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

Authors
Citation
An. Ahmad, Effect of coolant channel width on group constants and multiplication factor of research reactors using MTR type low enriched uranium fuel, ANN NUC ENG, 29(4), 2002, pp. 477-488
Citations number
5
Categorie Soggetti
Nuclear Emgineering
Journal title
ANNALS OF NUCLEAR ENERGY
ISSN journal
03064549 → ACNP
Volume
29
Issue
4
Year of publication
2002
Pages
477 - 488
Database
ISI
SICI code
0306-4549(200203)29:4<477:EOCCWO>2.0.ZU;2-R
Abstract
One dimensional transport theory lattice code WIMS-D/4 and three dimensiona l diffusion theory code CITATION have been used to study the effect of fuel loading on critical cores of low enriched uranium (LEU) fuelled material t esting reactors (MTRs). The fuel loading in a fuel element was varied by ch anging the fuel density in the fuel meat. In order to keep the reactor crit ically moderated, the optimal coolant channel width for a given fuel loadin g was calculated. For the purpose of optimization, the group constants D, S igma (a) and v Sigma (f), and infinite multiplication factor (k(infinity)) were calculated as a function of coolant channel width using wims-D/4. An i ncrease in U-235 loading per fuel plate results in an increase in the optim al coolant channel width and k(infinity) The calculated values were found t o be in good agreement with the typical design of MTR, CITATION was then us ed to determine the critical cores for different fuel loading with optimize d fuel dimensions. Both critical mass and volume were found to decrease wit h an increase in the fuel loading. The criticality studies of Pakistan rese arch reactor-1 (PARR-1) are in good agreement with the predictions. (C) 200 1 Elsevier Science Ltd. All rights reserved.