A Monte Carlo computer code MCNP4A simulation of the TRIGA Mark II ben
chmark experiment performed in 1992 is presented. It may be noted that
this benchmark experiment is one of very few high-enrichment benchmar
ks available. To minimize errors due to an inexact geometry model, the
TRlGA Mark II reactor core was very thoroughly modeled. All fresh fue
l and control elements as well as the vicinity of the core were precis
ely described. MCNP4A input was prepared in such a way that any desire
d core configuration could be simulated easily. Continuous energy cros
s-section data from ENDF/B-VI and ENDF/B-V (for Cr-nat, Fe-nat, and Ni
-nat) libraries and S(alpha,beta) scattering functions from the ENDF/B
-IV library were used in our calculations. The differences between END
F/B-VI and ENDF/B-V evaluations were examined on critical experiments.
Most of the steady-state operation experiments were simulated, includ
ing two critical experiments, namely, measurements of the excess react
ivity of the core, and the determination of control rod worths and fue
l element reactivity worth distribution. Excellent agreement with the
experimental results was observed.