Validation and verification

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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.

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 Large 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
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 [4] N/A EF / HZDR 2017/05/15

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

  1. ^ https://www.oecd-nea.org/science/wpncs/icsbep/handbook.html
  2. ^ 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.
  3. ^ 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.
  4. ^ 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.
  5. ^ Standard validation cases at Serpent website
  6. ^ 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.
  7. ^ 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.

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