CAJ | 학술논문

在核反应堆乏燃料后处理主工艺流程中，核燃料通常以溶液状态存在，可能发生核临界事故。研究核临界事故的产生机理和事故源项，对预防事故发生、缓解事故后果、事故应急响应与医学诊治均具有十分重要的意义。本文采用点堆动力学方程结合二维热传导方程，开发了基于圆柱形溶液贮存容器的瞬态特性分析程序GETAC ，利用该程序计算了法国SILENE瞬态实验装置模拟临界事故功率随时间的变化，得到了功率振荡在不同反应性引入大小、方式和有无外中子源等情况下的变化规律，计算分析结果与瞬态实验测量数据以及国外其他程序计算结果较一致。
재핵반응퇴핍연료후처리주공예류정중，핵연료통상이용액상태존재，가능발생핵림계사고。연구핵림계사고적산생궤리화사고원항，대예방사고발생、완해사고후과、사고응급향응여의학진치균구유십분중요적의의。본문채용점퇴동역학방정결합이유열전도방정，개발료기우원주형용액저존용기적순태특성분석정서GETAC ，이용해정서계산료법국SILENE순태실험장치모의림계사고공솔수시간적변화，득도료공솔진탕재불동반응성인입대소、방식화유무외중자원등정황하적변화규률，계산분석결과여순태실험측량수거이급국외기타정서계산결과교일치。
The nuclear fuel exists as solution in the process of spent fuel reprocessing , and it may result in nuclear criticality accident to occur .It is very important to study the mechanism and source term of the criticality accident for preventing accident , consequence mitigation , emergency response and medical diagnostic treatment . A transient analysis code GETAC was developed based on the cylindrical vessel with the point reactor kinetics equation and 2-D thermal conduction equation .Calculation was conducted with this code to simulate the power transient during criticality accident of the SILENE transient experimental facility of France .The power oscillation and its changes under conditions with different values and modes of reactivity insertion ,and with and without external neutron source were obtained .Simulation results are consistent with the transient experimental data and that of other code calculations .