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PANAMA程序及其在10MW高温气冷实验堆安全分析中的应用
引用本文:曹建主 奚树人. PANAMA程序及其在10MW高温气冷实验堆安全分析中的应用[J]. 核动力工程, 1998, 19(2): 162-167
作者姓名:曹建主 奚树人
作者单位:清华大学核能技术设计研究院
摘    要:PANAMA程序是德国在高温气冷堆安全研究中开发的一个实用程序,可以用来计算TRISO-包覆燃料颗粒在事故条件下的破损率,本文简介PANAMA模型,着重开发了PANAMA程序中SiC压力容器失效模式,并利用10MW高温气冷实验堆(HTR-1)包覆燃料颗粒的设计参数,计算了燃耗,温度,核芯直径以及各包覆层厚度对颗粒破损率的影响,结果分析表明破损率阻燃耗,温度和核志直径的增大面而增长较快,对缓冲层和S

关 键 词:PANAMA 高温 气冷堆 包覆燃料颗粒 安全分析

Application of PANAMA Program to Safety Analysis for the10MW High Temperature Gas Cooled Test Reactor
Cao Jianzhu Xi Shuren. Application of PANAMA Program to Safety Analysis for the10MW High Temperature Gas Cooled Test Reactor[J]. Nuclear Power Engineering, 1998, 19(2): 162-167
Authors:Cao Jianzhu Xi Shuren
Abstract:PANAMA program is developed for safety analysis of high temperature gas cooled reactor.It can be used to calculate the failure rate of TRISO coated fuel particles under accident conditions.In this paper,PANAMA model is simply described and the emphasis is stressed on SiC pressure vessel failure memode.On the basis of the specifications of fuel particles in HTR 10,the calculations show that how bumup,temperature,kernel diameter and thicknesses of coated layers affect the failure rate.The conclusion show failure rate rise rapidly when burnup,temperature or kernel diameter increase,and are also sensitive to the thicknesses of buffer layer and SiC layer.
Keywords:PANAMA program High temperature gas cooled test reactor Coated fuel particles failure rate
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