COMPARISON OF THERMAL HYDRAULIC AND NUCLEAR ASPECTS IN A STANDARD HEU CORE AND A TYPICAL LEU CORE FOR THE HFR PETTEN. A CASE STUDY
Within the framework of the RERTR program various HEU-LEU core calculations have been performed by ANL in a cooperative effort with ECN and JRC Petten. The main purpose of this work has been to gain competence in analysing HEU-LEU core conversions for high power Materials Testing Reactors and to assist in a possible HEU-LEU conversion of the HFR Petten. For reference purposes the present HFR standard core (HEU) in the old vessel geometry was calculated at first. As a next step the new vessel geometry and the increased fuel weights were taken into account. Subsequently various LEU HFR core options have been analyzed. Main parameters in the LEU study were the uranium loading in the meat, the fuel type, the thickness of the meat, the number of fuel plates per element and the type of burnable poison applied. Though the study has not yet been completed, one of its striking preliminary results concerns the increased power peaking in the LEU fuel elements as compared with the HEU situation. A preliminary analysis of the thermal characteristics of a typical LEU core as compared with a standard HEU core has been made and is presented in the paper. A short survey of the various LEU calculations is given. The thermal safety analysis procedure for the HFR, as based on the flow instability criterion, is clarified. Finally, the thermal comparison HEU versus LEU and the resulting conclusions are presented.
Bibliographic Reference: INTERNATIONAL MEETING ON RESEARCH AND TEST REACTOR CORE CONVERSION FROM HEU TO LEU FUELS, OAK BROOK, CHICAGO (USA), OCT. 15-18, 1984 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31815 ORA
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Record Number: 1989123021700 / Last updated on: 1987-01-01
Available languages: en