You need JavaScript to view this

Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

Abstract

This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs.
Authors:
"NONE"
Publication Date:
Jun 01, 1994
Product Type:
Technical Report
Report Number:
CAN/CSA-N286.7-94
Reference Number:
SCA: 990200; PA: AIX-27:032691; EDB-96:076211; NTS-96:017465; SN: 96001579036
Resource Relation:
Other Information: PBD: Jun 1994
Subject:
99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; ENGINEERED SAFETY SYSTEMS; COMPUTER CODES; QUALITY ASSURANCE; ANALYTICAL SOLUTION; CANADA; DESIGN; NUCLEAR POWER PLANTS; SAFETY STANDARDS; STANDARDS DOCUMENT
OSTI ID:
217780
Research Organizations:
Canadian Standards Association, Rexdale, ON (Canada)
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 0317-7874; Other: ON: DE96621277; TRN: CA9600029032691
Availability:
INIS; OSTI as DE96621277
Submitting Site:
INIS
Size:
41 p.
Announcement Date:

Citation Formats

Quality assurance of analytical, scientific, and design computer programs for nuclear power plants. Canada: N. p., 1994. Web.
Quality assurance of analytical, scientific, and design computer programs for nuclear power plants. Canada.
1994. "Quality assurance of analytical, scientific, and design computer programs for nuclear power plants." Canada.
@misc{etde_217780,
title = {Quality assurance of analytical, scientific, and design computer programs for nuclear power plants}
abstractNote = {This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs.}
place = {Canada}
year = {1994}
month = {Jun}
}