Executive Summary Objectives It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, ie the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An undesirable consequence of this situation is that the licensing approaches taken by nuclear safety authorities and by technical support organisations are determined independently with only limited informal technical co-ordination and information exchange. It is notable that several software implementations of nuclear s...
The work documented in this report was performed in support of the US Nuclear Regulatory Commission ...
In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-...
International audienceThe typology of the risks met in nuclear fuel cycle facilities is quite differ...
Foreword This consensus document has been revised and improved by the Regulator Task Force on Saf...
In the nuclear domain, regulators have strict requirements for safety critical software. In this pap...
In the nuclear domain, regulators have strict requirements for safety critical software. In this pap...
In the nuclear domain, regulators have strict requirements for safety-critical software. As a part o...
In the nuclear domain, regulators have strict requirements for safety-critical software. As a part o...
Key aspects and perspectives in Nuclear reactor Safety Technology (NST) are discussed in the paper. ...
Abstract: Software qualification includes such activities as a software Verification and Validation...
Key aspects and perspectives in Nuclear reactor Safety Technology (NST) are discussed in the paper. ...
Key aspects and perspectives in Nuclear reactor Safety Technology (NST) are discussed in the paper. ...
Designing and licensing a nuclear power plant and qualification of its subsystems and components is ...
Designing and licensing a nuclear power plant and qualification of its subsystems and components is ...
This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instru...
The work documented in this report was performed in support of the US Nuclear Regulatory Commission ...
In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-...
International audienceThe typology of the risks met in nuclear fuel cycle facilities is quite differ...
Foreword This consensus document has been revised and improved by the Regulator Task Force on Saf...
In the nuclear domain, regulators have strict requirements for safety critical software. In this pap...
In the nuclear domain, regulators have strict requirements for safety critical software. In this pap...
In the nuclear domain, regulators have strict requirements for safety-critical software. As a part o...
In the nuclear domain, regulators have strict requirements for safety-critical software. As a part o...
Key aspects and perspectives in Nuclear reactor Safety Technology (NST) are discussed in the paper. ...
Abstract: Software qualification includes such activities as a software Verification and Validation...
Key aspects and perspectives in Nuclear reactor Safety Technology (NST) are discussed in the paper. ...
Key aspects and perspectives in Nuclear reactor Safety Technology (NST) are discussed in the paper. ...
Designing and licensing a nuclear power plant and qualification of its subsystems and components is ...
Designing and licensing a nuclear power plant and qualification of its subsystems and components is ...
This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instru...
The work documented in this report was performed in support of the US Nuclear Regulatory Commission ...
In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-...
International audienceThe typology of the risks met in nuclear fuel cycle facilities is quite differ...