Table of Contents
International Journal of Nuclear Energy
Volume 2014, Article ID 167426, 8 pages
Research Article

Modeling of SPERT IV Reactivity Initiated Transient Tests in EUREKA-2/RR Code

Institute of Nuclear Science & Technology (INST), Atomic Energy Research Establishment (AERE), Ganakbari, Savar, P.O. Box 3787, Dhaka 1000, Bangladesh

Received 28 August 2014; Revised 18 November 2014; Accepted 18 November 2014; Published 9 December 2014

Academic Editor: Arkady Serikov

Copyright © 2014 N. H. Badrun et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


EUREKA-2/RR code has been used for SPERT IV reactor benchmark calculations against the experimental results provided by IAEA (International Atomic Energy Agency) obtained for a series of transient tests initiated by step insertion of different magnitudes of positive reactivity with varying degrees of different controlled parameters such as reactor initial power, coolant temperature and coolant flow condition. 20 out of 39 tests that fall under forced convection mode have been considered for the present simulation provided the reactor scram system is disabled. Peak power and peak clad temperature due to transient have been calculated and it was found that although peak clad temperature values agreed, the peak power values seem to underestimate the experimental values. Further study appears to be needed to identify the limitations in modeling or examining the effect of input parameters during modeling to obtain the better simulation results.