Description
Chairs: Jordi Rolans-Ribas and Hideki Kamide
For design and safety justification of fast reactors with liquid metal coolants, a complex of more than 20 experimental facilities of various functions and purposes, equipped with modern measuring instruments, including hydrodynamic, thermohydraulic and technological facilities, has been created at IPPE JSC.
In addition IPPE JSC has a complex of fast neutron facilities, including two...
In order to develop numerical modeling of hydrodynamics and heat exchange for substantiation of design and safety characteristics of fast reactors planning and carrying out experiments, generalizing the experimental results according to the physical laws and to their closing relations and verification of codes are required. To solve these problems, a complex of liquid metal facilities,...
The Thermal Hydraulic Experimental Test Article (THETA) is a 150-gallon reactor grade sodium facility built to study the phenomena that occur in a fast reactor during normal operations as well as accident scenarios. THETA will provide critical data to sodium fast reactor designers with higher fidelity than ever before for a scaled liquid sodium facility; THETA is instrumented with advanced...
In the frame of the implementation of fast breeder reactors in France initiated in the 1960’s, a lot of studies have been conducted by CEA/IPSN (now IRSN) on sodium fires and risks potentially induced by sodium in general. The experimental studies started at a fundamental level, in order to understand the basic phenomena concerning sodium fire. From 1972, R&D programs dealt with small and...
The purpose of this paper is to present the Mechanisms Engineering Test Loop (METL) facility installed at U.S. DOE’s Argonne National Laboratory located outside of Chicago, Illinois. The METL facility is a multipurpose intermediate-scale 750-gallon (2839l) sodium test facility used for the testing of liquid metal systems and components in prototypic reactor-grade sodium conditions. Some...
Multifunctional Research Fast Reactor (MBIR) is being built in the Russian Federation for justification of the new projects of nuclear power based on fast reactors operated in the closed nuclear fuel cycle. MBIR will make it possible to carry out a wide scope of reactor research including studies into new types of fuel and structural materials in combination with different coolants. It can...
Advanced nuclear technologies will play a significant role in meeting the growing demand for clean energy. To support the deployment of these technologies and enable long term innovation, the U.S. DOE has initiated a project to build a Versatile Test Reactor (VTR) with a compelling and urgent mission: testing innovative fuels, materials, sensors and instrumentation for various advanced...
Development and justification of innovative nuclear power technologies, spent nuclear fuel management and closed nuclear fuel cycle are the main issues that nuclear power industry faces nowadays.
Solving those tasks will be possible only with the help of modern research infrastructure permitting to conduct a full-scale experiments and to model various operating conditions. Russia is...
The Versatile Test Reactor (VTR) is a reactor under development in the United States of America to provide a very high-flux fast neutron source that will support the development of advanced reactor technologies. This reactor will accelerate the irradiation testing of advanced nuclear fuels, materials, and potentially other components. The development efforts are structured in several phases to...
