检索结果-南通市图书馆

Analysis of severe core damage accident progression for the heavy water reactor

Nuclear Science and Techniques 2010年第4期21卷 251-256页

作者： tong lili yuan kai yuan jingtian cao xuewu School of Mechanical Engineering Shanghai Jiao Tong University' Shanghai 200240 China

In this study,the severe accident progression analysis of generic Canadian deuterium uranium reactor 6 was preliminarily provided using an integrated severe accident analysis *** selected accident sequences were multiple steam generator tube rupture and large break loss-of-coolant accidents because these led to severe core damage with an assumed unavailability for several critical safety *** progressions of severe accident included a set of failed safety systems normally operated at full power,and initiative events led to primary heat transport system inventory blow-down or boil *** core heat-up and melting,steam generator response,fuel channel and calandria vessel failure were *** results showed that the progression of a severe core damage accident induced by steam generator tube rupture or large break loss-of-coolant accidents in a CANDU reactor was slow due to heat sinks in the calandria vessel and vault.

关键词：重水反应堆损坏事故蒸汽发生器堆芯 CANDU堆严重事故热传输系统事故分析

来源：

维普期刊数据库

同方期刊数据库评论

在线全文

学校读者我要写书评

暂无评论

Simulation of quenching in horizontal geometry channel

引用

Nuclear Science and Techniques 2010年第6期21卷 370-374页

作者： yuan jingtian tong lili cao xuewu Shanghai Jiao tong Univ Sch Mech Engn Shanghai 200240 Peoples R China

Two tests of refilling and reflooding in the horizontal geometry channel under different pressure conditions,respectively,are conducted to understand the thermal hydraulics behavior during a LOCA in the CANDU *** case of refilling a hot horizontal tube test and four cases of reflooding a horizontal fuel channel test series (35%and 60%break size of reactor inlet header with single-end injection or both-end injection,respectively) have been *** horizontal channel is simulated with the model splitting as parallel pipes with cross flow junction *** simulation results have been compared with the tests in terms of wall temperature or heated-pin surface *** results are reasonably acceptable and it shows that the code is applicable on horizontal channel quenching.

关键词：水平测试通道测试模型模拟几何淬火 CANDU堆压力条件热工水力

来源：

维普期刊数据库

同方期刊数据库评论

在线全文

学校读者我要写书评

暂无评论

欢迎您,

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

在线全文

在线全文

请选择保存的检索档案：

请选择收藏分类：

通借通还

欢迎您,

建议与咨询 留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

在线全文

在线全文

请选择保存的检索档案： 新增检索档案 确定 取消

请选择收藏分类： 新增自定义分类 确定 取消

通借通还

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

请选择保存的检索档案：

请选择收藏分类：