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AbstractAbstract
[en] The FPIN2 code simulates the thermal-mechanical response of fast reactor fuel pins to transient events. Temperatures of the fuel pin and coolant are calculated using a simple pin-in-a-pipe geometry. The mechanical analysis uses an implicit finite element formulation with linear shape functions which allow for general material behavior in the fuel and cladding including cracking and melting. This formulation provides a very convenient structure for implementing different models and improvements in algorithms. The paper summarizes the FPIN2 methodology and presents results for the transient response of both oxide and metallic fuel pins under similar overpower transients
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1986; 9 p; Conference on the science and technology of fast reactor safety; Channel Islands (UK); 12-16 May 1986; Available from NTIS, PC A02/MF A01; 1 as DE86014493; Portions of this document are illegible in microfiche products.
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Conference
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