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Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool

Marjan Kromar   ORCID icon 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

Puni tekst: engleski, pdf (822 KB) str. 0-0 preuzimanja: 59* citiraj
APA 6th Edition
Kromar, M. i Kurinčič, B. (2013). Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool. Journal of Energy, 62 (1-4), 0-0. Preuzeto s https://hrcak.srce.hr/199060
MLA 8th Edition
Kromar, Marjan i Bojan Kurinčič. "Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool." Journal of Energy, vol. 62, br. 1-4, 2013, str. 0-0. https://hrcak.srce.hr/199060. Citirano 28.05.2020.
Chicago 17th Edition
Kromar, Marjan i Bojan Kurinčič. "Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool." Journal of Energy 62, br. 1-4 (2013): 0-0. https://hrcak.srce.hr/199060
Harvard
Kromar, M., i Kurinčič, B. (2013). 'Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool', Journal of Energy, 62(1-4), str. 0-0. Preuzeto s: https://hrcak.srce.hr/199060 (Datum pristupa: 28.05.2020.)
Vancouver
Kromar M, Kurinčič B. Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool. Journal of Energy [Internet]. 2013 [pristupljeno 28.05.2020.];62(1-4):0-0. Dostupno na: https://hrcak.srce.hr/199060
IEEE
M. Kromar i B. Kurinčič, "Comparison of the SCALE, SERPENT and MCNP Criticality Safety Calculation of the NPP Krško Spent Fuel Pool", Journal of Energy, vol.62, br. 1-4, str. 0-0, 2013. [Online]. Dostupno na: https://hrcak.srce.hr/199060. [Citirano: 28.05.2020.]

Sažetak
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.

Hrčak ID: 199060

URI
https://hrcak.srce.hr/199060

Posjeta: 88 *