Original scientific paper
Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool
Marjan Kromar
orcid.org/0000-0001-8960-203X
; “Jožef Stefan” Institute Reactor Physics Division Jamova 39, 1001 Ljubljana, Slovenia
Bojan Kurinčič
; Nuclear Power Plant Krško Engineering Division - Nuclear Fuel & Reactor Core Vrbina 12, 8270 Krško, Slovenia
Abstract
Criticality safety reanalyzes of the NPP Krško spent fuel pool has been performed. Limiting
criticality cases at optimal moderation conditions are calculated using different SCALE code
versions (SCALE-4.4a, SCALE-5.1 and SCALE-6.1) with 44-group ENDF/B-V and 238-group
ENDF/B-VII.0 derived cross section libraries. Relative small discrepancies are observed.
Additional verification is provided with SERPENT and MCNP5 codes, which are capable to take
into account neutron continuous energy cross section library based on ENDF/B-VII.0 files.
Comparison has shown that the results of the pool design calculations are conservative, precluding
racks criticality even at optimum moderation conditions.
Keywords
Hrčak ID:
199060
URI
Publication date:
31.7.2017.
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