Diluted boron plugs can be formed in the loop seal of primary system of pressurized water reactors, e.g. during Small break LOCA (Loss of Coolant Accident) scenarios. The diluted boron plugs may reach the core at the time of possible restart of natural circulation causing the potential of neutron flux excursions and large power peaks - challenging core integrity. The consideration of boron adds complexity to the design of EOP (Emergency Operating Procedures) and AMP (Accident Management Procedures). Experiments relevant to boron dilution have been performed and system thermal-hydraulic codes are qualified to reproduce relevant phenomenology. The paper deals with a discussion about code capabilities with example of applications of codes.
Predictability of Boron Transport Phenomenon in PWR Based on PKL Experimental Program
D’Auria Francesco
Co-primo
Conceptualization
2010-01-01
Abstract
Diluted boron plugs can be formed in the loop seal of primary system of pressurized water reactors, e.g. during Small break LOCA (Loss of Coolant Accident) scenarios. The diluted boron plugs may reach the core at the time of possible restart of natural circulation causing the potential of neutron flux excursions and large power peaks - challenging core integrity. The consideration of boron adds complexity to the design of EOP (Emergency Operating Procedures) and AMP (Accident Management Procedures). Experiments relevant to boron dilution have been performed and system thermal-hydraulic codes are qualified to reproduce relevant phenomenology. The paper deals with a discussion about code capabilities with example of applications of codes.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
