TRIPOLI-4® Monte Carlo code ITER A-lite neutronic model validation

Jaboulay, Jean-Charles; Cayla, P.-Y.; Fausser, C.; Damian, F.; Lee, Yi-Kang; Puma, A. Li; Trama, Jean-Christophe

doi:10.1016/j.fusengdes.2014.02.038

Cited by 16 publications

(5 citation statements)

References 8 publications

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“…It can be ob tained that Dk eff = -0.024 % and s = = 0.016 %. The Dk eff re sult was within a ± 3s in ter val [25], which proves the ac cu racy of the SuperMC-OTF. To fur ther eval u ate the per for mance of SuperMC-OTF, the cal cu la tion times with the two meth ods are pro vided in tab.…”

Section: Ef Fec Tive Mul Ti Pli Ca Tion Fac Torsupporting

confidence: 54%

“…The k eff per for mance is af fected (more or less) by frac tions of key nuclides in the core re gion [27]. Some stud ies have in ves ti gated the re la tion ship be tween k eff and 208 Pb [25,26] in cool ant. Higher 15 N en rich ment of nitride fuel ma te rial has been ap plied to RBEC-M reac tors to im prove k eff per for mance.…”

Section: Ef Fec Tive Mul Ti Pli Ca Tion Fac Tormentioning

confidence: 99%

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Verification and application of SuperMC3.3 to lead-bismuth-cooled fast reactor

et al. 2019

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Lead-cooled fast re ac tors have mul ti lay ered de signs and large in ter nal tem per a ture dif ferences, which cause chal lenges in sim u lat ing re ac tor phys ics. SuperMC, a large-scale in tegrated soft ware sys tem for neutronics de sign, is in her ently able to ad dress com plex ge om etries and multi-tem per a ture prob lems. The pur pose of this study is to ver ify the ap pli ca bil ity of SuperMC to the lead-bis muth-cooled fast re ac tor RBEC-M. The multi-tem per a ture cross-sec tion gen er a tion func tion of SuperMC was em ployed and showed good per for mance. Based on the ENDF/B-VII.1 li brary, the ef fec tive mul ti pli ca tion fac tor k eff ob tained by SuperMC showed good agree ment with those from pre vi ous works. The re la tion ship of k eff and 15 N en rich ment ap plied to the fuel ma te rial was also stud ied, with the re sults show ing that in creased 15 N could sig nif i cantly im prove k eff. The ax ial power pro file and ki net ics param e ters for the bench mark were then cal cu lated and an a lyzed. This work thus ver i fied the ap pli ca bil ity of SuperMC for com pre hen sive neutronics sim u la tions for lead-bis muth-cooled fast re ac tors.

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Section: Ef Fec Tive Mul Ti Pli Ca Tion Fac Torsupporting

confidence: 54%

Section: Ef Fec Tive Mul Ti Pli Ca Tion Fac Tormentioning

confidence: 99%

Verification and application of SuperMC3.3 to lead-bismuth-cooled fast reactor

et al. 2019

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“…A huge effort of code and nuclear data verification was carried out to ensure energy balance coherence (comparison with NJOY HEATR module). In recent benchmark comparisons, between MCNP5 & TRIPOLI-4 ® , a good agreement is noticed for NH calculation: DEMO generic model [15] and ITER A-lite [10].…”

Section: Nuclear Heatingmentioning

confidence: 80%

“…The nuclear analysis of DEMO HCLL carried out at ENEA [9] is compared to the CEA one. This comparison is not a rigorous benchmark between TRIPOLI-4 ® and MCNP5 since the nuclear data are different, this kind of exercise have been done for ITER [10]. This paper presents the comparison of relevant nuclear responses: neutron wall loading, tritium breeding ratio, nuclear heating, neutron flux distribution, etc.…”

Section: Introductionmentioning

confidence: 99%

Comparison over the nuclear analysis of the HCLL blanket for the European DEMO

Jaboulay

Aiello

Aubert

et al. 2016

Fusion Engineering and Design

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This paper presents the comparison over the nuclear analysis of the European DEMO with HCLL blanket carried out with the TRIPOLI-4 ® Monte Carlo code and the JEFF-3.1.1 nuclear data library and with the MCNP5 Monte Carlo code and the FENDL-2.1 nuclear data library. The MCNP5 analysis was conducted firstly by ENEA with a detailed 3D model describing all the HCLL blanket internal structures. This MCNP5 model was converted into TRIPOLI-4 ® representation for performing the nuclear analysis at CEA with the objective to demonstrate consistency between both analyses. A very good agreement was obtained for all of the relevant nuclear responses (neutron wall loading, tritium breeding ratio, nuclear heating, neutron flux distribution, etc.), validating CEA's nuclear analysis approach, based on TRIPOLI-4 ® Monte Carlo code and JEFF-3.1.1 nuclear data library, for the European DEMO.

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“…Both MCAM and McCad provide the capability to generate a TRIPOLI-4 geometry input file from CAD file. MCAM was successfully tested on the ITER geometry [11] and was used to convert MCNP ITER A-lite model to the TRIPOLI syntax. In this work the TRIPOLI input file produced by McCad was tested.…”

Section: Tripoli-4mentioning

confidence: 99%