A logic generator and validator

Journal Article · Wed May 01 04:00:00 EDT 1985 · Nucl. Sci. Eng.; (United States)

OSTI ID:5122325

Szabo, J; Cain, D G; Okrent, D

The on-line monitoring of a power plant (or any process plant) has three primary functions: data acquisition, data analysis, and data presentation. Relative to the second of these functions, advanced methods for generating reliable data analysis computer codes are presented. The results are illustrated for a safety parameter display system that provides operators with a computer-graphic summary of a nuclear power plant's safety status. In the conventional method of analysis code production, the systems analyst or designer generates rules by which the plant status is being evaluated, while the transcription of those rules to a computer code is done separately by a programmer. Subsequently, the analysis code produced by the programmer must be validated against the specifications prepared by the systems analyst. A logic generator and logic validator are presented to streamline these processes. The logic generator acquires the relevant specifications through a systematic dialogue with the designer and then translates them automatically into an efficient computer logic code, thus solvin the problem of a designer who is not a programmer interfacing with a programmer who is not a designer. The logic generator enhances code reliability in two ways. First, it encourages the systems analyst to produce more reliable and relevant specifications because of the logical structured order in which the interactive session is being conducted. Second, because of the mass production mode b which the logic codes are being generated, proving once the correctness of the code production process ensures the accuracy of all codes to be generated in the future. In the postproduction stage, a logic validator enhances code reliability by displaying a structura overview of the data analysis code, allowing the user an additional opportunity for code evaluation.

• Research Organization: University of California, Los Angeles Mechanical, Aerospace and Nuclear Engineering Department, Los Angeles, California
• OSTI ID: 5122325
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 90:1; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
COMPUTER GRAPHICS
COMPUTERIZED SIMULATION
DATA ACQUISITION
DATA ANALYSIS
ELECTRONIC CIRCUITS
ENGINEERED SAFETY SYSTEMS
LOGIC CIRCUITS
MACHINE TRANSLATIONS
PERSONNEL
POWER REACTORS
PROGRAMMING
REACTOR MONITORING SYSTEMS
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SIMULATION
SYSTEMS ANALYSIS