The paper focuses on the introduction of modeling of the core for the case of the Tsinghua University experimental reactor,Keff in normal control rods positions are calculated in order to validate the exactitude of the model,and the result is consistent with that of the reference; the article has also concluded the approach of the modeling core which is worth to consulting.
用MCNP程序对清华大学试验核反应堆一号堆芯进行了建模,计算了正常棒位下的Keff值,计算结果与参考值吻合较好;提出了用MCNP进行反应堆堆芯建模的一般步骤和方法,此步骤和方法对研究其他各种反应堆堆芯的建模具有参考价值。
NETR (Nuclear Engineering Test Reactor)
核子工程试验反应堆
physical constants test reactor
物理常数试验反应堆
transient reactor test facility
瞬态反应堆试验装置
plutonium recycle test reactor
钚再循环试验反应堆
MORE (Organic Moderated Reactor Experiment)
有机慢化剂反应堆试验
pool test reactor
游泳池式试验反应堆
FARET (Fast Reactor Experiment Test)
快中子反应堆实验测试
engineering test reactor critical assembly
工程试验堆临界装置
Heat Balance Test for Determined Reactor Core Power
计算核反应堆堆芯功率的热平衡试验
Core Stable Flowrate Distribution of High Flux Engineering Test Reactor(HFETR)
高通量工程试验堆堆芯流量分配计算
The Study on 80 Fuel Assemblies Core for HFETR
高通量工程试验堆80盒元件堆芯研究
Rockfill Dam with Clay Core in Manla Multi-Purpose Water Project Study on Dynamic Characteristics of the Dam Material and Analysis on Its Seismic Response
满拉水利枢纽工程土心墙堆石坝筑坝材料动力特性试验与地震反应分析
aerospace systems test reactor
宇宙空间系统试验反应堆
tokamak fusion test reactor
托卡马克聚变试验反应堆
maritime gas-cooled reactor critical experiment
气冷式海上反应堆临界试验装置
special power excursion reactor test
试验功率突增的专用反应堆
ARBOR (Argonne Boiling Reactor Experiment)
阿尔贡沸腾式反应堆试验
spent or irradiated cartridge of nuclear reactors
核试验反应堆使用过或辐照过的容器
