[{"name":"热工与水力","count":521,"id":1},{"name":"回路与设备","count":383,"id":2},{"name":"安全与控制","count":356,"id":3},{"name":"结构与力学","count":327,"id":4},{"name":"堆芯物理与热工水力","count":310,"id":5},{"name":"其他","count":278,"id":6},{"name":"运行与维护","count":231,"id":7},{"name":"燃料与材料","count":173,"id":8},{"name":"核反应堆系统设计技术重点实验室专栏","count":163,"id":9},{"name":"物理与数学","count":148,"id":10},{"name":"核燃料及反应堆结构材料","count":130,"id":11},{"name":"安全与分析","count":124,"id":12},{"name":"控制与仪表","count":70,"id":13},{"name":"其它","count":68,"id":14},{"name":"反应堆物理及其设计、计算","count":63,"id":15},{"name":"核反应堆热工水力技术重点实验室专栏","count":59,"id":16},{"name":"Reactor Core Physics and Thermohydraulics","count":58,"id":17},{"name":"核燃料及反应堆材料","count":52,"id":18},{"name":"设备","count":44,"id":19},{"name":"Column of Science and Technology on Reactor System Design Technology Laboratory","count":36,"id":20},{"name":"核动力技术创新中心专栏","count":36,"id":21},{"name":"系统设备","count":36,"id":22},{"name":"核反应堆系统设计技术专栏","count":32,"id":23},{"name":"安全分析","count":31,"id":24},{"name":"仿真","count":29,"id":25},{"name":"Safety and Control","count":28,"id":26},{"name":"设备与回路","count":26,"id":27},{"name":"三废处理","count":25,"id":28},{"name":"综述","count":24,"id":29},{"name":"反应堆物理及其设计计算","count":23,"id":30},{"name":"辐射与屏蔽","count":22,"id":31},{"name":"热工水力","count":21,"id":32},{"name":"数字核能专栏","count":20,"id":33},{"name":"核动力技术创新专栏","count":20,"id":34},{"name":"热工与流体","count":20,"id":35},{"name":"电气仪控","count":19,"id":36},{"name":"设备的设计与制造","count":19,"id":37},{"name":"安全与质保","count":18,"id":38},{"name":"管理","count":18,"id":39},{"name":"设计与开发","count":18,"id":40},{"name":"Nuclear Fuel and Reactor Structural Materials","count":17,"id":41},{"name":"华龙一号专栏","count":17,"id":42},{"name":"Circulation and Equipment","count":16,"id":43},{"name":"仪表与控制","count":16,"id":44},{"name":"反应堆故障诊断专栏","count":16,"id":45},{"name":"抗震和应力分析、断裂力学","count":16,"id":46},{"name":"材料","count":16,"id":47},{"name":"测量及试验","count":16,"id":48},{"name":"反应堆物理","count":15,"id":49},{"name":"仪表与测量","count":14,"id":50},{"name":"抗震和应力分析、计算力学","count":14,"id":51},{"name":"特约稿","count":14,"id":52},{"name":"地下核电厂","count":13,"id":53},{"name":"Operation and Maintenance","count":12,"id":54},{"name":"反应堆燃料及材料重点实验室专栏","count":12,"id":55},{"name":"回路与设计","count":12,"id":56},{"name":"实验与调试","count":12,"id":57},{"name":"燃料及材料","count":12,"id":58},{"name":"核燃料技术发展专栏","count":11,"id":59},{"name":"反应堆物理专栏","count":10,"id":60},{"name":"运行与维修","count":10,"id":61},{"name":"Circuit Equipment and Operation Maintenance","count":9,"id":62},{"name":"回路设备与运行维护","count":9,"id":63},{"name":"流场、流固耦合分析及实验","count":9,"id":64},{"name":"系统与设备","count":9,"id":65},{"name":"调试与运行","count":9,"id":66},{"name":"辐射与防护","count":9,"id":67},{"name":"振动与冲击","count":8,"id":68},{"name":"设备及其设计制造","count":8,"id":69},{"name":"试验及试验方法","count":8,"id":70},{"name":"Column of Nuclear Power Technology Innovation Center","count":7,"id":71},{"name":"Structure and Mechanics","count":7,"id":72},{"name":"反应堆设计","count":7,"id":73},{"name":"核工程力学专栏","count":7,"id":74},{"name":"核物理与测量","count":7,"id":75},{"name":"流场、流固耦合及结构动力学分析","count":7,"id":76},{"name":"热工与水利","count":7,"id":77},{"name":"Structural Mechanics and Safety Control","count":6,"id":78},{"name":"总体","count":6,"id":79},{"name":"核燃料与材料","count":6,"id":80},{"name":"燃料","count":6,"id":81},{"name":"研究堆与核电厂运行研究专栏","count":6,"id":82},{"name":"结构力学与安全控制","count":6,"id":83},{"name":"调试","count":6,"id":84},{"name":"堆物理与实验","count":5,"id":85},{"name":"燃烧与材料","count":5,"id":86},{"name":"物理与教学","count":5,"id":87},{"name":"质量与管理","count":5,"id":88},{"name":"部件的设计制造","count":5,"id":89},{"name":"Column of Reactor Engineering","count":4,"id":90},{"name":"Column of Reactor Operation and Application","count":4,"id":91},{"name":"Other Columns","count":4,"id":92},{"name":"制造技术","count":4,"id":93},{"name":"反应堆工程专栏","count":4,"id":94},{"name":"反应堆物理及其计算","count":4,"id":95},{"name":"反应堆运行与应用专栏","count":4,"id":96},{"name":"地下核电站","count":4,"id":97},{"name":"战略研讨","count":4,"id":98},{"name":"断裂力学及缺陷评定","count":4,"id":99},{"name":"材料与燃料","count":4,"id":100},{"name":"核反应堆热工水力技术重点实验专栏","count":4,"id":101},{"name":"核燃料与反应堆结构材料","count":4,"id":102},{"name":"核运力技术创新中心专栏","count":4,"id":103},{"name":"燃料管理","count":4,"id":104},{"name":"质量保证","count":4,"id":105},{"name":"运行与回路","count":4,"id":106},{"name":"运行维修","count":4,"id":107},{"name":"Special Contribution","count":3,"id":108},{"name":"三代核电中的反应堆结构力学","count":3,"id":109},{"name":"先进轻水堆、小型堆和其他新堆型中的力学问题","count":3,"id":110},{"name":"反应堆总体","count":3,"id":111},{"name":"安全","count":3,"id":112},{"name":"安全裕控制","count":3,"id":113},{"name":"控制","count":3,"id":114},{"name":"核反应堆燃料及材料重点实验室专栏","count":3,"id":115},{"name":"核反应堆系统技术重点实验室专栏","count":3,"id":116},{"name":"核反应堆设计技术重点实验室专栏","count":3,"id":117},{"name":"核燃料及应堆材料","count":3,"id":118},{"name":"模拟与仿真","count":3,"id":119},{"name":"热水与水力","count":3,"id":120},{"name":"结核与力学","count":3,"id":121},{"name":"反应堆物理及其设计、计算辐射与屏蔽","count":2,"id":122},{"name":"数学与模拟","count":2,"id":123},{"name":"核燃料与反应堆材料","count":2,"id":124},{"name":"核燃料及其反应堆结构材料","count":2,"id":125},{"name":"辐照与屏蔽","count":2,"id":126},{"name":"回路与系统","count":1,"id":127},{"name":"设备制造","count":1,"id":128}]
