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Software reliability and safety in nuclear reactor protection systems

Description: Planning the development, use and regulation of computer systems in nuclear reactor protection systems in such a way as to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Computer Safety and Reliability Group, Lawrence Livermore that investigates different aspects of computer software in reactor National Laboratory, that investigates different aspects of computer software in reactor protection systems. There are two central themes in the rep… more
Date: November 1, 1993
Creator: Lawrence, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluating software for safety systems in nuclear power plants

Description: In 1991, LLNL was asked by the NRC to provide technical assistance in various aspects of computer technology that apply to computer-based reactor protection systems. This has involved the review of safety aspects of new reactor designs and the provision of technical advice on the use of computer technology in systems important to reactor safety. The latter includes determining and documenting state-of-the-art subjects that require regulatory involvement by the NRC because of their importance in… more
Date: January 11, 1994
Creator: Lawrence, J. D.; Persons, W. L.; Preckshot, G. G. & Gallagher, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear plant-aging research on reactor protection systems

Description: This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show th… more
Date: January 1, 1988
Creator: Meyer, L.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Defense against common mode failures in protection system design

Description: The introduction of digital instrumentation and control into reactor safety systems creates a heightened concern about common-mode failure. This paper discusses the concern and methods to cope with the concern. Common-mode failures have been a ``fact-of-life`` in existing systems. The informal introduction of defense-in-depth and diversity (D-in-D&D)-coupled with the fact that hardware common-mode failures are often distributed in time-has allowed systems to deal with past common-mode failures.… more
Date: August 27, 1997
Creator: Wyman, R. H. & Johnson, G. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Multichannel analog temperature sensing system

Description: A multichannel system that protects the numerous and costly water-cooled magnet coils on the translation section of the FRX-C/T magnetic fusion experiment is described. The system comprises a thermistor for each coil, a constant current circuit for each thermistor, and a multichannel analog-to-digital converter interfaced to the computer.
Date: August 1, 1985
Creator: Gribble, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fort St. Vrain experience report

Description: This report describes the core region constraint devices (RCDs) which will be installed in Fort St. Vrain to remedy core temperature fluctuations at high power-to-flow thresholds, summarizes the engineering analyses supporting the design, and evaluates effects on fuel handling operations. (DLC)
Date: June 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance requirements of the advanced neutron source reactor protection system

Description: Research reactors often have protection-systems performance requirements very different from those of commercial reactors. This paper discusses the special characteristics of the Advanced Neutron Source (ANS) reactor that control these requirements, and it presents some calculations used to quantify this performance.
Date: April 1, 1995
Creator: March-Leuba, J. & Battle, R.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Security monitoring subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: Security Monitoring acquires and processes sensor data for use by security personnel in the performance of their function. Security Monitoring is designed and implemented as a part of an overall security plan which is classified as Safeguards Information under 10CFR73.21.
Date: June 1, 1986
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fire detection and alarm subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: Fire Detection and Alarm is an early warning system used to detect and report the presence of a fire within the plant. It detects, annunciates, and records plant-wide fire alarms, subsystem trouble, and fire console operator actions.
Date: June 1, 1986
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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