PANAMA 程序及其在 10MW 高温气冷实验堆安全分析中的应用  

Application of PANAMA Program to Safety Analysis for the10MW High Temperature Gas Cooled Test Reactor

作　　者：曹建主[1] 奚树人[1] 

机构地区：[1]清华大学核能技术设计研究院

出　　处：《核动力工程》1998年第2期162-167,共6页Nuclear Power Engineering

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。本文简介了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１０）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随燃耗、温度和核芯直径的增大而增长较快，对缓冲层和ＳｉＣ层厚度的变化也比较敏感。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.

关 键 词：PANAMA 高温 气冷堆 包覆燃料颗粒 安全分析 

分 类 号：TL411.606[核科学技术—核技术及应用] TL364.1