This document briefly describes the elements of the Nuclear Regulatory Commission`s (NRC`s) software quality assurance program leading to software (code) qualification and identifies a test matrix for qualifying Transient Reactor Analysis Code (TRAC)-Pressurized Water Reactor Version (-P), or TRAC-P, to the NRC`s software quality assurance requirements. Code qualification is the outcome of several software life-cycle activities, specifically, (1) Requirements Definition, (2) Design, (3) Implementation, and (4) Qualification Testing. The major objective of this document is to define the TRAC-P Qualification Testing effort
The Transient Reactor Analysis Code (TRAC)-M system-wide and component data structures are to be rei...
Executive Summary Objectives It is widely accepted that the assessment of software cannot be l...
This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instru...
This report describes 15 different test problems in the TRAC-P (Transient Reactor Analysis Code) sta...
With the resurgence of nuclear power and increased interest in advanced nuclear reactors as an optio...
Abstract: Software qualification includes such activities as a software Verification and Validation...
The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk manag...
This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) t...
The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory ...
The Westinghouse AP600 reactor is an advanced pressurized water reactor with passive safety systems ...
The Computer Code Validation Matrix (CCVM) dealing with Separate Effect Test Facility (SETF) experim...
The Transient Reactor Analysis Code (TRAC) being developed at Los Alamos National Laboratory provide...
The work documented in this report was performed in support of the US Nuclear Regulatory Commission ...
The results obtained in a more-than-a-decade application of thermal-hydraulic system codes to the an...
The modern NPPs (Nuclear Power Plants) are the part of the very complex and demanding sector of indu...
The Transient Reactor Analysis Code (TRAC)-M system-wide and component data structures are to be rei...
Executive Summary Objectives It is widely accepted that the assessment of software cannot be l...
This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instru...
This report describes 15 different test problems in the TRAC-P (Transient Reactor Analysis Code) sta...
With the resurgence of nuclear power and increased interest in advanced nuclear reactors as an optio...
Abstract: Software qualification includes such activities as a software Verification and Validation...
The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk manag...
This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) t...
The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory ...
The Westinghouse AP600 reactor is an advanced pressurized water reactor with passive safety systems ...
The Computer Code Validation Matrix (CCVM) dealing with Separate Effect Test Facility (SETF) experim...
The Transient Reactor Analysis Code (TRAC) being developed at Los Alamos National Laboratory provide...
The work documented in this report was performed in support of the US Nuclear Regulatory Commission ...
The results obtained in a more-than-a-decade application of thermal-hydraulic system codes to the an...
The modern NPPs (Nuclear Power Plants) are the part of the very complex and demanding sector of indu...
The Transient Reactor Analysis Code (TRAC)-M system-wide and component data structures are to be rei...
Executive Summary Objectives It is widely accepted that the assessment of software cannot be l...
This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instru...