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Abstract
The work in this thesis deals with criticality safety analysis of the new spent fuel storage pool (NSFSP) in ETRR-l research reactor. Safe and efficient storage of spent fuel .’ l1anents is an important aspect of the safety and economy of nuclear reactors.
The multiplication factor (ketr) for the pool is calculated as a function of relevant lattice physics parameters. These calculations ffilve been dealt with for all cases (normal, Design ¬Based Accident (DBA), and hypothetical cases).
In this work, Monte Carlo code MCNP-4B was used in the criticality calculations. For ETRR-l both the asymptotic storage cell and entire storage pool were modeled using the . MCNP 4B code. Besides, several lattice parameters were varied to establ5h their influence •• k.tr. In normal conditions, the fuel elements are fully submerged in water and the water ture is 20°C.
The multiplication factor for the pool is evaluated for ftesh fuel elements, which is a ative approach, recommended by International Atomic Energy Agency (IAEA) . .. for normal conditions, the multiplication factor was calculated at 20°C. The results were . compared with those results obtained formerly during the design phase of the pool. In addition, ketr was determined at different number of grids in the pool, several pool pitches,
several water levels ftom normal conditions to dry conditions (total loss of water ftom the : • pool), and the multiplication factor for the pool as a function of the element U23S mass.
The results showed that the pool remains subcritical with decreasing pitch, and for of total watei loss, i.e. water replaced by air in MCNP calculations, ketr= 0.03008 . . e kctr for the U23S mass> 128 g show the capability of extending the capacity of the 1. The highest ketr is well below 1.0, so that safety of the pool is preserved