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10 MWt固态燃料熔盐堆控制棒失控抽出事故分析
Accident analyses of uncontrolled rod cluster control assembly bank withdrawal for 10-MWt thorium-based molten salt reactor-solid fuel
- 核技术 2016年39卷第10期 文章编号：100604
- 作者机构：
1.环境保护部核与辐射安全中心 北京 100082
2.中国科学院过程工程研究所 北京 100190
- 作者简介：
[ "靖剑平, 男, 1983年出生, 2010年于哈尔滨工业大学获博士学位, 研究领域为反应堆热工水力及安全分析", "JING Jianping, male, born in 1983, graduated from Harbin Institute of Technology with a doctoral degree in 2010, focusing on the reactor thermal hydraulic and safety analysis" ]
左嘉旭, E-mail:zuojiaxu@chinansc.cn ZUO Jiaxu, E-mail:zuojiaxu@chinansc.cn
- 基金信息：中国科学院战略性先导科技专项(XDA02050500)
DOI：10.11889/j.0253-3219.2016.hjs.39.100604
中图分类号： TL99收稿日期：2016-06-02，
修回日期：2016-08-17，
纸质出版日期：2016-10
- 稿件说明：
移动端阅览
靖剑平, 刘雅宁, 贾斌, 等. 10 MWt固态燃料熔盐堆控制棒失控抽出事故分析[J]. 核技术, 2016,39(10):100604
Jianping JING, Yaning LIU, Bin JIA, et al. Accident analyses of uncontrolled rod cluster control assembly bank withdrawal for 10-MWt thorium-based molten salt reactor-solid fuel[J]. Nuclear techniques, 2016, 39(10): 100604
靖剑平, 刘雅宁, 贾斌, 等. 10 MWt固态燃料熔盐堆控制棒失控抽出事故分析[J]. 核技术, 2016,39(10):100604 DOI： 10.11889/j.0253-3219.2016.hjs.39.100604.
Jianping JING, Yaning LIU, Bin JIA, et al. Accident analyses of uncontrolled rod cluster control assembly bank withdrawal for 10-MWt thorium-based molten salt reactor-solid fuel[J]. Nuclear techniques, 2016, 39(10): 100604 DOI： 10.11889/j.0253-3219.2016.hjs.39.100604.
摘要
钍基熔盐堆核能系统项目是中科院先导科技专项之一，其战略性目标是研发第四代熔盐冷却裂变反应堆核能系统。基于10 MWt固态燃料熔盐堆的系统设计，开发了适用于球床式反应堆系统的安全分析软件，并以高温气冷堆为对象对程序计算结果的准确性进行了验证。基于该软件程序，对固态燃料球床堆（Thorium Molten Salt Reactor-Solid Fuel，TMSR-SF）控制棒失控抽出事故进行了分析计算，研究了不同停堆限值及各停堆信号对事故的影响。计算结果表明，超功率停堆限值越高，出口温度限值越大，信号延迟时间越长，反应堆停堆越晚，堆芯功率和燃料最高温度越高。在TMSR-SF控制棒失控抽出事故下，燃料最高温度不超过860℃，远低于1 600℃的熔化温度限值。
Abstract
Background
2
Thorium-based molten salt reactor nuclear power system project is one of the "Strategic Priority Program" of Chinese Academy of Sciences
and its strategic goal is to develop the fourth generation moltensalt cooled fission reactor nuclear power system. Based on the system design of 10-MWt molten salt reactor-solid fuel
a safety analysis software is developed for the pebble bed reactor system and verified the correctness and accuracy for the high-temperature gas-cooled reactor of results calculated via this software program.
Purpose
2
This study aims at accident analyses of uncontrolled rod cluster control assembly bank withdrawal for thorium molten salt reactor-solid fuel (TMSR-SF) by using the developed program.
Methods
2
The TMSR-SF reactor core model is built according to the designed parameters. Analyses of the impacts of different shutdown limits and shutdown signals on the withdrawal accident of the TMSR-SF uncontrolled rod cluster control assembly bank is carried out through the safety analysis models such as neutron kinetics model
fluid flow and heat transfer model
control model
etc.
in the developed program.
Results
2
In the withdrawal accident of the uncontrolled rod cluster control assembly bank of the TMSR-SF
the maximum temperature of the reactor fuel temperature is no more than 860℃.
Conclusions
2
Computional results show that the higher the limit value of over power shutdown is
the greater the outlet temperature is; the longer the signal delay time is
the later the reactor shutdown happens
and the higher the core power and fuel temperature is. Compared with the limit value of shutdown
the outlet temperature reaches the limit later in time sequence
the maxumum fuel temperature is much lower than the fuel pebble melting temperature limit of 1 600℃ under no circumstances.
关键词
Keywords
references
Ingersoll D T, Forsberg C W, Ott L J, et al. Status of preceonceptual design of the Advanced High-Temperature Reactor (AHTR)[R]. Knoxville, Tennessee:Oak Ridge National Laboratory, ORNL/TM-2004/14, 2004
Varma V K, Holcomb D E, Peretz F J, et al. AHTR mechanical, structural, and neutronic precocenptual design[R]. Knoxville, Tennessee:Oak Ridge National Laboratory, ORNL/TM-2012/320, 2012
TMSR研究中心. 2 MWt固态钍基熔盐实验堆概念设计报告(上)[R].上海:中国科学院上海应用物理研究所, 2013
TMSR Research Center. The conceptual design report 2MWt solid thorium-based molten salt experiment reactor (Upper V01)[R]. Shanghai:Shanghai Institute of Applied Physics, Chinese Academy of Sciences, 2013
田 金 , 夏 晓彬 , 彭 超 , . 10-MWt固态钍基熔盐堆乏燃料贮存系统临界安全影响分析 . 核技术 , 2015 . 38 ( 5 ): 050602 DOI: 10.11889/j.0253-3219.2015.hjs.38.050602 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.050602 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract405.shtml .
Jin TIAN , Xiaobin XIA , Chao PENG , . Impact analysis of criticality safety for 10-MWt solid thorium-based molten salt reactor spent nuclear fuel storage system . Nuclear Techniques , 2015 . 38 ( 5 ): 050602 DOI: 10.11889/j.0253-3219.2015.hjs.38.050602 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.050602 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract405.shtml .
TMSR-SFl堆物理分总体. 10 MWt TMSR-SFl总体物理方案和参数[R].上海:中国科学院上海应用物理研究所, 2013
Reactor Physics Department of TMSR-SFI. Physics programs and parameters for 10-MWt TMSR-SF1[R]. Shanghai:Shanghai Institute of Applied Physics, Chinese Academy of Sciences, 2013
焦 小伟 , 王 凯 , 何 兆忠 , . 固态熔盐堆全厂断电ATWS事故工况下的堆芯安全探讨 . 核技术 , 2015 . 38 ( 2 ): 020604 DOI: 10.11889/j.0253-3219.2015.hjs.38.020604 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.020604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract358.shtml .
Xiaowei JIAO , Kai WANG , Zhaozhong HE , . Core safety discussion under station blackout ATWS accident of solid fuel molten salt reactor . Nuclear Techniques , 2015 . 38 ( 2 ): 020604 DOI: 10.11889/j.0253-3219.2015.hjs.38.020604 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.020604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract358.shtml .
梅 牡丹 , 邵 世威 , 何 兆忠 , . 固态钍基熔盐堆概率安全评价始发事件分析研究 . 核技术 , 2014 . 37 ( 9 ): 090601 DOI: 10.11889/j.0253-3219.2014.hjs.37.090601 http://doi.org/10.11889/j.0253-3219.2014.hjs.37.090601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract260.shtml .
Mudan MEI , Shiwei SHAO , Zhaozhong HE , . Research on initial event analysis for solid thorium molten salt reactor probabilistic safety assessment . Nuclear Techniques , 2014 . 37 ( 9 ): 090601 DOI: 10.11889/j.0253-3219.2014.hjs.37.090601 http://doi.org/10.11889/j.0253-3219.2014.hjs.37.090601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract260.shtml .
华能山东石岛湾核电有限公司.华能山东石岛湾核电厂高温气冷堆核电站示范工程初步安全分析报告[R].北京:中国华能集团公司, 2008
Huaneng Shidao Shandong Bay Nuclear Power Co., Ltd. Preliminary safety analysis report on the demonstration project of the high temperature gas cooled reactor nuclear power plant in Shidao Bay, Shandong, China[R]. Beijing:China Huaneng Group, 2008
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