Abstract
In order to join efforts to develop high-fidelity multi-physics tools for research reactor analysis, the KIT is conducting studies to modify the coupled multi-physics codes developed for power reactors. The coupled system uses the Monte Carlo Serpent 2 code for neutron analysis and the Subchanflow code for thermo-hydraulic analysis. Serpent treats temperature dependence using the target motion sampling method and Subchanflow was previously extended and validated with experimental data for plate-type reactor analysis. This work present for the first time the steady-state and transient neutron and thermo-hydraulic analysis of an MTR core defined in the IAEA 10 MW benchmark using Serpent2/Subchanflow. Important global and local parameters for nominal steady-state conditions were obtained, e.g., the lowest and highest core plate/channel power/temperature, the radial and axial core power profile at the plate level, and the core coolant temperature distribution at the subchannel level. The capabilities of Serpent2/Subchanflow to perform transient analysis with on-the-fly motion of the control plates were tested, namely with fast and slow reactivity insertion. Based on the unique results obtained for the first time at the subchannel and plate level, it can be stated that the coupled Serpent2/Subchanflow code is a very promising tool for research reactor safety-related investigations.
Highlights
A large number of research reactors, among others of TRIGA and Material Testing Reactor (MTR) design, are being operated all over the world for different purposes, such as training, medical application, the irradiation of different specimens, etc
This work present for the first time the steady-state and transient neutron and thermo-hydraulic analysis of an MTR core defined in the IAEA 10 MW benchmark using Serpent2/Subchanflow
Based on the unique results obtained for the first time at the subchannel and plate level, it can be stated that the coupled Serpent2/Subchanflow code is a very promising tool for research reactor safety-related investigations
Summary
A large number of research reactors, among others of TRIGA and MTR design, are being operated all over the world for different purposes, such as training, medical application, the irradiation of different specimens, etc. Several thermohydraulic studies for research reactors have been based on autonomous system/subchannel codes, which were adapted for this purpose in different ways, e.g., the use of equivalent plates and heuristic methods [1,2,3]. It is worth mentioning that MTR reactors present some particular characteristics, such as: small cores of complicated geometry, downward and upward mass flow, specific correlations for rectangular channels, low operating pressure, high-density power, and low fuel and cladding temperature.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have