Fuel element burnup determination in mixed TRIGA core using reactor calculations

Citation
M. Ravnik et al., Fuel element burnup determination in mixed TRIGA core using reactor calculations, NUCL TECH, 128(1), 1999, pp. 35-45
Citations number
13
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR TECHNOLOGY
ISSN journal
00295450 → ACNP
Volume
128
Issue
1
Year of publication
1999
Pages
35 - 45
Database
ISI
SICI code
0029-5450(199910)128:1<35:FEBDIM>2.0.ZU;2-T
Abstract
Calculations of fuel element burnup for realistic mixed core conditions in a 250-kW TRIGA Mark II reactor are presented. Two tyres of fuel elements ar e considered: 70% enriched FLIP and 20% enriched standard fuel elements. Tw o calculation models are compared. The first is based oil a one-dimensional two-group diffusion approximation (the TRIGAP computer code), and the seco nd is based on a two-dimensional four-group diffusion equation (the TRIGLAV computer code). In both cases the unit-cell group constants are generated with the WIMS code. Results of the calculations are intercompared to evalua te the influence of the two-dimensional effects on fuel element burnup. The following two-dimensional effects are considered: mixed rings, in-core wat er gaps, vicinity of control rods, and asymmetric core loading patterns.. R elative differences in fuel element burnup of 10% on average and up to 80% in extreme cases are observed because of the two-dimensional effects. The a ccuracy of the calculation is estimated also by comparing the calculated re sults to the measurements using the reactivity method.