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Application of Computational Fluid Dynamics (CFD) Codes for Nuclear Power Plant Design
Closed for proposals
Project Type
Project Code
I31022CRP
1955Approved Date
Status
Start Date
Expected End Date
Completed Date
7 October 2019Participating Countries
Description
The Coordinated Research Project (CRP) addresses the application of Computational Fluid Dynamics (CFD) computer codes to the process of optimizing the design of water cooled Nuclear Power Plants (NPP). Following a number of initiatives within IAEA where CFD codes are applied to a wide range of situations of interest in nuclear reactor technology, the CRP intends to constitute a systematic framework for the consistent application of those codes. Namely, the CRP will contribute to establish a common vision in relation to the capabilities of CFD codes and their qualification level. The CRP is also expected to provide a roadmap strengthening the application domain of the related technology. Blind analyses (i.e. code calculations performed without having access to experimental data) performed by participants will allow the achievement of the proposed objectives.
Objectives
The overall objectives of the CRP are to promote and oversee international collaboration among IAEA member states in the use of CFD as a qualified simulation tool in support of the design of advanced reactors. This synergizes with existing international activities in nuclear reactor safety and the use of CFD in industries. The scope for this CRP is three-fold: 1) providing an experimental database for validation of CFD application techniques; 2) demonstrating the applicability and the qualification level of CFD codes in situations of technological interest; and 3) developing a common ground for justifying and spreading the use of CFD codes in nuclear reactor design. The objective is achieved by gathering leading institutions involved with the application of CFD codes to agree on best-practice guidelines and in performing and documenting the analyses of relevant experiments.
Specific objectives
The above objectives are achieved by pursuing the following roadmap:
Issuing a status report on CFD Validation and Verification (V&V) based on the available expertise of CRP participants and to be delivered at the first RCM.
Acquiring an experimental data base for pressure drops at geometric discontinuities.
Acquiring in parallel a CFD calculational database for pressure drop at geometric discontinuities.
Acquiring an experimental database for connection between potential energy and turbulence in a gravity-driven environment.
Acquiring in parallel a CFD calculational database for connection between potential energy and turbulence in a gravity-driven environment.
Acquiring an experimental database for fluid mixing and heat transfer in a rod bundle.
Acquiring a CFD calculational database for fluid mixing and heat transfer in a rod bundle.
Issuing a synthesis report for V&V and new perspectives for the application of CFD codes in nuclear technology.
To encourage participants to define a series of topical, though relevant standard problems by which the use of CFD as an aid in reactor design technology could be qualified, and/or to contribute appropriate experimental data to such an exercise. The IAEA would provide the organization, and limited funding, by which results from multiple participation in numerical benchmarking exercises based on these standard problems would be synthesized.
To promote exposure of the activities undertaken within the project by writing papers at international conferences and organizing Technical Meetings. These could be in the form of stand-alone conferences or an expansion of the existing workshops in the CFD4NRS series, which are co-sponsored by the IAEA and the OECD-NEA.
Impact
CFD still has a significant role to play in the core design of existing GEN-II reactors, particularly in the design of spacer grids, for which wider safety margins to Critical Heat Flux (CHF) will bring with them better fuel economy, and higher power output. It is in this very context that a benchmarking exercise is currently being organized within this CRP to attest the readiness of the CFD numerical models to predict accurately the increased efficiency in turbulent heat transfer downstream of such spacer grids, and to assess the reliability of such models against measured test data.
Relevance
Of particular relevance to this CRP is the use of CFD in the design of advanced nuclear reactors: that is, those of type GEN-III, GEN-III+ and GEN-IV. In particular, CFD codes are useful in understanding and simulating the innovative physics and phenomenologies driving these new NPP concepts.