Verification of TRANSURANUS against temperature data from WWER type test fuel rods from Sofit experiments
Detailed data from in-pile fuel experiments have been made available through the IAEA/OECD-NEA database. The data from 2 SOFIT experiments, SOFIT-1.1 and SOFIT-1.3, have currently been included in this database. The SOFIT program was a joint venture between Kurchatov Institute (Russia) and Imatran Voima Oy (Finland). Four test fuel assemblies consisting of instrumented and non-instrumented rodlets of water moderated water cooled reactors (WWER)-type were irradiated in the MR-reactor in Moscow. The pellets and cladding tubes were from the standard WWER fuel production. The available data on the behaviour of the test rods were analyzed with the TRANSURANUS code. The results of the temperature calculations are described in this paper.
Bibliographic Reference: Paper presented: IAEA/OECD Data Base Training Meeting, Halden (NO), September 25-27, 1996
Availability: Available from (1) as Paper EN 40298 ORA
Record Number: 199710214 / Last updated on: 1997-04-01
Original language: en
Available languages: en