Abstract
This work presents the validation of the Serpent 2 depletion calculations using experimental data from the second Advanced Gas Reactor irradiation campaign (AGR-2) performed at Idaho National Laboratory (INL) in the Advanced Test Reactor (ATR). The AGR irradiation tests provide valuable experimental data in the effort to develop high-integrity TRISO particle fuel and test its performance under high-temperature irradiation conditions. This paper is part of an effort to develop accurate and computationally efficient multi-physics neutronics and thermal-hydraulics models which will feed fuel performance models for TRISO fuel particles in pebble bed reactors. The AGR-2 irradiation test contains both UCO and UO2 TRISO particles which were irradiated over 3.5 years. For this study, the AGR-2 test train is reconstructed in full detail using Serpent 2, and depletion calculations replicating the experimental irradiation conditions are performed. Using the results of these depletion calculations for all 12 irradiation cycles, the fast neutron flux is compared with the corresponding experimental data. The Serpent 2 results for the fast neutron flux (En > 0.18 MeV) differ on average by 7.30% from the experimental results. These results provide confidence in the performance of Serpent 2 depletion calculations for TRISO fuel particles.
| Original language | English |
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| Title of host publication | Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables |
| Subtitle of host publication | United to Provide Carbon Neutral Power", ICONE 2023 |
| Publisher | American Society of Mechanical Engineers (ASME) |
| ISBN (Print) | 9784888982566 |
| State | Published - 2023 |
| Externally published | Yes |
| Event | 30th International Conference on Nuclear Engineering, ICONE 2023 - Kyoto, Japan Duration: May 21 2023 → May 26 2023 |
Publication series
| Name | International Conference on Nuclear Engineering, Proceedings, ICONE |
|---|---|
| Volume | 2023-May |
Conference
| Conference | 30th International Conference on Nuclear Engineering, ICONE 2023 |
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| Country/Territory | Japan |
| City | Kyoto |
| Period | 05/21/23 → 05/26/23 |
Funding
This research is being performed using funding received from the DOE Office of Nuclear Energy's Nuclear Energy University Programs (NEUP) and the Nuclear Regulatory Commission (NRC). For the computational calculations, this research uses the Savio computational cluster resource provided by the Berkeley Research Computing program at the University of California, Berkeley (supported by the U.C. Berkeley Chancellor, Vice Chancellor for Research, and Chief Information Officer). This research is being performed using data provided by Idaho National Laboratory. We thank Dr. Blaise Collin, Dr. Mitchell Plummer, and Mr. Keith Wilson for the help and support provided for this work. This research is being performed using funding received from the DOE Office of Nuclear Energy's Nuclear Energy University Programs (NEUP) and the Nuclear Regulatory Commission (NRC). For the computational calculations, this research uses the Savio computational cluster resource provided by the Berkeley Research Computing program at the University of California, Berkeley (supported by the U.C. Berkeley Chancellor, Vice Chancellor for Research, and Chief Information Officer). This research is being performed using data provided by Idaho National Laboratory. We thank Dr. Blaise Collin, Dr. Mitchell Plummer, and Mr. Keith Wilson for theehlpnaduspport provided for thisowrk.
Keywords
- AGR-2
- fast neutron flux
- fuel performance
- Serpent 2
- TRISO fuel
- validation