Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method

机译：基于Th-U燃料循环的加速器驱动亚临界反应堆中子行为的计算方法评估

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Accelerator Driven Subcritical Reactor (ADSR), offer advantages in terms of flexibility in using exotic fuels, allowing operation with reactivity variations and in term of intrinsic safety. Neutronic parameters of a modeled ADSR has been investigated using MCNPX 2.6 computational method. According to the obtained data, a neutron flux of ∼ 1014 (n/s.cm2) is suitable for minor actinide incineration. The system can efficiently burn minor actinide with a ∼1017 atom/s rate and produce power in the fission region with good fission per absorption ratio of 0.863.

机译：加速器驱动的亚临界反应堆（ADSR）在使用外来燃料方面具有灵活性，可在反应性变化的条件下运行以及在本质安全方面具有优势。已使用MCNPX 2.6计算方法研究了模型化ADSR的中子学参数。根据获得的数据，约10 ^{14 （n / s.cm ^{2 ）的中子通量适合于小型act系元素焚烧。该系统可以以〜10 ^{17 原子/秒的速率有效地燃烧次要的act系元素，并在裂变区以每单位吸收比0.863的良好裂变产生能量。}}}

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《2013 IEEE Nuclear Science Symposium and Medical Imaging Conference》|2013年|1-5|共5页
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Feghhi S.A.H.; Gholamzadeh Z.; Tenreiro C.; Kim H.;
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1. Evaluation of the neutronic performance of a fast traveling wave reactor in the Th-U fuel cycle [J] . Alina Ye. Pomysukhina, Yury P. Sukharev, German N. Vlasichev Nuclear Energy and Technology . 2020,第2期

机译：评估TH-U燃料循环中快速波浪反应器的中性性能
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机译：基于中子输运方法的加速器驱动亚临界反应堆的束流瞬态分析
3. Calculation of the neutron importance and weighted neutron generation time using MCNIC method in accelerator driven subcritical reactors [J] . M.Hassanzadeh, S.A.H. Feghhi, H. Khalafi Nuclear Engineering and Design . 2013,第sepa期

机译：使用MCNIC方法计算加速器驱动的亚临界反应堆中子的重要性和加权中子产生时间
4. Neutronic Behavior Evaluation of An Accelerator Driven Subcritical Reactor Based on Th-U Fuel Cycle using Computational Method [C] . S. A. H. Feghhi, Z. Gholamzadeh, C. Tenreiro, IEEE Nuclear Science Symposium . 2013

机译：基于TH-U燃料循环的加速器驱动亚临界反应器的中性行为评价使用计算方法
5. Neutronics methods for the dynamic analysis of source-driven subcritical multiplying systems. [D] . Burns, Thomas Dean, Jr. 1999

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7. Figure 8 from: Pomysukhina AYe, Sukharev YP, Vlasichev GN (2020) Evaluation of the neutronic performance of a fast traveling wave reactor in the Th-U fuel cycle. Nuclear Energy and Technology 6(2): 77-82. https://doi.org/10.3897/nucet.6.54629 [O] . Alina Ye. Pomysukhina, Yury P. Sukharev, German N. Vlasichev 2020

机译：图8来自：Pomysukhina Aye，Sukharev YP，Vlasichev GN（2020）评估Th-U燃料循环中快速行驶波反应器的中性性能。核能和技术6（2）：77-82。 https://doi.org/10.3897/nucet.6.54629
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Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method

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