US-APWR人机系统接口系统验证和确认

K. Mashio, S. Hanada, Koichi Takahashi
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引用次数: 1

摘要

US-APWR目前正在接受美国核管理委员会的设计认证审查,是一个四回路渐进式压水反应堆,由三菱重工采用四列主动安全系统。数字仪表和控制(I&C)系统和人类系统接口(HSI)系统将应用于US-APWR。这种设计目前正在应用于日本最新的压水堆电厂和日本核电站的I&C现代化计划。US-APWR数字I&C和HSI系统(HSIS)利用计算机系统,包括基于计算机的程序和报警优先级,主要依靠具有软控制的HSIS,基于控制台的视觉显示单元(vdu)和大型平视总览显示面板。传统的硬连线控制仅限于系统级手动操作和多种驱动系统(DAS)。US-APWR的整体设计理念是通过在强大的数字环境中集成安全和非安全显示和控制系统来提高操作员的性能。这一理念是增强,多样性,通过应用独立的安全软显示和控制。此外,还介绍了非数字化的多种自动和手动驱动系统。与所有先进的设计一样,数字系统带来的问题和它们回答的问题一样多。为了解决这些新问题,在2008年7月和8月为期8周的时间里,完成了一项广泛的验证和确认(V&V)计划,目的是评估美国运营商在数字设计环境中的表现。(Robert E. Hall et al., 2008,“US-APWR人机系统接口系统V&V结果:对数字I&C设计的影响”,第17届国际核工程会议,ICONE17-75176)[1]在此期间,美国操作人员接受了三菱动态模拟器的训练。为了跟进上述V&V活动,在2009年春季进行了额外的测试,以解决由先前评估和参与者的评论和表现引起的人体工程差异(HEDs)。针对每种情况收集了每个船员的主观和客观数据,并进行了广泛的收敛措施分析,从而确定了特定设计和通用结论。本文讨论了US-APWR设计的数字HSIS、V&V项目数据收集和分析,以及与正在进行的数字系统对人的性能(如工作量、导航、态势感知、操作员培训和许可)的影响相关的研究结果。ASME版权所有©2010
本文章由计算机程序翻译,如有差异,请以英文原文为准。
US-APWR Human System Interface System Verification and Validation
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. (Robert E. Hall et al., 2008, “US-APWR Human Systems Interface System V&V Results: Impact on Digital I&C Design”, 17th International Conference on Nuclear Engineering, ICONE17-75176) [1] 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.Copyright © 2010 by ASME
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