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Abstract

In this paper results from comparative calculations for NPP Kozloduy water moderated water cooled reactor (WWER) operational fuel rods, with the two thermomechanical codes PIN-micro and TRANSURANUS, are presented and discussed. The purpose is to check the compliance of first approach results obtained by a very simple steady-state code, validated against WWER fuel rod data (PIN-micro), and by the sophisticated modern code TRANSURANUS, widely accepted as a reference code, during the initial stage of its WWER version development. Several input data sets for WWER fuel rods have been prepared, based on previous applications and experience with the PIN-micro code for operational fuel rods and on data collected from the open literature. All cases have been calculated with the PIN-micro code and with the standard version of the TRANSURANUS code using a usual model options set.

Additional information

Authors: STEFANOVA S, Institute for Nuclear Research and Nuclear Energy, Sofia (BG);SIMEONOVA V, Institute for Nuclear Research and Nuclear Energy, Sofia (BG);PASSAGE G, Institute for Nuclear Research and Nuclear Energy, Sofia (BG);HARALAMPIEVA T, National Electrical Company, Kozloduy NPP Branch (BG);PEYCHINOV T, National Electrical Company, Kozloduy NPP Branch (BG);LASSMANN K, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: Second International Seminar on Water Moderated Water Cooled Reactor (WWER) Fuel Performance, Modelling and Experimental Support, Sandanski (BG), 21-25 April 1997
Availability: Available from (1) as Paper EN 41194 ORA
Record Number: 199810342 / Last updated on: 1998-03-09
Category: PUBLICATION
Original language: en
Available languages: en
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