Perspectives on Validating Complex Human-Machine System Performance

2002 ◽  
Vol 46 (23) ◽  
pp. 1876-1877
Author(s):  
John M. O'Hara
Keyword(s):  
System Performance ◽  
Nuclear Power ◽  
Power Plants ◽  
Integrated System ◽  
Civil Aviation ◽  
Medical Systems ◽  
Commercial Aircraft ◽  
Actual Operation ◽  
Software And Hardware ◽  
Economic Considerations

The performance of complex systems, such as power plants and commercial aircraft, is based on the integration of human, software, and hardware elements. They are designed to operate safely under normal and disturbance conditions. Ideally one would validate that safety and productivity goals can be achieved prior to actual operation. While some types of systems can be tested in actual operational environments, validation is especially difficult when safety or economic considerations preclude testing the types of disturbance conditions that the integrated system is designed to handle. Thus the conceptual and methodological challenges to validating such systems are significant and new approaches are emerging. The papers in this symposium will describe approaches taken to validation using examples from commercial nuclear power, civil aviation, military, and medical systems.

FEM Analysis of Impact Tests for Steel Plate Concrete Panels against Scaled-Aircraft Impact

2013 ◽  
Vol 477-478 ◽  
pp. 777-783
Author(s):  
Xiu Yun Zhu ◽  
Rong Pan ◽  
Feng Sun
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Steel Plate ◽  
Experimental Result ◽  
Commercial Aircraft ◽  
Concrete Wall ◽  
Concrete Panels ◽  
Aircraft Model ◽  
The Impact ◽  
Aircraft Crash

Due to the rear-face steel plate of the steel plate concrete wall (SC) is very effective in preventing the perforation and scabbing of concrete, in order to resist the impact of commercial aircraft crash, steel plate concrete structures are usually used in the design of external walls of nuclear power plants. In this paper, the simulation analysis of the impact test of 1/7.5 scaled aircraft model impacting the steel plated concrete panels is carried out by using finite element code ANSYS/LS-DYNA. The Winfrith material model (*MAT_84) in ANSYS/LS-DYNA is used to simulate the concrete. The damage profile of panels and residual velocity of aircraft engine comparisons between the simulations and tests are presented in this paper. The results indicate that the damage modes from the impact simulations are very good agreement with the experimental result. It is verified that not only the selection of the material parameters needed for the steel plated concrete wall and aircraft model but also the entire analysis method was appropriate and effective. This paper provided the effective methodology for simulation of the response of the steel plated concrete structure of nuclear power plant due to commercial aircraft crash impact.

Hardness Prediction for Temper Bead Welding of Non-Consistent Layer Technique

2014 ◽  
Vol 783-786 ◽  
pp. 2851-2856
Author(s):  
Li Na Yu ◽  
Kazuyoshi Saida ◽  
Masahito Mochizuki ◽  
Masashi Kameyama ◽  
Takehiko Sera ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Large Scale ◽  
Repair Process ◽  
Heat Affect Zone ◽  
Thermal Cycles ◽  
The Neural Network ◽  
Actual Operation ◽  
Hardness Prediction ◽  
Controlled Deposition

Temper bead welding (TBW) is one effective repair welding method for the large-scale nuclear power plants. Consistent Layer (CSL) technique is the theoretically most authoritative method among the five temper bead welding techniques. However in the actual operation, CSL technique is difficult to perform, and non-CSL techniques (Controlled Deposition technique, Half Bead technique, et al) are mainly used in the actual repair process. The thermal cycles in heat affect zone (HAZ) of non-CSL technique are more complicated than that of CSL techniques. Through simplifying the complicated thermal cycles to 4 types of thermal cycles, the neural network-based hardness prediction system for non-CSL techniques has been constructed. The hardness distribution in HAZ of non-CSL techniques was calculated based on the thermal cycles numerically obtained by finite element method (FEM). The predicted hardness was in good accordance with the experimental results. It follows that the thermal cycle simplification methods are effective for estimating the tempering effect during temper bead welding of non-CSL techniques.

DEVELOPMENT OF A DISTRIBUTED INFORMATION AND COMPUTING CONTROL SYSTEM FOR THE NUCLEAR UNIT AT NOVOVORONEZH NPP

2022 ◽  
pp. 20-27
Author(s):  
Д.С. Синюков ◽  
А.Д. Данилов ◽  
А.А. Самодеенко ◽  
А.А. Иванников
Keyword(s):  
Information System ◽  
Service Life ◽  
Nuclear Power ◽  
Power Plants ◽  
Complex Function ◽  
Computing System ◽  
Software Tools ◽  
Distributed Information ◽  
Hardware Complex ◽  
Software And Hardware

Ядерные блоки атомных электростанций имеют длительный срок эксплуатации, что приводит к ситуации, когда в процессе эксплуатации технические и программные средства систем управления перестают отвечать текущим современным требованиям в плане надежности и безопасности их использования. В результате для продления срока действия ядерного блока требуется обязательное проведение модернизации информационно-вычислительной системы (ИВС) управления. Приводятся результаты такой работы, проведенной на 4 блоке Нововоронежской АЭС. При выборе оборудования для создания новой ИВС модернизируемого энергоблока был реализован принцип унификации. Программное обеспечение всех компонентов программно-технического комплекса ИВС, включая функции систем предоставления параметров безопасности и внутриреакторного контроля, реализовано на единых программных средствах. Представленные значения параметров сигналов на всех рабочих станциях программно-технического комплекса информационной системы, интерфейсы взаимодействия, человеко-машинный интерфейс и навигация по видеокадрам идентичны, что учитывает требования по оптимальному взаимодействию системы «человек-машина». Система удовлетворяет требованиям по обеспечению надёжности на основе резервирования, независимости, разнообразия, с учётом отказов по общей причине. Для этого ИВС была реализована в виде двухканальной информационной системы. Основной и дублирующий каналы измерения и обработки данных в программно-техническом комплексе ИВС функционируют одновременно в полном объеме. Разработанная информационно-вычислительная система позволила продлить срок эксплуатации 4 энергоблока Нововоронежской АЭС на 15 лет Nuclear units of nuclear power plants have a long service life, which leads to a situation when, during the operation, the technical and software tools of control systems no longer meet the current modern requirements in terms of reliability and safety of their use. As a result, in order to extend the validity period of the nuclear unit, mandatory modernization of the information and computing system (ICS) of management is required. This article presents the results of such work carried out at Unit 4 of the Novovoronezh NPP. When choosing the equipment to create a new ICS of the upgraded power unit, we implemented the principle of unification. The software of all components of the ICS software and hardware complex, including the functions of systems for providing security parameters and in-reactor control, is implemented on unified software tools. The representation of signal parameter values at all workstations of the software and hardware complex of the information system, the interfaces of human-machine interface interaction and navigation through video frames are identical, which takes into account the requirements for optimal interaction of the man-machine system. The system meets the requirements for ensuring reliability based on redundancy, independence, diversity, taking into account failures for a common reason. For this purpose, we implemented the ICS in the form of a two-channel information system. The main and backup channels of measurement and data processing in the ICS software and hardware complex function simultaneously in full. The developed information and computing system made it possible to extend the service life of 4 power units of the Novovoronezh NPP for 15 years

Human Factors Verification and Validation: Tecnatom’s Experience

2008 ◽  
Author(s):  
Pedro Trueba Alonso ◽  
Lui´s Ferna´ndez Illobre ◽  
Alfonso Jime´nez Ferna´ndez-Sesma ◽  
Fernando Ortega Pascual
Keyword(s):  
Human Factors ◽  
Nuclear Power ◽  
Power Plants ◽  
Integrated System ◽  
Verification And Validation ◽  
Regulatory Body ◽  
Human Factors Engineering ◽  
Human Engineering ◽  
Task Support ◽  
Methodological Aspects

Tecnatom has been performing Human Factors Engineering Verification and Validation (HFE V&V) from the mid-eighties. This activity started as one of the various activities of the post TMI requirements followed also in Spain: performing detailed Control Room Design Reviews (DCRDRs). All the existing Spanish Nuclear Power Plants (NPPs) were reviewed to identify Human Engineering Discrepancies (HEDs). DCRDRs were completed by the mid-nineties, and the following V&V activities have been related to new designs and plant modifications as part of the activities described in the Human Factors Program Review Model (HFE PRM), included in NUREG-0711 since 1994. The NRC recommends following the HFE PRM or an acceptable alternative method in the case of the HFE activities and the Spanish Regulatory Body (CSN) recommend the same approach for new designs, design modifications and even for conventional plants. The activities embedded in a HFE V&V process are Task Support Verification (TSV), HFE Design Verification (HFE DV) using NUREG-0700 HFE Guidelines, and Integrated System Validation (ISV), with the execution of performance based tests, mainly in simulator facilities. This paper describes some of the experience of Tecnatom during the past years regarding the execution of these V&V activities previously mentioned, and in relation to the applicability and methodological aspects of each of these activities. Methodological aspects regarding TSV are related to its execution when there is a no Task Analysis to use. Methodological aspects regarding the HFE DV are related to the type of HSI to verify (small or large), its development status (paper design or implemented), the selection and translation of applicable HFE guidelines, and the HED preparation. Methodological aspects regarding the ISV are related to the necessary crews, training, number of scenarios, issues to test, data collection and performance measures. The experience is mainly related to Tecnatom’s work is Spanish NPP like Jose´ Cabrera, Almaraz and Vandello´s and in the case of foreign plants Beznau and an advanced NPP in Taiwan amongst others.

Optimization Design Based on Human Factors V&V of Human System Interfaces in Nuclear Power Plant

2017 ◽  
Author(s):  
Ming Xiaoyang ◽  
Deng Shiguang ◽  
Jiang Xingwei
Keyword(s):  
Human Factors ◽  
Nuclear Power ◽  
Optimization Design ◽  
Power Plants ◽  
Integrated System ◽  
Intellectual Property Right ◽  
Control Room ◽  
Human System ◽  
Task Support ◽  
System Interfaces

The main control room, the monitor and control center of nuclear plant, integrates quantities of Human System Interfaces (HSIs), with which, the operators maintain the plant running safely and effectively under different working conditions[1]. Human Factors Verification and Validation (HF V&V) is one of the twelve elements of a Human Factor Engineering (HFE) program according to NUREG-0711. Research on V&V methods has been carried out for years, however, the V&V implementation in domestic nuclear power plants looks forward to being consummated. For HPR1000, the third generation of nuclear power technology with China’s self-owned independent intellectual property right[2], HF V&V activities include HSI HFE Design Verification (DV), HSI Task Support Verification (TSV), Partial Validation (PV), Integrated System Validation (ISV) and Human Engineering Discrepancy (HED) management. The V&V methods introduced in this paper gives an executable and effective way to evaluate whether the design conforms to HFE design principles and that the adequacy of the HSIs enable plant personnel to successfully perform their tasks and other operational goals, assuring plant safety. With these methods, plenty of suggestions based on the HEDs generated from different V&V activities are applied into the design of HSIs, and afterwards, an optimization for the main control room of HPR1000 will be achieved.

Human Factors Engineering Verification and Validation: A Case Study of a Nuclear Power Plant

2010 ◽  
Author(s):  
Fei Song ◽  
Shuhui Zhang
Keyword(s):  
Human Factors ◽  
Nuclear Power ◽  
Power Plants ◽  
Integrated System ◽  
Nuclear Industry ◽  
Verification And Validation ◽  
Human Factors Engineering ◽  
Design Guideline ◽  
Task Support ◽  
System Verification

Main control room in nuclear power plants (NPP) is a complex system where operators interact with a large amount of human system interface (HSI) resources, which is essential to the safety of the plant. In order to achieve a high standard of human factors engineering (HFE) level and ensure the effectiveness and efficiency of the system, verification and validation (V&V) should be performed before the delivery of the plant. This study firstly represents an overview of the HFE project and V&V activities applied in the nuclear industry and relative researches, then, a V&V program from an ongoing 300MW NPP project is discussed in detail. Comparative methods, existing system vs. design requirements, are mainly applied for the verification phase. In the HFE Design Verification, 10 different HFE design guideline sets and corresponding checklists are developed for the experienced reviewers to conduct a thoroughness and consistency review. Critical safety functions, risk important tasks, critical human actions and other necessary operations are verified in the Task Support Verification to insure that HSI provides all required resources for personnel tasks. Other than direct comparison, a development platform is also used to assist the analysis of display, alarm and other appropriate features. In the validation phase, an integrated system test would be completed on a full scope simulator with the participation of experienced operators from the utility as subjects and multi-discipline observers. Scenarios are carefully designed to ensure the representative of the test. Both objective and subjective results would be collected and processed mainly by the descriptive statistics method to find out the problems in the existing design. All the discrepancies found in the whole V&V would be involved in a specific database and tracked until resolved. Lessons learned from this case are discussed.

An Integrated Approach to Human System Interface Design in New Nuclear Power Plants

2009 ◽  
Author(s):  
Jose´ Manuel Viguera ◽  
Alfonso Jime´nez ◽  
Juan Antonio Burillo
Keyword(s):  
System Performance ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Human Factor ◽  
Integrated Approach ◽  
Careful Consideration ◽  
Final Decision ◽  
Human System ◽  
Human Factor Engineering

Nuclear power plants design is moving toward a wider use of digital computers, especially microprocessors, in information and control systems. The amount of automation and the role of the operator are under discussion in many countries. The view of the operator’s role presently varies. The main opinions can be summarized as follows: 1. Move toward a high degree of automation, fostering the machine role. 2. Use of computer-generated procedures providing information to skilled operators for them to make the final decision. 3. Use of digital systems to help the operator identify problems, decide on the appropriate corrective actions and aid in the execution of those actions. Tecnatom, S.A. has developed an integrated Human Factor Engineering (HFE) methodology, based on international regulations and experience obtained from several national and international projects, combining technology, organization and human elements to generate a Human-Centered Design. Human Factor Engineering (HFE) is the application of the knowledge of human capabilities and characteristics to develop equipment, facilities and systems. With the application of this knowledge, human performance, and therefore system performance, can be dramatically improved. Man/machine systems designed with the human as a key element are inherently safer and more reliable than those that are not. Until recently, design of these human-equipment interfaces has been secondary to “pure hardware” design; that is, equipment and facilities were designed without formal consideration of the implications for operators. Our approach is to systematically apply an HFE methodology that will produce: a) Human-System Interfaces that are easy, friendly to and consistent for the operators. b) Simulator-Assisted Engineering platforms for validation activities in the logic, control and human-system interface areas. c) Training Programs based on the systematic analysis of job and task requirements. d) Procedures derived from the same design process and analyses as the Human-System Interface and Training. Application of good HFE methodology during system development, implementation and operation is, from our point of view, vital for optimal system performance regarding operation activities. “A disciplined approach to HFE helps ensure that humans are considered integral system components, requiring careful consideration of how they will interact with their equipment.”

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