International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)

Methodical uncertainty of criticality precise calculations for fast lead reactor

28 Jun 2017, 17:50

1h 10m

Yekaterinburg

POSTER Track 6. Test Reactors, Experiments and Modeling and Simulations Poster Session 2

Speakers

Ms Ksenia Kalugina (JOINT-STOCK COMPANY «N.A. DOLLEZHAL RESEARCH AND DEVELOPMENT INSTITUTE OF POWER ENGINEERING»)Mrs Varvara Yufereva (JSC «N.A. Dollezhal Research and Developmant Institute of Power Engineering»)

Description

Criticality calculations for BFS-1 test facility with lead were performed using Monte-Carlo code MCU-BR to verify some evaluated neutron data files for fast spectra. These data files are RUSFOND, ENDF/B-VII.1, JEFF-3.2, JENDL-4.0, CENDL-3.1 and some combined data. The continuous energy treatment (ACE format) was used. Critical assemblies include the pellets consisted from fissionable materials, lead, stainless still and other. The average Keff evaluation for each critical assembly was obtained. Standard deviation for Keff at various data files is in interval 0,1% - 0,4% with probability of 0,55 - 0,82, for average Keff evaluation standard deviation is 0,14% with probability of 0,73.

Country/Int. Organization

JOINT-STOCK COMPANY «N.A. DOLLEZHAL RESEARCH AND DEVELOPMENT INSTITUTE OF POWER ENGINEERING»

Presentation materials

Material

Yufereva_Kalugina_Report_FR-17_ENG_2_ID_532.doc