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Modelling and Analysis of Radionuclides Transport and Source Term Evaluation within Containment / Confinement and Release to the Environment, for Research Reactors
Closed for proposals
Project Type
Project Code
J71011CRP
1261Approved Date
Status
Start Date
Expected End Date
Completed Date
18 January 2012Description
The CRP is intended to provide a comprehensive accident source term and modelling of radionuclide transport, with facility-specific on-site and off-site radiological consequence predictions for specific research reactors. Facility exclusion zones, emergency planning, emergency response, criteria of accident severity and potential security-related measures are among some of the areas that should benefit from the CRP data.
Objectives
The overall objective of the CRP was to encourage and foster the exchange of information among the participants, and to address some of the weaknesses in the safety analyses of research reactors observed during safety review missions at research reactors, particularly evaluation of the source term and radionuclide transport and release to the environment.
Specific objectives
Define and provide the specific modelling methods and/or analysis tools to determine:
(a)The Design Basis Accident (DBA) considered for a given type of research reactor and the associated source term;
(b) Fuel release fractions of the dominant radio-nuclides (with regard to potential dose consequences);
(c) Retention factors for radio-nuclides in the primary coolant water;
(d) The means of confinement (containment building or ventilation system) and its performance with respect to release of radioactive gases and liquids.
Increase the technical capability of the participating Member States to perform safety analysis, particularly assessment of radiological releases to the environment.
Perform accident analysis of a hypothetical research reactor, focusing on assessment of the source term, including release fractions from the fuel to the coolant water and transport to the environment.
Update the safety analyses of research reactors at the participants’ organizations, including verification of the adequacy of existing computer codes and the validity of information used for emergency planning and preparedness.
Impact
The overall impact of the CRP was enhancement of research reactor safety. This was accomplished through the exchange of information and experience among the CRP participants and with the broader research reactor community in the areas of evaluation of source terms and assessment of radiological consequences in the frame of safety analysis of research reactors. Specifically, addressing the discrepancies used in the radionuclides fraction release data, using conservative approaches for safety analysis and updating the safety analysis reports of research reactors at the participants’ organizations contributed toward enhancing the safety of these facilities and promoted similar enhancements at research reactors in other Member States. The CRP also resulted in benefits to the research reactor community through publications by the participants of their results in scientific papers in specialized journals and international topical meetings.
Relevance
The topics covered by the CRP were relevant to the Agency programme on enhancing the safety of research reactors, specifically on strengthening the capabilities of Member States to perform safety analysis and identify facility improvements based on the analysis.
The individual research contracts and agreements were relevant to enhancing the safety of the research reactors at the participants’ organizations.