Verification and Validation of Depletion Calculations for TRISO Fuel Against Data from the Second Advanced Gas Reactor Irradiation Campaign

被引：0

作者：

Siaraferas, Tatiana ^{[1
]}

Robert, Yves ^{[1
,2
]}

Fratoni, Massimiliano ^{[1
]}

机构：

[1] Univ Calif Berkeley, Dept Nucl Engn, Berkeley, CA 94720 USA

[2] Oak Ridge Natl Lab, Oak Ridge, TN USA

来源：

NUCLEAR TECHNOLOGY | 2025年

关键词：

Serpent; 2; verification and validation; AGR-2; TRISO fuel performance; depletion calculations; BURNUP;

D O I：

10.1080/00295450.2024.2430120

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Verification and validation of the Monte Carlo particle transport code Serpent 2 depletion calculation capabilities in the context of tristructural isotropic (TRISO) particles was performed against available data from the second Advanced Gas Reactor irradiation campaign (AGR-2), which was irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory. The AGR-2 test train contained both uranium oxycarbide (UCO) and uranium dioxide (UO2) TRISO particles, which were irradiated for 12 ATR power cycles over a period of 3.5 years. For this study, the AGR-2 test train was reconstructed in full detail using Serpent 2, and depletion calculations replicating the experimental irradiation conditions were performed. The fast neutron fluence and AGR-2 fuel burnup resulting from the depletion calculations for the 12 irradiation cycles are compared with the corresponding reported MCNP-computed data. The total AGR-2 fuel burnup accumulated by the end of the AGR-2 test train irradiation is also compared with available experimental data. The fission product inventory at the end of the AGR-2 irradiation obtained from the Serpent 2 depletion calculations is compared with the reported computational data. The Serpent 2 results for the fast neutron fluence (E-n > 0.18 MeV) differ on average by 5.10% from the MCNP-computed results. Similarly, the Serpent 2 model underpredicts the AGR-2 fuel burnup at the end of the irradiation by 5.13%, on average for all capsules, when compared with the MCNP-computed results and by 2.01% when compared with the experimental results. Last, the fission product inventory calculated by Serpent 2 is underpredicted by 5.27%, on average for all capsules, in comparison with the reference MCNP data. Serpent 2 is generally in satisfactory agreement with the AGR-2 reported values. These results provide confidence in the performance of Serpent 2 depletion calculations for TRISO fuel particles.

引用

页数：35