Validation of RELAP5 model of experimental test rig simulating the natural convection in MTR research reactors

In an attempt to understand the buildup of natural circulation in MTR pool type upward flow research reactors after loss of power, an experimental test rig was built to simulate the loop of natural circulation in MTR reactors. In this test rig the reactor core is simulated by two electrically heated, rectangular parallel channels. The channel's coolant and surface temperature at different operating conditions were measured. The measurements and their interpretation were published by the first three authors. In the present article the thermal hydraulic behavior of the test rig is complemented by theoretical analysis using RELAP5 system code. The analysis consisting of two parts; in the first part RELAP5 model is validated against the experimental measurements and in the second part the other non-measured hydraulic parameters are presented and analyzed. In spite of the low pressure of the test rig, the results show that RELAP5 Mode 3.3 qualitatively predicts the thermal hydraulic behaviour and the accompanied phenomenon of flow inversion in such facilities. Quantitatively, there is a difference between the predicted and measured values especially the surface temperature of channel's wall. This difference may be return to the uncertainties in initial conditions of experimental runs, the position of the thermocouples which buried inside the heat structure, and the heat transfer package in RELAP5.