Sub-Channel Analysis Code: MATRA
The sub-channel analysis code MATRA is descended from COBRA, and was originally developed by Korean Atomic Energy Research Institute (KAERI) for PWRs. In the frame of a bilateral collaboration between the Forschungszentrum Karlsruhe and KAERI, the MATRA code is being further modified for both heavy liquid metal and supercritical water cooled reactors.
- Lumped parameter approach
- Steady-state & transient analysis
- Capability for single and two-phase flows
- Applicability to various fluids
- Design of fuel assemblies of LM cooled reactors and water-cooled reactors
- Safety analysis of nuclear reactor cores
- Development of advanced nuclear reactor cores
- Under preparation
(1) Yoo, Y. J., Hwang, D. H. and Sohn, D. S., “Development of a Subchannal Analysis Code MATRA Applicable to PWRs and ALMRs,” J. of Korean Nuclear Society , Vol. 31, p. 314, 1999.
(2) Wheeler, C. L., et al., “COBRA-IV-i : An Interim Version of COBRA for Thermal-Hydraulic Analysis of Rod Bundle Nuclear Fuel Elements and Cores,” BNWL-1662, 1976.
System Analysis Code: ATHLET-MF
The system analysis code ATHLET-MF, which is developed by the Forschungszentrum Karlsruhe based on the ATHLET code of the Gesellschaft für Reaktorsicherheit (GRS), is applicable to multi-fluids nuclear systems.
- 1-dimensional, incompressible fluids with volumetric heat source
- Multi-fluid systems with thermal coupling
- General control simulation modules
- Option of user specified thermal-physical properties and physical models
- Separation of physical models from numerical methods
- Cooling system of spallation targets, e.g. XADS
- Analysis of MEGAPIE out-of-pile integral tests MITS
- Design analysis of ADS cooling systems
The ATHLET-MF has been applied to the cooling systems of various spallation targets, such as the target of the European experimental ADS (XADS). Figure 1 shows the transient behavior of LBE mass flow rate and temperature under start-up conditions.
- ATHLET User’s Manual, GRS, September 2001
- H.Y. Chen, X. Cheng, H.J. Neitzel, Application of ATHLET Code to Heavy liquid Metal Cooled Systems, Annual Meeting on Nucl. Tech. 2004, Dusseldorf, Germany, May 25-27, 2004