Community Research and Development Information Service - CORDIS


For programmes addressing the fuel rod behaviour under normal power reactor operation, it is required that the typical fuel rod temperatures should already be attained from approximately 150 W/cm LGHR. A 2DT code, extended and tailored for thermohydraulic investigations of LWR fuel rod testing capsules, was used to develop an appropriate irradiation device. In parallel out-of-pile tests with simulation heaters were performed in order to verify the new design. This paper describes the extension of the 2DT code with a two phase heat transfer module, and draws comparisons between model predictions and experimental results. The design adopted for the modified LWR fuel rod testing capsule is presented.

Additional information

Authors: KENNEDY D, JRC Petten Estab. (NL);MARKGRAF J F W, JRC Petten Estab. (NL);MCALLISTER S, JRC Petten Estab. (NL);RUYTER I, Kernforschungsanlage Julich GmbH (DE)
Bibliographic Reference: Paper presented: 30th Plenary Meeting of the European Working Group on Irradiation Technology, Mol (BE), Sept.28-30, 1988
Availability: Available from (1) as Paper EN 34416 ORA
Record Number: 198910249 / Last updated on: 1994-12-01
Original language: en
Available languages: en