CAJ | 학술논문

将非能动堆芯冷却系统（PXS）应用于聚变-裂变混合堆，使用RELAP5对混合堆一回路、部分二回路和PXS进行了建模，对冷管段双端剪切断裂大破口失水事故进行了瞬态计算和分析研究。计算结果显示：破口发生后出现两次燃料温度峰值，均发生在外包层，第1次峰值温度发生在约11 s ，为938.2 K ；第2次峰值温度发生在约50 s ，为608.7 K。两次燃料温度峰值均低于燃料U-10Zr的熔点，在可接受范围内。随着瞬态过程的深入，安注箱、堆芯补水箱及安全壳内储水箱的冷却水开始注入包层，使内外包层的坍塌液位开始回升，最终重新淹没堆芯。表明PXS在冷管段双端剪切断裂大破口失水事故下能保证混合堆堆芯的安全，将其应用于聚变-裂变混合堆是可行的。
장비능동퇴심냉각계통（PXS）응용우취변-렬변혼합퇴，사용RELAP5대혼합퇴일회로、부분이회로화PXS진행료건모，대랭관단쌍단전절단렬대파구실수사고진행료순태계산화분석연구。계산결과현시：파구발생후출현량차연료온도봉치，균발생재외포층，제1차봉치온도발생재약11 s ，위938.2 K ；제2차봉치온도발생재약50 s ，위608.7 K。량차연료온도봉치균저우연료U-10Zr적용점，재가접수범위내。수착순태과정적심입，안주상、퇴심보수상급안전각내저수상적냉각수개시주입포층，사내외포층적담탑액위개시회승，최종중신엄몰퇴심。표명PXS재랭관단쌍단전절단렬대파구실수사고하능보증혼합퇴퇴심적안전，장기응용우취변-렬변혼합퇴시가행적。
The passive core cooling system (PXS) was applied to fusion-fission hybrid reactor and a RELAP5 model was developed to represent the primary loop , partial secondary loop and the PXS components .The transient calculation and analysis were conducted for the double ended rupture LBLOCA on cold leg .The results show that two peak fuel temperatures appear in the outer blanket during the transient duration after the break happens .The first peak fuel temperature is 938.2 K at about 11 s and the second is 608.7 K at about 50 s ,but both are below the melting point of U-10Zr and within the acceptable range .With the transient process developing ,the coolant in ACC , CM T and IWST was injected to the blanket and the collapsed liquid level in the blanket started to rise ,and finally the reactor core was covered by injected coolant again .The results indicate that the PXS can ensure the safety of fusion-fission hybrid reactor in the double ended rupture LBLOCA on cold leg and it is feasible to apply the PXS to fusion-fission hybrid reactor .