Difference between revisions of "Validation and verification"
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<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="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="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> | ||
</references> | </references> | ||
Revision as of 15:14, 16 September 2016
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 publicly accessible documents 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.
Contents
Criticality
ICSBEP Criticality Benchmarks
Following is a list of cases from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP) [1]
| ICSBEP ID | Experiment | Description | Results | Refs. | Files | Added by | Date |
|---|---|---|---|---|---|---|---|
| HEU-MET-FAST-001 | Godiva | Bare sphere of highly enriched uranium | keff, βeff | [2] | input | JLe / VTT | 2015/11/18 |
| HEU-MET-FAST-002 | Topsy | Highly enriched uranium sphere surrounded by a thick reflector of natural uranium | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| PU-MET-FAST-001 | Jezebel | Bare sphere of plutonium | keff, βeff | [2] | input | JLe / VTT | 2015/11/18 |
| PU-MET-FAST-006 | Popsy | Plutonium sphere surrounded by a thick reflector of natural uranium | keff, βeff | [2] | input | JLe / VTT | 2015/11/18 |
| U233-MET-FAST-001 | Skidoo | Bare sphere of U-233 | keff, βeff | [2] | input | JLe / VTT | 2015/11/18 |
| U233-MET-FAST-006 | Flattop23 | U-233 sphere surrounded by a thick reflector of natural uranium | keff, βeff | [2] | input | JLe / VTT | 2015/11/18 |
| IEU-MET-FAST-007 | BigTen L | arge all-uranium-metal cylindrical core surrounded by a thick reflector of natural uranium | keff, αR | [2] | N/A | JLe / VTT | 2015/11/18 |
| IEU-MET-FAST-010 | ZPR-U9 | Cylindrical assembly of uranium metal with a thick depleted uranium reflector | keff, βeff | [2] | 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 | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| HEU-MET-INTER-001 | ZPR-HEU | Highly enriched uranium/iron cylinder reflected by stainless steel | keff, βeff | [2] | 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 | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| LEU-SOL-THERM-004 | Stacy-029, -033, -046 | Water-reflected cylindrical tank with uranyl nitrate solution | keff, αR | [2] | N/A | JLe / VTT | 2015/11/18 |
| LEU-SOL-THERM-007 | Stacy-030 | Unreflected cylindrical tank with uranyl nitrate solution | keff, αR | [2] | N/A | JLe / VTT | 2015/11/18 |
| LEU-SOL-THERM-016 | Stacy-125 | Water-reflected slabs of enriched uranyl nitrate solution | keff, αR | [2] | N/A | JLe / VTT | 2015/11/18 |
| LEU-SOL-THERM-021 | Stacy-215 | Unreflected cylindrical tank of uranyl nitrate solution | keff, αR | [2] | N/A | JLe / VTT | 2015/11/18 |
Other Criticality Experiments
Other criticality experiments, not included in the ICSBEP handbook are listed below.
| Experiment | Description | Results | Refs. | Files | Added by | Date |
|---|---|---|---|---|---|---|
| SNEAK-7A | Unmoderated PuO2/UO2 core with a depleted uranium reflector | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| SNEAK-7B | Unmoderated PuO2/UO2 core with a depleted uranium reflector | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| SNEAK-9C1 | Unmoderated core UO2 core with a depleted uranium reflector | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| SNEAK-9C2 | Unmoderated PuO2/UO2 core with Na and reflected by depleted uranium | keff, βeff | [2] | 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 | keff, βeff | [2] | 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 | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| FCA-XIX-1 | Highly enriched uranium core surrounded by UO2/Na and uranium metal blanket regions | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| FCA-XIX-2 | Plutonium/uranium core surrounded by UO2/Na and uranium metal blanket regions | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| FCA-XIX-3 | Plutonium core surrounded by UO2/Na and uranium metal blanket regions | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| TCA | Light water moderated low-enriched UO2 core in the tank-type critical assembly | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| IPEN | Low enriched UO2 fuel rods inside a light water filled tank | keff, βeff | [2] | N/A | JLe / VTT | 2015/11/18 |
| Winco | Slab tank assembly consisted of two thin coaxial slab tanks uranyl nitrate solution | keff, αR | [2] | N/A | JLe / VTT | 2015/11/18 |
| Sheba-II | Enriched uranyl fluoride Solution High-Energy Burst Assembly (SHEBA) | keff, αR | [2] | 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 | keff, αR | [2] | N/A | JLe / VTT | 2015/11/18 |
Research reactors & other experiments
| 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. | [3] | 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. | [4] | N/A | JLe / VTT | 2016/09/16 |
Spatial homogenization
Assembly-level code-to-code comparisons
This section contains comparison of group constants calculated by Serpent vs. results by other codes.
| 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 | [5] | N/A | JLe / VTT | 2015/11/18 |
Full-core calculations
This section contains studies in which deterministic calculations using Serpent-generated cross sections are compared to full-scale Serpent reference calculations and/or experimental data.
| 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 | [6] | 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 | [7] | input | JLe / VTT | 2016/08/26 |
References
- ^ https://www.oecd-nea.org/science/wpncs/icsbep/handbook.html
- ^ 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, 65 (2014) 272-279.
- ^ 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, 92 (2016) 369-377.
- ^ Ćalić, D., Žerovnik, G. Trkov, A. and Snoj, L. "Validation of the Serpent 2 code on TRIGA Mark II benchmark experiments." Appl. Radiat. Isot., 107 (2016) 165-170.
- ^ Standard validation cases at Serpent website
- ^ 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, 69 (2014) 212-225.
- ^ 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, 96 (2016) 324-331.
