CAJ | 학술논문

本文针对熔盐堆的溶液核燃料流动临界堆芯模型，从粒子守恒方程出发，推导出考虑溶液核燃料流动情形下的中子动力学方程，并分别用解析方法和数值方法对一维情况进行求解，考察燃料流动对有效增殖系数、中子通量分布和缓发中子先驱核分布的影响，相互验证。结果表明：燃料流动对有效增殖系数的影响较小，而对缓发中子先驱核的分布影响较大；并且在流速较大时，流动对瞬发中子通量分布的影响不能忽略。
본문침대용염퇴적용액핵연료류동림계퇴심모형，종입자수항방정출발，추도출고필용액핵연료류동정형하적중자동역학방정，병분별용해석방법화수치방법대일유정황진행구해，고찰연료류동대유효증식계수、중자통량분포화완발중자선구핵분포적영향，상호험증。결과표명：연료류동대유효증식계수적영향교소，이대완발중자선구핵적분포영향교대；병차재류속교대시，류동대순발중자통량분포적영향불능홀략。
Considering the fuel salt flow effect of the molten salt reactor or other reactors using solution of nuclear fuel, the neutron dynamic model was derived based on the particle conservation equations, and the critical problems was resolved using analytical and numerical methods respectively to study the flow effect to effective multiplication factor, neutron and delayed neutron precursors distribution. The calculation result shows that the influence of fuel flow to the effective multiplication factor is small, but large to the delayed neutron precursors distribution. In addition, the influence of fuel flow on the prompt neutron distribution can’t be ignored when the velocity of the fuel is large.