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小型快堆热膨胀反应性反馈的核热力耦合研究

Neutronic and Thermal-mechanical Coupling Study of the Reactivity Feedback of Thermal Expansion of Small Fast Reactors

  • 摘要: 与传统热中子堆相比,快堆燃料富集度较高、能谱较硬,反应堆运行过程中以U-238为主的多普勒展宽效应较弱,则堆芯结构形变对反应性的影响所占整体反应性反馈的份额增加。因此,对堆芯热膨胀反应性反馈效应的准确评估是快堆安全分析的一个重要组成部分。针对快中子脉冲堆,基于蒙特卡罗方法对热膨胀前后的模型进行临界计算,并结合有限元分析方法进行热力耦合计算,从而对Godiva-I和Godiva-IV脉冲堆的热膨胀反应性反馈效应开展核热力耦合计算分析研究。计算结果表明,燃料反应性温度系数计算值与实验值吻合良好,最大相对误差在5%以内,验证了该耦合方法的适用性和准确性。

     

    Abstract: Compared with traditional thermal neutron reactors, fast reactors have higher fuel enrichment and harder energy spectrum, and the Doppler broadening effect dominated by U-238 during reactor operation is weaker, so the influence of core structure deformation on reactivity accounts for a larger share of the overall reactivity feedback. Therefore, an accurate assessment of the reactive feedback effect of thermal expansion of the reactor core is an important part of the safety analysis of fast reactors. For pulse reactors, the critical calculation of the model before and after thermal expansion was carried out based on the Monte Carlo method, and the thermal-mechanical coupling calculation was carried out based on the finite element analysis method, so as to carry out the nuclear thermal coupling calculation and analysis of the thermal expansion reactivity feedback effect of Godiva-I pulse reactor and Godiva-IV pulse reactor. The calculation results show that the reactivity temperature coefficient of fuel expansion are in good agreement with the experimental values, and the maximum relative error is within 5%, which verifies the applicability and accuracy of the coupling method.

     

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