Abstract Fuel depletion analysis is important for the evolutionary behavior of nuclear materials in the reactor. For the accelerator-driven sub-critical system (ADS), the main research focuses on the transmutation of minor actinides (MA) and long-lived fission products (LLFP). To perform nuclide inventory calculation of ADS, a new nuclide point-depletion code IMPC-Depletion has been developed by utilizing Chebyshev Rational Approximation Method (CRAM) and Transmutation Trajectory Analysis method (TTA) to solve the Bateman equation. Besides, a new burnup code system named IMPC-Burnup2.0 which couples the OpenMC neutron transport code and IMPC-Depletion is also developed to perform burnup behavior analysis of ADS sub-critical system. Finally, the decay of Np237 and fixed neutron flux irradiation of 3.4% UO 2 are calculated and compared with other reference results to verify IMPC-Depletion. Moreover, IAEA-ADS and OECD/NEA ADS Minor Actinide Burner benchmark are calculated using IMPC-Burnup2.0 to testing the capability for burnup analysis for ADS sub-critical core. Numerical results show that IMPC-Burnup2.0 is reliable when compared with reference values and it can be used to solve burnup problem of ADS.

中文翻译：

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加速器驱动次临界系统燃耗计算代码IMPC-Burnup2.0的开发与验证

摘要 燃料消耗分析对于反应堆中核材料的演化行为具有重要意义。对于加速器驱动的亚临界系统（ADS），主要研究集中在次锕系元素（MA）和长寿命裂变产物（LLFP）的嬗变。为了执行 ADS 的核素清单计算，利用切比雪夫有理逼近法 (CRAM) 和嬗变轨迹分析法 (TTA) 求解贝特曼方程，开发了一种新的核素点消耗代码 IMPC-Depletion。此外，还开发了一种新的燃耗代码系统IMPC-Burnup2.0，它结合了OpenMC中子传输码和IMPC-Depletion，用于ADS亚临界系统的燃耗行为分析。最后是 Np237 的衰变和 3 的固定中子通量辐照。计算 4% UO 2 并与其他参考结果进行比较以验证 IMPC-Depletion。此外，IAEA-ADS和OECD/NEA ADS Minor Actinide Burner benchmark采用IMPC-Burnup2.0计算，测试ADS亚临界堆芯燃耗分析能力。数值结果表明IMPC-Burnup2.0与参考值相比是可靠的，可用于解决ADS的燃耗问题。