THERMAL HYDRAULIC ANALYSIS OF TAJOURA REACTOR CORE DURING TRANSIENT STATE AFTER COST-DOWN OF COOLING PRIAMERY PUMPS

Date

2016-3

Type

Article

Journal title

Journal of Engineering Research

Issue

Vol. 21 No. 21

Author(s)

BASHIR HASSAN HUSSIN AREBI

Pages

31 - 46

Abstract

ABSTRACT ( Simulation and analysis has been performed for the transient state after core scram caused by postulated cost-down of all three operating primary pumps of the Tajoura nuclear reactor. The scope of this study is to calculate the core important safety related parameters during the filling of the emergency tank after scram. The reactor at Tajoura Nuclear Research Center (TNRC) is a pool type and the core is IRT-4M type. The core fuel is LEU UO2-Al of 19.7 % U235 . The fuel assemblies include 6-tubes and 8-tubes. The maximum operating power for the reactor is 10 MW. The hottest fuel-assembly is used in the analysis and the initial conditions for the transient state is taken from the results of previous study which was established for the steady state core operation. The results from the analysis of the transient state showed that the fluid temperature increases from 67.7 o C to about 75 o C within 86.5 seconds from the core scram, where the clad temperature drops from 105.5 o C to 70.6 o C within 12 seconds from the scram, then increases to its maximum temperature of about 89 o C at 86.5 seconds from the core scram. The results of the transient state are compared with the results obtained from Argonne National Laboratory (ANL). The comparison shows significant differences between the temperatures calculated in this study and those obtained from Argonne National Laboratory (ANL). The results from this model appear more logical than those of ANL. This is because of the fewer assumption made in this study compared with that of ANL, moreover ANL does not simulate the first 10 seconds follows the scram.)

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