Lin Peng , Yuan Yang , Songyang Li , Zhonghao Nong , Simiao Tang
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引用次数: 0
Abstract
TRISO particles, recognized for their excellent ability to retain fission products and maintain structural integrity, are crucial candidates for space reactor applications. However, current studies primarily focus on conventional reactor conditions, leaving gaps in understanding their performance under the more demanding conditions of space reactors. This study aims to address these gaps by developing a thermal-mechanical coupling simulation for TRISO particles using the finite element method, incorporating comprehensive material properties, irradiation behaviors and fission gas release. The model was validated through tangential stress comparison in IAEA CRP-6 Case 8 and further verified with TRISO particle calculation results from the BISON code, demonstrating the reliability of the simulation and the accuracy of the model. Under space reactor conditions, the higher kernel power, prolonged fuel lifetime, and increased fission gas pressure significantly elevate the tensile stress in the CVD-SiC layer, raising its failure probability at the later stages of burnup. While the SiC layer remains highly reliable under conventional HTGR conditions, its failure probability under space reactor conditions may become substantial. Sensitivity analysis was conducted by varying five key parameters. The results revealed that higher temperatures, greater fission rates, and extended operation times significantly increase the buffer-IPyC gas pressure, posing the greatest challenge to TRISO particle performance in space reactors. These findings reveal the greatest challenges for TRISO particles in space reactors compared to conventional reactors and underscore the necessity of enhancing their designs to ensure reliability and structural integrity in space reactor applications.
TRISO粒子因其保留裂变产物和保持结构完整性的优异能力而得到认可,是空间反应堆应用的关键候选者。然而,目前的研究主要集中在常规反应堆条件下,在了解其在更苛刻的空间反应堆条件下的性能方面存在空白。本研究旨在通过采用有限元方法对TRISO粒子进行热-力学耦合模拟,包括材料综合性能、辐照行为和裂变气体释放,以解决这些空白。通过IAEA CRP-6 Case 8的切向应力对比和BISON代码的TRISO粒子计算结果对模型进行验证,验证了模拟的可靠性和模型的准确性。在空间反应堆条件下,更高的核功率、延长的燃料寿命和增加的裂变气体压力显著提高了CVD-SiC层的拉应力,提高了CVD-SiC层在燃耗后期的失效概率。虽然SiC层在常规高温高温堆条件下仍然具有很高的可靠性,但在空间堆条件下其失效概率可能会变得很大。通过改变5个关键参数进行敏感性分析。结果表明,更高的温度、更高的裂变速率和延长的运行时间显著增加了缓冲- ipyc气体压力,对空间反应堆中的TRISO粒子性能提出了最大的挑战。这些发现揭示了与传统反应堆相比,空间反应堆中TRISO粒子面临的最大挑战,并强调了加强其设计以确保空间反应堆应用的可靠性和结构完整性的必要性。
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.