Revised standard addresses design requirements for computers used in nuclear power-plant safety systems

Author

Matras, John R.

Author_Institution

Science Applications International Corp., Las Vegas, NV, USA

Volume

26

Issue

5

fYear

1993

fDate

5/1/1993 12:00:00 AM

Firstpage

76

Lastpage

79

Abstract

The IEEE Nuclear Engineering Committee has standards that address hardware issues. The IEEE Computer Society has standards addressing software. The P-7-4.3.2, IEEE standard criteria for digital computers in safety systems of nuclear power generating stations, which brings together standards from both groups to address the integration of computer hardware and software with noncomputer hardware, is discussed. P-7-4.3.2 is being developed to show the interrelationship of software and hardware requirements as they apply throughout the development process. The influence of system design development on system quality, system qualification, and system integrity, are described.<>

Keywords

fission reactor safety; nuclear engineering computing; nuclear power stations; standards; IEEE Nuclear Engineering Committee; IEEE standard criteria; P-7-4.3.2; computers; design requirements; hardware requirements; nuclear power-plant safety systems; software; software requirements; standards; system design development; system integrity; system qualification; system quality; Computer aided manufacturing; Computer industry; Computer networks; Hardware; Manufacturing industries; Nuclear power generation; Power generation; Software safety; Software standards; Standards development;

fLanguage

English

Journal_Title

Computer

Publisher

ieee

ISSN

0018-9162

Type

jour

DOI

10.1109/2.211913

Filename

211913