Development of tools for safety analysis of control software in advanced reactors
Creators
- 1. Advanced Systems Concepts Associates, El Segundo, CA (United States)
Description
Software based control systems have gained a pervasive presence in a wide variety of applications, including nuclear power plant control and protection systems which are within the oversight and licensing responsibility of the US Nuclear Regulatory Commission. While the cost effectiveness and flexibility of software based plant process control is widely recognized, it is very difficult to achieve and prove high levels of demonstrated dependability and safety assurance for the functions performed by process control software, due to the very flexibility and potential complexity of the software itself. The development of tools to model, analyze and test software design and implementations in the context of the system that the software is designed to control can greatly assist the task of providing higher levels of assurance than those obtainable by software testing alone. This report presents and discusses the development of the Dynamic Flowgraph Methodology (DFM) and its application in the dependability and assurance analysis of software-based control systems. The features of the methodology and full-scale examples of application to both generic process and nuclear power plant control systems are presented and discussed in detail. The features of a workstation software tool developed to assist users in the application of DFM are also described
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI96010063; NTIS; GPO.Files
27059935.pdf
Files
(3.3 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 116 p.
- Report number
- NUREG/CR--6465
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27059935
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CANDU TYPE REACTORS; CE STANDARD REACTOR; COMPUTER CODES; COMPUTERIZED CONTROL SYSTEMS; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR PROTECTION SYSTEMS; SAFETY ANALYSIS; TESTING
- Descriptors DEC
- CONTROL SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).