A computer code for calculating the temperature distribution for the instrumented fuel elements of PWR in pile experiments was compiled.
为配合堆内试验,编制了压水堆堆内试验仪表化燃料元件温度场计算机程序,计算试验装置中双包壳燃料元件的初始温度分布,确定燃料棒线功率在试验流量为6 t/h时的安全上限为290 W/cm。
burst cartridge detector
燃料元件包壳破损探测器
element rupture detector (FERD)
燃料元件破损探测器
seamless fuel clad tube
无缝燃料元件包壳管
delayed neutron failed element monitor
缓发中子破损燃料元件监测器
cerenkov effect failed element monitor
切伦科夫效应破损燃料元件监测器
failed fuel detection and location
破损燃料探测和定位
nuclear fuel rod sheath leak detector
核燃料棒包壳泄漏探测器
Nondestructive Experimental Measurement of Fuel Element Burnup in Xi'an Pulse Reactor
西安脉冲堆燃料元件燃耗无损实验测量
Research on the failure rate of coated fuel particles for HTGR
高温气冷堆包覆燃料颗粒破损率研究
fission product separator failed element monitor
裂变产物分离式破损燃料监测器
burst slug detector
释热元件损伤探测器
fuel-cladding interaction
燃料－包壳相互作用
cladding-fuel interaction
包壳－燃料相互作用
electrostatic collector failed element monitor
静电收集破损元件监测器
INHIBITION EFFECT OF THE OXYGEN ABSORBERS ON THE INNER WALL CORROSION OF FBR CLADDING TUBE
吸氧材料对快堆元件包壳内壁腐蚀的抑制作用
Development of New Zirconium Alloys for PWR Fuel Rod Claddings
压水堆燃料包壳新锆合金的发展(英文)
RESEARCH ON IRRADIATION DAMAGE OF CLADDING MATERIALS BY LIGHT ION BOMBARDMENT UNDER THE EXPERIMENTAL FBR DEVELOPMENT PROJECT
实验快堆发展计划中包壳材料轻离子辐照损伤探讨
maximum assessed fuel element temperature
燃料元件最高设定温度