. Filter-based and wrapper-based feature selectors are experimentally evaluated on different bakery products to identify the best performing approaches.

Typical IAEA inspection procedures for model plant

International Nuclear Information System (INIS)

Theis, W.

1984-01-01

This session briefly refers to the legal basis for IAEA inspections and to their objectives. It describes in detail the planning and performance of IAEA inspections, including the examination of records, the comparison of facility records with State reports, flow and inventory verifications, the design of statistical sampling plans, and Agency's independent verification measurements. In addition, the session addresses the principles of Material Balance and MUF evaluation, as well as the content and format of summary statements and related problems

Advanced inspection technology for non intrusive inspection (NII) program

International Nuclear Information System (INIS)

Zamir Mohamed Daud

2003-01-01

In the current economic environment, plants and facilities are under pressure to introduced cost saving as well as profit maximising measures. Among the many changes in the way things are run is a move towards Risk Based Inspection (RBI), with an emphasis on longer operating periods between shutdowns as well as to utilise components to their maximum capability. Underpinning and RBI program requires good data from an effective online inspections program, which would not require the shutdown of critical components. One methodology of online inspection is known as Non Intrusive Inspection (NII), an inspection philosophy with the objective of replacing internal inspection of a vessel by doing Non Destructive Testing (NDT) and inspections externally. To this end, a variety of advanced NDT techniques are needed to provide accurate online measurements. (Author)

Inspection technologies -Development of national safeguards technology-

International Nuclear Information System (INIS)

Hong, J. S.; Kim, B. K.; Kwack, E. H.

1996-12-01

17 facility regulations prepared by nuclear facilities according to the Ministerial Notices were evaluated. Safeguards inspection activities under Safeguards are described. Safeguards inspection equipments and operation manuals to be used for national inspection are also described. Safeguards report are produced and submitted to MOST by using the computerized nuclear material accounting system at state level. National inspection support system are developed to produce the on-site information for domestic inspection. Planning and establishment of policy for nuclear control of nuclear materials, international cooperation for nuclear control, CTBT, strengthening of international safeguards system, and the supply of PWRs to North Korea are also described. (author). 43 tabs., 39 figs

A risk-based restaurant inspection system in Los Angeles County.

Science.gov (United States)

Buchholz, U; Run, G; Kool, J L; Fielding, J; Mascola, L

2002-02-01

thermometers, and the presence of any food protection violation. In multivariate analysis, the size of restaurant, the incorrect storage of food, the reuse of food, and the presence of any food protection violation remained significant predictors for becoming a case restaurant. Our data suggest that routine restaurant inspections should concentrate on those establishments that have a large seating capacity or a poor inspection history. Evaluation of inspection data bases in individual local health departments and translation of those findings into inspection guidelines could lead to an increased efficiency and perhaps cost-effectiveness of local inspection programs.

Luminescence Imaging Strategies for Drone-Based PV Array Inspection

DEFF Research Database (Denmark)

Benatto, Gisele Alves dos Reis; Riedel, Nicholas; Mantel, Claire

2017-01-01

) acquisition under natural light conditions during several times of the day, under high sun irradiation, to unveil the sunlight noise characteristics towards an InGaAs detector. In order to bring more freedom to a drone-based inspection, we also show the preliminary results of a laser-line based...

In service inspection of pipes based on risk methods

International Nuclear Information System (INIS)

Mendoza G, G.; Viais J, J.; Carmona C, M.

2006-01-01

The politics of the Nuclear Regulatory Commission (by its initials in English NRC) of the United States of America on the use of the Probabilistic Safety Analysis (PSA) in activities of nuclear regulation it foments the use of this analysis technique to improve the decisions making, to reduce the unnecessary work in maintenance aspects, inspection and tests and to improve the regulatory efficiency. The inspection programs in service (ISI by its initials in English) developed by the American Society of Mechanical Engineers (by its initials in English ASME) it has been the one primary mechanism to prove the mechanical equipment in plants of nuclear energy, these programs indeed have been carried out in plants of nuclear energy by more of two decades. Their purpose is to identify the conditions, such as indications of cracks that are precursory of flights and ruptures which violate the integrity principles of the pressure frontier. The inspection in service activities include ultrasonic tests, surface tests and penetrating liquids test, also activities that include the scaffolds construction, removal of insulations and welding polishing. The inspections in service every 18 months during the times outside of service are executed. One of the objectives is to lower the costs of the inspections during the times outside of service and to reduce the exposure to the radiation by part of the personnel during these times out for inspections, while it is increased or it maintains the personnel's safety and the reliability. As part of the methodology a pipe segment is selected for which a fault in any point has the same consequences, being calculated the fault probability of the tube using the dimensions of the segment. In this work the inspection in service methodology is applied based on risk to an aspersion system of low pressure of the Laguna Verde Nucleo electric Central. For this system a reduction in the number of welding to inspect of 103 to only 15 is obtained

Integration of design and inspection

Science.gov (United States)

Simmonds, William H.

1990-08-01

Developments in advanced computer integrated manufacturing technology, coupled with the emphasis on Total Quality Management, are exposing needs for new techniques to integrate all functions from design through to support of the delivered product. One critical functional area that must be integrated into design is that embracing the measurement, inspection and test activities necessary for validation of the delivered product. This area is being tackled by a collaborative project supported by the UK Government Department of Trade and Industry. The project is aimed at developing techniques for analysing validation needs and for planning validation methods. Within the project an experimental Computer Aided Validation Expert system (CAVE) is being constructed. This operates with a generalised model of the validation process and helps with all design stages: specification of product requirements; analysis of the assurance provided by a proposed design and method of manufacture; development of the inspection and test strategy; and analysis of feedback data. The kernel of the system is a knowledge base containing knowledge of the manufacturing process capabilities and of the available inspection and test facilities. The CAVE system is being integrated into a real life advanced computer integrated manufacturing facility for demonstration and evaluation.

Nuclear power plant pressure vessels. Inservice inspections

International Nuclear Information System (INIS)

1995-01-01

The requirements for the planning and reporting of inservice inspections of nuclear power plant pressure vessels are presented. The guide specifically applies to inservice inspections of Safety class 1 and 2 nuclear power plant pressure vessels, piping, pumps and valves plus their supports and reactor pressure vessel internals by non- destructive examination methods (NDE). Inservice inspections according to the Pressure Vessel Degree (549/73) are discussed separately in the guide YVL 3.0. (4 refs.)

Quality Inspection and Analysis of Three-Dimensional Geographic Information Model Based on Oblique Photogrammetry

Science.gov (United States)

Dong, S.; Yan, Q.; Xu, Y.; Bai, J.

2018-04-01

In order to promote the construction of digital geo-spatial framework in China and accelerate the construction of informatization mapping system, three-dimensional geographic information model emerged. The three-dimensional geographic information model based on oblique photogrammetry technology has higher accuracy, shorter period and lower cost than traditional methods, and can more directly reflect the elevation, position and appearance of the features. At this stage, the technology of producing three-dimensional geographic information models based on oblique photogrammetry technology is rapidly developing. The market demand and model results have been emerged in a large amount, and the related quality inspection needs are also getting larger and larger. Through the study of relevant literature, it is found that there are a lot of researches on the basic principles and technical characteristics of this technology, and relatively few studies on quality inspection and analysis. On the basis of summarizing the basic principle and technical characteristics of oblique photogrammetry technology, this paper introduces the inspection contents and inspection methods of three-dimensional geographic information model based on oblique photogrammetry technology. Combined with the actual inspection work, this paper summarizes the quality problems of three-dimensional geographic information model based on oblique photogrammetry technology, analyzes the causes of the problems and puts forward the quality control measures. It provides technical guidance for the quality inspection of three-dimensional geographic information model data products based on oblique photogrammetry technology in China and provides technical support for the vigorous development of three-dimensional geographic information model based on oblique photogrammetry technology.

QUALITY INSPECTION AND ANALYSIS OF THREE-DIMENSIONAL GEOGRAPHIC INFORMATION MODEL BASED ON OBLIQUE PHOTOGRAMMETRY

Directory of Open Access Journals (Sweden)

S. Dong

2018-04-01

Full Text Available In order to promote the construction of digital geo-spatial framework in China and accelerate the construction of informatization mapping system, three-dimensional geographic information model emerged. The three-dimensional geographic information model based on oblique photogrammetry technology has higher accuracy, shorter period and lower cost than traditional methods, and can more directly reflect the elevation, position and appearance of the features. At this stage, the technology of producing three-dimensional geographic information models based on oblique photogrammetry technology is rapidly developing. The market demand and model results have been emerged in a large amount, and the related quality inspection needs are also getting larger and larger. Through the study of relevant literature, it is found that there are a lot of researches on the basic principles and technical characteristics of this technology, and relatively few studies on quality inspection and analysis. On the basis of summarizing the basic principle and technical characteristics of oblique photogrammetry technology, this paper introduces the inspection contents and inspection methods of three-dimensional geographic information model based on oblique photogrammetry technology. Combined with the actual inspection work, this paper summarizes the quality problems of three-dimensional geographic information model based on oblique photogrammetry technology, analyzes the causes of the problems and puts forward the quality control measures. It provides technical guidance for the quality inspection of three-dimensional geographic information model data products based on oblique photogrammetry technology in China and provides technical support for the vigorous development of three-dimensional geographic information model based on oblique photogrammetry technology.

A Laser-based Ultrasonic Inspection System to Detect Micro Fatigue Cracks

International Nuclear Information System (INIS)

Park, Seung Kyu; Baik, Sung Hoon; Park, Moon Cheol; Lim, Chang Hwan; Cha, Hyung Ki

2005-01-01

Laser-based ultrasonic techniques have been established as a viable non-contact alternative to piezoelectric transducers for generating and receiving ultrasound. Laser-based ultrasonic inspection system provides a number of advantages over the conventional generation by piezoelectric transducers, especially a non-contact generation and detection of ultrasonic waves, high spatial scanning resolution, controllable narrow-band and wide-band spectrum, absolute measurements of the moving distance, use of fiber optics, and an ability to operate on curved and rough surfaces and at hard-to-access locations like a nuclear power plant. Ochiai and Miura used the laser-based ultrasound to detect micro fatigue cracks for the inspection of a material degradation in nuclear power plants. This widely applicable laser-based ultrasonic inspection system is comparatively expensive and provides low signal-to-noise ratio to measure ultrasound by using the laser interferometer. Many studies have been carried out to improve the measuring efficiency of the laser interferometer. One of the widely used laser interferometer types to measure the ultrasound is the Confocal Fabry-Perot Interferometer(CFPI). The measurement gain of the CFPI is slightly and continually varied according to the small change of the cavity length and the fluctuations of the measuring laser beam frequency with time. If we continually adjust the voltage of a PZT which is fixed to one of the interferometer mirrors, the optimum working point of the CFPI can be fixed. Though a static stabilizer can fix the gain of the CFPI where the CW laser beam is targeted at one position, it can not be used when the CW laser beam is scanned like a scanning laser source(SLS) technique. A dynamic stabilizer can be used for the scanning ultrasonic inspection system. A robust dynamic stabilizer is needed for an application to the industrial inspection fields. Kromine showed that the SLS technique is effective to detect small fatigue cracks

40 CFR 60.36e - Inspection guidelines.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Inspection guidelines. 60.36e Section...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Emission Guidelines and Compliance Times for Hospital/Medical/Infectious Waste Incinerators § 60.36e Inspection guidelines. (a) For approval, a State plan shall...

Application of risk-based inspection methods for cryogenic equipment

CERN Multimedia

CERN. Geneva

2016-01-01

Risk-based Inspection (RBI) is widely applied across the world as part of Pressure Equipment Integrity Management, especially in the oil and gas industry, to generally reduce costs compared with time-based approaches and assist in assigning resources to the most critical equipment. One of the challenges in RBI is to apply it for low temperature and cryogenic applications, as there are usually no degradation mechanisms by which to determine a suitable probability of failure in the overall risk assessment. However, the assumptions used for other degradation mechanisms can be adopted to determine, qualitatively and semi-quantitatively, a consequence of failure within the risk assessment. This can assist in providing a consistent basis for the assumptions used in ensuring adequate process safety barriers and determining suitable sizing of relief devices. This presentation will discuss risk-based inspection in the context of cryogenic safety, as well as present some of the considerations for the risk assessme...

Probabilistic safety analysis and risk-based inspection of nuclear research reactors: state-of-the-art and implementation proposal

Energy Technology Data Exchange (ETDEWEB)

Marques, Raíssa O.; Vasceoncelos, Vanderley de; Soares, Wellington A.; Silva Júnior, Silvério F.; Raso, Amanda L.; Mesquita, Amir Z., E-mail: raissaomarques@gmail.com, E-mail: vasconv@cdtn.br, E-mail: soaresw@cdtn.br, E-mail: silvasf@cdtn.br, E-mail: amandaraso@hotmail.com, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

Industrial facilities systems deteriorate over time during operation, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core, and allow changes in fuel configurations in case of experimental tests. Ageing management of structures, systems and components important to safety of a nuclear research reactor throughout its lifetime is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration and aging effects are considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI applications to nuclear reactors is presented in this work. Advantages to apply these methodologies are also analyzed. PSA and RBI implementation proposal applied to nuclear research reactors is also presented, as well as its application to a TRIGA research nuclear reactor using computer codes developed by ReliaSoft® Corporation. (author)

Probabilistic safety analysis and risk-based inspection of nuclear research reactors: state-of-the-art and implementation proposal

International Nuclear Information System (INIS)

Marques, Raíssa O.; Vasceoncelos, Vanderley de; Soares, Wellington A.; Silva Júnior, Silvério F.; Raso, Amanda L.; Mesquita, Amir Z.

2017-01-01

Industrial facilities systems deteriorate over time during operation, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core, and allow changes in fuel configurations in case of experimental tests. Ageing management of structures, systems and components important to safety of a nuclear research reactor throughout its lifetime is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration and aging effects are considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI applications to nuclear reactors is presented in this work. Advantages to apply these methodologies are also analyzed. PSA and RBI implementation proposal applied to nuclear research reactors is also presented, as well as its application to a TRIGA research nuclear reactor using computer codes developed by ReliaSoft® Corporation. (author)

Knowledge-Based Inspection Capabilities

National Research Council Canada - National Science Library

Marrano, Lance R; Grussing, Michael N

2006-01-01

... does not present a compelling safety hazard. Abandoning certain inspection programs to reduce costs is not a viable alternative, however, because that could degrade real property investments, soldier quality of life, and mission-readiness...

Stereo vision based automated grasp planning

International Nuclear Information System (INIS)

Wilhelmsen, K.; Huber, L.; Silva, D.; Grasz, E.; Cadapan, L.

1995-02-01

The Department of Energy has a need for treating existing nuclear waste. Hazardous waste stored in old warehouses needs to be sorted and treated to meet environmental regulations. Lawrence Livermore National Laboratory is currently experimenting with automated manipulations of unknown objects for sorting, treating, and detailed inspection. To accomplish these tasks, three existing technologies were expanded to meet the increasing requirements. First, a binocular vision range sensor was combined with a surface modeling system to make virtual images of unknown objects. Then, using the surface model information, stable grasp of the unknown shaped objects were planned algorithmically utilizing a limited set of robotic grippers. This paper is an expansion of previous work and will discuss the grasp planning algorithm

Calculation of frequency of optimal inspection in non-notice inspection game

International Nuclear Information System (INIS)

Kumakura, Shinichi; Gotoh, Yoshiki; Kikuchi, Masahiro

2011-01-01

We consider a non-notice inspection game between an inspection party, who verifies absence of diversion of nuclear materials and misuse of nuclear facility, and a facility operator, who tries them in a nuclear facility. In the game, the payoff for each player, inspection party and facility operator, is composed of various elements (parameters) such as facility type, a type of nuclear material, number of inspection and others. Their payoffs consist of profits and costs (minus profit). Because of random nature by non-notice inspection, its deterrence effect and inspection number could have the potential to affect their payoffs. In this paper, their payoffs taking into consideration of the inspection environment above are represented as a function of inspection number. Then, the optimal number is calculated from a condition on their payoffs for number of inspection. Comparable statics analysis is performed in order to observe the change of inspection number which is equilibrium point by changing these parameters including deterrence effect, because the number derived depends on each parameter within the inspection environment. Based on the analysis results, necessary conditions to reduce the inspection number keeping inspection effect are pointed out. (author)

Management of Microbiologically Influenced Corrosion in Risk-Based Inspection Analysis

DEFF Research Database (Denmark)

Skovhus, Torben Lund; Andersen, Erlend S.; Hillier, Elisabeth

2018-01-01

Operating offshore oil and gas production facilities is often associated with high risk. To manage the risk, operators commonly use aids to support decision making in the establishment of a maintenance and inspection strategy. Risk-based inspection (RBI) analysis is widely used in the offshore...... industry as a means to justify the inspection strategy adopted. The RBI analysis is a decision-making technique that enables asset managers to identify the risk related to failure of their most critical systems and components, with an effect on safety, environmental, and business-related issues. Risk...... influenced corrosion (MIC) is a degradation mechanism that has received increased attention from corrosion engineers and asset operators in the past decades. In this paper, the most recent models that have been developed to assess the impact of MIC on asset integrity will be presented and discussed. From...

Information-Driven Inspections

International Nuclear Information System (INIS)

Laughter, Mark D.; Whitaker, J. Michael; Lockwood, Dunbar

2010-01-01

New uranium enrichment capacity is being built worldwide in response to perceived shortfalls in future supply. To meet increasing safeguards responsibilities with limited resources, the nonproliferation community is exploring next-generation concepts to increase the effectiveness and efficiency of safeguards, such as advanced technologies to enable unattended monitoring of nuclear material. These include attribute measurement technologies, data authentication tools, and transmission and security methods. However, there are several conceptual issues with how such data would be used to improve the ability of a safeguards inspectorate such as the International Atomic Energy Agency (IAEA) to reach better safeguards conclusions regarding the activities of a State. The IAEA is pursuing the implementation of information-driven safeguards, whereby all available sources of information are used to make the application of safeguards more effective and efficient. Data from continuous, unattended monitoring systems can be used to optimize on-site inspection scheduling and activities at declared facilities, resulting in fewer, better inspections. Such information-driven inspections are the logical evolution of inspection planning - making use of all available information to enhance scheduled and randomized inspections. Data collection and analysis approaches for unattended monitoring systems can be designed to protect sensitive information while enabling information-driven inspections. A number of such inspections within a predetermined range could reduce inspection frequency while providing an equal or greater level of deterrence against illicit activity, all while meeting operator and technology holder requirements and reducing inspector and operator burden. Three options for using unattended monitoring data to determine an information-driven inspection schedule are to (1) send all unattended monitoring data off-site, which will require advances in data analysis techniques to

On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

Energy Technology Data Exchange (ETDEWEB)

Caffrey, Gus J. [Idaho National Laboratory, Idaho Falls, ID (United States); Egger, Ann E. [Idaho National Laboratory, Idaho Falls, ID (United States); Krebs, Kenneth M. [Idaho National Laboratory, Idaho Falls, ID (United States); Milbrath, B. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jordan, D. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Warren, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wilmer, N. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2015-09-01

We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy—Osiris—software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

International Nuclear Information System (INIS)

Caffrey, Gus J.; Egger, Ann E.; Krebs, Kenneth M.; Milbrath, B. D.; Jordan, D. V.; Warren, G. A.; Wilmer, N. G.

2015-01-01

We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy-Osiris-software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

Strategic planning of developing automatic optical inspection (AOI) technologies in Taiwan

International Nuclear Information System (INIS)

Fan, K C; Hsu, C

2005-01-01

In most domestic hi-tech industries in Taiwan, the automatic optical inspection (AOI) equipment is mostly imported. In view of the required specifications, AOI consists of the integration of mechanical-electrical-optical-information technologies. In the past two decades, traditional industries have lost their competitiveness due to the low profit rate. It is possible to promote a new AOI industry in Taiwan through the integration of its strong background in mechatronic technology in positioning stages with the optical image processing techniques. The market requirements are huge not only in domestic need but also in global need. This is the main reason to promote the AOI research for the coming years in Taiwan. Focused industrial applications will be in IC, PCB, LCD, communication, and MEMS parts. This paper will analyze the domestic and global AOI equipment market, summarize the necessary fish bone technology diagrams, survey the actual industrial needs, and propose the strategic plan to be promoted in Taiwan

Strategic planning of developing automatic optical inspection (AOI) technologies in Taiwan

Science.gov (United States)

Fan, K. C.; Hsu, C.

2005-01-01

In most domestic hi-tech industries in Taiwan, the automatic optical inspection (AOI) equipment is mostly imported. In view of the required specifications, AOI consists of the integration of mechanical-electrical-optical-information technologies. In the past two decades, traditional industries have lost their competitiveness due to the low profit rate. It is possible to promote a new AOI industry in Taiwan through the integration of its strong background in mechatronic technology in positioning stages with the optical image processing techniques. The market requirements are huge not only in domestic need but also in global need. This is the main reason to promote the AOI research for the coming years in Taiwan. Focused industrial applications will be in IC, PCB, LCD, communication, and MEMS parts. This paper will analyze the domestic and global AOI equipment market, summarize the necessary fish bone technology diagrams, survey the actual industrial needs, and propose the strategic plan to be promoted in Taiwan.

RBI - Risk Based Inspection: new concept applied to management of FPSOs (Floating, Production and Storage Offshore) structural integrity; IBR-Inspecao baseada em risco: um novo conceito aplicado a gestao da integridade estrutural de FPSOs

Energy Technology Data Exchange (ETDEWEB)

Farias, Bruno de; Figueiredo, Eduardo; Luiz, Marcio [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil); Meurer, Gustavo; Duarte, Romulo; Belligotti, Rufo; Krzonkalla, Viviane [ABS Consulting, Rio de Janeiro, RJ (Brazil)

2008-07-01

Due to the difficulties of adapting the plan of inspection, typical of oil tankers, the units of the FPSO, began to occur large periods of unavailability of the cargo tanks. Also, with the expansion of the fleet, began to notice a difficulty in meeting the plan of inspection of the FPSO's hull. To improve the management of structural integrity of its FPSO's, PETROBRAS aims to ABS Consulting with the development and implementation of Risk-Based Inspection, known as RBI. This concept is applicable to various branches of industry. The companies began their implementation of oil by refineries. The development application for a ship's hull is recent and PETROBRAS is one of the first companies to implement the IBR for monitoring of the FPSO hull. (author)

Sea bed mapping and inspection

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

The conference has 24 presentations on the topics: Sea bed mapping, inspection, positioning, hydrography, marine archaeology, remote operation vehicles and computerized simulation technologies, oil field activities and plans, technological experiences and problems. (tk)

Improved plant availability by advanced condition based inspections

International Nuclear Information System (INIS)

Hulshof, Harry J.M.; Noteboom, Jan W.; Welberg, Paul G.M.; Bruijn, Leo E.

2004-01-01

An industrial plant has to operate safely, reliably and efficiently at the lowest possible cost. Plant availability plays an important role regarding economic life optimisation. Industrial installations that are under pressure and are operating at high temperatures have a limited life due to creep and fatigue. It is, therefore, of critical importance to know the location of any possible weak spots in the installation. To avoid safety risks, unplanned plant shutdown and, as a consequence, high costs for unavailability, cycling and repair, periodic inspections and strain measurements are recommended. A Speckle Image Correlation Analysis (SPICA) system enables on-stream measurement of deformation due to creep in critical areas like the heat-affected zone in welds. Plant management and operators use the strain measurements to take action when necessary and, consequently, prevent failures. In those plants that have been provided with SPICA-technology for some years plant availability has improved significantly as a result. Another important development for yielding improved availability concerns steam drums. During some 20 years, KEMA has been performing automated ultrasonic steam drum inspections from outside. The Dutch authorities accepted this methodology in this period as an alternative (rather than an addition) after several pilot projects. An advantage of this inspection methodology is the possibility to record of the inspection results and possibility of thus trending these data. The resulting reduction of through time appeared a major benefit for plant owners. Since the authorities adopted the RBI approach during the last 10 years, another advantage of the inspection methodology became apparent: complete scanning and recording of the inspection data of circumferential and longitudinal (butt and fillet) welds, inspection of nozzle welds and inner radius as well as corrosion mapping has been covering all higher risk areas in these drums. This enhanced inspection

Improved plant availability by advanced condition based inspections

Energy Technology Data Exchange (ETDEWEB)

Hulshof, Harry J.M.; Noteboom, Jan W; Welberg, Paul G.M.; Bruijn, Leo E

2004-06-01

An industrial plant has to operate safely, reliably and efficiently at the lowest possible cost. Plant availability plays an important role regarding economic life optimisation. Industrial installations that are under pressure and are operating at high temperatures have a limited life due to creep and fatigue. It is, therefore, of critical importance to know the location of any possible weak spots in the installation. To avoid safety risks, unplanned plant shutdown and, as a consequence, high costs for unavailability, cycling and repair, periodic inspections and strain measurements are recommended. A Speckle Image Correlation Analysis (SPICA) system enables on-stream measurement of deformation due to creep in critical areas like the heat-affected zone in welds. Plant management and operators use the strain measurements to take action when necessary and, consequently, prevent failures. In those plants that have been provided with SPICA-technology for some years plant availability has improved significantly as a result. Another important development for yielding improved availability concerns steam drums. During some 20 years, KEMA has been performing automated ultrasonic steam drum inspections from outside. The Dutch authorities accepted this methodology in this period as an alternative (rather than an addition) after several pilot projects. An advantage of this inspection methodology is the possibility to record of the inspection results and possibility of thus trending these data. The resulting reduction of through time appeared a major benefit for plant owners. Since the authorities adopted the RBI approach during the last 10 years, another advantage of the inspection methodology became apparent: complete scanning and recording of the inspection data of circumferential and longitudinal (butt and fillet) welds, inspection of nozzle welds and inner radius as well as corrosion mapping has been covering all higher risk areas in these drums. This enhanced inspection

The evidence base for school inspection frameworks

NARCIS (Netherlands)

Scheerens, Jaap; Ehren, Melanie Catharina Margaretha; Ehren, Melanie C.M.

2016-01-01

This chapter describes how Inspectorates of Education operationalize different inspection goals (control, improvement, and liaison) in their inspection indicator frameworks. The chapter provides an overview and examples of the indicators used across a number of countries and how these are

The evidence base for school inspection frameworks

NARCIS (Netherlands)

Scheerens, Jaap; Ehren, Melanie Catharina Margaretha

2015-01-01

This article describes how Inspectorates of Education operationalize different inspection goals (control, improvement, liaison) in their inspection indicator frameworks. The paper provides an overview and examples of the indicators used across a number of countries and how these are incorporated in

Endoscopic inspection of steam turbines

International Nuclear Information System (INIS)

Maliniemi, H.; Muukka, E.

1990-01-01

For over ten years, Imatran Voima Oy (IVO) has developed, complementary inspection methods for steam turbine condition monitoring, which can be applied both during operation and shutdown. One important method used periodically during outages is endoscopic inspection. The inspection is based on the method where the internal parts of the turbine is inspected through access borings with endoscope and where the magnified figures of the internal parts is seen on video screen. To improve inspection assurance, an image-processing based pattern recognition method for cracks has been developed for the endoscopic inspection of turbine blades. It is based on the deduction conditions derived from the crack shape. The computer gives an alarm of a crack detection and prints a simulated image of the crack, which is then checked manually

Poolside fuel assembly inspection campaigns performed at Kernkraftwerk Leibstadt during summer 1997

International Nuclear Information System (INIS)

Zwicky, H.U.; Wiktor, C.G.; Schrire, D.

1998-01-01

In order to minimise fuel cycle costs, fuel assembly discharge burnup and average U-235 enrichment were increasing over past years in the Kernkraftwerk Leibstadt (KKL) plant. In parallel, high burnup verification programs were defined in collaboration with fuel suppliers. The aim of these programs is to demonstrate safe and reliable fuel performance up to the designed burnup limit and to identify any problems in due time. This is not only achieved by detailed poolside inspections of lead test assemblies, but also by hot cell post-irradiation examination of selected rods. In the frame of a hot cell examination campaign, enhanced localised corrosion in the vicinity of spacers on SVEA-96 fuel rods was identified in May 1997 as a potential problem. The average rod burnup of the investigated rods was around 50 MWd/kgU after 5 one year cycles of operation. As fuel operation up to six cycles is foreseen in KKLs fuel management plants, the risk of fuel failures caused by enhanced localised corrosion could not be excluded. An action plan was therefore developed in order to identify the root cause. Part of the action plan were two poolside inspection campaigns: 1. Visual inspection of 38 assemblies unloaded during refuelling outage 1996 after 5 cycles in operation. This campaign was performed in June 1997. It gave a broader data base to develop a concept for fuel management for the upcoming refuelling outage scheduled in August 1997. 2. Visual inspection, oxide layer thickness measurements, crud sampling and rod diameter measurements on 29 assemblies with different operation histories. This campaign was performed during the outage. A large portion of the inspected bundles was re-inserted for continued operation. The collected data confirmed that assumptions made for reload licensing and safety analyses were conservative. The inspection campaigns performed at KKL during summer 1997 by ABB Atom demonstrated that it is possible to address unexpected problems in a short time

Inspection of training activities by the NRC's Office of Inspection and Enforcement

International Nuclear Information System (INIS)

Ruhlman, W.A.

1975-01-01

New requirements in the Code of Federal Regulations, the issuance of new Regulatory Guides and ANSI Standards, have indicated the increased emphasis being placed on training by forces in the Nuclear Industry and the Nuclear Regulatory Commission. A brief description is presented of the functions of the Office of Inspection and Enforcement in the training areas. Three areas are examined: general inspection techniques; training inspection scope; and training inspection bases

Luminescence imaging strategies for drone-based PV array inspection

DEFF Research Database (Denmark)

Benatto, Gisele Alves dos Reis; Riedel, Nicholas; Mantel, Claire

2017-01-01

The goal of this work is to perform outdoor defect detection imaging that will be used in a fast, accurate and automatic drone-based survey system for PV power plants. The imaging development focuses on techniques that do not require electrical contact, permitting automatic drone inspections...

Simulation in Quality Management – An Approach to Improve Inspection Planning

Directory of Open Access Journals (Sweden)

H.-A. Crostack

2005-01-01

Full Text Available Production is a multi-step process involving many different articles produced in different jobs by various machining stations. Quality inspection has to be integrated in the production sequence in order to ensure the conformance of the products. The interactions between manufacturing processes and inspections are very complex since three aspects (quality, cost, and time should all be considered at the same time while determining the suitable inspection strategy. Therefore, a simulation approach was introduced to solve this problem.The simulator called QUINTE [the QUINTE simulator has been developed at the University of Dortmund in the course of two research projects funded by the German Federal Ministry of Economics and Labour (BMWA: Bundesministerium für Wirtschaft und Arbeit, the Arbeitsgemeinschaft industrieller Forschungsvereinigungen (AiF, Cologne/Germany and the Forschungsgemeinschaft Qualität, Frankfurt a.M./Germany] was developed to simulate the machining as well as the inspection. It can be used to investigate and evaluate the inspection strategies in manufacturing processes. The investigation into the application of QUINTE simulator in industry was carried out at two pilot companies. The results show the validity of this simulator. An attempt to run QUINTE in a user-friendly environment, i.e., the commercial simulation software – Arena® is also described in this paper.NOTATION: QUINTE Qualität in der Teilefertigung  (Quality in  the manufacturing process  

A fuzzy knowledge based method for maintenance planning in a power system

International Nuclear Information System (INIS)

Sergaki, Amalia; Kalaitzakis, Kostas

2002-01-01

The inspection planning in electric power industry is used to assess the safety and reliability of system components and to increase the ability of failure situation identification before it actually occurs. It reflects the implications of the available information on the operational and maintenance history of the system. The output is a ranked list of components, with the most critical ones at the top, which indicates the selection of the components to be inspected. In this paper, we demonstrate the use of a fuzzy relational database model for manipulating the data required for the criticality component ranking in thermal power systems inspection planning, incorporating criteria concerning aspects of safety and reliability, economy, variable operational conditions and environmental impacts. Often, qualitative thresholds and linguistic terms are used for the component criticality analysis. Fuzzy linguistic terms for criteria definitions along with fuzzy inference mechanisms allow the exploitation of the operators' expertise. The proposed database model ensures the representation and handling of the aforementioned fuzzy information and additionally offers to the user the functionality for specifying the precision degree by which the conditions involved in a query are satisfied. In order to illustrate the behavior of the model, a case study is given using real inspection data

Organizational Learning, Building and Sustaining Core Competencies: Knowledge Management Initiatives on Inspection and Regulatory Enforcement in BAPETEN Indonesia

International Nuclear Information System (INIS)

Daeng Beta, W. P.; Nurwidi Astuti, Y. H.; Hermawan, A. S.; Syaifulloh, S.

2016-01-01

Full text: Regulatory inspection and law enforcement are among the core competencies of the Indonesia Nuclear Energy Regulatory Agency (BAPETEN). Knowledge management (KM) initiatives are based on strategic planning of BAPETEN. KM in BAPETEN is in its early stage, it is realized since 2015–2016, although its elements have stayed in service for 18 years. Its architecture and performance-information are: to conduct risk based inspection for medical, industrial and research facilities; to plan, monitor and evaluate of effective inspection, including standard operating procedures (SOPs); to utilize inspectors for safety security of radiation sources along with coordination with related stakeholders; to enforce the safety and security facilities report to users; to optimize reliable data communication, processing and information technology (B@LIS); to perform regulatory enforcement along with other related stakeholders. KM processes are performed through the “Socialization, Externalization, Combination, Internalization” (SECI) model. Technical knowledge for inspectors are based on the IAEA–TECDOC–1526 plus supporting knowledge. With KM, innovation products can easily be used, because they are documented, distributed in a KM portal, knowledge is shared through the BAPETEN website, B@LIS database and others. Our challenge is that KM initiatives still need a tremendous effort, not only internally, but also externally, especially in coordination and collaboration. Information access brings about not only positive but also negative impacts. Innovations in regulatory inspection and law enforcement in BAPETEN are planned innovations, sustained, and systematically performed. (author

76 FR 65165 - Importation of Plants for Planting; Risk-Based Sampling and Inspection Approach and Propagative...

Science.gov (United States)

2011-10-20

..., this 14th day of October 2011. Kevin Shea, Acting Administrator, Animal and Plant Health Inspection... DEPARTMENT OF AGRICULTURE Animal and Plant Health Inspection Service [Docket No. APHIS-2011-0092] Importation of Plants for Planting; Risk-Based Sampling and Inspection Approach and Propagative Monitoring and...

Evaluation of computer-based NDE techniques and regional support of inspection activities

International Nuclear Information System (INIS)

Taylor, T.T.; Kurtz, R.J.; Heasler, P.G.; Doctor, S.R.

1991-01-01

This paper describes the technical progress during fiscal year 1990 for the program entitled 'Evaluation of Computer-Based nondestructive evaluation (NDE) Techniques and Regional Support of Inspection Activities.' Highlights of the technical progress include: development of a seminar to provide basic knowledge required to review and evaluate computer-based systems; review of a typical computer-based field procedure to determine compliance with applicable codes, ambiguities in procedure guidance, and overall effectiveness and utility; design and fabrication of a series of three test blocks for NRC staff use for training or audit of UT systems; technical assistance in reviewing (1) San Onofre ten year reactor pressure vessel inservice inspection activities and (2) the capability of a proposed phased array inspection of the feedwater nozzle at Oyster Creek; completion of design calculations to determine the feasibility and significance of various sizes of mockup assemblies that could be used to evaluate the effectiveness of eddy current examinations performed on steam generators; and discussion of initial mockup design features and methods for fabricating flaws in steam generator tubes

Evaluation of Contamination Inspection and Analysis Methods through Modeling System Performance

Science.gov (United States)

Seasly, Elaine; Dever, Jason; Stuban, Steven M. F.

2016-01-01

Contamination is usually identified as a risk on the risk register for sensitive space systems hardware. Despite detailed, time-consuming, and costly contamination control efforts during assembly, integration, and test of space systems, contaminants are still found during visual inspections of hardware. Improved methods are needed to gather information during systems integration to catch potential contamination issues earlier and manage contamination risks better. This research explores evaluation of contamination inspection and analysis methods to determine optical system sensitivity to minimum detectable molecular contamination levels based on IEST-STD-CC1246E non-volatile residue (NVR) cleanliness levels. Potential future degradation of the system is modeled given chosen modules representative of optical elements in an optical system, minimum detectable molecular contamination levels for a chosen inspection and analysis method, and determining the effect of contamination on the system. By modeling system performance based on when molecular contamination is detected during systems integration and at what cleanliness level, the decision maker can perform trades amongst different inspection and analysis methods and determine if a planned method is adequate to meet system requirements and manage contamination risk.

Dry Cask Storage Inspection and Monitoring. Interim Report.

Energy Technology Data Exchange (ETDEWEB)

Bakhtiari, Susan [Argonne National Lab. (ANL), Argonne, IL (United States); Elmer, Thomas W. [Argonne National Lab. (ANL), Argonne, IL (United States); Koehl, Eugene R. [Argonne National Lab. (ANL), Argonne, IL (United States); Wang, Ke [Argonne National Lab. (ANL), Argonne, IL (United States); Raptis, Apostolos C. [Argonne National Lab. (ANL), Argonne, IL (United States); Kunerth, Dennis C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Birk, Sandra M. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-03-04

Recently, the U.S. Nuclear Regulatory Commission (NRC) issued the guidance on the aging management of dry storage facilities that indicates the necessity to monitor the conditions of dry cask storage systems (DCSSs) over extended periods of time.1 Part of the justification of the aging management plans is the requirement for inspection and monitoring to verify whether continued monitoring, inspection or mitigation are necessary. To meet this challenge Argonne National Laboratory (ANL) in collaboration with Idaho National Laboratory (INL) is conducting scoping studies on current and emerging nondestructive evaluation/examination (NDE) and online monitoring (OLM) technologies for DCSS integrity assessments. The scope of work plan includes identification and verification of technologies for long-term online monitoring of DCSSs’ crucial physical parameters such as temperature, pressure, leakage and structural integrity in general. Modifications have been made to the current technologies to accommodate field inspections and monitoring. A summary of the scoping studies and experimental efforts conducted to date as well as plans for future activities is provided below.

In-field inspection support software: A status report on the Common Inspection On-site Software Package (CIOSP) project

International Nuclear Information System (INIS)

Novatchev, Dimitre; Titov, Pavel; Siradjov, Bakhtiiar; Vlad, Ioan; Xiao Jing

2001-01-01

Full text: IAEA has invested much thought and effort into developing software that can assist inspectors during their inspection work. Experience with such applications has been steadily growing and IAEA has recently commissioned a next-generation software package. This kind of software accommodates inspection tasks that can vary substantially in function depending on the type of installation being inspected as well as ensures that the resulting software package has a wide range of usability and can preclude excessive development of plant-specific applications. The Common Inspection On-site Software Package is being developed in the Department of Safeguards to address the limitations of the existing software and to expand its coverage of the inspection process. CIOSP is 'common' in that it is aimed at providing support for as many facilities as possible with the minimum re-configuration. At the same time it has to cater to varying needs of individual facilities, different instrumentation and verification methods used. A component-based approach was taken to successfully tackle the challenges that the development of this software presented. CIOSP consists of the following major components: A framework into which individual plug-ins supporting various inspection activities can integrate at run-time; A central data store containing all facility configuration data and all data collected during inspections; A local data store, which resides on the inspector's computer, where the current inspection's data is stored; A set of services used by all plug-ins (i.e. data transformation, authentication, replication services etc.). This architecture allows for incremental development and extension of the software with plug-ins that support individual inspection activities. The core set of components along with the framework, the Inventory Verification, Book Examination and Records and Reports Comparison plug-ins have been developed. The development of the Short Notice Random

Developing an App by Exploiting Web-Based Mobile Technology to Inspect Controlled Substances in Patient Care Units

Science.gov (United States)

2017-01-01

We selected iOS in this study as the App operation system, Objective-C as the programming language, and Oracle as the database to develop an App to inspect controlled substances in patient care units. Using a web-enabled smartphone, pharmacist inspection can be performed on site and the inspection result can be directly recorded into HIS through the Internet, so human error of data translation can be minimized and the work efficiency and data processing can be improved. This system not only is fast and convenient compared to the conventional paperwork, but also provides data security and accuracy. In addition, there are several features to increase inspecting quality: (1) accuracy of drug appearance, (2) foolproof mechanism to avoid input errors or miss, (3) automatic data conversion without human judgments, (4) online alarm of expiry date, and (5) instant inspection result to show not meted items. This study has successfully turned paper-based medication inspection into inspection using a web-based mobile device. PMID:28286761

Seed-a distributed data base architecture for global management of steam-generator inspection data

International Nuclear Information System (INIS)

Soon Ju Kang; Yu Rak Choi; Hee Gon Woo; Seong Su Choi

1996-01-01

This paper deals with a data management system - called SEED (Steam-generator Eddy-current Expert Database) for global handling of SG (steam generator) tube inspection data in nuclear power plants. The SEED integrates all stages in SG tube inspection process and supports all data such as raw eddy current data, inspection history data, SG tube information, etc. SEED implemented under client/server computing architecture for supporting LAN/WAN based graphical user interface facilities using WWW programming tools. (author)

A brick-architecture-based mobile under-vehicle inspection system

Science.gov (United States)

Qian, Cheng; Page, David; Koschan, Andreas; Abidi, Mongi

2005-05-01

In this paper, a mobile scanning system for real-time under-vehicle inspection is presented, which is founded on a "Brick" architecture. In this "Brick" architecture, the inspection system is basically decomposed into bricks of three kinds: sensing, mobility, and computing. These bricks are physically and logically independent and communicate with each other by wireless communication. Each brick is mainly composed by five modules: data acquisition, data processing, data transmission, power, and self-management. These five modules can be further decomposed into submodules where the function and the interface are well-defined. Based on this architecture, the system is built by four bricks: two sensing bricks consisting of a range scanner and a line CCD, one mobility brick, and one computing brick. The sensing bricks capture geometric data and texture data of the under-vehicle scene, while the mobility brick provides positioning data along the motion path. Data of these three modalities are transmitted to the computing brick where they are fused and reconstruct a 3D under-vehicle model for visualization and danger inspection. This system has been successfully used in several military applications and proved to be an effective safer method for national security.

Development of inspection and maintenance program for reactor and reactivity control units in HANARO

International Nuclear Information System (INIS)

Cho, Yeong-Garp

1998-01-01

This paper summarizes the overall program for inspection and maintenance of reactor structure and Reactivity Control Units (RCU) of HANARO during lifetime. The long-term plan for in-service inspection is introduced in the viewpoint of the structural integrity of reactor and RCU, and the operability of RCU mechanism. This program includes the list of components to be inspected, the schedule of inspection and maintenance, and the development of special tools and test rig that are required for the remote inspection and maintenance of reactor and RCU components. Preliminary results of the evaluation on the lifetime of RCU components are summarized based on the operation history since the installation of reactor. A test rig will be designed and constructed for the purposes of verifying the prolonged lifetime of RCU components being used, the performance of special tools, and the rehearsal of maintenance work as well. (author)

General inspection strategy for fault diagnosis-minimizing the inspection costs

International Nuclear Information System (INIS)

Reinertsen, Rune; Wang Xiaozhong

1995-01-01

In this paper, a general inspection strategy for system fault diagnosis is presented. The procedure presented in this paper, is an improvement of methods described in papers by , and . This general strategy provides the optimal inspection procedure when the inspections require unequal effort and the minimum cut set probabilities are unequal. This feature makes the procedure described in this paper more useful for practical applications than the most recent procedure presented in the paper by Najmus-Saqib and Ishaque, which requires the minimum cut set probabilities to be equal. The inspection strategy described in this paper is based on first inspecting the basic event that will provide the maximum information gain per unit cost invested. The information gain is measured by the decrease of Shannon entropy. A detailed tutorial example is presented

Health products inspection

International Nuclear Information System (INIS)

Stoltz, M.

2009-01-01

To protect public health, the Health Products Inspection is a public service mission where the application of regulations concerning activities on human health products and cosmetic products is verified. This mission permits a global approach to assess the health products risk-based benefit and, in monitoring by laboratory testing and by on site inspections, to verify their compliance with appropriate regulations. The seventy five inspectors perform about eight hundred inspections per year, in France and abroad. These inspections are related to data provided in the health products assessment and also to manufacturing and delivery practices. The French inspection body is also involved in the training of foreign inspectors and in the harmonization of national, European and international practices either for operators than for the competent authorities. (author)

Space Shuttle Communications Coverage Analysis for Thermal Tile Inspection

Science.gov (United States)

Kroll, Quin D.; Hwu, Shian U.; Upanavage, Matthew; Boster, John P.; Chavez, Mark A.

2009-01-01

The space shuttle ultra-high frequency Space-to-Space Communication System has to provide adequate communication coverage for astronauts who are performing thermal tile inspection and repair on the underside of the space shuttle orbiter (SSO). Careful planning and quantitative assessment are necessary to ensure successful system operations and mission safety in this work environment. This study assesses communication systems performance for astronauts who are working in the underside, non-line-of-sight shadow region on the space shuttle. All of the space shuttle and International Space Station (ISS) transmitting antennas are blocked by the SSO structure. To ensure communication coverage at planned inspection worksites, the signal strength and link margin between the SSO/ISS antennas and the extravehicular activity astronauts, whose line-of-sight is blocked by vehicle structure, was analyzed. Investigations were performed using rigorous computational electromagnetic modeling techniques. Signal strength was obtained by computing the reflected and diffracted fields along the signal propagation paths between transmitting and receiving antennas. Radio frequency (RF) coverage was determined for thermal tile inspection and repair missions using the results of this computation. Analysis results from this paper are important in formulating the limits on reliable communication range and RF coverage at planned underside inspection and repair worksites.

Evaluation and improvement in nondestructive examination (NDE) reliability for inservice inspection of light water reactors

International Nuclear Information System (INIS)

Doctor, S.R.; Andersen, E.S.; Bowey, R.E.; Diaz, A.A.; Good, M.S.; Heasler, P.G.; Hockey, R.L.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V.

1991-01-01

This program is intended to establish the effectiveness, reliability and adequacy of inservice inspection of reactor pressure vessels and primary piping systems and the impact of ISI reliability on system integrity. The objectives of the program include: (a) determine the effectiveness and reliability of ultrasonic inservice inspection (ISI) performed on commercial, light water reactor pressure vessels and piping; (b) recommend Code changes to the inspection procedures to improve the reliability of ISI; (c) using fracture mechanics analysis, determine the impact of NDE unreliability on system safety and determine the level of inspection reliability required to assure a suitably low failure probability; (d) evaluate the degree of reliability improvement which could be achieved using improved NDE techniques; and (e) based on importance of component to safety, material properties, service conditions, and NDE uncertainties, formulate improved inservice inspection criteria (including sampling plan, frequency, and reliability of inspection) for revisions to ASME Section XI and regulatory requirements needed to assure suitably low failure probabilities

Bridging of inspection with corrosion management

International Nuclear Information System (INIS)

Zamaluddin Ali; Mohd Hawari Hassan; Rohana Jaafar

2009-01-01

Formerly, Inspection and Corrosion Engineers have less interaction and sharing of information to each other even they are working in the same plant or organization. Inspection finding either from visual inspection or NDT techniques rarely shared with corrosion engineers. Similarly corrosion engineers rarely discussed their corrosion prediction and potential damage mechanism with inspection engineers. A demanding request of more holistic plant safety and asset integrity promoted the introduction and implementation of Risk Based Inspection (RBI). RBI analysis demands the input mainly from both disciplines i.e. Inspection and Corrosion Engineers. Most of RBI methodologies are once-off analysis approach which also promoted once-off interaction between Inspection and Corrosion Engineers. PETRONAS has developed a methodology with supporting software, integrating both Inspection and Corrosion disciplines. PETRONAS Risk Based Inspection (PRBI) is intended to promote continuous integration of Inspection and Corrosion management of the plant through out the whole life cycle starting from the design stage to fabrication, operation and decommissions stage. (author)

Methodological aspects of a GIS-based environmental health inspection program used in the Athens 2004 Olympic and Para Olympic Games.

Science.gov (United States)

Hadjichristodoulou, Christos; Soteriades, Elpidoforos S; Kolonia, Virginia; Falagas, Matthew E; Pantelopoulos, Efstathios; Panagakos, Georgios; Mouchtouri, Varvara; Kremastinou, Jeni

2005-09-02

The use of geographical information system (GIS) technologies in public health surveillance is gradually gaining momentum around the world and many applications have already been reported in the literature. In this study, GIS technology was used to help county departments of Public Health to implement environmental health surveillance for the Athens 2004 Olympic and Para Olympic Games. In order to assess the workload in each Olympic county, 19 registry forms and 17 standardized inspection forms were developed to register and inspect environmental health items requiring inspection (Hotels, restaurants, swimming pools, water supply system etc), respectively. Furthermore, related databases were created using Epi Info 2002 and a geographical information system (GIS) were used to implement an integrated Environmental Health inspection program. The project was conducted in Athens by the Olympic Planning Unit (OPU) of the National School of Public Health, in close cooperation with the Ministry of Health and Social Solidarity and the corresponding departments of Public Health in all municipalities that were scheduled to host events during the Athens 2004 Olympic and Para Olympic games. A total of 44,741 premises of environmental health interest were geocoded into GIS databases and several electronic maps were developed. Using such maps in association with specific criteria, we first identified the maximum workload required to execute environmental health inspections in all premises within the eleven Olympic County Departments of Public Health. Six different scenarios were created for each county, based on devised algorithms in order to design the most effective and realistic inspection program using the available inspectors from each municipality. Furthermore, GIS applications were used to organize the daily inspection program for the Olympic games, provide coloured displays of the inspection results and link those results with the public health surveillance of specific

Methodological aspects of a GIS-based environmental health inspection program used in the Athens 2004 Olympic and Para Olympic Games

Directory of Open Access Journals (Sweden)

Pantelopoulos Efstathios

2005-09-01

Full Text Available Abstract Background The use of geographical information system (GIS technologies in public health surveillance is gradually gaining momentum around the world and many applications have already been reported in the literature. In this study, GIS technology was used to help county departments of Public Health to implement environmental health surveillance for the Athens 2004 Olympic and Para Olympic Games. Methods In order to assess the workload in each Olympic county, 19 registry forms and 17 standardized inspection forms were developed to register and inspect environmental health items requiring inspection (Hotels, restaurants, swimming pools, water supply system etc, respectively. Furthermore, related databases were created using Epi Info 2002 and a geographical information system (GIS were used to implement an integrated Environmental Health inspection program. The project was conducted in Athens by the Olympic Planning Unit (OPU of the National School of Public Health, in close cooperation with the Ministry of Health and Social Solidarity and the corresponding departments of Public Health in all municipalities that were scheduled to host events during the Athens 2004 Olympic and Para Olympic games. Results A total of 44,741 premises of environmental health interest were geocoded into GIS databases and several electronic maps were developed. Using such maps in association with specific criteria, we first identified the maximum workload required to execute environmental health inspections in all premises within the eleven Olympic County Departments of Public Health. Six different scenarios were created for each county, based on devised algorithms in order to design the most effective and realistic inspection program using the available inspectors from each municipality. Furthermore, GIS applications were used to organize the daily inspection program for the Olympic games, provide coloured displays of the inspection results and link those

A strategy for the risk-based inspection of pressure safety valves

International Nuclear Information System (INIS)

Chien, C.-H.; Chen, C.-H.; Chao, Y.J.

2009-01-01

The purpose of a pressure safety valve (PSV) is to protect the life and safety of pressure vessels in a pressurized system. If a weakened PSV fails to function properly, a catastrophic event might occur if no other protective means are provided. By utilizing the as-received test data and statistical analysis of the aging conditions of PSVs in lubricant process units, a risk-based inspection (RBI) system was developed in this study. First of all, the characteristics of PSV were discussed from the practical viewpoint of engineering inspection and maintenance. The as-received test data, which shows obvious PSV damage, will be separated from the data used in the following statistical analysis. Then, the relationship between the aging conditions and the corresponding PSV parameters was analyzed by using the statistical technique-analysis of variance (ANOVA). Finally, a strategy for semi-quantitative RBI is proposed. Also, a definitive estimated inspection interval for every PSV is suggested. The outcome indicated most of the risks result from a few PSVs, for which the corresponding inspection intervals will be shorter than the 2 years in accordance with relative standards and local government regulations

Development of a risk-based in-service inspection program for an LMR

International Nuclear Information System (INIS)

King, R.W.; Buschman, H.W.

1996-01-01

The emerging application of risk-based assessment technology to the operation and maintenance of nuclear power plants holds considerable promise for improving efficiency and reducing operating costs. Experimental Breeder Reactor II (EBR-II) is a liquid-metal-cooled fast reactor (LMR) that operated for 30 yr before shutting down in September 1994 due to program termination. Prior to the shutdown of EBR-II, an in-service inspection (ISI) program was developed that exploited certain advantages of the LMR design. For example, it demonstrated passive response to plant upset events, low-pressure primary coolant, and compatibility of the coolant and reactor materials. This ISI program was based on work currently being done by an American Society of Mechanical Engineers (ASME) Research Task Force on Risk-Based Inspection

Linac based photofission inspection system employing novel detection concepts

International Nuclear Information System (INIS)

Stevenson, John; Gozani, Tsahi; Elsalim, Mashal; Condron, Cathie; Brown, Craig

2011-01-01

Rapiscan Systems is developing a LINAC based cargo inspection system for detection of special nuclear material (SNM) in cargo containers. The system, called Photofission Based Alarm Resolution (PBAR) is being developed under a DHD/DNDO Advanced Technology Demonstration (ATD) program. The PBAR system is based on the Rapiscan Eagle P9000 X-ray system, which is a portal system with a commercial 9 MeV LINAC X-ray source. For the purposes of the DNDO ATD program, a conveyor system was installed in the portal to allow scanning and precise positioning of 20 ft ISO cargo containers. The system uses a two step inspection process. In the first step, the basic scan, the container is quickly and completely inspected using two independent radiography arrays: the conventional primary array with high spatial resolution and a lower resolution spectroscopic array employing the novel Z-Spec method. The primary array uses cadmium tungstate (CdWO 4 ) detectors with conventional current mode readouts using photodiodes. The Z-Spec array uses small plastic scintillators capable of performing very fast (up to 10 8 cps) gamma-ray spectroscopy. The two radiography arrays are used to locate high-Z objects in the image such as lead, tungsten, uranium, which could be potential shielding materials as well as SNM itself. In the current system, the Z-Spec works by measuring the energy spectrum of transmitted X-rays. For high-Z materials the higher end of the energy spectrum is more attenuated than for low-Z materials and thus has a lower mean energy and a narrower width than low- and medium-Z materials. The second step in the inspection process is the direct scan or alarm clearing scan. In this step, areas of the container image, which were identified as high Z, are re-inspected. This is done by precisely repositioning the container to the location of the high-Z object and performing a stationary irradiation of the area with X-ray beam. Since there are a large number of photons in the 9 MV

An Analytic Hierarchy Process for School Quality and Inspection: Model Development and Application

Science.gov (United States)

Al Qubaisi, Amal; Badri, Masood; Mohaidat, Jihad; Al Dhaheri, Hamad; Yang, Guang; Al Rashedi, Asma; Greer, Kenneth

2016-01-01

Purpose: The purpose of this paper is to develop an analytic hierarchy planning-based framework to establish criteria weights and to develop a school performance system commonly called school inspections. Design/methodology/approach: The analytic hierarchy process (AHP) model uses pairwise comparisons and a measurement scale to generate the…

The ground based plan

International Nuclear Information System (INIS)

1989-01-01

The paper presents a report of ''The Ground Based Plan'' of the United Kingdom Science and Engineering Research Council. The ground based plan is a plan for research in astronomy and planetary science by ground based techniques. The contents of the report contains a description of:- the scientific objectives and technical requirements (the basis for the Plan), the present organisation and funding for the ground based programme, the Plan, the main scientific features and the further objectives of the Plan. (U.K.)

User interface inspection methods a user-centered design method

CERN Document Server

Wilson, Chauncey

2014-01-01

User Interface Inspection Methods succinctly covers five inspection methods: heuristic evaluation, perspective-based user interface inspection, cognitive walkthrough, pluralistic walkthrough, and formal usability inspections. Heuristic evaluation is perhaps the best-known inspection method, requiring a group of evaluators to review a product against a set of general principles. The perspective-based user interface inspection is based on the principle that different perspectives will find different problems in a user interface. In the related persona-based inspection, colleagues assume the

Application of the risk based inspection in chemical and nuclear installations: a critical evaluation

International Nuclear Information System (INIS)

Sousa, Anna Leticia Barbosa de

2004-01-01

Risk-based Inspection (RBI) has arisen as an opportunity for the industry to give a specific treatment to items as equipment integrity, failures consequences and the level of risk of each piece of equipment in the inspection programs definitions. Risk-based inspection programs are replacing the traditional ones based on prescriptive requirements, for both the oil and nuclear industries. The aim of this thesis is to demonstrate how the nuclear industry has gotten over several difficulties in implementing risk-based programs considering that its safety design and regulations have traditionally been based on deterministic and prescriptive criteria and requirements. During the development of the work, the study has shown how the absence of a rigid regulation favored the dissemination of RBI diffusion in the oil industry, mainly in the USA, where such industries do not face those difficulties found by the European plants, as long as it is well known that in Europe there are complex interrelations among documents from different countries with diversity of regulation procedures. (author)

POTENTIAL OF UAV-BASED LASER SCANNER AND MULTISPECTRAL CAMERA DATA IN BUILDING INSPECTION

Directory of Open Access Journals (Sweden)

D. Mader

2016-06-01

Full Text Available Conventional building inspection of bridges, dams or large constructions in general is rather time consuming and often cost expensive due to traffic closures and the need of special heavy vehicles such as under-bridge inspection units or other large lifting platforms. In consideration that, an unmanned aerial vehicle (UAV will be more reliable and efficient as well as less expensive and simpler to operate. The utilisation of UAVs as an assisting tool in building inspections is obviously. Furthermore, light-weight special sensors such as infrared and thermal cameras as well as laser scanner are available and predestined for usage on unmanned aircraft systems. Such a flexible low-cost system is realized in the ADFEX project with the goal of time-efficient object exploration, monitoring and damage detection. For this purpose, a fleet of UAVs, equipped with several sensors for navigation, obstacle avoidance and 3D object-data acquisition, has been developed and constructed. This contribution deals with the potential of UAV-based data in building inspection. Therefore, an overview of the ADFEX project, sensor specifications and requirements of building inspections in general are given. On the basis of results achieved in practical studies, the applicability and potential of the UAV system in building inspection will be presented and discussed.

Plant inspection tours with mobile data logging system

International Nuclear Information System (INIS)

Roesser, U.

2006-01-01

The MDE Mobile Data Logging System has been introduced in a number of German power plants for efficient logging, evaluation, and quality-assured documentation of data recorded on plant inspection tours by means of pocket PCs instead of slips of paper. It will be installed in other nuclear power plants in the near future. The MDE system is composed of the pocket PCs for logging data during plant inspection tours, the associated docking stations installed in the respective areas of application, one PC or, if necessary, several PCs with the appropriate user software, and the associated network links. To install the software in the power plant, lists of rooms and measurement stations as well as other positions on an inspection course are transmitted to the MDE system. When the system has been commissioned, inspection tours are planned in accordance with past experience and optimized in the computer. User experience is taken into account in program updates. New functions improve user comfort and ease of evaluation. Additions to the MDE software, and applications in other areas, are tentatively planned and will be implemented as the need arises. (orig.)

Activities for turbine maintenance: planning, implementation and evaluation of inspection results; Actividades para el mantenimiento de la turbina: planificacion, ejecucion y evaluacion de resultados de las inspecciones

Energy Technology Data Exchange (ETDEWEB)

Azcue, J.; Sanchez, M. A.; Alvaro, M.

2014-04-01

The article will cover the most significant aspects of how Tecnatom carry out the turbine maintenance work, both from the point of view of the inspection itself as the pre-and post tasks associated. Thus, the issues that will be part of the article are the Manual Inspection Service (MISI) and the inspection database, ISI WEB. These tools are essential for planning field work and serve as a guide to run later turbine inspections in different plants. Following this introduction the inspection teams and the techniques used by Tecnatom will be described. finally, the article will contain a small mention about management studies of life and integrity analysis of the turbine that can be performed, as well as involvement in its safe operation that is derived from them. Ultimately, the intention is to provide a comprehensive approach to the issue in question, the turbine maintenance work, so that the reader can get an ideal of the whole process. (Author)

Development of an automatic reactor inspection system

International Nuclear Information System (INIS)

Kim, Jae Hee; Eom, Heung Seop; Lee, Jae Cheol; Choi, Yoo Raek; Moon, Soon Seung

2002-02-01

Using recent technologies on a mobile robot computer science, we developed an automatic inspection system for weld lines of the reactor vessel. The ultrasonic inspection of the reactor pressure vessel is currently performed by commercialized robot manipulators. Since, however, the conventional fixed type robot manipulator is very huge, heavy and expensive, it needs long inspection time and is hard to handle and maintain. In order to resolve these problems, we developed a new automatic inspection system using a small mobile robot crawling on the vertical wall of the reactor vessel. According to our conceptual design, we developed the reactor inspection system including an underwater inspection robot, a laser position control subsystem, an ultrasonic data acquisition/analysis subsystem and a main control subsystem. We successfully carried out underwater experiments on the reactor vessel mockup, and real reactor ready for Ulchine nuclear power plant unit 6 at Dusan Heavy Industry in Korea. After this project, we have a plan to commercialize our inspection system. Using this system, we can expect much reduction of the inspection time, performance enhancement, automatic management of inspection history, etc. In the economic point of view, we can also expect import substitution more than 4 million dollars. The established essential technologies for intelligent control and automation are expected to be synthetically applied to the automation of similar systems in nuclear power plants

Assessing risk factors in the organic control system: evidence from inspection data in Italy.

Science.gov (United States)

Zanoli, Raffaele; Gambelli, Danilo; Solfanelli, Francesco

2014-12-01

Certification is an essential feature in organic farming, and it is based on inspections to verify compliance with respect to European Council Regulation-EC Reg. No 834/2007. A risk-based approach to noncompliance that alerts the control bodies to activate planning inspections would contribute to a more efficient and cost-effective certification system. An analysis of factors that can affect the probability of noncompliance in organic farming has thus been developed. This article examines the application of zero-inflated count data models to farm-level panel data from inspection results and sanctions obtained from the Ethical and Environmental Certification Institute, one of the main control bodies in Italy. We tested many a priori hypotheses related to the risk of noncompliance. We find evidence of an important role for past noncompliant behavior in predicting future noncompliance, while farm size and the occurrence of livestock also have roles in an increased probability of noncompliance. We conclude the article proposing that an efficient risk-based inspection system should be designed, weighting up the known probability of occurrence of a given noncompliance according to the severity of its impact. © 2014 Society for Risk Analysis.

Inspection Strategies for Concrete Bridges

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Thoft-Christensen, Palle

1989-01-01

In this paper an optimal inspection strategy for concrete bridges based on periodic routine and detailed inspections is presented. The failure mode considered is corrosion of the reinforcement due to chlorides. A simple modelling of the corrosion and of the inspection strategy is presented....... The optimal inspection strategy is determined from an optimization problem, where the design variables are time intervals between detailed inspections and the concrete cover. The strategy is illustrated on a simple structure, namely a reinforced concrete beam....

Pipeline rehabilitation planning

Energy Technology Data Exchange (ETDEWEB)

Palmer-Jones, Roland; Hopkins, Phil; Eyre, David [PENSPEN (United Kingdom)

2005-07-01

An operator faced with an onshore pipeline that has extensive damage must consider the need for rehabilitation, the sort of rehabilitation to be used, and the rehabilitation schedule. This paper will consider pipeline rehabilitation based on the authors' experiences from recent projects, and recommend a simple strategy for planning pipeline rehabilitation. It will also consider rehabilitation options: external re-coating; internal lining; internal painting; programmed repairs. The main focus will be external re-coating. Consideration will be given to rehabilitation coating types, including tape wraps, epoxy, and polyurethane. Finally it will discuss different options for scheduling the rehabilitation of corrosion damage including: the statistical comparison of signals from inspection pigs; statistical comparison of selected measurements from inspection pigs and other inspections; the use of corrosion rates estimated for the mechanisms and conditions; expert judgement. (author)

Automobile inspection system based on wireless communication

Science.gov (United States)

Miao, Changyun; Ye, Chunqing

2010-07-01

This paper aims to research the Automobile Inspection System based on Wireless Communication, and suggests an overall design scheme which uses GPS for speed detection and Bluetooth and GPRS for communication. The communication between PDA and PC was realized by means of GPRS and TCP/IP; and the hardware circuit and software for detection terminal were devised by means of JINOU-3264 Bluetooth Module after analyzing the Bluetooth and its communication protocol. According to the results of debugging test, this system accomplished GPRS based data communication and management as well as the real-time detection on auto safety performance parameters in crash test via PC, whereby the need for mobility and reliability was met and the efficiency and level of detection was improved.

Fast in-situ tool inspection based on inverse fringe projection and compact sensor heads

Science.gov (United States)

Matthias, Steffen; Kästner, Markus; Reithmeier, Eduard

2016-11-01

Inspection of machine elements is an important task in production processes in order to ensure the quality of produced parts and to gather feedback for the continuous improvement process. A new measuring system is presented, which is capable of performing the inspection of critical tool geometries, such as gearing elements, inside the forming machine. To meet the constraints on sensor head size and inspection time imposed by the limited space inside the machine and the cycle time of the process, the measuring device employs a combination of endoscopy techniques with the fringe projection principle. Compact gradient index lenses enable a compact design of the sensor head, which is connected to a CMOS camera and a flexible micro-mirror based projector via flexible fiber bundles. Using common fringe projection patterns, the system achieves measuring times of less than five seconds. To further reduce the time required for inspection, the generation of inverse fringe projection patterns has been implemented for the system. Inverse fringe projection speeds up the inspection process by employing object-adapted patterns, which enable the detection of geometry deviations in a single image. Two different approaches to generate object adapted patterns are presented. The first approach uses a reference measurement of a manufactured tool master to generate the inverse pattern. The second approach is based on a virtual master geometry in the form of a CAD file and a ray-tracing model of the measuring system. Virtual modeling of the measuring device and inspection setup allows for geometric tolerancing for free-form surfaces by the tool designer in the CAD-file. A new approach is presented, which uses virtual tolerance specifications and additional simulation steps to enable fast checking of metric tolerances. Following the description of the pattern generation process, the image processing steps required for inspection are demonstrated on captures of gearing geometries.

Neural network Hilbert transform based filtered backprojection for fast inline x-ray inspection

Science.gov (United States)

Janssens, Eline; De Beenhouwer, Jan; Van Dael, Mattias; De Schryver, Thomas; Van Hoorebeke, Luc; Verboven, Pieter; Nicolai, Bart; Sijbers, Jan

2018-03-01

X-ray imaging is an important tool for quality control since it allows to inspect the interior of products in a non-destructive way. Conventional x-ray imaging, however, is slow and expensive. Inline x-ray inspection, on the other hand, can pave the way towards fast and individual quality control, provided that a sufficiently high throughput can be achieved at a minimal cost. To meet these criteria, an inline inspection acquisition geometry is proposed where the object moves and rotates on a conveyor belt while it passes a fixed source and detector. Moreover, for this acquisition geometry, a new neural-network-based reconstruction algorithm is introduced: the neural network Hilbert transform based filtered backprojection. The proposed algorithm is evaluated both on simulated and real inline x-ray data and has shown to generate high quality reconstructions of 400  ×  400 reconstruction pixels within 200 ms, thereby meeting the high throughput criteria.

Cargo container inspection test program at ARPA's Nonintrusive Inspection Technology Testbed

Science.gov (United States)

Volberding, Roy W.; Khan, Siraj M.

1994-10-01

An x-ray-based cargo inspection system test program is being conducted at the Advanced Research Project Agency (ARPA)-sponsored Nonintrusive Inspection Technology Testbed (NITT) located in the Port of Tacoma, Washington. The test program seeks to determine the performance that can be expected from a dual, high-energy x-ray cargo inspection system when inspecting ISO cargo containers. This paper describes an intensive, three-month, system test involving two independent test groups, one representing the criminal smuggling element and the other representing the law enforcement community. The first group, the `Red Team', prepares ISO containers for inspection at an off-site facility. An algorithm randomly selects and indicates the positions and preparation of cargoes within a container. The prepared container is dispatched to the NITT for inspection by the `Blue Team'. After in-gate processing, it is queued for examination. The Blue Team inspects the container and decides whether or not to pass the container. The shipment undergoes out-gate processing and returns to the Red Team. The results of the inspection are recorded for subsequent analysis. The test process, including its governing protocol, the cargoes, container preparation, the examination and results available at the time of submission are presented.

System Enhancements for Mechanical Inspection Processes

Science.gov (United States)

Hawkins, Myers IV

2011-01-01

Quality inspection of parts is a major component to any project that requires hardware implementation. Keeping track of all of the inspection jobs is essential to having a smooth running process. By using HTML, the programming language ColdFusion, and the MySQL database, I created a web-based job management system for the 170 Mechanical Inspection Group that will replace the Microsoft Access based management system. This will improve the ways inspectors and the people awaiting inspection view and keep track of hardware as it is in the inspection process. In the end, the management system should be able to insert jobs into a queue, place jobs in and out of a bonded state, pre-release bonded jobs, and close out inspection jobs.

Linac based photofission inspection system employing novel detection concepts

Energy Technology Data Exchange (ETDEWEB)

Stevenson, John, E-mail: jstevenson@rapiscansystems.com [Rapiscan Laboratories, Inc., 520 Almanor Avenue, Sunnyvale, CA 94085 (United States); Gozani, Tsahi, E-mail: tgozani@rapiscansystems.com [Rapiscan Laboratories, Inc., 520 Almanor Avenue, Sunnyvale, CA 94085 (United States); Elsalim, Mashal; Condron, Cathie; Brown, Craig [Rapiscan Laboratories, Inc., 520 Almanor Avenue, Sunnyvale, CA 94085 (United States)

2011-10-01

Rapiscan Systems is developing a LINAC based cargo inspection system for detection of special nuclear material (SNM) in cargo containers. The system, called Photofission Based Alarm Resolution (PBAR) is being developed under a DHD/DNDO Advanced Technology Demonstration (ATD) program. The PBAR system is based on the Rapiscan Eagle P9000 X-ray system, which is a portal system with a commercial 9 MeV LINAC X-ray source. For the purposes of the DNDO ATD program, a conveyor system was installed in the portal to allow scanning and precise positioning of 20 ft ISO cargo containers. The system uses a two step inspection process. In the first step, the basic scan, the container is quickly and completely inspected using two independent radiography arrays: the conventional primary array with high spatial resolution and a lower resolution spectroscopic array employing the novel Z-Spec method. The primary array uses cadmium tungstate (CdWO{sub 4}) detectors with conventional current mode readouts using photodiodes. The Z-Spec array uses small plastic scintillators capable of performing very fast (up to 10{sup 8} cps) gamma-ray spectroscopy. The two radiography arrays are used to locate high-Z objects in the image such as lead, tungsten, uranium, which could be potential shielding materials as well as SNM itself. In the current system, the Z-Spec works by measuring the energy spectrum of transmitted X-rays. For high-Z materials the higher end of the energy spectrum is more attenuated than for low-Z materials and thus has a lower mean energy and a narrower width than low- and medium-Z materials. The second step in the inspection process is the direct scan or alarm clearing scan. In this step, areas of the container image, which were identified as high Z, are re-inspected. This is done by precisely repositioning the container to the location of the high-Z object and performing a stationary irradiation of the area with X-ray beam. Since there are a large number of photons in the 9

From PISC to risk informed inspection

International Nuclear Information System (INIS)

Crutzen, S.; Lemaitre, P.; Fabbri, L.

1998-01-01

In this paper the correlation between inspection effectiveness, inspection qualification and risk informed inspection will be treated in view of harmonisation of inspection of nuclear plant components. Through the different phases of the PISC programme the necessity has been demonstrated to show the effectiveness of the inspection through a formal process of qualification in order to ensure that a certain level of effectiveness has been reached. Inspection qualification is indeed the way to quantify the capability level of inspection techniques used. The targets to be met by the inspection is information which should be obtained from risk based analyses. (author)

Probabilistic Fatigue Life Updating for Railway Bridges Based on Local Inspection and Repair.

Science.gov (United States)

Lee, Young-Joo; Kim, Robin E; Suh, Wonho; Park, Kiwon

2017-04-24

Railway bridges are exposed to repeated train loads, which may cause fatigue failure. As critical links in a transportation network, railway bridges are expected to survive for a target period of time, but sometimes they fail earlier than expected. To guarantee the target bridge life, bridge maintenance activities such as local inspection and repair should be undertaken properly. However, this is a challenging task because there are various sources of uncertainty associated with aging bridges, train loads, environmental conditions, and maintenance work. Therefore, to perform optimal risk-based maintenance of railway bridges, it is essential to estimate the probabilistic fatigue life of a railway bridge and update the life information based on the results of local inspections and repair. Recently, a system reliability approach was proposed to evaluate the fatigue failure risk of structural systems and update the prior risk information in various inspection scenarios. However, this approach can handle only a constant-amplitude load and has limitations in considering a cyclic load with varying amplitude levels, which is the major loading pattern generated by train traffic. In addition, it is not feasible to update the prior risk information after bridges are repaired. In this research, the system reliability approach is further developed so that it can handle a varying-amplitude load and update the system-level risk of fatigue failure for railway bridges after inspection and repair. The proposed method is applied to a numerical example of an in-service railway bridge, and the effects of inspection and repair on the probabilistic fatigue life are discussed.

Study on in-service visual inspection using TV camera for core support graphite components in the HTTR

International Nuclear Information System (INIS)

Ishihara, Masahiro; Shibata, Taiju; Kikuchi, Takayuki; Mogi, Haruyoshi

1999-01-01

To maintain the structural integrity of graphite components during plant operation a visual inspection using a TV camera as an in-service inspection is planned in the High Temperature Engineering Test Reactor. In order to verify the in-service inspection method a preliminary analytical and experimental studies were performed. In the analytical study the harmful flaw size was determined from a viewpoint of structural integrity based on the fracture mechanics approach. Furthermore, the visible flaw size was determined by the TV camera performance test with graphite test specimens having several kinds of artificial flaws. This paper presents the analytical result on the harmful flaw size and the experimental result on the visible flaw size. From both results the applicability on the visual inspection by the TV camera as the in-service inspection is discussed in this paper. (author)

Nondestructive inspection of chemical warfare based on API-TOF

International Nuclear Information System (INIS)

Wang Xinhua; Zheng Pu; He Tie; An Li; Yang Jie; Fan Yu

2013-01-01

Background: Real-time, fast, accurate, nondestructive inspection (NDI) and quantitative analysis for chemical warfare are very imperative for chemical defense, anti-terror and nation security. Purpose: Associated Particles Technique (APT)/Neutron Time of Flight (TOF) has been developed for non-invasive inspection of sealed containers with chemical warfare agents. Methods: A prototype equipment for chemical warfare is consisted of an APT neutron generator with a 3×3 matrix of semiconductor detectors of associated alpha-particles, the shielding protection of neutron and gamma-ray, arrayed NaI(Tl)-based detectors of gamma-rays, fully-digital data acquisition electronics, data analysis, decision-making software, support platform and remote control system. Inelastic scattering gamma-ray pulse height spectra of sarin, VX, mustard gas and adamsite induced by 14-MeV neutron are measured. The energies of these gamma rays are used to identify the inelastic scattering elements, and the intensities of the peaks at these energies are used to reveal their concentrations. Results: The characteristic peaks of inelastic scattering gamma-ray pulse height spectra show that the prototype equipment can fast and accurately inspect chemical warfare. Conclusion: The equipment can be used to detect not only chemical warfare agents but also other hazardous materials, such as chemical/toxic/drug materials, if their chemical composition is in any way different from that of the surrounding materials. (authors)

Evaluation of computer-based ultrasonic inservice inspection systems

International Nuclear Information System (INIS)

Harris, R.V. Jr.; Angel, L.J.; Doctor, S.R.; Park, W.R.; Schuster, G.J.; Taylor, T.T.

1994-03-01

This report presents the principles, practices, terminology, and technology of computer-based ultrasonic testing for inservice inspection (UT/ISI) of nuclear power plants, with extensive use of drawings, diagrams, and LTT images. The presentation is technical but assumes limited specific knowledge of ultrasonics or computers. The report is divided into 9 sections covering conventional LTT, computer-based LTT, and evaluation methodology. Conventional LTT topics include coordinate axes, scanning, instrument operation, RF and video signals, and A-, B-, and C-scans. Computer-based topics include sampling, digitization, signal analysis, image presentation, SAFI, ultrasonic holography, transducer arrays, and data interpretation. An evaluation methodology for computer-based LTT/ISI systems is presented, including questions, detailed procedures, and test block designs. Brief evaluations of several computer-based LTT/ISI systems are given; supplementary volumes will provide detailed evaluations of selected systems

Study on In-Service Inspection Program and Inspection Technologies for Commercialized Sodium-Cooled Fast Reactor

International Nuclear Information System (INIS)

Masato Ando; Shigenobu Kubo; Yoshio Kamishima; Toru Iitsuka

2006-01-01

The objective of in-service inspection of a nuclear power plant is to confirm integrity of function of components necessary to safety, and satisfy the needs to protect plant investment and to achieve high plant ability. The sodium-cooled fast reactor, which is designed in the feasibility study on commercialized fast reactor cycle systems in Japan, has two characteristics related to in-service inspection. The first is that all sodium coolant boundary structures have double-wall system. Continuous monitoring of the sodium coolant boundary structures are adopted for inspection. The second characteristic is the steam generator with double-wall-tubes. Volumetric testing is adopted to make sure that one of the tubes can maintain the boundary function in case of the other tube failure. A rational in-service inspection concept was developed taking these features into account. The inspection technologies were developed to implement in-service inspection plan. The under-sodium viewing system consisted of multi ultrasonic scanning transducers, which was used for imaging under-sodium structures. The under-sodium viewing system was mounted on the under-sodium vehicle and delivered to core internals. The prototype of under-sodium viewing system and vehicle were fabricated and performance tests were carried out under water. The laboratory experiments of volumetric testing for double-wall-tubes of steam generator, such as ultrasonic testing and remote-field eddy current testing, were performed and technical feasibility was assessed. (authors)

The Ontario hydro low pressure turbine disc inspection program automated ultrasonic inspection systems - an overview

International Nuclear Information System (INIS)

Huggins, J.W.; Chopcian, M.; Grabish, M.

1990-01-01

An overview of the Ontario Hydro Low Pressure Turbine Disc Inspection Program is presented. The ultrasonic inspection systems developed in-house to inspect low pressure turbine discs at Pickering and Bruce Nuclear Generating stations are described. Three aspects of the program are covered: PART I - Background to inspection program, disc cracking experience, and development of an in-house inspection capability: PART II - System development requirements; ultrasonic equipment, electromechanical subsystems and instrumentation console: PART III - Customized software for flaw detection, sizing, data acquisition/storage, advanced signal processing, reports, documentation and software based diagnostics

Technical evaluation report on the Third 10-year Interval Inservice Inspection Program Plan: Florida Power and Light Company, Turkey Point Nuclear Power Plant, Units 3 and 4 (Docket Numbers 50-250 and 50-251)

International Nuclear Information System (INIS)

Brown, B.W.; Feige, E.J.; Galbraith, S.G.; Porter, A.M.

1995-02-01

This report presents the results of the evaluation of the Turkey Point Nuclear Power Plant, Units 3 and 4, Third 10-Year Interval Inservice Inspection Program Plan, Revision 0, submitted September 9, 1993, including the requests for relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, requirements that the licensee has determined to be impractical. The Turkey Point Nuclear Power Plant, Units 3 and 4, Third 10-Year Interval Inservice Inspection Program Plan is evaluated in Section 2 of this report. The inservice inspection (ISI) program plan is evaluated for (a) compliance with the appropriate edition/addenda of Section XI, (b) acceptability of the examination sample, (c) correctness of the application of system or component examination exclusion criteria, and (d) compliance with ISI-related commitments identified during previous Nuclear Regulatory Commission (NRC) reviews. The requests for relief are evaluated in Section 3 of this report

OSE inspection of computer security: Review

International Nuclear Information System (INIS)

Jaehne, E.M.

1987-01-01

The inspection process within the Department of Energy (DOE) serves the function of analyzing and reporting on the performance of security measures and controls in specific areas at sites throughout DOE. Three aspects of this process are discussed based on experience in computer security: Policy basis of performance inspections; Role and form of standards and criteria in inspections; and Conducting an inspection using the standards and criteria. Inspections are based on DOE and other applicable policy in each area. These policy statements have a compliance orientation in which the paper trail is often more clearly discernible than the security intention. The relationship of policy to performance inspections is discussed. To facilitate bridging the gap between the paper trail and the security intention defined by policy, standards and criteria were developed in each area. The consensus process and structure of the resulting product for computer security are discussed. Standards and criteria are inspection tools that support the site in preparing for an inspection and the inspector in conducting one. They form a systematic approach that facilitates consistency in the analysis and reporting of inspection results. Experience using the computer security standards and criteria is discussed

High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station

International Nuclear Information System (INIS)

Wong, S.; DiBiasio, A.; Gunther, W.

1993-09-01

The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant

High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station

Energy Technology Data Exchange (ETDEWEB)

Wong, S.; DiBiasio, A.; Gunther, W. [Brookhaven National Lab., Upton, NY (United States)

1993-09-01

The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant.

Risk Based Inspection Methodology and Software Applied to Atmospheric Storage Tanks

Science.gov (United States)

Topalis, P.; Korneliussen, G.; Hermanrud, J.; Steo, Y.

2012-05-01

A new risk-based inspection (RBI) methodology and software is presented in this paper. The objective of this work is to allow management of the inspections of atmospheric storage tanks in the most efficient way, while, at the same time, accident risks are minimized. The software has been built on the new risk framework architecture, a generic platform facilitating efficient and integrated development of software applications using risk models. The framework includes a library of risk models and the user interface is automatically produced on the basis of editable schemas. This risk-framework-based RBI tool has been applied in the context of RBI for above-ground atmospheric storage tanks (AST) but it has been designed with the objective of being generic enough to allow extension to the process plants in general. This RBI methodology is an evolution of an approach and mathematical models developed for Det Norske Veritas (DNV) and the American Petroleum Institute (API). The methodology assesses damage mechanism potential, degradation rates, probability of failure (PoF), consequence of failure (CoF) in terms of environmental damage and financial loss, risk and inspection intervals and techniques. The scope includes assessment of the tank floor for soil-side external corrosion and product-side internal corrosion and the tank shell courses for atmospheric corrosion and internal thinning. It also includes preliminary assessment for brittle fracture and cracking. The data are structured according to an asset hierarchy including Plant, Production Unit, Process Unit, Tag, Part and Inspection levels and the data are inherited / defaulted seamlessly from a higher hierarchy level to a lower level. The user interface includes synchronized hierarchy tree browsing, dynamic editor and grid-view editing and active reports with drill-in capability.

Automated reticle inspection data analysis for wafer fabs

Science.gov (United States)

Summers, Derek; Chen, Gong; Reese, Bryan; Hutchinson, Trent; Liesching, Marcus; Ying, Hai; Dover, Russell

2009-04-01

To minimize potential wafer yield loss due to mask defects, most wafer fabs implement some form of reticle inspection system to monitor photomask quality in high-volume wafer manufacturing environments. Traditionally, experienced operators review reticle defects found by an inspection tool and then manually classify each defect as 'pass, warn, or fail' based on its size and location. However, in the event reticle defects are suspected of causing repeating wafer defects on a completed wafer, potential defects on all associated reticles must be manually searched on a layer-by-layer basis in an effort to identify the reticle responsible for the wafer yield loss. This 'problem reticle' search process is a very tedious and time-consuming task and may cause extended manufacturing line-down situations. Often times, Process Engineers and other team members need to manually investigate several reticle inspection reports to determine if yield loss can be tied to a specific layer. Because of the very nature of this detailed work, calculation errors may occur resulting in an incorrect root cause analysis effort. These delays waste valuable resources that could be spent working on other more productive activities. This paper examines an automated software solution for converting KLA-Tencor reticle inspection defect maps into a format compatible with KLA-Tencor's Klarity Defect(R) data analysis database. The objective is to use the graphical charting capabilities of Klarity Defect to reveal a clearer understanding of defect trends for individual reticle layers or entire mask sets. Automated analysis features include reticle defect count trend analysis and potentially stacking reticle defect maps for signature analysis against wafer inspection defect data. Other possible benefits include optimizing reticle inspection sample plans in an effort to support "lean manufacturing" initiatives for wafer fabs.

The SWAMI inspection robot: Fernald site requirements

International Nuclear Information System (INIS)

Hazen, F.B.

1993-01-01

The purpose of this document is to introduce and describe the Stored Waste Autonomous Mobile Inspector (SWAMI) robot project and to identify issues that will need to be addressed prior to its field demonstration at Fernald in mid-1995. SWAMI is a mobile robotic vehicle that will perform mandated weekly inspections of waste containers. Fernald has a large inventory of these containers and a need to protect workers from radiation hazards while enhancing the efficiency and effectiveness of the inspections. Fernald's role in this project is to supply the demonstration site and make all necessary preparations. This includes identification of the test areas and plans, and identification and compliance to Federal, State, DOE, and Site regulations on system safety and quality. In addition, Fernald will link SWAMI output images to off-line mass data storage, and also to an on-line ORACLE database. The authors shall initiate a dialog with State and Federal regulators towards the near term goal of acceptance of the SWAMI test plan and a longer term goal of acceptance of SWAMI as a supplement and improvement to present mandated RCRA inspections

Inspection Qualification Centre in NPP 'Kozloduy'

International Nuclear Information System (INIS)

Mikhovski, M.

2000-01-01

In May 1999 according to the working plan of the IAEA project RER 4/020 and the decision of the NPP the Inspection Qualification Centre (IQC) has been established in order to provide examination services in the NPP. During year 1999 IVC (AEA Technology) in the framework of the DTI project provides consulting and technical assistance to the NPP, IQC, Bulgarian Academy of Sciences and Regulatory Authorities in setting up the IQC infrastructure. Now IQC work as an independent inspection body B type. The IQC activities for the period 1999-2000 are presented and further tasks are outlined

Supervision and inspection plans of plants activities; Plan de inspeccion y supervision de actividades en planta

Energy Technology Data Exchange (ETDEWEB)

Feijoo, J. P.

2009-07-01

Any idea of hierarchization between supervisor and supervised in inspection and supervision activities should necessarily be dismissed, and the independence of the supervisor when executing has tasks should be guaranteed. The inspection and supervision program enable the detection and resolution of materials and human problems alike. In addition, they are a solution to anticipate potential problems in the future, which results in a very significant reduction of industrial accidents and human errors, as well as better use and upkeep of equipment. With these programs we improve our management and our work, and without a doubt they help to strengthen the safety culture in Cofrentes Nuclear Power Plant. (Author)

The Mission Operations Planning Assistant

Science.gov (United States)

Schuetzle, James G.

1987-01-01

The Mission Operations Planning Assistant (MOPA) is a knowledge-based system developed to support the planning and scheduling of instrument activities on the Upper Atmospheric Research Satellite (UARS). The MOPA system represents and maintains instrument plans at two levels of abstraction in order to keep plans comprehensible to both UARS Principal Investigators and Command Management personnel. The hierarchical representation of plans also allows MOPA to automatically create detailed instrument activity plans from which spacecraft command loads may be generated. The MOPA system was developed on a Symbolics 3640 computer using the ZetaLisp and ART languages. MOPA's features include a textual and graphical interface for plan inspection and modification, recognition of instrument operational constraint violations during the planning process, and consistency maintenance between the different planning levels. This paper describes the current MOPA system.

The ASME research task force on risk-based in-service inspection

International Nuclear Information System (INIS)

Balkey, K.R.; Chapman, O.J.V.

1997-01-01

The use of risk-based methods in the development of in-service inspection (ISI) and in-service testing (IST) programs for nuclear power plant and other industrial applications has been studied for the last several years through the American Society of Mechanical Engineers Centre for Research and Technology Development (ASME 1991, 1992, 1994, 1996). The results of this work are being used as a foundation to develop specific requirements for implementation of risk-based technology in ASME Codes and Standards, regulatory requirements and industry programs both in the U.S. and other countries. This paper provides a brief overview of the ASME Research Methodology and how it has been adapted for application to the inspection of piping within the USA. It also relates how the reliability of nondestructive examination (NDE) methods for pressure boundary components can impact the risk and discusses the relationship between this and NDE qualification/demonstration now being implemented in Europe and the USA. (orig.)

A delay time model for a mission-based system subject to periodic and random inspection and postponed replacement

International Nuclear Information System (INIS)

Yang, Li; Ma, Xiaobing; Zhai, Qingqing; Zhao, Yu

2016-01-01

We propose an inspection and replacement policy for a single component system that successively executes missions with random durations. The failure process of the system can be divided into two states, namely, normal and defective, following the delay time concept. Inspections are carried out periodically and immediately after the completion of each mission (random inspections). The failed state is always identified immediately, whereas the defective state can only be revealed by an inspection. If the system fails or is defective at a periodic inspection, then replacement is immediate. If, however, the system is defective at a random inspection, then replacement will be postponed if the time to the subsequent periodic inspection is shorter than a pre-determined threshold, and immediate otherwise. We derive the long run expected cost per unit time and then investigate the optimal periodic inspection interval and postponement threshold. A numerical example is presented to demonstrate the applicability of the proposed maintenance policy. - Highlights: • A delay time model of inspection is introduced for mission-based systems. • Periodic and random inspections are performed to check the state. • Replacement of the defective system at a random inspection can be postponed.

Development of a risk-based inservice inspection program for a liquid metal reactor

International Nuclear Information System (INIS)

King, R.W.; Buschman, H.W.

1996-01-01

The emerging application of risk-based assessment technology to the operation and maintenance of nuclear power plants holds considerable promise for improving efficiency and reducing operating costs. EBR-II is liquid-metal-cooled fast reactor which operated for thirty years before shutting down in September 1994 due to program termination. Prior to the shutdown of EBR-II, an in-service inspection (ISI) program was developed that exploited certain advantages of the liquid-metal reactor design, e.g., demonstrated passive response to plant upset events, low pressure primary coolant and compatibility of the coolant and reactor materials. Many of the systems cannot be inspected due to inaccessibility of the components. However, application of a risk-based approach provided the basis for reducing or eliminating inspections in some areas that would otherwise be required. Development and implementation of the risk-based ISI program was interrupted by the DOE-mandated shutdown of EBR-II, so the potential benefits of this approach in terms of reduced O and M costs have yet to be realized. Through the development of this program, however it is clear that there is potential for substantial cost-savings while improving the risk-profile of the facility through this approach

A Steel Ball Surface Quality Inspection Method Based on a Circumferential Eddy Current Array Sensor.

Science.gov (United States)

Zhang, Huayu; Xie, Fengqin; Cao, Maoyong; Zhong, Mingming

2017-07-01

To efficiently inspect surface defects on steel ball bearings, a new method based on a circumferential eddy current array (CECA) sensor was proposed here. The best probe configuration, in terms of the coil quality factor (Q-factor), magnetic field intensity, and induced eddy current density on the surface of a sample steel ball, was determined using 3-, 4-, 5-, and 6-coil probes, for analysis and comparison. The optimal lift-off from the measured steel ball, the number of probe coils, and the frequency of excitation current suitable for steel ball inspection were obtained. Using the resulting CECA sensor to inspect 46,126 steel balls showed a miss rate of ~0.02%. The sensor was inspected for surface defects as small as 0.05 mm in width and 0.1 mm in depth.

Korean experience with steam turbine blade inspection

International Nuclear Information System (INIS)

Jung, Hyun Kyu; Park, D.Y.; Park, Hyung Jin; Chung, Min Hwa

1990-01-01

Several turbine blade accidents in Korea have emphasized the importance of their adequate periodic inspection. As a typical example, a broken blade was found in the Low Pressure (LP) turbine at the 950 MWe KORI unit 3 during the 1986 overhaul after one year commercial operation. Since then the Manufacturer and the Utility company (KEPCO) have been concerned about the need of blade root inspection. The ultrasonic testing was applied to detect cracks in the blade roots without removing the blades from rotor. Due to the complex geometry of the roots, the test results could not be evaluated easily. We feel that the currently applied UT technique seems to be less reliable and more effective method of inspection must be developed in the near future. This paper describes the following items: The causes and analysis of blade damage The inspection techniques and results The remedial action to be taken (Repair and Replacement) The future plan

Airplane tire inspection by image processing techniques

OpenAIRE

Jovancevic , Igor; Arafat , Al; Orteu , Jean-José; Sentenac , Thierry

2016-01-01

International audience; In this paper, we propose a new approach to detect and inspect airplane tires. We use normalized correlation based template matching to detect tires and GrabCut segmentation method to extract them from the background. We inspect the tires condition by investigating the tire treads. Ridge based intensity profiling gives satisfying inspection results.

Risk-based prioritization and its application to inspection of valves in the water sector

International Nuclear Information System (INIS)

Marlow, David R.; Beale, David J.; Mashford, John S.

2012-01-01

Isolation valves facilitate the effective operation and maintenance of water supply networks, but their sheer number presents a significant asset management challenge. If left unmanaged, valve reliability issues can become widespread. Inspections provide a means of increasing reliability, but a survey of industry practices indicated that some utilities did not have such a program in place. To improve asset management and reduce business risk exposure, such utilities need an effective means of commencing inspection programs. From a theoretical perspective, risk concepts provide a means of optimizing maintenance effort. However, in the face of poor data on reliability or condition, pragmatic approaches to risk-based prioritization are needed. One such approach, risk indexing, is considered in this paper. Background on the research is presented, including the application of risk-based inspection concepts within the water sector. The development of a risk indexing scheme is then investigated, drawing on two industry workshops in which the analytical hierarchy process was used to set relative weights. It is concluded that risk indexing provides the basis for a rational prioritization process in the absence of data on valve reliability or condition. - Highlights: ► Importance of valve inspections to water network reliability. ► Theoretical perspective of risk concepts that provide a means of optimizing inspection programs. ► Pragmatic approaches to prioritization in light of poor valve data. ► Development and assessment of a risk index scheme. ► Use of the analytical hierarchy process to set relative weights of risk factors.

A real-time surface inspection system for precision steel balls based on machine vision

Science.gov (United States)

Chen, Yi-Ji; Tsai, Jhy-Cherng; Hsu, Ya-Chen

2016-07-01

Precision steel balls are one of the most fundament components for motion and power transmission parts and they are widely used in industrial machinery and the automotive industry. As precision balls are crucial for the quality of these products, there is an urgent need to develop a fast and robust system for inspecting defects of precision steel balls. In this paper, a real-time system for inspecting surface defects of precision steel balls is developed based on machine vision. The developed system integrates a dual-lighting system, an unfolding mechanism and inspection algorithms for real-time signal processing and defect detection. The developed system is tested under feeding speeds of 4 pcs s-1 with a detection rate of 99.94% and an error rate of 0.10%. The minimum detectable surface flaw area is 0.01 mm2, which meets the requirement for inspecting ISO grade 100 precision steel balls.

Evaluation of inspection and enforcement programs of other regulatory, safety, and professional organizations: Phase I

International Nuclear Information System (INIS)

Thompson, S.R.; Speaker, D.M.; Cohen, S.

1977-09-01

This volume presents findings in five topical areas from a survey of the inspection and enforcement programs of 20 agencies and an in-depth study of six of those agencies. It was found that agencies using resident inspectors generally assign them in groups to prevent capture and improve supervision, use some sort of performance appraisal system, and place enforcement power in the field. Enforcement powers vary: many have ''shutdown'' power, and the majority combine inspection and enforcement in the field. Civil and administrative remedies appear easier to use than criminal remedies. Inspector management techniques include training, career planning, and evaluation. Inspection methods usually include hands-on verification, and inspection frequency is often based on past performance. Most programs assess their effectiveness in some way, and about half rate licensee performance. Information is seldom formally transmitted from I and E to other agency elements. After examining these areas, a variety of topics were recommended for further study, including assigning residents in pairs, developing a performance appraisal system, placing more enforcement power in the field, and providing more ''hands-on'' inspection activities

GIMIS - Integral Solution for the In-Service Inspection Management of Components in NPPs

International Nuclear Information System (INIS)

Borovic, Damir; Vukovic, Igor

2014-01-01

Performance of in-service testing and inspection of components and systems in nuclear power plants are required in order to maintain the nuclear power plant while in operation and to return the plant to service, following plant outages. GIMIS is comprehensive software that integrates all processes, functions and data related to planning, administrating and executing inspections on systems, structures and components in nuclear power plants. The software is designed as a web application developed using the Microsoft ASP.NET technology, database is a Microsoft SQL, and client is composed of JavaScript frameworks. It can be adapted to local language, regulations, and requirements according to the power plant needs. The application consists of seven interdependent modules, namely: components, equipment, personnel, requirements, inspection planning, inspection execution, and reports. GIMIS deals with component, equipment and personnel management (both internally employed and outsourced), also provides full component history including uploaded documentation, drawings, previous inspection results, and supports various types of requirements. It enables scheduling facilitation using component data and compliance requirements, offers generation of all inspection relevant documentation and reports, and covers the equipment management including calibration requirements, certification of equipment and allocation to specific inspections/outages, as well as personnel certifications and allocation to specific inspections/outages. The paper describes the content and functionality of the GIMIS application and provides information of its built-in capabilities and features. (authors)

Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2014

Energy Technology Data Exchange (ETDEWEB)

Silvas, A. J. [National Security Technologies, LLC, Las Vegas, NV (United States). Nevada Test Site; Lantow, Tiffany A. [National Security Technologies, LLC, Las Vegas, NV (United States). Nevada Test Site

2015-03-25

This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2014 and includes inspection and repair activities completed at the following CAUs; CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Photographs taken during inspections are included in Appendix D. The annual post-closure inspections were conducted on May 28, 2014. Maintenance was required at CAU 407. Animal burrows were backfilled and erosion repairs were performed. Vegetation monitoring was performed at CAU 407 in June 2014. The vegetation monitoring report is included in Appendix E.

Influence of visual clutter on the effect of navigated safety inspection: a case study on elevator installation.

Science.gov (United States)

Liao, Pin-Chao; Sun, Xinlu; Liu, Mei; Shih, Yu-Nien

2018-01-11

Navigated safety inspection based on task-specific checklists can increase the hazard detection rate, theoretically with interference from scene complexity. Visual clutter, a proxy of scene complexity, can theoretically impair visual search performance, but its impact on the effect of safety inspection performance remains to be explored for the optimization of navigated inspection. This research aims to explore whether the relationship between working memory and hazard detection rate is moderated by visual clutter. Based on a perceptive model of hazard detection, we: (a) developed a mathematical influence model for construction hazard detection; (b) designed an experiment to observe the performance of hazard detection rate with adjusted working memory under different levels of visual clutter, while using an eye-tracking device to observe participants' visual search processes; (c) utilized logistic regression to analyze the developed model under various visual clutter. The effect of a strengthened working memory on the detection rate through increased search efficiency is more apparent in high visual clutter. This study confirms the role of visual clutter in construction-navigated inspections, thus serving as a foundation for the optimization of inspection planning.

CASTOR - Advanced System for VVER Steam Generator Inspection

International Nuclear Information System (INIS)

Mateljak, Petar

2014-01-01

From the safety point of view, steam generator is a very important component of a nuclear power plant. Only a thin tube wall prevents leakage of radioactive material from the primary side into the environment. Therefore, it is very important to perform inspections in order to detect pipe damage and apply appropriate corrective actions during outage. Application of the nondestructive examination (NDE) technique, that can locate degradation and measure its size and orientation, is an integral part of nuclear power plant maintenance. The steam generator inspection system is consisted of remotely controlled manipulator, testing instrument and software for data acquisition and analysis. Recently, the inspection systems have evolved to a much higher level of automation, efficiency and reliability resulting in a lower cost and shorter outage time. Electronic components have become smaller and deal with more complex algorithms. These systems are very fast, precise, reliable and easy to handle. The whole inspection, from the planning, examination, data analysis and final report, is now a highly automated process, which makes inspection much easier and more reliable. This paper presents the new generation of INETEC's VVER steam generator inspection system as ultimate solution for steam generator inspection and repair. (author)

Experience on inspection at PFPF

International Nuclear Information System (INIS)

Aoki, I.; Yamamoto, Y.; Takahashi, Saburo; Ooshima, Hirofumi; Kuniyasu, Kazufusa.

1993-01-01

In order to reduce a personal radiation exposure, Plutonium Fuel Production Facility (PFPF) introduced an automated MOX fabrication technology. Safeguards system for the PFPF was designed and installed so as to be compatible with automated process operation as much as possible. Introduction of these system in PFPF made possible to do the inspection measurements with unattended mode and Near Real Time Material Accountancy (NRTA), consequently inspection has been carrying out effectively and efficiently. This paper describes the new Inspection activities as a comparison with old Inspection activities based on our experience. (author)

Crack characterization for in-service inspection planning

International Nuclear Information System (INIS)

Waale, J.; Ekstroem, P.

1995-12-01

During in-service inspection by non destructive testing the reliability is highly dependent on how the equipment is adjusted to the specific object and to the anticipated crack feature.The crack feature and morphology vary widely between different cracking mechanisms and between material types in which the cracks appear. The major objective of this study was to characterize a number of morphology parameters for common crack mechanism and structure material combinations. Critical morphology parameters are crack orientation, shape, width, surface roughness and branching. The crack parameters were evaluated from failure analyses reported from the nuclear and non-nuclear industry. In addition, a literature review was carried out on crack parameter reports and on failure analysis reports, which were further evaluated. The evaluated crack parameters were plotted and statistically processed in data groups with respect to crack mechanism and material type. The fatigue crack mechanism were classified as mechanical, thermal or corrosion fatigue and stress corrosion crack mechanism as intergranular, transgranular or inter dendritic stress corrosion cracking. Furthermore, some common weld defects were characterized for comparison. The materials were divided into three broad groups, ferritic low alloy steels, stainless steels and nickel base alloys. The results indicate significant differences between crack parameters when comparing data from different crack mechanism/material type combinations. Typical parameter values and scatter were derived for several combinations where the data was sufficient for statistical significance. 10 refs, 105 figs, 14 tabs

Crack characterization for in-service inspection planning

Energy Technology Data Exchange (ETDEWEB)

Waale, J [SAQ Inspection Ltd, Stockholm (Sweden); Ekstroem, P [ABB Atom AB, Vaesteraas (Sweden)

1995-12-01

During in-service inspection by non destructive testing the reliability is highly dependent on how the equipment is adjusted to the specific object and to the anticipated crack feature.The crack feature and morphology vary widely between different cracking mechanisms and between material types in which the cracks appear. The major objective of this study was to characterize a number of morphology parameters for common crack mechanism and structure material combinations. Critical morphology parameters are crack orientation, shape, width, surface roughness and branching. The crack parameters were evaluated from failure analyses reported from the nuclear and non-nuclear industry. In addition, a literature review was carried out on crack parameter reports and on failure analysis reports, which were further evaluated. The evaluated crack parameters were plotted and statistically processed in data groups with respect to crack mechanism and material type. The fatigue crack mechanism were classified as mechanical, thermal or corrosion fatigue and stress corrosion crack mechanism as intergranular, transgranular or inter dendritic stress corrosion cracking. Furthermore, some common weld defects were characterized for comparison. The materials were divided into three broad groups, ferritic low alloy steels, stainless steels and nickel base alloys. The results indicate significant differences between crack parameters when comparing data from different crack mechanism/material type combinations. Typical parameter values and scatter were derived for several combinations where the data was sufficient for statistical significance. 10 refs, 105 figs, 14 tabs.

A joint spare part and maintenance inspection optimisation model using the Delay-Time concept

International Nuclear Information System (INIS)

Wang Wenbin

2011-01-01

Spare parts and maintenance are closely related logistics activities where maintenance generates the need for spare parts. When preventive maintenance is present, it may need more spare parts at one time because of the planned preventive maintenance activities. This paper considers the joint optimisation of three decision variables, e.g., the ordering quantity, ordering interval and inspection interval. The model is constructed using the well-known Delay-Time concept where the failure process is divided into a two-stage process. The objective function is the long run expected cost per unit time in terms of the three decision variables to be optimised. Here we use a block-based inspection policy where all components are inspected at the same time regardless of the ages of the components. This creates a situation that the time to failure since the immediate previous inspection is random and has to be modelled by a distribution. This time is called the forward time and a limiting but closed form of such distribution is obtained. We develop an algorithm for the optimal solution of the decision process using a combination of analytical and enumeration approaches. The model is demonstrated by a numerical example. - Highlights: → Joint optimisation of maintenance and spare part inventory. → The use of the Delay-Time concept. → Block-based inspection. → Fixed order interval but variable order quantity.

Intelligent Automated Nuclear Fuel Pellet Inspection System

International Nuclear Information System (INIS)

Keyvan, S.

1999-01-01

At the present time, nuclear pellet inspection is performed manually using naked eyes for judgment and decisionmaking on accepting or rejecting pellets. This current practice of pellet inspection is tedious and subject to inconsistencies and error. Furthermore, unnecessary re-fabrication of pellets is costly and the presence of low quality pellets in a fuel assembly is unacceptable. To improve the quality control in nuclear fuel fabrication plants, an automated pellet inspection system based on advanced techniques is needed. Such a system addresses the following concerns of the current manual inspection method: (1) the reliability of inspection due to typical human errors, (2) radiation exposure to the workers, and (3) speed of inspection and its economical impact. The goal of this research is to develop an automated nuclear fuel pellet inspection system which is based on pellet video (photographic) images and uses artificial intelligence techniques

Methodology for identifying and representing knowledge in the scope of CMM inspection resource selection

Science.gov (United States)

Martínez, S.; Barreiro, J.; Cuesta, E.; Álvarez, B. J.; González, D.

2012-04-01

This paper is focused on the task of elicitation and structuring of knowledge related to selection of inspection resources. The final goal is to obtain an informal model of knowledge oriented to the inspection planning in coordinate measuring machines. In the first tasks, where knowledge is captured, it is necessary to use tools that make easier the analysis and structuring of knowledge, so that rules of selection can be easily stated to configure the inspection resources. In order to store the knowledge a so-called Onto-Process ontology has been developed. This ontology may be of application to diverse processes in manufacturing engineering. This paper describes the decomposition of the ontology in terms of general units of knowledge and others more specific for selection of sensor assemblies in inspection planning with touch sensors.

A Steel Ball Surface Quality Inspection Method Based on a Circumferential Eddy Current Array Sensor

Directory of Open Access Journals (Sweden)

Huayu Zhang

2017-07-01

Full Text Available To efficiently inspect surface defects on steel ball bearings, a new method based on a circumferential eddy current array (CECA sensor was proposed here. The best probe configuration, in terms of the coil quality factor (Q-factor, magnetic field intensity, and induced eddy current density on the surface of a sample steel ball, was determined using 3-, 4-, 5-, and 6-coil probes, for analysis and comparison. The optimal lift-off from the measured steel ball, the number of probe coils, and the frequency of excitation current suitable for steel ball inspection were obtained. Using the resulting CECA sensor to inspect 46,126 steel balls showed a miss rate of ~0.02%. The sensor was inspected for surface defects as small as 0.05 mm in width and 0.1 mm in depth.

Towards formalization of inspection using petrinets

International Nuclear Information System (INIS)

Javed, M.; Naeem, M.; Bahadur, F.; Wahab, A.

2014-01-01

Achieving better quality software has always been a challenge for software developers. Inspection is one of the most efficient techniques, which ensure the quality of software during its development. To the best of our knowledge, current inspection techniques are not realized by any formal approach. In this paper, we propose an inspection technique, which is not only backed by the formal mathematical semantics of Petri nets, but also supports inspecting concurrent processes. We also use a case study of an agent based distributed processing system to demonstrate the inspection of concurrent processes. (author)

Implementation of in-service inspection program for HANARO

International Nuclear Information System (INIS)

Wu, J.S.; Park, Y.C.; Cho, Y.G.; Jun, B.J.

2001-01-01

HANARO, a 30 MW multi-purpose research reactor in Korea has been successfully in operation for 6 years since its initial criticality in February 1995. It is mainly used for the research areas including nuclear fuel and material irradiation tests, radioisotope production, neutron beam application, neutron activation analysis and neutron transmutation doping. HANARO was designed to perform for at least 20 years under full power operating condition. It is expected that the actual reactor lifetime will be much more than the design lifetime, due to a safety reassessment based on realistic data, preventive maintenance and appropriate in-service inspections (ISI). Since ageing may affect the overall safety of the reactor facility, it is needed to detect and evaluate the effects on aged components and systems related to safety. During the lifetime of the reactor, structures, systems and components are subjected to environmental conditions of stress, temperature and irradiation that may lead to changes in the material properties and could result in unexpected failures. Evidence of ageing problems appears progressively. A rigorous inspection and visual examination based on a periodic ISI program should be established. It is desirable that the ageing surveillance activities is scheduled as early as possible and continued throughout the operating life of the reactor. An inspection plan for safety related structures, systems and components subjected to the ageing conditions is requested by the regulatory body to assess the safety status of reactor facility. A long-term ISI program for HANARO has been established for safety-related systems and components in the context of the overall reactor ageing management. The objective of this paper is to describe the ISI program and the result of the visual inspection as the first ISI. (orig.)

Development of inspection robots for bridge cables.

Science.gov (United States)

Yun, Hae-Bum; Kim, Se-Hoon; Wu, Liuliu; Lee, Jong-Jae

2013-01-01

This paper presents the bridge cable inspection robot developed in Korea. Two types of the cable inspection robots were developed for cable-suspension bridges and cable-stayed bridge. The design of the robot system and performance of the NDT techniques associated with the cable inspection robot are discussed. A review on recent advances in emerging robot-based inspection technologies for bridge cables and current bridge cable inspection methods is also presented.

Application of corrosion screening tools for riser inspection

International Nuclear Information System (INIS)

Zamir Mohamed Daud; Vijayan, S.

2003-01-01

As offshore facilities approach the end of their design life, owners would like to assess the condition and integrity of plant and equipment. Detailed inspection, including non-destructive testing (NDT), are implemented and results are utilised for predictive maintenance and estimating useful remaining life. Except for risk based inspection, the extent of surface coverage required would be more compared to inspection of pre-determined spots. Risers, for example, usually have several layers of coating that prevent use of conventional techniques for inspection of corrosion. Complete coverage requires access (including removal coatings and insulation). Inspection utilising the conventional NDT tools can be very slow and expensive. However, recent advances have forwarded the use of specialised NDT techniques that were developed for inspection of corrosion under insulation (CUI). This paper details two screening inspection tools, LIXI Profiler and RTD-INCOTEST that have been applied to inspection of risers. LIXI Profiler is based on attenuation of penetrating radiation by materials, and RTD-INCOTEST is based on decay of pulsed eddy current in materials. (Author)

Analysis of risk of nonconformities and applied quality inspection methods in the process of aluminium profiles coating based on FMEA results

Directory of Open Access Journals (Sweden)

Krzysztof Knop

2017-10-01

Full Text Available The article presents the results of risk analysis associated with nonconformities of aluminium profiles in the process of coating and quality inspection methods used to their detection. Analysis of risk was done based on results of FMEA method. Evaluated quality inspection methods were distinguished based on the term of inspection in the ISO 9000:2005 norm. Manufacturing process of aluminium profile in micro-technological approach was presented. Triple quantification of nonconformities risk based on the FMEA method by using three different approaches was conducted. Analysis of nonconformities risks associated with the use of specific quality inspection methods was done. In the last part the analysis of causes of critical nonconformities, proposals for improvement actions reducing the risk of the critical nonconformities and applied critical quality inspection method were showed.

Machine vision based quality inspection of flat glass products

Science.gov (United States)

Zauner, G.; Schagerl, M.

2014-03-01

This application paper presents a machine vision solution for the quality inspection of flat glass products. A contact image sensor (CIS) is used to generate digital images of the glass surfaces. The presented machine vision based quality inspection at the end of the production line aims to classify five different glass defect types. The defect images are usually characterized by very little `image structure', i.e. homogeneous regions without distinct image texture. Additionally, these defect images usually consist of only a few pixels. At the same time the appearance of certain defect classes can be very diverse (e.g. water drops). We used simple state-of-the-art image features like histogram-based features (std. deviation, curtosis, skewness), geometric features (form factor/elongation, eccentricity, Hu-moments) and texture features (grey level run length matrix, co-occurrence matrix) to extract defect information. The main contribution of this work now lies in the systematic evaluation of various machine learning algorithms to identify appropriate classification approaches for this specific class of images. In this way, the following machine learning algorithms were compared: decision tree (J48), random forest, JRip rules, naive Bayes, Support Vector Machine (multi class), neural network (multilayer perceptron) and k-Nearest Neighbour. We used a representative image database of 2300 defect images and applied cross validation for evaluation purposes.

Automated PCB Inspection System

Directory of Open Access Journals (Sweden)

Syed Usama BUKHARI

2017-05-01

Full Text Available Development of an automated PCB inspection system as per the need of industry is a challenging task. In this paper a case study is presented, to exhibit, a proposed system for an immigration process of a manual PCB inspection system to an automated PCB inspection system, with a minimal intervention on the existing production flow, for a leading automotive manufacturing company. A detailed design of the system, based on computer vision followed by testing and analysis was proposed, in order to aid the manufacturer in the process of automation.

Electrical Distribution System Functional Inspection (EDSFI) data base program

International Nuclear Information System (INIS)

Gautam, A.

1993-01-01

This document describes the organization, installation procedures, and operating instructions for the database computer program containing inspection findings from the US Nuclear Regulatory Commission's (NRC's) Electrical Distribution System Functional Inspections (EDSFIs). The program enables the user to search and sort findings, ascertain trends, and obtain printed reports of the findings. The findings include observations, unresolved issues, or possible deficiencies in the design and implementation of electrical distribution systems in nuclear plants. This database will assist those preparing for electrical inspections, searching for deficiencies in a plant, and determining the corrective actions previously taken for similar deficiencies. This database will be updated as new EDSFIs are completed

Post-Closure Inspection Report for the Tonopah Test Range, Nevada. For Calendar Year 2015, Revision 0

International Nuclear Information System (INIS)

Matthews, Patrick; Petrello, Jaclyn

2016-01-01

This report provides the results of the annual post-closure inspections conducted at the closed corrective action units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2015 and includes inspection and repair activities completed at the following CAUs; CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved closure reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Field notes are included in Appendix D. The annual post-closure inspections were conducted on May 12, 2015. Maintenance was required at CAU 453. Cracking along the north trench was repaired. One monument is missing at CAU 424; it will be replaced in 2016. Postings at CAUs 407, 424, 453, and 487 contain contact information for TTR Security. It was noted that protocols may not be in place to ensure that the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) is notified if access is needed at these sites. NNSA/NFO is working with the U.S. Air Force and Sandia to determine whether more appropriate contact information or new protocols are warranted for each CAU. Based on these inspections, there has not been a significant change in vegetation, and vegetation monitoring was not recommended at CAU 400 or CAU 407 in 2015.

Post-Closure Inspection Report for the Tonopah Test Range, Nevada. For Calendar Year 2015, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Matthews, Patrick [Navarro, Las Vegas, NV (United States); Petrello, Jaclyn [Navarro, Las Vegas, NV (United States)

2016-03-01

This report provides the results of the annual post-closure inspections conducted at the closed corrective action units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2015 and includes inspection and repair activities completed at the following CAUs; CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved closure reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Field notes are included in Appendix D. The annual post-closure inspections were conducted on May 12, 2015. Maintenance was required at CAU 453. Cracking along the north trench was repaired. One monument is missing at CAU 424; it will be replaced in 2016. Postings at CAUs 407, 424, 453, and 487 contain contact information for TTR Security. It was noted that protocols may not be in place to ensure that the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) is notified if access is needed at these sites. NNSA/NFO is working with the U.S. Air Force and Sandia to determine whether more appropriate contact information or new protocols are warranted for each CAU. Based on these inspections, there has not been a significant change in vegetation, and vegetation monitoring was not recommended at CAU 400 or CAU 407 in 2015.

Maintenance Planning of Offshore Wind Turbine using Condition Monitoring Information

DEFF Research Database (Denmark)

Ramírez, José G. Rangel; Sørensen, John Dalsgaard

2009-01-01

Deterioration processes such as fatigue and corrosion are typically affecting offshore structures. To "control" this deterioration, inspection and maintenance activities are developed. Probabilistic methodologies represent an important tool to identify the suitable strategy to inspect and control...... the deterioration in structures such as offshore wind turbines (OWT). Besides these methods, the integration of condition monitoring information (CMI) can optimize the mitigation activities as an updating tool. In this paper, a framework for risk-based inspection and maintenance planning (RBI) is applied for OWT....... With the integration of CMI by means Bayesian inference, a slightly change of first inspection times are coming up, influenced by the reduction of the uncertainty and harsher or milder external agents....

Improved in-service inspection program for management of degradation in steam generator tubing

International Nuclear Information System (INIS)

Kurtz, R.; Heasler, P.; Muscara, J.

1992-01-01

This paper presents an overview of significant results from NRC-sponsored research on steam generator tube integrity and inspection. Burst test results are described along with empirical models to relate flaw geometry and size to tube burst pressure. Results of round robin examinations of a retired-from-service steam generator to determine eddy current inspection reliability are presented. An evaluation and comparison of various sampling plans for in-service inspection of steam generators is discussed. Finally, performance demonstration qualification efforts for eddy current inspection systems are described

Advances based on digital technology named TEDDY+ for inspection of eddy current

International Nuclear Information System (INIS)

Barcenilla, V.; Hernandez, J.; Ribes, B.

2007-01-01

As a result of the recent developing line of eddy current data acquisition system a new product based on digital technology named TEDDY+, comes to the market. With only 4 kg of weight constitutes a great advance with regards to other equipment's available in the market. These advances, have enabled, among others, to increase considerably the signal to noise (S/N) ratio, avoid typical saturation problems in the eddy current signal, increase the inspection speed, eliminate the reference probe, detect the air/tube signal in real time, and the possibility to integrate the tester inside a push puller thanks to its reduced size and to have integrated as part of the ET equipment the mechanical systems control board. Two product lines have been developed, one oriented to any market and application (nuclear market, industrial and aeronautical, chemical and petrochemical, etc) and other specially dedicated to the massive inspection of tubes, named TEDDY+SP (Suitcase Pusher). Both lines are prepared to use eddy current arrays which clearly constitute the future of the eddy current inspection systems. The new TEDDY+ line of products presented in this paper constitutes one of the most powerful and reliable existing in the market. These improvements and novelties place the new ET inspection system from Tecnatom as one of the most powerful and reliable in the market. (Author)

Development of Inspection Robots for Bridge Cables

Directory of Open Access Journals (Sweden)

Hae-Bum Yun

2013-01-01

Full Text Available This paper presents the bridge cable inspection robot developed in Korea. Two types of the cable inspection robots were developed for cable-suspension bridges and cable-stayed bridge. The design of the robot system and performance of the NDT techniques associated with the cable inspection robot are discussed. A review on recent advances in emerging robot-based inspection technologies for bridge cables and current bridge cable inspection methods is also presented.

Fuel assembly inspection device

International Nuclear Information System (INIS)

Yaginuma, Yoshitaka

1998-01-01

The present invention provides a device suitable to inspect appearance of fuel assemblies by photographing the appearance of fuel assemblies. Namely, the inspection device of the present invention measures bowing of fuel assembly or each of fuel rods or both of them based on the partially photographed images of fuel assembly. In this case, there is disposed a means which flashily projects images in the form of horizontal line from a direction intersecting obliquely relative to a horizontal cross section of the fuel assembly. A first image processing means separates the projected image pictures including projected images and calculates bowing. A second image processing means replaces the projected image pictures of the projected images based on projected images just before and after the photographing. Then, images for the measurement of bowing and images for inspection can be obtained simultaneously. As a result, the time required for the photographing can be shortened, the time for inspection can be shortened and an effect of preventing deterioration of photographing means by radiation rays can be provided. (I.S.)

Behavior-based evacuation planning

KAUST Repository

Rodriguez, Samuel

2010-05-01

In this work, we present a formulation of an evacuation planning problem that is inspired by motion planning and describe an integrated behavioral agent-based and roadmap-based motion planning approach to solve it. Our formulation allows users to test the effect on evacuation of a number of different environmental factors. One of our main focuses is to provide a mechanism to investigate how the interaction between agents influences the resulting evacuation plans. Specifically, we explore how various types of control provided by a set of directing agents effects the overall evacuation planning strategies of the evacuating agents. ©2010 IEEE.

Behavior-based evacuation planning

KAUST Repository

Rodriguez, Samuel; Amato, Nancy M

2010-01-01

In this work, we present a formulation of an evacuation planning problem that is inspired by motion planning and describe an integrated behavioral agent-based and roadmap-based motion planning approach to solve it. Our formulation allows users to test the effect on evacuation of a number of different environmental factors. One of our main focuses is to provide a mechanism to investigate how the interaction between agents influences the resulting evacuation plans. Specifically, we explore how various types of control provided by a set of directing agents effects the overall evacuation planning strategies of the evacuating agents. ©2010 IEEE.

Do school inspections improve primary school performance?

OpenAIRE

Dinand Webbink; Rob Luginbuhl; I. de Wolf

2007-01-01

Inspectors from the Dutch Inspectorate of Education inspect primary schools, write inspection reports on each inspected school, and make recommendations as to how each school can improve. We test whether these inspections result in better school performance. Using a fixed-effects model, we find evidence that school inspections do lead to measurably better school performance. Our assessment of school performance is based on the Cito test scores of pupils in their final year of primary school. ...

Post-Closure Inspection Report for the Tonopah Test Range, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2006 and includes inspection and repair activities completed at the following nine CAUs: CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 404: Roller Coaster Lagoons and Trench (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 426: Cactus Spring Waste Trenches (TTR); CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR). Post-closure inspections were conducted on May 9, 2006, May 31, 2006, and November 15, 2006. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2006, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 400, CAU 407, CAU 426, CAU 453, and CAU 487 in 2006. During the May inspection of CAU 400, it was identified that the east and west sections of chickenwire fencing beyond the standard fencing were damaged; they were repaired in June 2006. Also in June 2006, the southeast corner fence post and one warning sign at CAU 407 were reinforced and reattached, the perimeter fencing adjacent to the gate at CAU 426 was tightened, and large animal

Post-Closure Inspection Report for the Tonopah Test Range, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2007-06-01

This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2006 and includes inspection and repair activities completed at the following nine CAUs: CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 404: Roller Coaster Lagoons and Trench (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 426: Cactus Spring Waste Trenches (TTR); CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR). Post-closure inspections were conducted on May 9, 2006, May 31, 2006, and November 15, 2006. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2006, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 400, CAU 407, CAU 426, CAU 453, and CAU 487 in 2006. During the May inspection of CAU 400, it was identified that the east and west sections of chickenwire fencing beyond the standard fencing were damaged; they were repaired in June 2006. Also in June 2006, the southeast corner fence post and one warning sign at CAU 407 were reinforced and reattached, the perimeter fencing adjacent to the gate at CAU 426 was tightened, and large animal

Defect inspection in hot slab surface: multi-source CCD imaging based fuzzy-rough sets method

Science.gov (United States)

Zhao, Liming; Zhang, Yi; Xu, Xiaodong; Xiao, Hong; Huang, Chao

2016-09-01

To provide an accurate surface defects inspection method and make the automation of robust image region of interests(ROI) delineation strategy a reality in production line, a multi-source CCD imaging based fuzzy-rough sets method is proposed for hot slab surface quality assessment. The applicability of the presented method and the devised system are mainly tied to the surface quality inspection for strip, billet and slab surface etcetera. In this work we take into account the complementary advantages in two common machine vision (MV) systems(line array CCD traditional scanning imaging (LS-imaging) and area array CCD laser three-dimensional (3D) scanning imaging (AL-imaging)), and through establishing the model of fuzzy-rough sets in the detection system the seeds for relative fuzzy connectedness(RFC) delineation for ROI can placed adaptively, which introduces the upper and lower approximation sets for RIO definition, and by which the boundary region can be delineated by RFC region competitive classification mechanism. For the first time, a Multi-source CCD imaging based fuzzy-rough sets strategy is attempted for CC-slab surface defects inspection that allows an automatic way of AI algorithms and powerful ROI delineation strategies to be applied to the MV inspection field.

Chapter 4. Assessment and inspection of nuclear installations

International Nuclear Information System (INIS)

2001-01-01

Supervisory activity of Nuclear Regulatory Authority of the Slovak Republic (UJD) upon the safety of nuclear installations in compliance with the 'Atomic Act' and other legal regulations includes also inspection and assessment activities of UJD. Assessment activity of UJD in relation to nuclear installations lies in assessment of safety documentation for constructions realised as nuclear installations, or constructions through which changes are realised on nuclear installations. The scope of safety documentation required for the assessment is stipulated in the Atomic Act. In 2000 the assessment activity focused first of all on Unit 1 of NPP Bohunice after completing its Gradual Reconstruction Programme, on National Repository of Radioactive waste in Mochovce and on radioactive waste conditioning and treatment technology in Jaslovske Bohunice. Activities of UJD in assessment focused mainly on control of compliance with requirements for nuclear safety, assessment of commissioning programmes, operating procedures, limits and conditions, etc. The assessment of changes, which influence nuclear safety of nuclear installations in operation, realisation of which is conditioned by the approval from UJD, is a significant part of the assessment activity of UJD. Mainly it is the assessment of design changes, changes in limits and conditions, operating procedures, changes in programmes of periodical testing of equipment important in terms of nuclear safety, changes in physical protection of nuclear equipment, etc. The assessment of nuclear installations operational safety, based on assessment of operational events, on maintaining limits and conditions of safe operation, on operational safety performance indicators and on inspection results is a separate category in the assessment activity of UJD. Inspection activity specified in the 'Atomic Act' is governed by an internal guideline, an important part of which is an annual inspection plan that considers the following types of

Planning of the regulatory inspection activity during manufacturing, construction and operation of the Italian nuclear plants

International Nuclear Information System (INIS)

Messore, G.A.

1977-01-01

After a brief review of the provisions in force in Italy on the inspection of nuclear installations the paper deals with the main criteria which determine the general and annual inspection programmes for every nuclear installation and the procedures for recording the results of inspections. It also describes the classification of nuclear installations into different categories according to the degree of hazard presented by their respective activities and consequently, the selection of the minimum number of inspections to be conducted every year for each of these categories. (NEA) [fr

Vision-Based Corrosion Detection Assisted by a Micro-Aerial Vehicle in a Vessel Inspection Application

Directory of Open Access Journals (Sweden)

Alberto Ortiz

2016-12-01

Full Text Available Vessel maintenance requires periodic visual inspection of the hull in order to detect typical defective situations of steel structures such as, among others, coating breakdown and corrosion. These inspections are typically performed by well-trained surveyors at great cost because of the need for providing access means (e.g., scaffolding and/or cherry pickers that allow the inspector to be at arm’s reach from the structure under inspection. This paper describes a defect detection approach comprising a micro-aerial vehicle which is used to collect images from the surfaces under inspection, particularly focusing on remote areas where the surveyor has no visual access, and a coating breakdown/corrosion detector based on a three-layer feed-forward artificial neural network. As it is discussed in the paper, the success of the inspection process depends not only on the defect detection software but also on a number of assistance functions provided by the control architecture of the aerial platform, whose aim is to improve picture quality. Both aspects of the work are described along the different sections of the paper, as well as the classification performance attained.

Packaging supplier inspection guide

International Nuclear Information System (INIS)

Stromberg, H.M.; Gregg, R.E.; Kido, C.; Boyle, C.D.

1991-05-01

This is document is a guide for conducting quality assurance inspections of transportations packaging suppliers, where suppliers are defined as designers, fabricators, distributors, users, or owners of transportation packaging. This document can be used during an inspection to determine regulatory compliance within the requirements of 10 Code of Federal Regulations, Part 71, Subpart H (10 CFR 71.101--71.135). The guidance described in this document provides a framework for an inspection. It provides the inspector with the flexibility to adapt the methods and concepts presented here to meet the needs of the particular facility being inspected. The guide was developed to ensure a structured and consistent approach for inspections. The method treats each activity at a supplier facility as a separate entity (or functional element), and combines the activities within the framework of an ''inspection tree.'' The method separates each functional element into several areas of performance and then identifies guidelines, based on regulatory requirements, to be used to qualitatively rate each area. This document was developed to serve as a field manual to facilitate the work of inspectors. 1 ref., 1 fig., 5 tabs

Non-destructive inservice inspections

International Nuclear Information System (INIS)

Kauppinen, P.; Sarkimo, M.; Lahdenperae, K.

1998-01-01

In order to assess the possible damages occurring in the components and structures of operating nuclear power plants during service the main components and structures are periodically inspected by non-destructive testing techniques. The reliability of non-destructive testing techniques applied in these inservice inspections is of major importance because the decisions concerning the needs for repair of components are mainly based on the results of inspections. One of the targets of this research program has been to improve the reliability of non-destructive testing. This has been addressed in the sub-projects which are briefly summarised here. (author)

Can non-destructive inspection be reliable

International Nuclear Information System (INIS)

Silk, M.G.; Stoneham, A.M.; Temple, J.A.G.

1988-01-01

The paper on inspection is based on the book ''The reliability of non-destructive inspection: assessing the assessment of structures under stress'' by the present authors (published by Adam Hilger 1987). Emphasis is placed on the reliability of inspection and whether cracks in welds or flaws in components can be detected. The need for non-destructive testing and the historical attitudes to non-destructive testing are outlined, along with the case of failure. Factors influencing reliable inspection are discussed, and defect detection trials involving round robin tests are described. The development of reliable inspection techniques and the costs of reliability and unreliability are also examined. (U.K.)

Waste Calcining Facility remote inspection report

International Nuclear Information System (INIS)

Patterson, M.W.; Ison, W.M.

1994-08-01

The purpose of the Waste Calcining Facility (WCF) remote inspections was to evaluate areas in the facility which are difficult to access due to high radiation fields. The areas inspected were the ventilation exhaust duct, waste hold cell, adsorber manifold cell, off-gas cell, calciner cell and calciner vessel. The WCF solidified acidic, high-level mixed waste generated during nuclear fuel reprocessing. Solidification was accomplished through high temperature oxidation and evaporation. Since its shutdown in 1981, the WCFs vessels, piping systems, pumps, off-gas blowers and process cells have remained contaminated. Access to the below-grade areas is limited due to contamination and high radiation fields. Each inspection technique was tested with a mock-up in a radiologically clean area before the equipment was taken to the WCF for the actual inspection. During the inspections, essential information was obtained regarding the cleanliness, structural integrity, in-leakage of ground water, indications of process leaks, indications of corrosion, radiation levels and the general condition of the cells and equipment. In general, the cells contain a great deal of dust and debris, as well as hand tools, piping and miscellaneous equipment. Although the building appears to be structurally sound, the paint is peeling to some degree in all of the cells. Cracking and spalling of the concrete walls is evident in every cell, although the east wall of the off-gas cell is the worst. The results of the completed inspections and lessons learned will be used to plan future activities for stabilization and deactivation of the facility. Remote clean-up of loose piping, hand tools, and miscellaneous debris can start immediately while information from the inspections is factored into the conceptual design for deactivating the facility

Inspection qualification and implementation of ENIQ in Sweden

International Nuclear Information System (INIS)

Zettervall, Tommy

2013-01-01

Many countries are currently considering their approaches to inspection qualification and risk-informed in-service inspection (RI-ISI) and are carefully assessing experience data. In Europe most of the utilities operating nuclear power plants have joined together to form the European Network for Inspection Qualification ENIQ. In practice, qualification can be performed with varying degrees of complexity and cost, varying from capability statement based on existing evidence, through to an extensive qualification consisting of a detailed Technical Justification (TJ) together with open and blind trials on full-scale test blocks. An Inspection Qualification is an investigation and demonstration, which confirm that an inspection system has the ability to solve its specific tasks. The qualification is a Quality Assurance of an inspection system based on documents and practical trials. A reliable inspection system, based on a reliable qualification and correct prerequisites, will reduce total costs for Licensees and increase the credibility of the inspection result. To get such inspection system, which could be valid for many years, it's of necessity to fulfil all included parts in the process. It begins with the Technical Specification from Licensee, where input data and requirements about the actual component are specified. To get an inspection system that could live over time, the Technical Justification is of importance. Finally the test blocks and used simulation techniques play an important part of the final result, and these test blocks together with TJ form the basis for qualification body's decision. (author)

Effective Hull IMMR plan

Energy Technology Data Exchange (ETDEWEB)

Franco, Mireille

2010-07-01

The objective of the Hull Inspection, Maintenance and Repair Plan is to ensure the total integrity of the Floating Production Unit. To be efficient, the Monitoring has to be part of the Hull Inspection, Monitoring, Maintenance and Repair Plan (IMMR). The IMMR Plan should be developed during the design and project phases and take into account the interfaces between the different systems and teams' tasks in operation. The IMMR is multidisciplinary and form part of the hand-over to ensure an efficient and early implementation. Implementation of such a complex plan requires: - Cross-functionality: take advantage of the synergies - Boldness: break the mould and think outside the box - Listening: be attentive, be available, - Mutual support: during good and bad times. This paper presents the way Total believe the Hull IMMR Plan shall be developed, implemented and followed up. (Author)

46 CFR 153.812 - Inspection for Certificate of Inspection.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Inspection for Certificate of Inspection. 153.812... CARGOES SHIPS CARRYING BULK LIQUID, LIQUEFIED GAS, OR COMPRESSED GAS HAZARDOUS MATERIALS Design and Equipment Testing and Inspection § 153.812 Inspection for Certificate of Inspection. The rules governing the...

Optimal Inspection and Maintenance Strategies for Structural Systems

DEFF Research Database (Denmark)

Sommer, A. M.

The aim of this thesis is to give an overview of conventional and optimal reliability-based inspection and maintenance strategies and to examine for specific structures how the cost can be reduced and/or the safety can be improved by using optimal reliability-based inspection strategies....... For structures with several almost similar components it is suggested that individual inspection strategies should be determined for each component or a group of components based on the reliability of the actual component. The benefit of this procedure is assessed in connection with the structures considered....... Furthermore, in relation to the calculations performed the intention is to modify an existing program for determination of optimal inspection strategies. The main purpose of inspection and maintenance of structural systems is to prevent or delay damage or deterioration to protect people, environment...

Inspection Methods for Physical Protection Project: annual report, March-December 1981

International Nuclear Information System (INIS)

Bowden, D.D.; Green, J.N.; Minichino, C.; Thatcher, R.M.; Tyler, G.C.

1982-01-01

The report details the current production status of the expanded replacement inspection procedures for physical protection of power reactors, for strategic special nuclear material fixed sites, and for transportation of special nuclear material. In addition to the expanded replacement procedures, the final production status is reported for the new series of inspection procedures for special nuclear material of moderate and low strategic significance at fixed sites, for personnel training and qualifications plan (Appendix B to 10 CFR 73), for safeguards contingency plan (Appendix C to 10 CFR 73), and for licensee implementing procedures evaluation. Other deliverables, trips, management meetings, training, and changes in personnel are discussed

Present state of 'Mutsu', the general inspection of safety and the repair of shielding

International Nuclear Information System (INIS)

1980-01-01

The Agency has carried out the works based on the plan for the repair of shielding and the general inspection of safety in the nuclear ship ''Mutsu'' also in 1979. As for the repair of shielding, the permission by the prime minister to alter the nuclear reactor installation was obtained. The contents of the alteration are the repair of primary and secondary shieldings and the additional construction of a tank for storing liquid waste. As for the general inspection of safety, the tests for confirming the functions of main machinery and equipments have been carried out since January, 1979. A set of testing apparatuses was made as the preparation for the flaw detection test of steam generator tubes. As for the general inspection of softwares, the re-evaluation of the design of nuclear reactor plant and the analysis of the accidents in nuclear reactor plant were almost completed. Considering the accident of TMI No. 2 reactor, the inspection of softwares is in progress. The contract for these repair and inspection is not yet made, and the negotiations are under way. The nuclear ship ''Mutsu'' was brought to Sasebo Port in October, 1978, and dry-docked in July, 1979. As the result of inspection, any rust and wear were not found on the bottom plates, rudder and propeller. The survey of environmental radioactivity in Sasebo and Ominato, the budget for the repair and inspection, and the movement of the government are also reported. (Kako, I.)

Short-Run Contexts and Imperfect Testing for Continuous Sampling Plans

Directory of Open Access Journals (Sweden)

Mirella Rodriguez

2018-04-01

Full Text Available Continuous sampling plans are used to ensure a high level of quality for items produced in long-run contexts. The basic idea of these plans is to alternate between 100% inspection and a reduced rate of inspection frequency. Any inspected item that is found to be defective is replaced with a non-defective item. Because not all items are inspected, some defective items will escape to the customer. Analytical formulas have been developed that measure both the customer perceived quality and also the level of inspection effort. The analysis of continuous sampling plans does not apply to short-run contexts, where only a finite-size batch of items is to be produced. In this paper, a simulation algorithm is designed and implemented to analyze the customer perceived quality and the level of inspection effort for short-run contexts. A parameter representing the effectiveness of the test used during inspection is introduced to the analysis, and an analytical approximation is discussed. An application of the simulation algorithm that helped answer questions for the U.S. Navy is discussed.

Analysis of risk of nonconformities and applied quality inspection methods in the process of aluminium profiles coating based on FMEA results

OpenAIRE

Krzysztof Knop

2017-01-01

The article presents the results of risk analysis associated with nonconformities of aluminium profiles in the process of coating and quality inspection methods used to their detection. Analysis of risk was done based on results of FMEA method. Evaluated quality inspection methods were distinguished based on the term of inspection in the ISO 9000:2005 norm. Manufacturing process of aluminium profile in micro-technological approach was presented. Triple quantification of nonconformities risk b...

Development of inspection and evaluation guidelines for light water reactor internals

International Nuclear Information System (INIS)

Aoki, T.; Yamashita, H.; Sakai, K.

2002-01-01

Full text: In Japan, before a nuclear power plant reaches its 30 years of operation, the Japanese utilities carry out a 'study on plant life management'. Reflecting the results of that study into the maintenance, the utilities make efforts to maintain and improve the safety and reliability of their nuclear power plants. In this study, all safety related components are evaluated from the viewpoint of aging degradation, assuming a long-term operation. If a crack should be found at components such as reactor internals, which is deemed important for safety and are difficult to repair or replace may provide a serious impact on the plant operation and management. Reactor internals, for instance, made of austenitic stainless steel and nickel base alloy, are not completely free from aging degradation including stress corrosion cracking (SCC). Therefore, it is concluded in the study on plant life management that they are required continuous planned inspections to confirm their integrity while continuing plant operation. If an aging degradation such as SCC should be found at the reactor internals, a great amount of labor and time may be required for root cause investigation and analysis and subsequent repairs because it is very difficult to reach to the degraded portion due to structural, dimensional and environmental restrictions. Therefore, such situations may provide serious impact on plant operation and management. As to the reactor internals and other components with similar characteristics, it is strongly recommended that contingency plan should be prepared in advance. Thus, considering the significance of aging degradation, it is necessary to develop some standard rules for the inspection and evaluation of reactor internals. Such rules should specify when, where and how to inspect. They should also specify the evaluation method in case such degradation as a crack is found, and the repair method and extent if repairs are required. These standard rules must be

Vibrational Based Inspection of Civil Engineering Structures

DEFF Research Database (Denmark)

Rytter, Anders

at the University of Aalborg from 1988 to 1991. Secondly, a research project, In-Field Vibration Based Inspection of Civil Engineering Structures, which has been performed as a pilot project by the Consulting Engineers Rambøll, Hannemann and Højlund in cooperation with the department of Building Technology......The thesis has been written in relation to two different research projects. Firstly, an offshore test programme, Integrated Experimental/Numerical Analysis of the Dynamic behavior of offshore structures, which was performed at the department of Building Technology and Structural Engineering...... and Structural Engineering at the University of Aalborg since the beginning of 1992. Both projects have been supported by the Danish Technical Research Council. Further, the first mentioned project was supported by the Danish Energy Agency. Their financial support is gratefully acknowledged....

Unannounced inspection for integrated safeguards: A theoretical perspective

International Nuclear Information System (INIS)

Canty, M.J.; Avenhaus, R.

2001-01-01

Full text: The application of a safeguards verification regime based on existing agreements under INFCIRC/153 and on the Additional Protocol, INFCIRC/540, has the potential to allow the International Atomic Energy Agency (IAEA) to relax its traditional facility and material-oriented inspection procedures. The relaxation will take into account the IAEA's enhanced access to information as well as complementary access to locations gained through the application of extended measures foreseen under the Additional Protocol. It will reflect the associated confidence achieved at the State level. It is generally agreed that such a trade-off between the new strengthening measures and the traditional measures is reasonable and desirable, both from the point of view of the inspected State, which would like to receive tangible credit for providing increased openness and transparency in its peaceful nuclear activities, and from the viewpoint of the IAEA, which must apportion its limited inspection resources efficiently. An often-discussed proposal to reduce routine inspection effort while maintaining safeguards effectiveness is to replace scheduled interim inspections with a smaller number of random, unannounced visits. Intuitively, the unpredictability aspect is appealing, as it places the potential diverter in a permanent state of uncertainty. There are also some disadvantages, however, such as the difficulty of planning and implementing truly random inspections and the burden experienced by facility operators obliged to accommodate them. An objective evaluation of a randomized inspection regime vis-a-vis conventional routine inspections requires an objective measure of effectiveness and a means of optimizing that measure - in other words a theoretical framework for analyzing verification problems. In our paper we provide such a framework by quantifying the notion of timely detection and by treating the problem consistently a strategic one. We present a series of models which

Phased Array Ultrasonic Inspection of Titanium Forgings

International Nuclear Information System (INIS)

Howard, P.; Klaassen, R.; Kurkcu, N.; Barshinger, J.; Chalek, C.; Nieters, E.; Sun, Zongqi; Fromont, F. de

2007-01-01

Aerospace forging inspections typically use multiple, subsurface-focused sound beams in combination with digital C-scan image acquisition and display. Traditionally, forging inspections have been implemented using multiple single element, fixed focused transducers. Recent advances in phased array technology have made it possible to perform an equivalent inspection using a single phased array transducer. General Electric has developed a system to perform titanium forging inspection based on medical phased array technology and advanced image processing techniques. The components of that system and system performance for titanium inspection will be discussed

[Legislation and inspection for the health and safety of workers. Efficacy and limits].

Science.gov (United States)

Tozzi, G A

2009-01-01

To provide information regarding Occupational Health and Safety (OHS) Inspections in Europe. The dynamics that are transforming regulatory subsystems and complementary inspection services are described. Simplification initiatives, the limits and difficulties of applying the different models of Health and Safety Management Systems are discussed. Examples are given on how to evaluate legislation and technical standards during planning and enforcement. Different approaches for studying characteristics, methodologies and efficacy in practice of OHS Inspection are provided. Targeted inspections need to respond to the needs of enterprises and workers. Impartiality must be guaranteed and workers' participation should be facilitated.

Generic safety insights for inspection of boiling water reactors

International Nuclear Information System (INIS)

Higgins, J.C.; Taylor, J.H.; Fresco, A.N.; Hillman, B.M.

1987-01-01

As the number of operating nuclear power plants (NPP) increases, safety inspection has increased in importance. However, precisely what is important, and what is not important? What should one focus inspection efforts on. Over the last two years Probabilistic Risk Assessment (PR) techniques have been developed to aid in the inspection process. Broad interest in generic PRA-based methods has arisen in the past year, since only about 25% of the US nuclear power plants have completed PRAs, and also, inspectors want PRA-based tools for these plants. This paper describes the BNL program to develop generic BWR PRA-based inspection insights or inspection guidance designed to be applied to plants without PRAs

Development of an ITER relevant inspection robot

Energy Technology Data Exchange (ETDEWEB)

Gargiulo, L.; Bayetti, P.; Cordier, J.J.; Grisolia, C.; Hatchressian, J.C. [Association Euratom-CEA, Cadarache (France). Dept. de Recherche sur la Fusion Controlee; Friconneau, J.P.; Keller, D.; Perrot, Y. [CEA-LIST Robotics and Interactive Systems Unit, Fontenay aux Roses (France)

2007-07-01

Robotic operations are one of the major maintenance challenges for ITER and future fusion reactors. In particular, in vessel inspection operations without loss of conditioning could be very useful. Within this framework, the aim of the project called AIA (Articulated Inspection Arm) is to demonstrate the feasibility of a multi-purpose in-vessel Remote Handling inspection system using a long reach, limited payload carrier (up to 10 kg). It is composed of 5 segments with 11 degrees of freedom and a total range of 8 m. The project is currently developed by the CEA within the European workprogramme. Its first in situ tests are planned this summer on the Tore Supra tokamak at Cadarache (France). They will validate chosen concepts for operations under ITER relevant vacuum and temperature conditions. After qualification, the arm will constitute a promising tool for generic application. Several processes are already considered for ITER maintenance and will be demonstrated on the AIA robot carrier: - The first embedded process is the viewing system. It is currently being manufactured and will allow for close visual inspection of the complex Plasma Facing Components (limiters, neutralisers, RF antennae, diagnostic windows, etc.). - In situ localisation of leakage based on helium sniffer is also studied to improve maintenance operations. - Finally the laser ablation system for PFC detritiation, also developed in CEA laboratories, is being fitted to be implanted into the robot and put into operation in Tore Supra. This paper deals with the integration of the robot in the Tore Supra tokamak and the advances in the development of the listed processes. It also introduces the current test campaign aiming to qualify the robot performance and reliability under vacuum and temperature conditions. (orig.)

Development of an ITER relevant inspection robot

International Nuclear Information System (INIS)

Gargiulo, L.; Bayetti, P.; Cordier, J.J.; Grisolia, C.; Hatchressian, J.C.

2007-01-01

Robotic operations are one of the major maintenance challenges for ITER and future fusion reactors. In particular, in vessel inspection operations without loss of conditioning could be very useful. Within this framework, the aim of the project called AIA (Articulated Inspection Arm) is to demonstrate the feasibility of a multi-purpose in-vessel Remote Handling inspection system using a long reach, limited payload carrier (up to 10 kg). It is composed of 5 segments with 11 degrees of freedom and a total range of 8 m. The project is currently developed by the CEA within the European workprogramme. Its first in situ tests are planned this summer on the Tore Supra tokamak at Cadarache (France). They will validate chosen concepts for operations under ITER relevant vacuum and temperature conditions. After qualification, the arm will constitute a promising tool for generic application. Several processes are already considered for ITER maintenance and will be demonstrated on the AIA robot carrier: - The first embedded process is the viewing system. It is currently being manufactured and will allow for close visual inspection of the complex Plasma Facing Components (limiters, neutralisers, RF antennae, diagnostic windows, etc.). - In situ localisation of leakage based on helium sniffer is also studied to improve maintenance operations. - Finally the laser ablation system for PFC detritiation, also developed in CEA laboratories, is being fitted to be implanted into the robot and put into operation in Tore Supra. This paper deals with the integration of the robot in the Tore Supra tokamak and the advances in the development of the listed processes. It also introduces the current test campaign aiming to qualify the robot performance and reliability under vacuum and temperature conditions. (orig.)

Feature-Learning-Based Printed Circuit Board Inspection via Speeded-Up Robust Features and Random Forest

Directory of Open Access Journals (Sweden)

Eun Hye Yuk

2018-06-01

Full Text Available With the coming of the 4th industrial revolution era, manufacturers produce high-tech products. As the production process is refined, inspection technologies become more important. Specifically, the inspection of a printed circuit board (PCB, which is an indispensable part of electronic products, is an essential step to improve the quality of the process and yield. Image processing techniques are utilized for inspection, but there are limitations because the backgrounds of images are different and the kinds of defects increase. In order to overcome these limitations, methods based on machine learning have been used recently. These methods can inspect without a normal image by learning fault patterns. Therefore, this paper proposes a method can detect various types of defects using machine learning. The proposed method first extracts features through speeded-up robust features (SURF, then learns the fault pattern and calculates probabilities. After that, we generate a weighted kernel density estimation (WKDE map weighted by the probabilities to consider the density of the features. Because the probability of the WKDE map can detect an area where the defects are concentrated, it improves the performance of the inspection. To verify the proposed method, we apply the method to PCB images and confirm the performance of the method.

Modelling inspection policies for building maintenance.

Science.gov (United States)

Christer, A H

1982-08-01

A method of assessing the potential of an inspection maintenance policy as opposed to an existing breakdown maintenance policy for a building complex is developed. The method is based upon information likely to be available and specific subjective assessments which could be made available. Estimates of the expected number of defects identified at an inspection and the consequential cost saving are presented as functions of the inspection frequency.

A plan for safety and integrity of research reactor components

International Nuclear Information System (INIS)

Moatty, Mona S. Abdel; Khattab, M.S.

2013-01-01

Highlights: ► A plan for in-service inspection of research reactor components is put. ► Section XI of the ASME Code requirements is applied. ► Components subjected to inspection and their classes are defined. ► Flaw evaluation and its acceptance–rejection criteria are reviewed. ► A plan of repair or replacement is prepared. -- Abstract: Safety and integrity of a research reactor that has been operated over 40 years requires frequent and thorough inspection of all the safety-related components of the facility. The need of increasing the safety is the need of improving the reliability of its systems. Diligent and extensive planning of in-service inspection (ISI) of all reactor components has been imposed for satisfying the most stringent safety requirements. The Safeguards Officer's responsibilities of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code ASME Code have been applied. These represent the most extensive and time-consuming part of ISI program, and identify the components subjected to inspection and testing, methods of component classification, inspection and testing techniques, acceptance/rejection criteria, and the responsibilities. The paper focuses on ISI planning requirements for welded systems such as vessels, piping, valve bodies, pump casings, and control rod-housing parts. The weld in integral attachments for piping, pumps, and valves are considered too. These are taken in consideration of safety class (1, 2, 3, etc.), reactor age, and weld type. The parts involve in the frequency of inspection, the examination requirements for each inspection, the examination method are included. Moreover the flaw evaluation, the plan of repair or replacement, and the qualification of nondestructive examination personnel are considered

Mobile robot teleoperation system for plant inspection based on collecting and utilizing environment data

International Nuclear Information System (INIS)

Kawabata, Kuniaki; Watanabe, Nobuyasu; Asama, Hajime; Kita, Nobuyuki; Yang, Hai-quan

2004-01-01

This paper describes about development of a mobile robot teleoperation system for plant inspection. In our system, the robot is an agent for collecting the environment data and is also teleoperated by the operator utilizing such accumulated environment data which is displayed on the operation interface. The robot equips many sensors for detecting the state of the robot and the environment. Such redundant sensory system can be also utilized to collect the working environment data on-site while the robot is patrolling. Here, proposed system introduces the framework of collecting and utilizing environment data for adaptive plant inspection using the teleoperated robot. A view simulator is primarily aiming to facilitate evaluation of the visual sensors and algorithms and is also extended as the Environment Server, which is the core technology of the digital maintenance field for the plant inspection. In order to construct detailed seamless digital maintenance field mobile robotic technology is utilized to supply environment data to the server. The sensory system on the robot collect the environment data on-site and such collected data is uploaded to the Environment Server for compiling accurate digital environment data base. The robot operator also can utilize accumulated environment data by referring to the Environment Server. In this paper, we explain the concept of our teleoperation system based on collecting and utilizing environment data. Using developed system, inspection patrol experiments were attempted in the plant mock-up. Experimental results are shown by using an omnidirectional mobile robot with sensory system and the Environment Server. (author)

Update on the EPRI power generation risk-based inservice inspection pilot plant studies

International Nuclear Information System (INIS)

Gosselin, S.R.

1997-01-01

The scope for ASME Section XI ISI programs is largely based on deterministic results contained in design stress reports. These reports are normally very conservative and may not be an accurate representation of failure potential. Service experience has shown that failures are due to either corrosion or fatigue and typically occur in areas not included in the plant's ISI program. Consequently, nuclear plants are devoting significant resources to inspection programs that provide minimum benefit. As an alternative, significant industry attention has been devoted to the application of risked-based selection criteria in order to determine the scope of inservice inspection (ISI) programs at nuclear power plants. Preliminary EPRI studies indicate that the application of these techniques will allow operating nuclear plants to reduce the examination scope of current ISI programs by as much as 60 to 80%, significantly reduce costs, and continue to maintain high nuclear plant safety standards

Modeling and optimizing periodically inspected software rejuvenation policy based on geometric sequences

International Nuclear Information System (INIS)

Meng, Haining; Liu, Jianjun; Hei, Xinhong

2015-01-01

Software aging is characterized by an increasing failure rate, progressive performance degradation and even a sudden crash in a long-running software system. Software rejuvenation is an effective method to counteract software aging. A periodically inspected rejuvenation policy for software systems is studied. The consecutive inspection intervals are assumed to be a decreasing geometric sequence, and upon the inspection times of software system and its failure features, software rejuvenation or system recovery is performed. The system availability function and cost rate function are obtained, and the optimal inspection time and rejuvenation interval are both derived to maximize system availability and minimize cost rate. Then, boundary conditions of the optimal rejuvenation policy are deduced. Finally, the numeric experiment result shows the effectiveness of the proposed policy. Further compared with the existing software rejuvenation policy, the new policy has higher system availability. - Highlights: • A periodically inspected rejuvenation policy for software systems is studied. • A decreasing geometric sequence is used to denote the consecutive inspection intervals. • The optimal inspection times and rejuvenation interval are found. • The new policy is capable of reducing average cost and improving system availability

Development of a remote inspection system for NSSS components

International Nuclear Information System (INIS)

Choi, Yoo Rark; Kim, Jae Hee; Lee, Jae Cheol

2004-03-01

Different operating systems of computerized inspection equipment cause serious problems in graphic user interface between control computers of inspection equipment and remote user computers. Management cost of interface version is very expensive even if the system has been developed. A solution for the interface problems in accessing the remote inspection system is web-based technology. But time-delay problem of web and java, a compiled type S/W that cooperates with web in control computers of inspection equipment is necessary to solve it. This report describes solutions for developing a remote inspection system based on web and java technology

Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2009

International Nuclear Information System (INIS)

2010-01-01

This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2009 and includes inspection and repair activities completed at the following seven CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 426: Cactus Spring Waste Trenches (TTR); (5) CAU 453: Area 9 UXO Landfill (TTR); (6) CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR); and (7) CAU 487: Thunderwell Site (TTR). The annual post-closure inspections were conducted May 5-6, 2009. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2009, and the vegetation monitoring report is included in Attachment F. Maintenance was performed at CAU 453. Animal burrows observed during the annual inspection were backfilled, and a depression was restored to grade on June 25, 2009. Post-closure site inspections should continue as scheduled. Vegetation survey inspections have been conducted annually at CAUs 400, 404, 407, and 426. Discontinuation of vegetation surveys is recommended at the CAU 400 Bomblet Pit and CAU 426, which have been successfully revegetated. Discontinuation of vegetation surveys is also recommended at CAU 404, which has been changed to an administrative closure with no inspections

Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2009

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2010-05-28

This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2009 and includes inspection and repair activities completed at the following seven CAUs: · CAU 400: Bomblet Pit and Five Points Landfill (TTR) · CAU 407: Roller Coaster RadSafe Area (TTR) · CAU 424: Area 3 Landfill Complexes (TTR) · CAU 426: Cactus Spring Waste Trenches (TTR) · CAU 453: Area 9 UXO Landfill (TTR) · CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR) · CAU 487: Thunderwell Site (TTR) The annual post-closure inspections were conducted May 5–6, 2009. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2009, and the vegetation monitoring report is included in Attachment F. Maintenance was performed at CAU 453. Animal burrows observed during the annual inspection were backfilled, and a depression was restored to grade on June 25, 2009. Post-closure site inspections should continue as scheduled. Vegetation survey inspections have been conducted annually at CAUs 400, 404, 407, and 426. Discontinuation of vegetation surveys is recommended at the CAU 400 Bomblet Pit and CAU 426, which have been successfully revegetated. Discontinuation of vegetation surveys is also recommended at CAU 404, which has been changed to an administrative closure with no inspections required. Vegetation

Toward a drone-based EL and PL inspection tool for PV power plants

DEFF Research Database (Denmark)

Riedel, Nicholas; Benatto, Gisele Alves dos Reis; Thorsteinsson, Sune

2017-01-01

of image detail and qualitative insight compared to IR thermography. Furthermore, detection and identification of incipient or severe faults in PV panels is more straightforward.This project proposes for the first time a fast and accurate automatic drone-based inspection method for large PV plants...

Reliability prediction for structures under cyclic loads and recurring inspections

Directory of Open Access Journals (Sweden)

Alberto W. S. Mello Jr

2009-06-01

Full Text Available This work presents a methodology for determining the reliability of fracture control plans for structures subjected to cyclic loads. It considers the variability of the parameters involved in the problem, such as initial flaw and crack growth curve. The probability of detection (POD curve of the field non-destructive inspection method and the condition/environment are used as important factors for structural confidence. According to classical damage tolerance analysis (DTA, inspection intervals are based on detectable crack size and crack growth rate. However, all variables have uncertainties, which makes the final result totally stochastic. The material properties, flight loads, engineering tools and even the reliability of inspection methods are subject to uncertainties which can affect significantly the final maintenance schedule. The present methodology incorporates all the uncertainties in a simulation process, such as Monte Carlo, and establishes a relationship between the reliability of the overall maintenance program and the proposed inspection interval, forming a “cascade” chart. Due to the scatter, it also defines the confidence level of the “acceptable” risk. As an example, the damage tolerance analysis (DTA results are presented for the upper cockpit longeron splice bolt of the BAF upgraded F-5EM. In this case, two possibilities of inspection intervals were found: one that can be characterized as remote risk, with a probability of failure (integrity nonsuccess of 1 in 10 million, per flight hour; and other as extremely improbable, with a probability of nonsuccess of 1 in 1 billion, per flight hour, according to aviation standards. These two results are compared with the classical military airplane damage tolerance requirements.

Practical method for generation expansion planning based on the dynamic programming. Dynamic programming ni motozuku dengen keikaku shuho

Energy Technology Data Exchange (ETDEWEB)

Tanabe, R.; Yasuda, K.; Yokoyama, R. (Tokyo Metropolitan Univ., Tokyo (Japan))

1992-05-20

To supply cheap, high-reliable and a planty of the electricity is an important task of the electric supply system because the requirement for the electricity is rapidly increased in Japan. In order to solve this problem, the authors of the paper are developing a most suitable practical method based on algorithm, according to which the generation expansion planning is divided into two problems: the optimal generation mix and the optimal generation construction process and the two problems are solved respectively. But there are some bad points in the method, for example, there are only approximative practical restriction of the capacity of single machine and the existing electric supply etc., because the optimal generation mix is determined on the basis of non-linear planning. So, in the present paper, the electric supply support system is practically constructed while proposing an unified generation expansion planning based on the dynamic programming that is possible to consider these restrictions strictly and the usefullness of the method is inspected. 12 refs., 7 figs., 5 tabs.

Remote inspection system for nuclear power plants

International Nuclear Information System (INIS)

Inagaki, K.; Fujii, M.; Doi, A.; Harima, T.

1977-01-01

A remote inspection system for nuclear power plants was constructed based on an analysis of inspections performed by an operator on patrol. This system consists of an operator's console and a remote station. The remote station, equipped with five kinds of sensors, is steered along the inspection route by a photoelectric guiding system or may be manually controlled from an operator's console in a main control room. Signals for control and inspection data are multiplexed and transmitted through a coaxial cable

Monitoring Interior and Exterior Wall Inspections within a Virtual Environment

Directory of Open Access Journals (Sweden)

A. Z. Sampaio

2012-01-01

Full Text Available This paper describes two prototype applications based on the Virtual Reality (VR technology for use in maintenance planning of buildings. In a building, the paint coating applied to interior walls and the different types of materials applied to façades convey their aesthetic character and also perform an important function of protection. This a construction component which is exposed to agents of deterioration related to its use, needing the regular evaluation of its state of repair. The applications support the performance of such periodic inspections and the monitoring of interior and exterior wall maintenance, using the VR technology. Used during an inspection visit, the applications allow users to consult a database of irregularities, normally associated with the coating, classified by the most probable causes and by the recommended repair methodologies. In addition, a chromatic scale related to the degree of deterioration of the coating, defined as a function of the time between the dates of the application of the paint and the scheduled repainting, can be attributed to each element of coating monitored. This use of the VR technology allows inspections and the evaluation of the degree of wear and tear of materials to be carried out in a highly direct and intuitive manner.

A risk-informed approach to optimising in-service inspection of piping

International Nuclear Information System (INIS)

Billington, A.; Monette, P.

1999-01-01

Traditional criteria for the selection of in-service inspection locations in piping, have come to be regarded as being out-of-touch with current knowledge of piping failures and with current measures of safety importance. An alternative , risk-informed, method has been developed and successfully licensed, that systematically establishes an inspection plan addressing all safety-related piping systems, in a way that is optimized with respect to the safety gain achieved through in-service inspection. The principles of the method are discussed and the results of several applications are summarized, all of which demonstrate that the risk-informed program would lead to significant improvements in the overall level of plant safety, while at the same time re-distributing the inspections in such a way that reduces both plant costs and radiation exposure to personnel.(author)

Examples of in-service inspections and typical maintenance schedule for low-power research reactors

International Nuclear Information System (INIS)

Boeck, H.

1997-01-01

In-service inspection methods for low-power research reactors are described which have been developed during the past 37 years of the operation of the TRIGA reactor Vienna. Special tools have been developed during this period and their application for maintenance and in-serve inspection is discussed. Two practical in-service inspections at a TRIGA reactor and at a MTR reactor are presented. Further a typical maintenance plan for a TRIGA reactor is listed in the annex. (author)

Image acquisition, transmission and assignment in 60Co container inspection system

International Nuclear Information System (INIS)

Wu Zhifang; Zhou Liye; Liu Ximing; Wang Liqiang

1999-01-01

The author describes the data acquisition mode and image reconstruction method in 60 Co container inspection system, analyzes the relationship between line pick period and geometry distortion, makes clear the demand to data transmitting rate. It discusses several data communication methods, draws up a plan for network, realizes automatic direction and reasonable assignment of data in the system, cooperation of multi-computer and parallel processing, thus greatly improves the systems inspection efficiency

Eddy current automatic inspection of heat exchangers in nuclear power stations

International Nuclear Information System (INIS)

Cazal, M.; Scopelliti, J.D.; Mendez, J.

1997-01-01

This presentation describes the eddy current tube inspection techniques for heavy heat exchangers in nuclear power stations. The purpose of these eddy current tests, is first to determine the integrity of the heat exchanger tubes, and to characterize the related types of defects in each case following to their analysis and cause determination and subsequent inspection planning. This task requires a group highly qualified personnel with high tech automate equipment. The organization of the group required a correct function and task assignment in order to achieve efficiency in scheduling, with simultaneous inspection to different components in a continuous base and uninterruptedly. A lead specialist is in charge of the group, which is set up by several shift supervisors, a qualified tele manipulator installation crew a number of qualified tele manipulator operators, and the specialist for data acquisition and certified eddy current signal evaluators plus some other support technicians and administrations helpers. In order to comply with inspection requirements, a bunch of technical procedures had to be developed. The following equipment is available nowadays: Zetec SM-13, SM-23 and SM-22 tele manipulators for inspection probes positioning, with different shapes and configuration (rotating probes, flexible probes for U-Bends, and magnetic saturation probes endowed with their own driving units) and remote data acquisition units identified as MIZ-18 A and MIZ-30, which are remotely operated from a mobile lab installed in a trailer, outside the reactor building. The available equipment allows a simultaneous inspection of three different plant components (two steam generators and a moderator heat exchanger). We are also in a position of performing eddy current tube inspection in more than a NSP at the same time. The Zetec Eddynet software is used in the manipulator operation and for the data acquisition and defect evaluation. This software operates within Windows

Development of automatic inspection robot for nuclear power plants

International Nuclear Information System (INIS)

Yamada, K.; Suzuki, K.; Saitoh, K.; Sakaki, T.; Ohe, Y.; Mizutani, T.; Segawa, M.; Kubo, K.

1987-01-01

This robot system has been developed for automatic inspection of nuclear power plants. The system configuration is composed of vehicle that runs on monorail, the sensors on the vehicle, an image processer that processes the image information from the sensors, a computer that creates the inspection planning of the robot and an operation panel. This system has two main features, the first is the robot control system. The vehicle and the sensors are controlled by the output data calculated in the computer with the three dimensional plant data. The malfunction is recognized by the combination of the results of image processing, information from the microphone and infrared camera. Tests for a prototype automatic inspection robot system have been performed in the simulated main steam piping room of a nuclear power plant

Real-time distortion correction for visual inspection systems based on FPGA

Science.gov (United States)

Liang, Danhua; Zhang, Zhaoxia; Chen, Xiaodong; Yu, Daoyin

2008-03-01

Visual inspection is a kind of new technology based on the research of computer vision, which focuses on the measurement of the object's geometry and location. It can be widely used in online measurement, and other real-time measurement process. Because of the defects of the traditional visual inspection, a new visual detection mode -all-digital intelligent acquisition and transmission is presented. The image processing, including filtering, image compression, binarization, edge detection and distortion correction, can be completed in the programmable devices -FPGA. As the wide-field angle lens is adopted in the system, the output images have serious distortion. Limited by the calculating speed of computer, software can only correct the distortion of static images but not the distortion of dynamic images. To reach the real-time need, we design a distortion correction system based on FPGA. The method of hardware distortion correction is that the spatial correction data are calculated first under software circumstance, then converted into the address of hardware storage and stored in the hardware look-up table, through which data can be read out to correct gray level. The major benefit using FPGA is that the same circuit can be used for other circularly symmetric wide-angle lenses without being modified.

Enabling inspection solutions for future mask technologies through the development of massively parallel E-Beam inspection

Science.gov (United States)

Malloy, Matt; Thiel, Brad; Bunday, Benjamin D.; Wurm, Stefan; Jindal, Vibhu; Mukhtar, Maseeh; Quoi, Kathy; Kemen, Thomas; Zeidler, Dirk; Eberle, Anna Lena; Garbowski, Tomasz; Dellemann, Gregor; Peters, Jan Hendrik

2015-09-01

The new device architectures and materials being introduced for sub-10nm manufacturing, combined with the complexity of multiple patterning and the need for improved hotspot detection strategies, have pushed current wafer inspection technologies to their limits. In parallel, gaps in mask inspection capability are growing as new generations of mask technologies are developed to support these sub-10nm wafer manufacturing requirements. In particular, the challenges associated with nanoimprint and extreme ultraviolet (EUV) mask inspection require new strategies that enable fast inspection at high sensitivity. The tradeoffs between sensitivity and throughput for optical and e-beam inspection are well understood. Optical inspection offers the highest throughput and is the current workhorse of the industry for both wafer and mask inspection. E-beam inspection offers the highest sensitivity but has historically lacked the throughput required for widespread adoption in the manufacturing environment. It is unlikely that continued incremental improvements to either technology will meet tomorrow's requirements, and therefore a new inspection technology approach is required; one that combines the high-throughput performance of optical with the high-sensitivity capabilities of e-beam inspection. To support the industry in meeting these challenges SUNY Poly SEMATECH has evaluated disruptive technologies that can meet the requirements for high volume manufacturing (HVM), for both the wafer fab [1] and the mask shop. Highspeed massively parallel e-beam defect inspection has been identified as the leading candidate for addressing the key gaps limiting today's patterned defect inspection techniques. As of late 2014 SUNY Poly SEMATECH completed a review, system analysis, and proof of concept evaluation of multiple e-beam technologies for defect inspection. A champion approach has been identified based on a multibeam technology from Carl Zeiss. This paper includes a discussion on the

Point-based POMDP Risk Based Inspection of Offshore Wind Substructures

DEFF Research Database (Denmark)

Morato, Pablo G.; Mai, Quang A.; Rigo, Philippe

2018-01-01

This article presents a novel methodology to select the optimal maintenance strategy of an offshore wind structural component, providing a flexible and reliable support to decision-making and balancing inspection, repair and failure costs. The procedure to create a “Point-Based” Partially...

Targeted In-service Inspections Using Risk Insights

International Nuclear Information System (INIS)

Kulat, S.; Montgomery, B.; Robin Graybeal, M.

2012-01-01

This paper includes a discussion of the historical background and rationale for development of a targeted In-service Inspection (ISI) program using risk insights, known as Risk-Informed In-service Inspection (RI-ISI). RI-ISI programs are optimized inspection programs which target specific welds for inspection based upon potential degradation mechanisms and consequences of failure. Inspections are performed on those welds that are the highest contributors to plant risk. Additionally the inspections are tailored to detect the specific postulated degradation mechanisms. As a result, the numbers of inspections are reduced along with the associated cost and radiation exposure, while maintaining or improving the level of quality and safety. Provided in this paper are the basic principles of RI-ISI program development, and a summary of the impact of the implementation of such programs. For example, implementation of a Risk-Informed In-service Inspection program results in a reduction of both cost and radiation exposure. Cost savings are estimated at between USD 1,000,000 and USD 2,300,000 per unit per ten year interval for a Class 1 and2 RI-ISI application. Cost savings are estimated based on average cost per weld of USD 7600 for examination, including the following activities: erection and removal of scaffolding, removal and replacement of insulation, removal and replacement of interferences, weld preparation, examination, documentation, craft support. Reduction in radiation exposure is estimated at 75% to 90% for a Class 1 and2 RI-ISI application. Reduction in radiation exposure is due to the following factors: number of welds selected for examination decreases by 60% to 75%, surface examinations essentially eliminated, within a given risk category, welds can be selected for examination based on additional factors such as the minimization of radiation exposure.(author).

Comparison of CT based-CTV plan and CT based-ICRU38 plan in brachytherapy planning of uterine cervix cancer

International Nuclear Information System (INIS)

Cho, Jung Keun; Han, Tae Jong

2007-01-01

Purpose : In spite of recent remarkable improvement of diagnostic imaging modalities such as CT, MRI, and PET and radiation therapy planing systems, ICR plan of uterine cervix cancer, based on recommendation of ICRU38(2D film-based) such as point A, is still used widely. A 3-dimensional ICR plan based on CT image provides Dose-Volume Histogram(DVH) information of the tumor and normal tissue. In this study, we compared tumor-dose, rectal-dose and bladder-dose through an analysis of DVH between CTV plan and ICRU38 plan based on CT image. Method and Material : We analyzed 11 patients with a cervix cancer who received the ICR of Ir-192 HDR. After 40Gy of external beam radiation therapy, ICR plan was established using PLATO(Nucletron) v.14.2 planning system. CT scan was done to all the patients using CT-simulator(Ultra Z, Philips). We contoured CTV, rectum and bladder on the CT image and established CTV plan which delivers the 100% dose to CTV and ICRU plan which delivers the 100% dose to the point A. Result : The volume(average±SD) of CTV, rectum and bladder in all of 11 patients is 21.8±6.6cm 3 , 60.9±25.0cm 3 , 111.6±40.1cm 3 respectively. The volume covered by 100% isodose curve is 126.7±18.9cm 3 in ICRU plan and 98.2±74.5cm 3 in CTV plan(p=0.0001), respectively. In (On) ICRU planning 22.0cm 3 of CTV volume was not covered by 100% isodose curve in one patient whose residual tumor size is greater than 4cm, while more than 100% dose was irradiated unnecessarily to the normal organ of 62.2±4.8cm 3 other than the tumor in the remaining 10 patients with a residual tumor less than 4cm in size. Bladder dose recommended by ICRU 38 was 90.1±21.3% and 68.7±26.6% in ICRU plan and in CTV plan respectively(p=0.001) while rectal dose recommended by ICRU 38 was 86.4±18.3% and 76.9±15.6% in ICRU plan and in CTV plan, respectively(p=0.08). Bladder and rectum maximum dose was 137.2±50.1%, 101.1±41.8% in ICRU plan and 107.6±47.9%, 86.9±30.8% in CTV plan, respectively

Evaluating the Usefulness and the Ease of Use of a Web-based Inspection Data Collection Tool

OpenAIRE

Dreyer, H.M.; Laitenberger, O.

1998-01-01

This paper contributes a valid and reliable measurement instrument in the form of a questionnaire to determine, from a userüs perspective, the usefulness and ease of use of a Web-based Inspection Process Support tool (WIPS) that we developed for inspection data collection. The questionnaire is built upon the work of Fred Davis on perceived usefulness, ease of use, and usage of information technology. To validate the questionnaire and its underlying model as well as to evaluate WIPS, we perfor...

A condition-based maintenance policy with non-periodic inspections for a two-unit series system

International Nuclear Information System (INIS)

Castanier, B.; Grall, A.; Berenguer, C.

2005-01-01

This paper considers a condition-based maintenance policy for a two-unit deteriorating system. Each unit is subject to gradual deterioration and is monitored by sequential non-periodic inspections. It can be maintained by good as new preventive or corrective replacements. Every inspection or replacement entails a set-up cost and a component-specific unit cost but if actions on the two components are combined, the set-up cost is charged only once. A parametric maintenance decision framework is proposed to coordinate inspection/replacement of the two components and minimize the long-run maintenance cost of the system. A stochastic model is developed on the basis of the semi-regenerative properties of the maintained system state and the associated cost model is used to assess and optimize the performance of the maintenance model. Numerical experiments emphasize the interest of a control of the operation groupings

Guide to the periodic inspection of nuclear reactor steel pressure vessels

International Nuclear Information System (INIS)

1969-01-01

This Guide is intended to provide general information and guidance to reactor owners or operators, inspection authorities, certifying authorities or regulatory bodies who are responsible for establishing inspection procedures for specific reactors or reactor types, and for the preparation of national codes or standards. The recommendations of the Guide apply primarily to water-cooled steel reactor vessels which are at a sufficiently early stage of design so that recommendations to provide accessibility for inspection can be incorporated into the early stages of design and inspection planning. However, much of the contents of the Guide are also applicable in part to vessels for other reactor types, such as gas-cooled, pressure-tube, or liquid-metal-cooled reactors, and also to some existing water-cooled reactors and reactors which are in advanced stage of design or construction. 46 refs, figs, 1 tab

Factors to consider when planning a pipeline inspection: making an informed best choice

Energy Technology Data Exchange (ETDEWEB)

Scott, Ben [GE Oil and Gas, PII Pipeline Solutions, Cramlington Northumberland (United Kingdom)

2009-07-01

When managing pipeline integrity, the quality of inspection information is critical to determining the true condition of the pipeline, and predicting its future condition over time. The cost of a pipeline failure is nearly always much more than the cost of using a quality inspection service to obtain accurate information on the condition of the line. With pressure to reduce costs for all services, the focus often falls on the two most visible areas, tool selection and short-term service cost. These are important factors, but what is equally important is the quality and reliability of the data obtained and its effect on pipeline integrity. Without reliable data our information on pipeline condition is uncertain at best. These issues of data quality are often not well understood since many specialist technical factors are involved. This paper highlights some of the issues that need to be considered so that their importance and the effort that goes into them can be appreciated better. At the end of the day, the prime requirement is a safe, accurate and reliable inspection, delivering a good specification over a wide range of pipeline conditions and flow velocities. (author)

Good clinical practice regulatory inspections: Lessons for Indian investigator sites

Directory of Open Access Journals (Sweden)

R Marwah

2010-01-01

Full Text Available Regulatory inspections are important to evaluate the integrity of the data submitted to health authorities (HAs, protect patient safety, and assess adequacy of site/sponsor quality systems to achieve the same. Inspections generally occur after submission of data for marketing approval of an investigational drug. In recent years, there has been a significant increase in number of inspections by different HAs, including in India. The assessors/inspectors generally do a thorough review of site data before inspections. All aspects of ICH-GCP, site infrastructure, and quality control systems are assessed during the inspection. Findings are discussed during the close out meeting and a detailed inspection report issued afterward, which has to be responded to within 15-30 days with effective Corrective and Preventive Action Plan (CAPA. Protocol noncompliance, inadequate/inaccurate records, inadequate drug accountability, informed consent issues, and adverse event reporting were some of the most common findings observed during recent Food and Drug Administration (FDA inspections. Drug development is being increasingly globalized and an increased number of patients enrolled in studies submitted as part of applications come from all over the world including India. Because of the steep increase in research activity in the country, inexperienced sites, and more stakeholders, increased efforts will be required to ensure continuous quality and compliance. HAs have also made clear that enforcement will be increased and be swift, aggressive, and effective.

An optimal inspection strategy for randomly failing equipment

International Nuclear Information System (INIS)

Chelbi, Anis; Ait-Kadi, Daoud

1999-01-01

This paper addresses the problem of generating optimal inspection strategies for randomly failing equipment where imminent failure is not obvious and can only be detected through inspection. Inspections are carried out following a condition-based procedure. The equipment is replaced if it has failed or if it shows imminent signs of failure. The latter state is indicated by measuring certain predetermined control parameters during inspection. Costs are associated with inspection, idle time and preventive or corrective actions. An optimal inspection strategy is defined as the inspection sequence minimizing the expected total cost per time unit over an infinite span. A mathematical model and a numerical algorithm are developed to generate an optimal inspection sequence. As a practical example, the model is applied to provide a machine tool operator with a time sequence for inspecting the cutting tool. The tool life time distribution and the trend of one control parameter defining its actual condition are supposed to be known

Project W-314 specific test and evaluation plan for AZ tank farm upgrades

International Nuclear Information System (INIS)

Hays, W.H.

1998-01-01

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made by the addition of the SN-631 transfer line from the AZ-O1A pit to the AZ-02A pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation P1 an (TEP). Testing includes Validations and Verifications (e.g., Commercial Grade Item Dedication activities, etc), Factory Tests and Inspections (FTIs), installation tests and inspections, Construction Tests and Inspections (CTIs), Acceptance Test Procedures (ATPs), Pre-Operational Test Procedures (POTPs), and Operational Test Procedures (OTPs). The STEP will be utilized in conjunction with the TEP for verification and validation

Pathology Residents Comprise Inspection Team for a CAP Self-Inspection

Directory of Open Access Journals (Sweden)

Stacy G. Beal MD

2017-03-01

Full Text Available We report our experience at the University of Florida in which residents and fellows served as the inspection team for a College of American Pathologists (CAP self-inspection. We aimed to determine whether the CAP self-inspection could serve as a learning opportunity for pathology residents and fellows. To prepare for the inspection, we provided a series of 4 lunchtime seminars covering numerous laboratory management topics relating to inspections and laboratory quality. Preparation for the inspection began approximately 4 months prior to the date of the inspection. The intent was to simulate a CAP peer inspection, with the exception that the date was announced. The associate residency program director served as the team leader. All residents and fellows completed inspector training provided by CAP, and the team leader completed the team leader training. A 20 question pre- and posttest was administered; additionally, an anonymous survey was given after the inspection. The residents’ and fellows’ posttest scores were an average of 15% higher than on the pretest ( P < .01. The surveys as well as subjective comments were overwhelmingly positive. In conclusion, the resident’s and fellow’s experience as an inspector during a CAP self-inspection was a useful tool to learn accreditation and laboratory management.

Inspection, evaluation and maintenance guidelines for reactor vessel internals in JAPAN

International Nuclear Information System (INIS)

Sakashita, Akihiro; Goto, Tomoya; Hirano, Shinro; Dozaki, Koji

2010-01-01

Inspection and Evaluation Guidelines for reactor internals has been taken into the Rules on Fitness-for–Service for Nuclear Power Plants of The Japan Society of Mechanical Engineers. It is a base of the maintenance plan of each Nuclear Power Plant. A plant maintenance methodology will have more importance to maintain the plant safety and stable plant operation. This paper introduces the systematization of the maintenance such as repair, replacement, preventive maintenance in these guidelines. Maintenance methodologies are classified follows. Repair: methodology to reinforce degraded parts by some methods or prevent progress of degradation of without replacement of the existing structure when the degradation of structure is actualized. Replacement: methodology to replace the existing structure with new one when the degradation of structure is actualized. Preventive maintenance : methodology to mitigate the damaged condition. When the maintenance methodologies are implemented in the actual plant, we have to consider the feedback of the inspection program and plant life management. (author)

RBI - Risk Based Inspection: new technologies and methods applied to inspections of FPSO (Floating Production, Storage and Offloading Vessel) hull; IBR - Inspecao Baseada em Risco: novas tecnologias e metodos aplicados as inspecoes de casco de FPSOs

Energy Technology Data Exchange (ETDEWEB)

Farias, Bruno de; Figueiredo, Eduardo; Luiz, Marcio [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil); Meurer, Gustavo; Duarte, Romulo; Oliveira, Thais; Krzonkalla, Viviane [ABS Consulting, Rio de Janeiro, RJ (Brazil)

2008-07-01

With the aging of the FPSO's, which are fundamental to the operation Offshore, better techniques and technologies must be applied to assess more accurately the actual efficiency and structural conditions of producing unit. With the emergence of new engineering techniques and equipment and methods of structural inspection, is now possible to use these new technologies to better manage risk and reliability of the structure of the FPSO, with that, the inspections and methods are more rational and efficient. The Risk-Based Inspection is the tool for monitoring operation of industrial plants with systemic use of technology in conjunction with risk analysis and reliability. His concept is applicable to various branches of industry. The companies began their implementation of oil by refineries. The group of ABS Consulting with PETROBRAS has been developing and implementing these new technologies in inspections of hulls of FPSO's. Applied successfully in the units of the Campos basin, these methods are used by the group of Risk-Based Inspection to improve the efficiency of all the steps involved with the structural integrity of the unit. (author)

Machine Vision based Micro-crack Inspection in Thin-film Solar Cell Panel

Directory of Open Access Journals (Sweden)

Zhang Yinong

2014-09-01

Full Text Available Thin film solar cell consists of various layers so the surface of solar cell shows heterogeneous textures. Because of this property the visual inspection of micro-crack is very difficult. In this paper, we propose the machine vision-based micro-crack detection scheme for thin film solar cell panel. In the proposed method, the crack edge detection is based on the application of diagonal-kernel and cross-kernel in parallel. Experimental results show that the proposed method has better performance of micro-crack detection than conventional anisotropic model based methods on a cross- kernel.

Multi-Canister overpack inservice inspection and maintenance

International Nuclear Information System (INIS)

SMITH, K.E.

1998-01-01

The factors to be considered in establishing inservice inspection and maintenance requirements for the Multi-Canister Overpack (MCO) include evaluating the likelihood of degradation to the MCO pressure boundary due to erosion and corrosion, reviewing commercial practice for NRC licensed spent nuclear fuel storage systems, and examining the individual MCO components for maintenance needs. Reviews of the potential for MCO erosion and corrosion conclude that neither will pose a threat to the MCO pressure boundary. Consistent with commercial practice for spent fuel storage systems, the MCO closure weld will be helium leak tested prior to placement in interim storage. Beyond the CSB facility related monitoring plans (radiological monitoring, emissions monitoring, vault cooling data, etc.), no inservice inspection or maintenance of the MCO is required during interim storage

Advanced Approach of Reactor Pressure Vessel In-service Inspection

International Nuclear Information System (INIS)

Matokovic, A.; Picek, E.; Pajnic, M.

2006-01-01

The most important task of every utility operating a nuclear power plant is the continuously keeping of the desired safety and reliability level. This is achieved by the performance of numerous inspections of the components, equipment and system of the nuclear power plant in operation and in particular during the scheduled maintenance periods at re-fueling time. Periodic non-destructive in-service inspections provide most relevant criteria of the integrity of primary circuit pressure components. The task is to reliably detect defects and realistically size and characterize them. One of most important and the most extensive examination is a reactor pressure vessel in-service inspection. That inspection demand high standards of technology and quality and continual innovation in the field of non-destructive testing (NDT) advanced technology as well as regarding reactor pressure vessel tool and control systems. A remote underwater contact ultrasonic technique is employed for the examination of the defined sections (reactor welds), whence eddy current method is applied for clad surface examinations. Visual inspection is used for examination of the vessel inner surface. The movement of probes and data positioning are assured by using new reactor pressure vessel tool concept that is fully integrated with NDT systems. The successful performance is attributed thorough pre-outage planning, training and successful performance demonstration qualification of chosen NDT techniques on the specimens with artificial and/or real defects. Furthermore, use of advanced approach of inspection through implementation the state of the art examination equipment significantly reduced the inspection time, radiation exposure to examination personnel, shortening nuclear power plant outage and cutting the total inspection costs. The advanced approach as presented in this paper offer more flexibility of application (non-destructive tests, local grinding action as well as taking of boat samples

Development and performance of inspection equipment for pressure tubes in Fugen

International Nuclear Information System (INIS)

Naruo, Kazuteru; Tanimoto, Ken-ichi; Ohta, Takeo; Nakamura, Takahisa; Imaizumi, Kiyoshi.

1984-01-01

The pressure tubes of Fugen are the important equipment as the many tubes compose the core, and since they are made of Zr-2.5% Nb alloy which has been used for the first time in Japan, they have become the object of monitoring (the follow-up investigation of the change of inside diameter, the presence of defects and so on) in addition to the in-service inspection. In this paper, on the inspection equipment for pressure tubes, that has been developed independently by the Power Reactor and Nuclear Fuel Development Corp. in order to carry out the ISI and monitoring, the course of development and the construction and the performance are reported, and the results of having used it for the fourth regular inspection of Fugen are described. The 10-year plan of the ISI and monitoring of pressure tubes is shown. The core of Fugen is composed of 224 pressure tubes, therefore, the inspection is carried out by sampling inspection. The monitoring is carried out on four tubes for the follow-up investigation and one tube that shows the severest operation history at the time of inspection. The equipment performs ultrasonic flaw detection, the measurement of inside diameter and the visual inspection of internal surface. (Kako, I.)

Use of volunteers' information to support proactive inspection of hydraulic structures

Science.gov (United States)

Cortes Arevalo, Juliette; Sterlacchini, Simone; Bogaard, Thom; Frigerio, Simone; Junier, Sandra; Schenato, Luca; van den Giesen, Nick

2016-04-01

Proactive management is particularly important to deal with the increasing occurrence of hydro-meteorological hazards in mountain areas were threats are often caused by multiple and sudden onset hazards such as debris flows. Citizen volunteers can be involved in supporting technicians on inspecting the structures' functional status. Such collaborative effort between managing organizations and local volunteers becomes more important under limited resources. To consider volunteers' information in support of proactive inspection of hydraulic structures, we developed a methodology applicable in day-to-day risk management. At first, in collaboration with technicians-in-charge, a data collection approach was developed for first level or pre-screening visual inspections that can be performed by volunteers. Methods comprise of a data collection exercise, an inspection forms and a learning session based on existent procedures in the FVG region and neighbouring regions. To systematically evaluate the individual inspection reports, we designed a support method by means of a multi-criteria method with fuzzy terms. The method allows the technicians-in-charge to categorize the reports in one of three levels, each corresponding with a course of action. To facilitate the evaluation of inspection reports, we transformed the decision support method into a prototype Web-GIS application. The design process of the Web-GIS framework followed a user-centred approach. The conceptual design incorporates four modules for managing the inspection reports: 1) Registered users, 2) Inspection planning; 3) Available reports and 4) Evaluation of reports. The development of the prototype focused on the evaluation module and was implemented based on standard and interoperable open source tools. Finally, we organized a workshop with technicians in the study area to test the decision support method and get insights about the usefulness of the Web-GIS framework. Participants that took part of the

Robotic inspection technology-process an toolbox

Energy Technology Data Exchange (ETDEWEB)

Hermes, Markus [ROSEN Group (United States). R and D Dept.

2005-07-01

Pipeline deterioration grows progressively with ultimate aging of pipeline systems (on-plot and cross country). This includes both, very localized corrosion as well as increasing failure probability due to fatigue cracking. Limiting regular inspecting activities to the 'scrapable' part of the pipelines only, will ultimately result into a pipeline system with questionable integrity. The confidence level in the integrity of these systems will drop below acceptance levels. Inspection of presently un-inspectable sections of the pipeline system becomes a must. This paper provides information on ROSEN's progress on the 'robotic inspection technology' project. The robotic inspection concept developed by ROSEN is based on a modular toolbox principle. This is mandatory. A universal 'all purpose' robot would not be reliable and efficient in resolving the postulated inspection task. A preparatory Quality Function Deployment (QFD) analysis is performed prior to the decision about the adequate robotic solution. This enhances the serviceability and efficiency of the provided technology. The word 'robotic' can be understood in its full meaning of Recognition - Strategy - Motion - Control. Cooperation of different individual systems with an established communication, e.g. utilizing Bluetooth technology, support the robustness of the ROSEN robotic inspection approach. Beside the navigation strategy, the inspection strategy is also part of the QFD process. Multiple inspection technologies combined on a single carrier or distributed across interacting container must be selected with a clear vision of the particular goal. (author)

Automated visual inspection system based on HAVNET architecture

Science.gov (United States)

Burkett, K.; Ozbayoglu, Murat A.; Dagli, Cihan H.

1994-10-01

In this study, the HAusdorff-Voronoi NETwork (HAVNET) developed at the UMR Smart Engineering Systems Lab is tested in the recognition of mounted circuit components commonly used in printed circuit board assembly systems. The automated visual inspection system used consists of a CCD camera, a neural network based image processing software and a data acquisition card connected to a PC. The experiments are run in the Smart Engineering Systems Lab in the Engineering Management Dept. of the University of Missouri-Rolla. The performance analysis shows that the vision system is capable of recognizing different components under uncontrolled lighting conditions without being effected by rotation or scale differences. The results obtained are promising and the system can be used in real manufacturing environments. Currently the system is being customized for a specific manufacturing application.

Guidelines for risk-based fish inspection

OpenAIRE

2015-01-01

Fish and fishery products are nutritious and healthy and are an important source of food and livelihood for many millions of people worldwide. Fish inspection is concerned with ensuring that the consumer has access to safe and nutritious fish and fish products, whether the fish is from domestic sources of supply, imported or to be exported to consumers in another country. The present guidelines will assist fish inspectors to carry out these responsibilities--Publisher's description.

Ultrasonic inspection

International Nuclear Information System (INIS)

Satittada, Gannaga

1984-01-01

Ultrasonic inspection is one of the most widely used methods for nondestructive inspection. The beam of high-frequency sound wave, ultrasonic wave, is introduced into the material. It travels through the material with some attendant loss of energy and can be reflected at interfaces. The reflected beam is detected and analyzed. Ultrasonic inspection is used to detect flaws in metal parts as well as in welded, brazed and bonded joints during research work and developing production and service. It is also used to detect and locate porosity, pipe, and flakes. In addition, it can be used for the measurement of metal thickness. Ultrasonic inspection is therefore used for quality control and material inspection in all major industries

Optimizing image-based patterned defect inspection through FDTD simulations at multiple ultraviolet wavelengths

Science.gov (United States)

Barnes, Bryan M.; Zhou, Hui; Henn, Mark-Alexander; Sohn, Martin Y.; Silver, Richard M.

2017-06-01

The sizes of non-negligible defects in the patterning of a semiconductor device continue to decrease as the dimensions for these devices are reduced. These "killer defects" disrupt the performance of the device and must be adequately controlled during manufacturing, and new solutions are required to improve optics-based defect inspection. To this end, our group has reported [Barnes et al., Proc. SPIE 1014516 (2017)] our initial five-wavelength simulation study, evaluating the extensibility of defect inspection by reducing the inspection wavelength from a deep-ultraviolet wavelength to wavelengths in the vacuum ultraviolet and the extreme ultraviolet. In that study, a 47 nm wavelength yielded enhancements in the signal to noise (SNR) by a factor of five compared to longer wavelengths and in the differential intensities by as much as three orders-of-magnitude compared to 13 nm. This paper briefly reviews these recent findings and investigates the possible sources for these disparities between results at 13 nm and 47 nm wavelengths. Our in-house finite-difference time-domain code (FDTD) is tested in both two and three dimensions to determine how computational conditions contributed to the results. A modified geometry and materials stack is presented that offers a second viewpoint of defect detectability as functions of wavelength, polarization, and defect type. Reapplication of the initial SNR-based defect metric again yields no detection of a defect at λ = 13 nm, but additional image preprocessing now enables the computation of the SNR for λ = 13 nm simulated images and has led to a revised defect metric that allows comparisons at all five wavelengths.

Audit and Evaluation Plan FY 2002

National Research Council Canada - National Science Library

2002-01-01

.... These projects also have been coordinated in the joint audit and inspection planning groups that address coverage in each major functional area. The plan also includes audit policy and oversight projects planned to start in FY 2002; however, intelligence coverage will be addressed separately.

Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2007

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2008-01-01

This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2007 and includes inspection and repair activities completed at the following nine CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 404: Roller Coaster Lagoons and Trench (TTR); (3) CAU 407: Roller Coaster RadSafe Area (TTR); (4) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); (5) CAU 424: Area 3 Landfill Complexes (TTR); (6) CAU 426: Cactus Spring Waste Trenches (TTR); (7) CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); (8) CAU 453: Area 9 UXO Landfill (TTR); and (9) CAU 487: Thunderwell Site (TTR). In a letter from the Nevada Division of Environmental Protection (NDEP) dated December 5, 2006, NDEP concurred with the request to reduce the frequency of post-closure inspections of CAUs at TTR to an annual frequency. This letter is included in Attachment B. Post-closure inspections were conducted on May 15-16, 2007. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in May 2007, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 453. Animal burrows observed during the annual inspection at CAU 453 were backfilled on August 1, 2007. At this time, the TTR post-closure site inspections should continue as

Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2007

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2008-06-01

This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2007 and includes inspection and repair activities completed at the following nine CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 404: Roller Coaster Lagoons and Trench (TTR); (3) CAU 407: Roller Coaster RadSafe Area (TTR); (4) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); (5) CAU 424: Area 3 Landfill Complexes (TTR); (6) CAU 426: Cactus Spring Waste Trenches (TTR); (7) CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); (8) CAU 453: Area 9 UXO Landfill (TTR); and (9) CAU 487: Thunderwell Site (TTR). In a letter from the Nevada Division of Environmental Protection (NDEP) dated December 5, 2006, NDEP concurred with the request to reduce the frequency of post-closure inspections of CAUs at TTR to an annual frequency. This letter is included in Attachment B. Post-closure inspections were conducted on May 15-16, 2007. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in May 2007, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 453. Animal burrows observed during the annual inspection at CAU 453 were backfilled on August 1, 2007. At this time, the TTR post-closure site inspections should continue as

Flexible Visual Quality Inspection in Discrete Manufacturing

OpenAIRE

Petković, Tomislav; Jurić, Darko; Lončarić, Sven

2013-01-01

Most visual quality inspections in discrete manufacturing are composed of length, surface, angle or intensity measurements. Those are implemented as end-user configurable inspection tools that should not require an image processing expert to set up. Currently available software solutions providing such capability use a flowchart based programming environment, but do not fully address an inspection flowchart robustness and can require a redefinition of the flowchart if a small variation is int...

RSE-M: In-Service Inspection Rules for Mechanical Components of PWR Nuclear Islands