Burnup analysis and in-core fuel management study of the 3MW TRIGA MARK II research reactor

Reactivity Initiated Transient Response of TRIGA with the Progress of Core Burnt

“…There is a link between neutronic and thermal hydraulic analysis of a reactor core since heat energy generated in the core is induced by the fission neutrons. This paper considers reports of Huda et al [1], Rahman et al, [2], and Mahmood et al…”

“…To make the most effective use of reactor with the extension of its core life time, efforts have been paid in improving its in-core fuel management by the calculation of different neutronics parameters including individual fuel burnup at different cycles of reactor operation. Contribution of Huda et al [1],  Corresponding author. E-mail address: nhbadrun@yahoo.com DOI: https://doi.org/10.17146/aij.2020.…”

“…So, reactor operators may overlook reactor data on safety parameters for unprotected TRIGA core with its core burnt status. Hence, based on neutronics of TRIGA burnt core [1][2][3], the aim of present work is then of three fold; firstly, to report the pattern of core power and clad temperature for each reactivity imposed with each duration at each burn step; secondly, to evaluate the inserted maximum reactivity for which there will be obtained no fuel clad failure at different core burnt steps; and thirdly, to report for each amount and duration of inserted reactivity, how the maximum values of core power and clad temperature vary with the progress of core burnt. Coupled point kinetics, neutronics, and thermal hydraulics code EUREKA-2/RR has been used for this purpose.…”

Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup

“…If trace back reports of Huda et al [1], Rahman et al [2] , Mahmood et al [3], it is recognized that individual fuel element burnup together with power peaking factors calculations have been carried so far for about 700 MWD burnt of TRIGA core until 2012. These previous calculations were mostly conducted by using three dimensional continuous energy Monte Carlo code MVP considering cross section data library JENDL3.3.…”

“…To make the most effective use of reactor with the extension of its core life time, efforts have been paid in improving its in-core fuel management of the reactor by the calculation of different necessary parameters including individual fuel burnup at different cycles of reactor operation. Contribution of Huda et al [1], Rahman et al [2], Mahmood et al [3] can be referred in this regard. In fact, for every modification of reactor core, it needs thermal hydraulic safety assessment prior to  Corresponding author.…”