الفهرس 
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Abstract
Loss of Coolant Accident(LOCA) and Loss of Flow Accident(LOFA), are considered as design basis accidents, and classified as limiting faults. The qualitative and quantitative analysis of these accidents are of major
importance in the area of reactor safety analysis.Simultaneous occurence of one of these accidents
and the loss of function of engineered safety feature systems(ESFs) may yeild failar6 uf one or more barriers
and hence having serious environmental impacts. The relevant reviewed studies are generally classified as experimentally oriented and theoretically oriented ones. The latter include physical models, mathematical models, cause and effect analysis, fault and event tree analysis, and computer codes that are constructed to conduct all computational steps in the proposed models.
The present stud¥ discusses the core behavior under normal arid accidental conditions through detailed and lumped parameter models for LOFA analysis. Assuming
simul taneous occurence of LOFA a..”’ld failure of the engineered safety feature systems(ESFs), the main objective of the present work is to develope mathematical models that simulate the following cases:
1- Core thermal-hydraulic behavior•of a pressurized