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Analyses are carried out to assess the impact of nuclear data uncertaintieson keff for the European Lead Cooled Training Reactor (ELECTRA) using the TotalMonte Carlo method. A large number of Pu-239 random ENDF-formated librariesgenerated using the TALYS based system were processed into ACE format withNJOY99.336 code and used as input into the Serpent Monte Carlo neutrontransport code to obtain distribution in keff. The keff distribution obtainedwas compared with the latest major nuclear data libraries - JEFF-3.1.2,ENDF/B-VII.1 and JENDL-4.0. A method is proposed for the selection ofbenchmarks for specific applications using the Total Monte Carlo approach.Finally, an accept/reject criterion was investigated based on chi square valuesobtained using the Pu-239 Jezebel criticality benchmark. It was observed thatnuclear data uncertainties in keff were reduced considerably from 748 to 443pcm by applying a more rigid acceptance criteria for accepting random files.

Combining Total Monte Carlo and Benchmarks for nuclear data uncertainty propagation on an LFRs safety parameters