@proceedings {51747, title = {OPTIMIZATION OF MATERIAL TEST RESEARCH REACTOR CORE FOR ISOTOPE PRODUCTION}, journal = {Research Reactors: Safe Management and Effective Utilization}, year = {2011}, pages = {1-3}, publisher = {iaea}, address = {Morocco}, abstract = {

In this paper Neutronic calculation (deterministic approach) has been carried out to characterize the neutron flux in
locations used for isotope production to achieve optimum utilization of the reactor. In neutronic calculations a number of
approximations take place. As a result even if one uses the same codes the results might be different. It is thus of importance
to care about the model used. Comparison between different model and with published experimental results has been done. In
this work three deferent model of the standard fuel has been tested to determine the accurate one, then it used for core
calculation. Calculation of reactivities at deferent cycles, calculation of power densities, neutron flux, and burn-up as well as
search for equilibrium were performed to determine the equilibrium core. Standard computer codes WIMSD-5B and
CITVAP were used.

}, url = {http://www-pub.iaea.org/MTCD/Publications/PDF/P1575_CD_web/datasets/abstracts/B19AbdAlaziz.html}, author = {R.O. ABD ALAZIZ and A.A. ESMAT and Abou-Shady, H.} }