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[en] This paper reports the using of the PARET computer code for determining the response of the Tehran Research Reactor (TRR) upgraded core to the ramp reactivity insertion of USD1.5/0.5s. This ramp reactivity insertion has been analyzed in two; without any scram and with an overpower scram conditions. The results show that the maximum clad surface temperature during this reactivity insertion without any scram is increased up to 248 C. This value is adequately below the melting point of aluminum alloy (630 C). Therefore, the upgraded core of TRR shows a margin of about 382 C for the reactivity insertion accident of USD1.5/0.5s.(author)
Source
Pevec, D.; Debrecin, N. (eds.); Croatian Nuclear Society, Zagreb (Croatia); International Atomic Energy Agency, Vienna (Austria); European Nuclear Society, Brussels (Belgium); 996 p; ISBN 953-96132-8-0; 
; 2004; [8 p.]; 5. International Conference: Nuclear Option in Countries with Small and Medium Electricity Grids; Dubrovnik (Croatia); 16-20 May 2004; Available E-mail: jalil_jafari@yahoo.com
; 2004; [8 p.]; 5. International Conference: Nuclear Option in Countries with Small and Medium Electricity Grids; Dubrovnik (Croatia); 16-20 May 2004; Available E-mail: jalil_jafari@yahoo.com