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research-article

Criticality calculations and basic sensitivity/uncertainty investigation of LR-0 benchmark core with various material insertions in SCALE

[+] Author and Article Information
Tomás Czakoj

Research Centre Rez, 250 68 Husinec-Rez 130, Czech Republic
tomas.czakoj@cvrez.cz

Evzen Losa

Research Centre Rez, 250 68 Husinec-Rez 130, Czech Republic
evzen.losa@cvrez.cz

1Corresponding author.

ASME doi:10.1115/1.4041692 History: Received June 20, 2018; Revised October 03, 2018

Abstract

Three dimensional Monte Carlo code KENO-VI of SCALE-6.2.2 code system was applied for criticality calculation of LR-0 reactor core. A central module placed in the center of the core was filled by graphite, FLINA and FLIBE materials. The multiplication factor was obtained for all cases using both ENDF/B-VII.0 and ENDF/B-VII.1 nuclear data libraries. Obtained results were compared with benchmark calculations in MCNP6 using ENDF/B-VII.0 library. The results of KENO-VI calculations are found to be in good agreement with results obtained by the MCNP6. The discrepancies are typically within tens of pcm excluding the case with FLINA filling. Sensitivities and uncertainties of the reference case with no filling were determined by a continuos-energy version of TSUNAMI sequence of SCALE-6.2.2. The obtained uncertainty in multiplication factor due to the uncertainties in nuclear data is about 650 pcm with ENDF/B-VII.1.

Copyright (c) 2018 by ASME
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