Innovative Methods in Research Reactor Analysis: Benchmark against Experimental Data on Neutronics and Thermalhydraulic Computational Methods and Tools for Operation and Safety Analysis of Research Reactors.
Closed for Proposals
Project Type
Coordinated Research ProjectProject Code
J71013
CRP
1496
Approved Date
9 May 2008Project Status
ClosedStart Date
17 October 2008Expected End Date
31 December 2012Completed Date
26 March 2013Description
The proposed CRP will involve for the first time benchmarking against experimental data of the thermalhydraulic and neutronic computer codes for research reactor analysis. In the process, a set of experimental data for code benchmarking will be established and the need for a more detailed work will be defined. Equally important, a detailed comparison of results between different organizations and codes will be performed and the user effects will be identified. The activities of this CRP will contribute to enhance the capabilities of the participants in performing analysis for research reactors aimed at improving the design, operation and the safety performance of research reactors and associated experiments.
Objectives
The overall objective of this CRP is to encourage cooperation and foster exchange of information in the areas of neutronic and thermal-hydraulic numerical analyses for improving research reactor design, operation, and safety.
Specific Objectives
Develop a comprehensive database of characteristics, experiments and data for the facilities participating in the CRP that is useful for benchmarking neutronic and thermal-hydraulic computer codes.
Develop recommendations on open issues for future research and development activities involving research reactors.
Enhance the capabilities of the CRP participants in performing research reactor numerical analysis and safety assessment.
Identify user effect on the results predicted by the computer codes.
Increase cooperation among research reactor analysts related to experiments and modelling.
Perform benchmark studies of neutronic and thermal-hydraulic computer codes against experimental data.
Transfer know-how in the area of research reactor numerical analysis, including design, safety analysis, operation, and utilization.
Impact
Nine participants provided sets of experimental measurements in a format and contents suitable for computer code benchmarking, which significantly contributed to the success of the CRP in making available, for the first time, such experimental database for computer code benchmarking for research reactor safety analysis and operation. The two IAEA publications resulting from the CRP will be valuable resources for research reactor designers, operating organizations and regulatory bodies for developing and benchmarking computer models of research reactors. This will lead to improved capabilities of Member States for both research reactor safety analysis and optimization of utilization activities.
Relevance
The topics covered by the CRP were relevant to the Agency programmes on enhancing the safety and utilization of research reactors. Specific to the safety of research reactors, the CRP was relevant to steady state and transient neutronic and thermal-hydraulic analyses of reactor cores and cooling systems for establishing appropriate designs, operating regimes and safety system settings. In the case of utilization, benchmarked neutronic codes will facilitate optimization of existing or design of new experimental facilities, interpretation of corresponding experimental data and analysis. The extensive research reactor data base will foster code and related data libraries validation and new developments.
CRP Publications
ANS Conf. Proceedings
Proceedings of the ANS Winter Meeting, San Diego, CA, USA, 11-15 Nov. 2012; ANS Transactions Vol. 107 (2012).
2012
Alicia Doval, Pablo Adelfang, Danas Ridikas and Amgad Shokr, “IAEA Coordinated Research Project on benchmarking of RR experiments from 10 facilities world-wide”,