View source for Validation and verification

This page collects together all documents related to Serpent validation. The different categories are listed below. Each entry should include one or several references to <u>publicly accessible documents</u> where the results are reported. If you have additional documentation related to an already listed case, you can just add the reference in the list.

Serpent input and output files can be also be provided. When the input consists of multiple files, link to zip or gzip archives.

== Criticality ==

This section lists calculation cases from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP)<ref name="icsbep"/> and other sources. The main (but not only) purpose of the calculations is validation for criticality safety. 
=== ICSBEP Criticality Benchmarks ===

{|class="wikitable" style="text-align: left;"
! ICSBEP ID 
! Experiment
! Description
! Results 
! Refs. 
! Files
! Added by
! Date
|-  
| HEU-MET-FAST-001 
| Godiva 
| Bare sphere of highly enriched uranium 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| [[HEU-MET-FAST-001 | input]]
| JLe / VTT
| 2015/11/18
|-
| HEU-MET-FAST-002 
| Topsy 
| Highly enriched uranium sphere surrounded by a thick reflector of natural uranium 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| PU-MET-FAST-001 
| Jezebel 
| Bare sphere of plutonium 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| [[PU-MET-FAST-001 | input]]
| JLe / VTT
| 2015/11/18
|-
| PU-MET-FAST-006 
| Popsy 
| Plutonium sphere surrounded by a thick reflector of natural uranium 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| [[PU-MET-FAST-006 | input]]
| JLe / VTT
| 2015/11/18
|-
| U233-MET-FAST-001 
| Skidoo 
| Bare sphere of U-233 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| [[U233-MET-FAST-001 | input]]
| JLe / VTT
| 2015/11/18
|-
| U233-MET-FAST-006 
| Flattop23 
| U-233 sphere surrounded by a thick reflector of natural uranium 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| [[U233-MET-FAST-006 | input]]
| JLe / VTT
| 2015/11/18
|-
| IEU-MET-FAST-007 
| BigTen
| Large all-uranium-metal cylindrical core surrounded by a thick reflector of natural uranium 
| k<sub>eff</sub>, &alpha;<sub>R</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| IEU-MET-FAST-010 
| ZPR-U9 
| Cylindrical assembly of uranium metal with a thick depleted uranium reflector 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| MIX-MET-FAST-011 
| ZPR-MOX 
| Cylindrical assembly of mixed fissile plutonium and uranium metal reflected by graphite 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| HEU-MET-INTER-001 
| ZPR-HEU 
| Highly enriched uranium/iron cylinder reflected by stainless steel 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| PU-MET-INTER-002 
| ZPR-Pu 
| Cylindrical plutonium/carbon/stainless steel assembly with stainless steel and iron reflectors 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| LEU-SOL-THERM-004 
| Stacy-029, -033, -046 
| Water-reflected cylindrical tank with uranyl nitrate solution 
| k<sub>eff</sub>, &alpha;<sub>R</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| LEU-SOL-THERM-007 
| Stacy-030 
| Unreflected cylindrical tank with uranyl nitrate solution 
| k<sub>eff</sub>, &alpha;<sub>R</sub>
| <ref name="ifp"/>
| [[LEU-SOL-THERM-007 | input]]
| JLe / VTT
| 2015/11/18
|-
| LEU-SOL-THERM-016 
| Stacy-125 
| Water-reflected slabs of enriched uranyl nitrate solution 
| k<sub>eff</sub>, &alpha;<sub>R</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| LEU-SOL-THERM-021 
| Stacy-215 
| Unreflected cylindrical tank of uranyl nitrate solution 
| k<sub>eff</sub>, &alpha;<sub>R</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|}

=== Other Criticality Experiments ===

{|class="wikitable" style="text-align: left;"
! Experiment
! Description
! Results 
! Refs. 
! Files
! Added by
! Date
|-
| SNEAK-7A 
| Unmoderated PuO2/UO2 core with a depleted uranium reflector 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| SNEAK-7B 
| Unmoderated PuO2/UO2 core with a depleted uranium reflector 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| SNEAK-9C1 
| Unmoderated core UO2 core with a depleted uranium reflector
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| SNEAK-9C2 
| Unmoderated PuO2/UO2 core with Na and reflected by depleted uranium 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| Masurca-R2 
| Unmoderated core with enriched uranium fuel surrounded by a UO2–Na mixture blanket and by steel shielding 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| Masurca-Z2 
| Unmoderated core with plutonium and depleted uranium fuel surrounded by a UO2–Na mixture blanket and by steel shielding 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| FCA-XIX-1 
| Highly enriched uranium core surrounded by UO2/Na and uranium metal blanket regions
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| FCA-XIX-2 
| Plutonium/uranium core surrounded by UO2/Na and uranium metal blanket regions
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| FCA-XIX-3 
| Plutonium core surrounded by UO2/Na and uranium metal blanket regions 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| TCA 
| Light water moderated low-enriched UO2 core in the tank-type critical assembly
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| IPEN 
| Low enriched UO2 fuel rods inside a light water filled tank 
| k<sub>eff</sub>, &beta;<sub>eff</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| Winco 
| Slab tank assembly consisted of two thin coaxial slab tanks uranyl nitrate solution
| k<sub>eff</sub>, &alpha;<sub>R</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| Sheba-II 
| Enriched uranyl fluoride Solution High-Energy Burst Assembly (SHEBA)
| k<sub>eff</sub>, &alpha;<sub>R</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| SHE-8 
| A hexagonal core with graphite matrix tubes and low enriched uranium fuel dispersed in graphite rods
| k<sub>eff</sub>, &alpha;<sub>R</sub>
| <ref name="ifp"/>
| N/A
| JLe / VTT
| 2015/11/18
|}

=== Application Specific Validation ===

{|class="wikitable" style="text-align: left;"
! Application
! Description
! Results 
! Refs. 
! Files
! Added by
! Date
|-
| SNF wet storage (78 cases)
| Hexagonal fuel assemblies separated by borated steel and water.
| k<sub>eff</sub>
| <ref name="SerpentCritSafetyValidation17"/>
| N/A
| VVa / VTT
| 2017/05/02
|}

== Research reactors & other experiments ==

This section collects studies involving full-scale modelling of research reactors and other experimental facilities. The results may include criticality calculations, but also other reactor physics data (flux or power distributions, spectral indices, etc.). Experiments focused on criticality safety validation alone should be included in the section above.

{|class="wikitable" style="text-align: left;"
! Calculation case
! Description
! Refs. 
! Files
! Added by
! Date
|-
| Full-core burnup calculations for the OPAL research reactor 
| First six operating cycles simulated at INVAP with Serpent 2, and compared to experimental results
| <ref name="opal1"/>
| N/A
| JLe / VTT
| 2016/03/02
|-
| Triga Mark II benchmark experiments
| Serpent 2 and MCNP calculations for the Triga Mark II reactor at JSI, Slovenia
| <ref name="triga1"/>
| N/A
| JLe / VTT
| 2016/09/16
|-
| FREYA fast critical experiments
| Characterization of the critical VENUS-F cores (SCK.CEN, Belgium) with Serpent 2 in the framework of the FP7 EURATOM project FREYA
| <ref name="freya1"/>
| N/A
| EF / HZDR
| 2017/05/15
|-
| Prismatic HTGR critical assembly calculations
| Reactor physics calculations for the VHTRC (JAEA, Japan) critical assembly using Serpent 2 and SCALE/KENO-VI
| <ref name="bostelmann1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| Pebble-bed HTGR critical assembly calculations
| Criticality calculations for the ASTRA (Kurchatov Institute, Russia) critical assembly using Serpent 2
| <ref name="rintala1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| VVER-1000 mock-up calculations
| Criticality and other reactor physics calculations calculations for the LR-0 reactor (Rez, Czech Republic) using Serpent 2
| <ref name="chersola1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| VENUS-2 Benchmark
| Criticality and power distribution, comparison to experimental data an MCNP calculations
| <ref name="calic1"/>
| N/A
| JLe / VTT
| 2022/05/22
|-
| Reactor dosimetry calculations for FiR 1 Triga Mk-II reactor
| Comparison of predicted reaction rates of nickel and manganese at 9 different positions to measurements
| <ref name="fir1"/>
| N/A
| JLe / VTT
| 2022/05/23
|-
| Criticality benchmarks for the Pavia Triga Mk-II reactor
| Comparison of multiplication factor and control rod calibration curves to measurements
| <ref name="pavia1"/>
| N/A
| JLe / VTT
| 2022/05/23
|}

== Burnup calculations ==

This section includes validation calculations involving fuel burnup. The results may include material compositions, criticality power distributions, etc. Since experimental data is scarce, also code-to-code comparisons may be included.

{|class="wikitable" style="text-align: left;"
! Calculation case
! Description
! Experimental data
! Refs. 
! Files
! Added by
! Date
|-
| LWR-PROTEUS Phase-II calculations
| Isotopic compositions calculated using Serpent 2, MCNPX and VESTA and compared to experimental data
| YES
| <ref name="peccia1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| 2D infinite-lattice PWR assembly burnup calculations (Kr&scaron;ko NPP)
| ''k''<sub>eff</sub> and pin-power distributions calculated using Serpent 1, DRAGON, FA2D and SCALE/NEWT
| NO
| <ref name="grgic1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| Full-core GFR burnup calculations (Allegro)
| ''k''<sub>eff</sub>, flux spectra and isotopic compositions calculated using Serpent 2 and MONTEBURNS
| NO
| <ref name="chersola2"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| Full-core SFR burnup calculations
| ''k''<sub>eff</sub> , power distribution and isotopic compositions calculated using Serpent 2 and KANEXT
| NO
| <ref name="lopez1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| OECD/NEA Burn-up Credit Criticality Safety Benchmark Phase VII calculations
| ''k''<sub>eff</sub> and isotopic compositions calculated using Serpent 2 and MCNP6
| NO
| <ref name="herrero1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| CB6 benchmark on VVER-440 final disposal
| Decay and criticality calculations, comparison between Serpent 2 and ORIGEN
| NO
| <ref name="lahtinen1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| AER VVER-440 GD Fuel Burnup Benchmark
| ''k''<sub>eff</sub> and isotopic compositions calculated using Serpent 2 and compared to benchmark reference results
| NO
| <ref name="lotsch1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| OECD/NEA benchmark for VVER-1000 fuel assembly with GD
| ''k''<sub>eff</sub> and isotopic compositions calculated using Serpent 2 and compared to benchmark reference results
| NO
| <ref name="lotsch1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| OECD/NEA benchmark for VVER-1000 fuel assembly with LEU and MOX fuel
| ''k''<sub>eff</sub>, reactivity coefficients and isotopic compositions calculated using Serpent 2 and SCALE, and compared to benchmark reference results
| NO
| <ref name="mercatali1"/>
| N/A
| JLe / VTT
| 2017/05/16
|-
| OECD/NEA Burn-up Credit Criticality Safety Benchmark Phase III-C
| ''k''<sub>eff</sub>, isotopic compositions calculated for BWR assemblies with various codes including Serpent 2 with cross comparison.
| NO
| <ref name="P3C"/>
| N/A
| VVa / VTT
| 2020/08/25
|-
| SKB Decay heat blind test benchmark
| Decay heat, mass of <sup>137</sup>Cs and <sup>148</sup>Nd 
| YES
| <ref name="SKB1"/>
| N/A
| JLe / VTT
| 2022/05/13
|}

== Dynamic simulations and transients ==

This section includes validation calculations involving time-dependent neutronics and reactor transients. 

{|class="wikitable" style="text-align: left;"
! Calculation case
! Description
! Experimental data
! Refs. 
! Files
! Added by
! Date
|-
| Serpent-SUBCHANFLOW calculations for the SPERT-IIIE hot full power tests
| Transient experiments T-84 and T-85 are calculated using pin-by-pin coupling and compared with experimental results
| YES
| <ref name="ferraro1"/>
| N/A
| JLe / VTT
| 2022/05/23
|-
| Serpent-OpenFOAM calculations for the TREAT reactor
| TREAT M2 transient 2580
| YES
| <ref name="sorrell1"/>
| N/A
| JLe / VTT
| 2022/05/23
|}

== Fusion ==

This section includes validation calculations for fusion applications. 

{|class="wikitable" style="text-align: left;"
! Calculation case
! Description
! Experimental data
! Refs. 
! Files
! Added by
! Date
|-
| Variance reduction and shielding calculations for fusion applications
| SINBAD and EU DEMO HCPB, comparison to MCNP and experimental data 
| YES
| <ref name="valentine1"/>
| N/A
| JLe / VTT
| 2022/05/23
|-
| Serpent and MCNP calculations for the EU-DEMO BL2017 model
| EU DEMO HCPB breeding blanket
| NO
| <ref name="lu1"/>
| N/A
| JLe / VTT
| 2022/05/23
|-
| Serpent and MCNP fusion neutronics analyses at JET
| Comparison of fluxes and reaction rates at several positions
| NO
| <ref name="zohar1"/>
| N/A
| JLe / VTT
| 2022/05/23
|}

== Photon transport ==

This section is intended for validation studies concerning the photon transport capabilities of Serpent.

{|class="wikitable" style="text-align: left;"
! Calculation case
! Description
! Modelled cases
! Refs. 
! Files
! Added by
! Date
|-
| Kansas <sup>60</sup>Co gamma-ray skyshine experiment
| <sup>60</sup>Co source placed in a horizontally shielded concrete silo with or without roofing. Exposure rates measured between 30 m and 700 m from the source. Comparisons to experimental data and MCNP6.
| Experiments 1, 2 and 3.
| <ref name="gammaVV17"/>
| N/A
| VVa / VTT
| 2017/01/27
|-
| Hupmobile TLD experiment
| Dose rates from a <sup>137</sup>Cs source to TLDs inside a teflon cylinder. Comparisons to MCNP6, no experimental data.
| One experiment with a <sup>137</sup>Cs source.
| <ref name="gammaVV17"/>
| N/A
| VVa / VTT
| 2017/01/27
|-
| Dose rate from irradiated PWR assemblies
| Benchmark calculation of gamma dose rate from 1 m distance of PWR-UOX and PWR-MOX assemblies
| UOX and MOX assembly 30 v and 3.7 v after irradiation.
| <ref name="EschbachGLOBAL17"/>
| N/A
| VVa / VTT
| 2021/01/28
|-
| Radiation shielding for neutrons and photons
| ICSBEP ALARM-benchmarks
| ALARM-CF-FE-SHIELD-001 and ALARM-CF-PB-SHIELD-001
| <ref name="hakkinen1"/>
| N/A
| JLe / VTT
| 2022/05/23
|}

== Direct full core modelling (computational benchmark) ==

This section is intended for code-to-code validation studies for direct full core (2D or 3D) modelling.

{|class="wikitable" style="text-align: left;"
! Calculation case
! Description
! Modelled cases
! Refs. 
! Files
! Added by
! Date
|-
| 
| 
| 
| 
| 
| 
| 
|}

== Direct full core modelling (experimental data) ==


This section is intended for code-to-code or code-to-experiment validation studies for direct full core (2D or 3D) modelling of real world reactors with experimental data available.

{|class="wikitable" style="text-align: left;"
! Calculation case
! Description
! Modelled cases
! Refs. 
! Files
! Added by
! Date
|-
| Khmelnitsky-2 (X2) benchmark
| Khmelnitsky-2 initial core loading at HZP state. Comparison to experimentally measured data.
| Measured critical state k-eff, critical boron, ITCs, SCRAM worths, CR group #10 differential and integral worth.
| <ref name="BilodidANE20_X2"/>
| -
| VVa / VTT
| 2021-06-24
|}

== Reduced-order methods ==

This section is intended for validation studies in which Serpent-generated cross sections are used for nodal diffusion and other reduced-order calculations. The studies may include comparison to experimental data or reference Serpent 3D calculations. Also comparison of group constants calculated by Serpent vs. results by other codes can be included.

=== Full-core calculations ===

{|class="wikitable" style="text-align: left;"
! Calculation case
! Code sequence
! Description
! Results 
! Refs. 
! Files
! Added by
! Date
|-
| MIT BEAVRS Benchmark 
| Serpent-ARES 
| 1000 MW PWR HZP initial core calculations using nodal diffusion code ARES 
| Power distributions 
| <ref name="ares1"/>
| N/A
| JLe / VTT
| 2015/11/18
|-
| MIT BEAVRS Benchmark 
| Serpent-ARES 
| 1000 MW PWR HFP initial core and burnup calculations using nodal diffusion code ARES 
| Power distributions, control rod bank worths, boron dilution curve 
| <ref name="ares2"/>
| [[BEAVRS benchmark |input]]
| JLe / VTT
| 2016/08/26
|}

=== Assembly-level code-to-code comparisons ===

{|class="wikitable" style="text-align: left;"
! Calculation case
! Reference codes
! Description
! Refs. 
! Files
! Added by
! Date
|-
| Standard test cases run for each update 
| MCNP5 
| PWR, BWR, CANDU, SFR and HTGR calculations using different cross section libraries
| <ref name="std1"/>
| N/A
| JLe / VTT
| 2015/11/18
|}

== References ==

<references>
<ref name="icsbep">https://www.oecd-nea.org/science/wpncs/icsbep/handbook.html</ref>
<ref name="ifp">Leppänen, J., Aufiero, M., Fridman, E., Rachamin, R., and van der Marck, S. ''"Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code."'' Ann. Nucl. Energy, [http://www.sciencedirect.com/science/article/pii/S0306454913005628 65 (2014) 272-279].</ref>
<ref name="SerpentCritSafetyValidation17">Valtavirta, V. ''"Criticality safety validation of Serpent for nuclear fuel wet storage calculations"'' Customer Report, [https://serpent.vtt.fi/download/VTT-CR-02424-17_web.pdf VTT-CR-02424-17 (link to report)] (2017).</ref>
<ref name="std1">[https://serpent.vtt.fi/validation/lattice_calculations/ Standard validation cases at Serpent website]</ref>
<ref name="ares1">Leppänen, J., Mattila, R. and Pusa, M. ''"Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark - Initial core at HZP conditions."'' Ann. Nucl. Energy, [http://www.sciencedirect.com/science/article/pii/S030645491400084X 69 (2014) 212-225].</ref>
<ref name="ares2">Leppänen, J. and Mattila, R. ''"Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark – HFP conditions and fuel cycle 1 simulation."'' Ann. Nucl. Energy, [http://www.sciencedirect.com/science/article/pii/S0306454916304121 96 (2016) 324-331].</ref>
<ref name="opal1">Ferraro, D. and Villarion, E. ''"Full 3-D core calculations with refueling for the OPAL Research Reactor using Monte Carlo Code Serpent 2."'' Ann. Nucl. Energy, [http://www.sciencedirect.com/science/article/pii/S0306454916300640 92 (2016) 369-377].</ref>
<ref name="triga1">Ćalić, D., Žerovnik, G. Trkov, A. and Snoj, L. ''"Validation of the Serpent 2 code on TRIGA Mark II benchmark experiments."''  Appl. Radiat. Isot., [http://www.sciencedirect.com/science/article/pii/S0969804315302165 107 (2016) 165-170].</ref>
<ref name="fir1">Viitanen, T. and Leppänen, J. ''"Validating the Serpent Model of FiR 1 Triga Mk-II Reactor by Means of Reactor Dosimetry."'' EJP Web conferences, [https://doi.org/10.1051/epjconf/201610603010 106 (2016) 03010].</ref>
<ref name="freya1">Fridman, E., Kochetkov, A., and  Krása, A. ''"Modeling of FREYA fast critical experiments with the Serpent Monte Carlo code."'' Ann. Nucl. Energy, [http://www.sciencedirect.com/science/article/pii/S0306454917300488 108 (2017) 239–252].</ref>
<ref name="bostelmann1">Bostelmann, F., Hammer H., Ortensi, J., Strydom G., Velkov, K. and Zwermann, W.. ''"Criticality calculations of the Very High Temperature Reactor Critical
Assembly benchmark with Serpent and SCALE/KENO-VI."'' Ann. Nucl. Energy, [http://www.sciencedirect.com/science/article/pii/S0306454915300177 90 (2016) 343–352].</ref>
<ref name="rintala1">Rintala, V., Suikkanen, H., Leppänen, J. and Kyrki-Rajamäki, R. ''"Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code."'' Ann. Nucl. Energy, [http://www.sciencedirect.com/science/article/pii/S0306454914006008 77 (2015) 223-230].</ref>
<ref name="chersola1">Chersola, D., Mazzini, G., Kostal, M., Miglierini, B., Hrehor, M., Lomonaco, G., Borreani, W. and Ruscak, M. ''"Application of Serpent 2 and MCNP6 to study different criticality
configurations of a VVER-1000 mock-up."'' Ann. Nucl. Energy, [http://www.sciencedirect.com/science/article/pii/S0306454916301086 94 (2016) 109-122].</ref>
<ref name="chersola2">Chersola, D., Lomonaco, G., Marotta, R. and Mazzini, G. ''"Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration."'' Nucl. Eng. Design, [http://www.sciencedirect.com/science/article/pii/S0029549314001964 273 (2014) 542-554].</ref>
<ref name="calic1">Ćalić, D., Štancar, Ž. and Snoj, L. ''"Analysis of VENUS-2 benchmark using Serpent 2 code."''  Ann. Nucl. Energy., [https://doi.org/10.1016/j.anucene.2018.02.051 116 (2018) 334-346].</ref>
<ref name="grgic1">Grgić, D., Jecmenica, R. and Pevec, D. ''"Lattice codes pin power prediction comparison."'' Nucl. Eng. Design, [http://www.sciencedirect.com/science/article/pii/S0029549311010089 246 (2012) 27-40].</ref>
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</references>

[[Category:Validation and verification|*]]