前言 研究性重水反应堆的改建,在堆物理和工程启动期间,对轴向和径向中子通量分布、总流量、流量分配因子、工艺管入口压力等重要参数进行了测量。利用这些参数,以及早些时候完成的临界热负荷试验,采用热管和热点因子分析方法确定堆的最大允许功率Nmax。计算中,规定活性区各点元件表面温度Tw应该低于对应冷却剂的饱和温度Ts,并留有适当的裕度。如用不等式表示这个裕度,则 INTRODUCTION Reconstruction of a research heavy water reactor has measured important parameters such as axial and radial neutron flux distribution, total flow, flow distribution factor, and process tube inlet pressure during reactor physics and engineering start-up. Using these parameters, as well as the earlier critical heat load tests completed, heat pipe and hot spot factor analysis were used to determine the maximum allowable reactor power, Nmax. Calculation, the provisions of the active zone at each point of the element surface temperature Tw should be lower than the corresponding coolant saturation temperature Ts, leaving appropriate margin. If you use inequalities that this margin, then