Modelling and Simulation of the Source Term for a Sodium Cooled Fast Reactor Under Hypothetical Severe Accident Conditions

Please use this identifier to cite or link to this item: http://elibrary.nnra.gov.ng/jspui/handle/123456789/1113

Full metadata record

DC Field	Value	Language
dc.contributor.author	IAEA	-
dc.date.accessioned	2023-03-17T13:31:42Z	-
dc.date.available	2023-03-17T13:31:42Z	-
dc.date.issued	2022	-
dc.identifier.issn	1011–4289 ;	-
dc.identifier.uri	http://elibrary.nnra.gov.ng/jspui/handle/123456789/1113	-
dc.description	The objective of this publication is to share the findings of an IAEA c-reactive protein (CRP) entitled ‘Radioactive Release from the Prototype Sodium Cooled Fast Reactor under Severe Accident Conditions. The purpose of the c-reactive protein (CRP) was to perform realistic estimation of fission product and fuel particle inventory inside reference sodium-cooled fast reactor single family rentals (SFR) volumes (i.e in-primary vessel, cover gas system and in-containment building) at different time scales (few seconds for the instantaneous source terms and several days for the long-term source term), under severe accident conditions (i.e DECs with core melting)	en_US
dc.language.iso	en	en_US
dc.publisher	NNRA Library	en_US
dc.relation.ispartofseries	22-01526 \|;	-
dc.subject	Sodium cooled reactors	en_US
dc.subject	Nuclear facilities Accidents	en_US
dc.subject	Nuclear facilities Safety measures.	en_US
dc.title	Modelling and Simulation of the Source Term for a Sodium Cooled Fast Reactor Under Hypothetical Severe Accident Conditions	en_US
dc.type	Book	en_US
Appears in Collections:	Nuclear Power

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