In the framework of the IAEA Coordinated Research Project on "Studies of Innovative Reactor Technology Options for Effective Incineration of Radioactive Waste", a benchmark exercise was undertaken to analyse the behaviour of the MYRRHA facility in various accidental conditions. The transients were simulated by means of the RELAP and SITHER codes and the following set of accident scenarios was considered: loss of flow, loss of heat sink, overpower transient, overcooling and partial blockage of a subassembly. In addition, those accidents were simulated in two different situations depending on whether the proton beam is cut off (protected case) or not (unprotected case). In the IAEA benchmark two sub-critical core configurations are considered: a typical core configuration composed only of (U-Pu)O2 MOX fuel assemblies and another one including additional U-free minor actinides fuel assemblies. The present paper summarized the main results obtained with both cores.
|Title of host publication
|Advanced Reactor technology Options for Utilization and Transmutation of Actinides in Spent Nuclear Fuel
|Place of Publication
|IAEA - International Atomic Energy Agency
|Published - Sep 2009
|International Atomic Energy Agency Technical Documents