Abstracts and Available Papers Presented at the
1998 International RERTR Meeting
Neutronic Calculations Regarding
the New LEU 6x6 Fuel Bundle
for 14 MW TRIGA-SSR, in Order to Increase
the Reactor Power up to 21 MW
C. Iorgulis, M. Ciocanescu, M. Preda, M. Mladin
Institute for Nuclear Research
In order to meet the increasing demands of terminal flux for
the experimental devices which will be loaded with CANDU natural uranium pins (or clusters
), is necessary to rise the reactor power up to 21 MW.
In this respect we consider in our evaluations a new 6x6 TRIGA fuel bundle geometry (the actual fuel bundle contains 5x5 pins).
The paper will contain a comparative analysis regarding: flux and power distribution across the 29 fuel bundles standard core, and fuel managements patterns, in order to maximize the discharge fuel burnup and core lifetime.
PDF version available
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