Effect of spray parameter on containment depressurization during LOCA in KAPP 3 and 4, 700 MWE IPHWR

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22106060

Sharma, S. K.; Bhartia, D. K.; Mohan, N.; Malhotra, P. K.; Ghadge, S. G. ^[1]

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1. Directorate of Reactor Safety and Analysis, Nuclear Power Corporation of India Limited, C-3,Nabhikiya Urja Bhavan, Anushaktinagar,, Mumbai 400094 (India)

KAPP 3 and 4 is an Indian Pressurized Heavy Water Reactor (IPHWR) of 700 MWe capacities. It is a pressure tube type reactor with heavy water as moderator and coolant and natural Uranium Dioxide as fuel. It consists of 392 horizontal fuel channel assemblies and surrounded by three separate water systems i.e. primary coolant, moderator and calandria vault water system. Containment of Indian PHWR is an ultimate barrier, which is designed to envelope whole reactor systems, to prevent the spread of active air-borne fission products in accident condition. Containment Spray System has been provided for energy as well as activity removal from the Containment system. This paper discusses about the studies done to assess the effect of spray parameters such as spray flow rate, droplets diameter and height of fall on containment peak pressure and temperature, long term containment depressurization and energy removal from the containment during Loss of Coolant Accident (LOCA). The spray flow rate and droplets diameter play an important role in removing residual energy from containment atmosphere, which influences depressurization of containment. It is obvious that faster depressurization of containment during postulated LOCA helps in limiting radiological consequences. From radiological considerations, droplets diameter is required to be kept to the lowest practically possible value and flow rate of spray should be high. Spray water droplets fall height governs the exposure time of droplets, which is the direct indication of energy removal rate. However, it is observed from the sensitivity studies that for a height of spray droplet fall more than 16.5 m, for the range of spray water flow rate and droplets sizes considered in the analyses, there is no significant change in heat removal. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22106060
• Resource Relation: Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 12 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AFTER-HEAT REMOVAL
CONTAINMENT SPRAY SYSTEMS
COOLANTS
DEPRESSURIZATION
DROPLETS
FISSION PRODUCTS
FLOW RATE
INDIA
LOSS OF COOLANT
MODERATORS
NATURAL URANIUM
PHWR TYPE REACTORS
PRESSURE TUBES
PRIMARY COOLANT CIRCUITS
SENSITIVITY ANALYSIS
URANIUM DIOXIDE