Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor

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Abstract

The assessment of the (safety-related) performance of the driver fuel rods of the reactor is of key importance to the licensing process of MYRRHA, which is currently in its “pre-licensing” phase. Although the fuel rod design is largely based on past (sodium) fast reactor experience, the use of LBE as the coolant requires a thorough re-evaluation of the fuel design for specific MYRRHA conditions. This paper presents preliminary results.

Details

Original languageEnglish
Title of host publicationTRANSACTIONS- AMERICAN NUCLEAR SOCIETY
Place of PublicationUnited States
Pages1201-1204
Publication statusPublished - 1 Apr 2012
Event2012 American Nuclear Society annual meeting - Chicago, United States
Duration: 23 Jun 201229 Jun 2012

Conference

Conference2012 American Nuclear Society annual meeting
CountryUnited States
CityChicago
Period2012-06-232012-06-29

Keywords

  • MYRRHA, fuel performance

ID: 246776