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Benchmark of Transition from Forced to Natural Circulation Experiment with Heavy Liquid Metal Loop
Closed for proposals
Project Type
Project Code
I31038CRP
2300Approved Date
Status
Start Date
Expected End Date
Participating Countries
Description
The Coordinated Research Project (CRP) focuses on thermal-hydraulic analysis of the tests performed at the forced to natural circulation experimental (NACIE) facility at ENEA (Italy) in 2017.Transient analysis of thermal hydraulic phenomena in NACIE loop tests provides an excellent opportunity for validation of the physical and mathematical models and numerical simulation codes using actual experimental data. The experimental data are available both for integral values and local temperature distribution that makes it possible the validation and comparison of reactor system codes, subchannel analysis and CFD simulations versus experimental data.
Objectives
The overall objective of the CRP is to improve the Member States' analytical capabilities in the field of simulation of fast reactors cooled by heavy liquid metals.
A necessary condition towards achieving this objective is a wide international validation and qualification effort of the analysis methodology and codes currently employed in the fields of fast reactor neutronics, thermal hydraulics and plant dynamics to achieve enhanced safety. It will aim to enable Member States to make informed decisions on the development of new or advanced fast reactor designs, and to increase cooperation between Member States in achieving advances in fast reactor technology development through international collaborative R&D.
The CRP will be implemented as a programmatic activity of the IAEA Project 1.1.5.3 “Advanced technology for fast reactors” starting with the IAEA Program and Budget Cycle 2022 – 2023. The Project 1.1.5.3 has the objective, among others, to enable Member States to make informed decisions on the development of new or advanced fast reactor designs, and to increase cooperation between Member States in achieving advances in fast reactor technology development through international collaborative R&D. Given its aforementioned overall objective, the CRP clearly responds to the objectives of the IAEA Project 1.1.5.3.
Specific objectives
Contribute to validation of the simulation codes and models
Investigate the applicability of existing codes to the heavy liquid metals coolants
Investigation of the heat transfer of the wire wrapped fuel assembly