Effect of coolant channel width on group constants and multiplication factor of research reactors using MTR type low enriched uranium fuel

Abstract

One dimensional transport theory lattice code wims-d/4 and three dimensional diffusion theory code citation have been used to study the effect of fuel loading on critical cores of low enriched uranium (LEU) fuelled material testing reactors (MTRs). The fuel loading in a fuel element was varied by changing the fuel density in the fuel meat. In order to keep the reactor critically moderated, the optimal coolant channel width for a given fuel loading was calculated. For the purpose of optimization, the group constants D, Σ a and νΣ f, and infinite multiplication factor ( k ∞) were calculated as a function of coolant channel width using wims-d/4. An increase in 235U loading per fuel plate results in an increase in the optimal coolant channel width and k ∞. The calculated values were found to be in good agreement with the typical design of MTR. citation was then used to determine the critical cores for different fuel loading with optimized fuel dimensions. Both critical mass and volume were found to decrease with an increase in the fuel loading. The criticality studies of Pakistan research reactor-1 (PARR-1) are in good agreement with the predictions.