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US-APWR HUMAN SYSTEM INTERFACE SYSTEM VERIFICATION VALIDATION PROGRAM FOR DIGITAL IC DESIGN

机译:用于数字化I&C设计的US-APWR人机界面系统验证和验证程序

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The US-APWR, currently under Design Certification review by the U.S. Nuclear Regulatory Commission, is a four loop evolutionary pressurized water reactor with a four train active safety system applied by Mitsubishi Heavy Industries. The digital Instrumentation and Control (I&C) System and Human Systems Interface (HSI) system are to be applied to the US-APWR. This design is currently being applied to the latest Japanese PWR plant and to nuclear power plant I&C modernization program in Japan. The US-APWR digital I&C and HSI system (HSIS) utilizes computerized systems, including computer-based procedures and alarm prioritization, relying principally on an HSIS with soft controls, console based visual display units (VDUs) and a large, heads up, overview display panel. Conventional hard-wired controls are limited to system level manual actions and a Diverse Actuation System (DAS). The overall design philosophy of the US-APWR is based on the concept that operator performance will be enhanced through the integration of safety and non-safety display and control systems in a robust digital environment. This philosophy is augmented, for diversity, by the application of independent safety soft displays and controls. In addition, non-digital diverse automatic and manual actuation system is introduced. As with all the advanced designs, the digital systems open as many questions as they answer. To address these new questions, for an eight week period during the months of July and August 2008, an extensive verification and validation (V&V) program was completed with the objective of assessing US operators' performance in this digital design environment. Over this time period, U.S. operating crews were subjected to exercise in Mitsubishi dynamic simulator. To follow up above mentioned V&V activities, additional test during the months of this spring in 2009 has been carried out to resolve human engineering discrepancies (HEDs) induced from the previous evaluation and the participants' comments and performance. Subjective and objective data were collected on each crew for each scenario and an extensive convergent measures analysis was performed, resulting in the identification of both specific design as well as generic conclusions. This paper discusses the digital HSIS of the US-APWR design, the V&V program data collection and analysis, and the study results related to the ongoing discussion of the impacts of digital systems on human performance, such as workload, navigation, situation awareness, operator training and licensing.
机译:US-APWR目前正在接受美国核监管委员会的设计认证审查,是由三菱重工应用的具有四列主动安全系统的四回路渐进式压水堆。数字仪器和控制(I&C)系统和人机界面(HSI)系统将应用于US-APWR。目前,该设计已应用于日本最新的压水堆电厂以及日本的核电厂I&C现代化计划。 US-APWR数字I&C和HSI系统(HSIS)利用包括基于计算机的程序和警报优先级在内的计算机化系统,主要依靠具有软控制,基于控制台的可视显示单元(VDU)和大型抬头,概述的HSIS显示屏。常规的硬接线控件仅限于系统级手动操作和多样化执行系统(DAS)。 US-APWR的总体设计理念基于这样的概念,即在健壮的数字环境中,通过集成安全和非安全显示和控制系统,可以提高操作员的性能。为了实现多样性,通过独立安全的软性显示器和控件的应用增强了这一理念。另外,引入了非数字多样的自动和手动致动系统。与所有高级设计一样,数字系统会回答许多问题。为了解决这些新问题,在2008年7月和2008年8月的八周时间内,完成了一项广泛的验证与确认(V&V)计划,目的是评估美国运营商在此数字设计环境中的性能。在此期间,美国操作人员在三菱动态模拟器中进行了锻炼。为了跟进上述V&V活动,2009年春季在几个月内进行了额外的测试,以解决由先前的评估以及参与者的评论和表现引起的人体工程学差异(HED)。针对每种情况,收集了每个机组人员的主观和客观数据,并进行了广泛的收敛性分析,从而确定了具体设计和一般性结论。本文讨论了US-APWR设计的数字HSIS,V&V程序数据的收集和分析,以及与正在进行的有关数字系统对人类绩效影响的讨论有关的研究结果,例如工作量,导航,态势感知,操作员培训和许可。

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