Independent assessment for new nuclear reactor safety

Assessment of Cfd Codes Used in Nuclear Reactor Safety Simulations

The spectacular growth in computer hardware over the last quarter century and the accompanying advances in software development have resulted in the availability of reliable numerical tools for addressing safety issues in Nuclear Power Plants (NPPs). The first step forward was undertaken in the 1970s with the development of system codes using the two-fluid model approach [1], such as RELAP-5 [2...

Radiation Safety Assessment of the New Neutron Radiography System at Tehran Research Reactor

Recently, a new Neutron Radiography (NR) beam line has been designed, constricted, installed and tested based on the use of E-beam tube of Tehran Research Reactor (TRR). Initial tests have been shown that the system can be used for different samples and purposes such as nuclear plates and rods fuels.  For this end the system need a suitable irradiation room which should be installed at the NR b...

Safety Aspects of Nuclear Reactor Control

Reactor control and safety systems are discussed with emphasis on safety considerations. Consideration is given to the importance of reactor characteristics, control and safety system characteristics, the operational program of the reactor, and credible accidents, in a determination of safety of operation. Ecperience with research reactor control and safety systems has led to the development of...

Computational Fluid Dynamics for Nuclear Reactor Safety-5 (CFD4NRS-5)

Effective Independent Safety Assessment

The purpose of an Independent Safety Auditor (ISA) is to audit, assess and review processes used in a project to show compliance to best and appropriate practice and to assess the adequacy of the evidence. The main objective of using an ISA in any project is to provide assurance that a contractor considers and addresses safety issues. An ISA needs to be convinced that the process captures, unde...