Development of an advanced human–machine interface for next generation nuclear power plants

Chang, Soon Heung; Choi, Seong Soo; Park, Jin Kyun; Heo, Gyunyoung; Kim, Han Gon

doi:10.1016/s0951-8320(98)00073-8

Cited by 30 publications

(8 citation statements)

References 10 publications

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“…Since the early seventies of the last century, more than 80 different SRATs have been developed to attempt to estimate and predict software reliability; these techniques roughly correspond to software development lifecycle phases [19]: early prediction models, software reliability growth models, input-domain-based models, architecture-based models, hybrid black-box models, and hybrid white-box models. Particularly reliability growth models have been widely accepted and used in the practice and continue to be recommended by several industrial standards [12] [13].…”

Section: Software Reliability Assessment Techniquesmentioning

confidence: 99%

Event-Based GUI Testing and Reliability Assessment Techniques -- An Experimental Insight and Preliminary Results

Belli

Beyazit

Güler

2011

2011 IEEE Fourth International Conference on Software Testing, Verification and Validation Workshops

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Abstract-It is widely accepted that graphical user interfaces (GUIs) highly affect-positive or negative-the quality and reliability of human-machine systems. In spite of this fact, quantitative assessment of the reliability of GUIs is a relatively young research field. Existing software reliability assessment techniques attempt to statistically describe the software testing process and to determine and thus predict the reliability of the system under consideration (SUC). These techniques model the reliability of the SUC based on particular assumptions and preconditions on probability distribution of cumulative number of failures, failure data observed, and form of the failure intensity function, etc. We expect that the methods used for modeling a GUI and related frameworks used for testing it also affect the factors mentioned above, especially failure data to be observed and prerequisites to be met. Thus, the quality of the reliability assessment process, and ultimately also the reliability of the GUI, depends on the methods used for modeling and testing the SUC. This paper attempts to gain some experimental insight into this problem. GUI testing frameworks based on event sequence graphs and event flow graphs were chosen as examples. A case study drawn from a large commercial webbased system is used to carry out the experiments and discuss the results.

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Section: Software Reliability Assessment Techniquesmentioning

confidence: 99%

Event-Based GUI Testing and Reliability Assessment Techniques -- An Experimental Insight and Preliminary Results

Belli

Beyazit

Güler

2011

2011 IEEE Fourth International Conference on Software Testing, Verification and Validation Workshops

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show abstract

“…Interface detailed design is domain specific. In nuclear power plants, for example, there are CAD/MCNP interface program prototype (Sato, Lida, & Nishitani, 2006), RFX interface (which is used by one of the largest nuclear fusion experiments of the coordinated nuclear fusion experiment program of the European Community), and an advanced human-machine interface for next generation nuclear power plants (Chang, Choi, Park, Heo, & Kim, 1999).…”

Section: Introductionmentioning

confidence: 99%

An Experimental Study on Three General Interface Layout Designs for Chemical Process Plants

Liu

Lin

Teng

et al. 2014

Hum Ftrs & Erg Mfg Svc

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The human‐machine interface design is not a new problem; however, existing knowledge appears to be focused either on interface conceptual design, which determines what information at what time needs to be displayed, or on interface detailed design, which determines the form of display elements. This article presents a study on interface layout design. Three interface layout designs were proposed based on the proximity compatibility priniciple, which were on the same interface conceptual design. In particular, the first interface layout design is with the highest degree of proximity cognition and the second and third with a reduced degree of proximity cognition. They are called sophisticated, semisophisticated, and nonsophisticated interfaces, respectively. An experiment with a simple process plant was conducted to understand user behaviors on the three interfaces. It is noted that in order to provide an unbiased comparative evaluation of these interfaces the same application problem and similar look‐and‐feel forms of interfaces were designed. In the experiment, three general classes of tasks were considered, namely, normal control operation, fault detection (or monitoring), and fault diagnosis. Two categories of measures were used: the performance measure and the subjective measure. The major results obtained from the experiment are 1) the nonsophisticated interface is the best for fault detections in terms of performance measure; besides, this interface has the lowest mental workload for fault detection; 2) the sophisticated interface is the best for normal operation in terms of performance measure; 3) there appears no significant difference for fault diagnosis in terms of performance measures for all these three interfaces; 4) for normal operation and fault diagnosis, the mental workloads for the three interfaces have no significant difference. Overall, the experiment suggests that the nonsophisticated interface be used in practice with additional two reasons: 1) most of time in the chemical process plant today is the fault detection or operation monitoring task, and 2) it is relatively easier for the nonsophisticated interface to adapt to changes in the chemical process plant design, which are common in today's manufacturing environments.

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“…Recently, there has been prompt research in developing computer-based systems, including human-system interfaces in the main control rooms of nuclear power plants (NPPs) [1,2]. O'Hara et al introduced the characteristics of computer-based systems, which can integrate various types of information into a legible interface and present them to an individual [3].…”

Section: Introductionmentioning

confidence: 99%

Empirical investigation of communication characteristics under a computer-based procedure in an advanced control room

Kim¹,

Kim²,

Jang³

et al. 2012

Journal of Nuclear Science and Technology

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With the development of computer-based control rooms including a computer-based procedure (CBP), shift supervisors (SSs) can directly access plant information through a CBP or personal displays instead of depending on other board operators (BOs) to obtain plant information. In relation to this change, we examined the characteristics of SS inquiry patterns in the computer-based control rooms of nuclear power plants during emergency situations. Operator behaviors and speech patterns were observed and analyzed through several experiments on simulated accident scenarios in a full-scope simulator for an advanced computer-based main control room. We found that the SS inquiry in the advanced control room had less dependency on the BOs, and that the inquiry patterns varied according to the operators and operating dates. From these findings, the necessity to establish communication standards under computer-based control rooms was discussed with some recommendations. Another requirement to reduce the cognitive workload of SSs was also discussed.Keywords: crew communication; computer-based control room; computer-based procedure; human error IntroductionRecently, there has been prompt research in developing computer-based systems, including human-system interfaces in the main control rooms of nuclear power plants (NPPs) [1,2]. O'Hara et al. introduced the characteristics of computer-based systems, which can integrate various types of information into a legible interface and present them to an individual [3]. For example, a computer-based procedure (CBP) allows operators to easily search or identify parameters or states of plants by presenting the relevant parameters in a given procedure. Because of this function of the CBP, an operator can operate power plants by simply following up the CBP rather than finding the parameters from instruments or indicators.On the other hand, the introduction of a CBP can influence the behaviors of the operating crew conducting the required operations based on the operating procedures. During emergency situations in a conventional main control room, a shift supervisor (SS) generally proceeds with emergency operation procedures (EOPs) and requests information from board operators (BOs) to obtain information relevant to the current plant states [4]. The SS also controls the plants

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Development of an advanced human–machine interface for next generation nuclear power plants

Cited by 30 publications

References 10 publications

Event-Based GUI Testing and Reliability Assessment Techniques -- An Experimental Insight and Preliminary Results

Event-Based GUI Testing and Reliability Assessment Techniques -- An Experimental Insight and Preliminary Results

An Experimental Study on Three General Interface Layout Designs for Chemical Process Plants

Empirical investigation of communication characteristics under a computer-based procedure in an advanced control room

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