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熔融物堆内滞留条件下压力容器变形
Pressure vessel deformation under in-vessel retention condition
- 核技术 2016年39卷第10期 文章编号：100603
- 作者机构：
环境保护部核与辐射安全中心 北京 100082
- 作者简介：
[ "温爽, 男, 1984年出生, 2012年于法国蒙彼利埃第二大学获博士学位, 研究领域是核电厂设备力学分析", "WEN Shuang, male, born in 1984, graduated from University of Montpellier 2 (France) with a doctoral degree in 2012, focusing on mechanical analysis of equipment in nuclear power plants" ]
高新力, E-mail:laborforce@163.com GAO Xinli, E-mail:laborforce@163.com
- 基金信息：国家科技重大专项课题(2013ZX06002001-003)
DOI：10.11889/j.0253-3219.2016.hjs.39.100603
中图分类号： TL351.6收稿日期：2016-03-28，
修回日期：2016-06-16，
纸质出版日期：2016-10
- 稿件说明：
移动端阅览
温爽, 李铁萍, 李聪新, 等. 熔融物堆内滞留条件下压力容器变形[J]. 核技术, 2016,39(10):100603
Shuang WEN, Tieping LI, Congxin LI, et al. Pressure vessel deformation under in-vessel retention condition[J]. Nuclear techniques, 2016, 39(10): 100603
温爽, 李铁萍, 李聪新, 等. 熔融物堆内滞留条件下压力容器变形[J]. 核技术, 2016,39(10):100603 DOI： 10.11889/j.0253-3219.2016.hjs.39.100603.
Shuang WEN, Tieping LI, Congxin LI, et al. Pressure vessel deformation under in-vessel retention condition[J]. Nuclear techniques, 2016, 39(10): 100603 DOI： 10.11889/j.0253-3219.2016.hjs.39.100603.
摘要
熔融物堆内滞留（In-Vessel Retention，IVR）已经成为第三代反应堆一项关键的严重事故缓解策略，而压力容器外部冷却（External Reactor Vessel Cooling，ERVC）技术则是保证IVR得以成功实施的关键。当发生堆芯熔化时，高温熔融物对压力容器（Reactor Pressure Vessel，RPV）下封头的热冲击会导致RPV壁面和由其构成的外部冷却通道的形状发生变化，使局部传热恶化，进而造成IVR的失效。因此，有必要对IVR条件下RPV壁面的变形进行研究。本文利用有限元软件ANSYS对RPV进行了几何建模、温度场分析和力学场分析。结果表明，在RPV外部实现冷却、内部实现泄压的前提下，壁面变形为13.85-18.75 mm。在1 MPa内压的作用下，高温蠕变会使壁面变形随时间增大，但其增量有限。热膨胀是造成壁面变形的主要因素。
Abstract
Background
2
In-vessel retention (IVR) has become an important severe accident mitigation strategy for advanced light water reactor in recent years. The successful implementation of IVR depends on the external reactor vessel cooling (ERVC) technique. In case of core melt
the bottom head of reactor pressure vessel (RPV) becomes deformed due to the thermal impacts of high temperature
and causes the narrowing of external coolant channel which is the gap between pressure vessel outer wall and insulation layer. This phenomenon could lead to local heat transfer deterioration and then causes the failure of IVR.
Purpose
2
The aim of this paper is to analyze the deformation of reactor pressure vessel under IVR condition.
Methods
2
The thermal and mechanical calculations of reactor pressure vessel are performed by using the finite element methods. This work can be divided into two steps. The first step is the evaluation of the thermal field of RPV
and the second step is the calculation of stress and displacement of RPV based on its temperature fields.
Results
2
The result shows that the maximum vertical deformation of RPV caused by the thermal dilatation is 13.11 mm
while the deformation caused by the other mechanical loads is only about 0.61 mm. After 100-h
the creep leads the vertical deformation increases to 13.85 mm from 13.72 mm. The size reduction of external coolant channel due to the reactor pressure vessel deformation is between 13.85 mm and 18.75 mm.
Conclusion
2
With internal pressure of 1 MPa
the deformation of reactor pressure vessel produced by high temperature creep increases as time increases
but the value remains small. The thermal dilatation is the most important factor of the reactor pressure vessel deformation under IVR condition.
关键词
Keywords
references
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