Issues of verification and validation of application-specific integrated circuits in reactor trip systems
Concepts of using application-specific integrated circuits (ASICs) in nuclear reactor safety systems are evaluated. The motivation for this evaluation stems from the difficulty of proving that software-based protection systems are adequately reliable. Important issues concerning the reliability of computers and software are identified and used to evaluate features of ASICS. These concepts indicate that ASICs have several advantages over software for simple systems. The primary advantage of ASICs over software is that verification and validation (V V) of ASICs can be done with much higher confidence than can be done with software. A method of performing this V V on ASICS is being developed at Oak Ridge National Laboratory. The purpose of the method's being developed is to help eliminate design and fabrication errors. It will not solve problems with incorrect requirements or specifications.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6587350
- Report Number(s):
- CONF-930401-4; ON: DE93008567
- Country of Publication:
- United States
- Language:
- English
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Reactor protection system design using application specific integrated circuits
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Related Subjects
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
426000 -- Engineering-- Components
Electron Devices & Circuits-- (1990-)
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
ELECTRONIC CIRCUITS
ENGINEERED SAFETY SYSTEMS
EVALUATION
INTEGRATED CIRCUITS
MICROELECTRONIC CIRCUITS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
ON-LINE CONTROL SYSTEMS
ON-LINE SYSTEMS
POWER PLANTS
REACTOR PROTECTION SYSTEMS
RELIABILITY
THERMAL POWER PLANTS