【作者】 陈立新； 朱磊； 马腾跃； 江新标； 陈达；

【Author】 CHEN Li-xin;ZHU Lei;MA Teng-yue;JIANG Xin-biao;CHEN Da;Department of Nuclear Science & Engineering,Nanjing University of Aeronautics & Astronautics;Northwest Institute of Nuclear Technology;

【机构】 南京航空航天大学核科学与工程系； 西北核技术研究所；

【摘要】 为获得脉冲运行瞬态的堆芯温度场变化情况,本文开发了适用于低温、常压工况的脉冲反应堆瞬态热工分析子通道程序PRC-STAC。利用TRIGA MARKⅡ反应堆的瞬态参数对程序进行了验证,验证结果表明,二者符合较好。利用PRC-STAC程序计算了西安脉冲堆燃料元件和堆芯冷却剂的瞬态热工参数,并讨论了脉冲运行对燃料元件的安全影响。更多还原

【Abstract】 In order to obtain the temperature field variation of the pulsed reactor in pulse operation,a transient thermal analysis sub-channel code named PRC-STAC was developed.It’s applicable to the pulsed reactor at low temperature and atmospheric pressure.Compared with the transient parameters of the TRIGA MARK Ⅱreactor,the correctness of the PRC-STAC code was validated.The transient thermal parameters of the Xi’an Pulsed Reactor were calculated with the PRC-STAC,and the safety influence on the fuel element in pulse operation was discussed finally.更多还原