TY - CONF TI - The lumped parameter model for fuel pins AB - The use of a lumped fuel-pin model in a thermal-hydraulic code is advantageous because of computational simplicity and efficiency. The model uses an averaging approach over the fuel cross section and makes some simplifying assumptions to describe the transient equations for the averaged fuel, fuel centerline and sheath temperatures. It is shown that by introducing a factor in the effective fuel conductivity, the analytical solution of the mean fuel temperature can be modified to simulate the effects of the flux depression in the heat generation rate and the variation in fuel thermal conductivity. The simplified analytical method used in the transient equation is presented. The accuracy of the lumped parameter model has been compared with the results from the finite difference method. (author). 4 refs., 2 tabs., 4 figs. AU - "Liu, W S [Ontario Hydro, Toronto, ON (Canada)]" KW - "21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS" KW - "CANDU TYPE REACTORS" KW - "LOSS OF COOLANT" KW - "HEAT TRANSFER" KW - "MATHEMATICAL MODELS" KW - "CALCULATION METHODS" KW - "DARLINGTON-1 REACTOR" KW - "FUEL ELEMENT CLUSTERS" KW - "FUEL ELEMENTS" KW - "URANIUM DIOXIDE" DO - https://doi.org/ UR - https://www.osti.gov/etdeweb/servlets/purl/546011 PB - CY - Canada PY - 1995 DA - 1996-12-31 LA - English J2 - [] VL - C1 - Canadian Nuclear Society, Toronto, ON (Canada) C2 - C3 - INIS-CA-0053; CONF-950623- C4 - C5 - INIS; OSTI as DE98603788 L3 - Conference: 35. annual conference of the Canadian Nuclear Association and 16th annual conference of the Canadian Nuclear Society, Saskatoon (Canada), 4-7 Jun 1995; Other Information: PBD: 1995; Related Information: Is Part Of CNS proceedings of the 16. annual conference, volume I and II; Wight, A.L.; Loewer, R. [eds.]; PB: [2 v. ] p. ER -