Abstracts and Available Papers Presented at the 1999 International RERTR Meeting
NEUTRONIC SAFETY AND TRANSIENT ANALYSES FOR POTENTIAL LEU
CONVERSION OF THE IR-8 RESEARCH REACTOR
J. R. Deen, N. A. Hanan, R. S.
Smith and J. E. Matos
Argonne National Laboratory
Argonne, IL, USA 60349-4815
P. M. Egorenkov and V. A.
Russian Research Centre
Reactor Technology and Material
Moscow 123182, Russia
Kinetic parameters, isothermal reactivity
feedback coefficients and three transients for the IR-8 research reactor cores
loaded with either HEU(90%), HEU(36%), or LEU (19.75%) fuel assemblies (FA)
were calculated using three dimensional diffusion theory flux solutions,
RELAP5/MOD3.2 and PARET. The prompt neutron generation time and effective
delayed neutron fractions were calculated for fresh and
beginning-of-equilibrium-cycle cores. Isothermal reactivity feedback
coefficients were calculated for changes in coolant density, coolant
temperature and fuel temperature in fresh and equilibrium cores. These kinetic
parameters and reactivity coefficients were used in transient analysis models
to predict power histories, and peak fuel, clad and coolant temperatures. The
transients modeled were a rapid and slow loss-of-flow, a slow reactivity
insertion, and a fast reactivity insertion.