小型反应堆安全特性比较分析
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摘要
随着全球核电的发展,小型堆由于具有高安全性、结构简化、用途广泛等特点而受到越来越多国家的关注。研发设计小型反应堆,提高堆型的安全性、多应用性,是未来核电发展一个重要选择。针对世界上众多的小型堆技术,文章介绍了轻水堆、高温气冷堆、液态金属反应堆、熔盐堆四种反应堆技术为代表的主要堆型,对比其设计特点和设计参数,总结了小型反应堆总体安全特征,并对四种小型反应堆的固有安全特性和工程安全设计进行分析,为后续的堆型发展提供思路。
With the development of nuclear power, because of the characteristics of high safety, simplified structure and wide use, small reactors are attracting more and more attention. The development and design of small reactors to improve the safety and application of reactors is an important choice for the development of nuclear power in the future. In view of the existing small reactor technology, four kinds of reactor technologies, such as light water reactor, high temperature gas cooled reactor, liquid metal reactor and molten salt reactor, are introduced. The design characteristics and design parameters are summarized and compared, in particular, the inherent safety characteristics and engineering safety design of the four types of heap are analyzed, providing ideas for the development of small reactors.
With the development of nuclear power, because of the characteristics of high safety, simplified structure and wide use, small reactors are attracting more and more attention. The development and design of small reactors to improve the safety and application of reactors is an important choice for the development of nuclear power in the future. In view of the existing small reactor technology, four kinds of reactor technologies, such as light water reactor, high temperature gas cooled reactor, liquid metal reactor and molten salt reactor, are introduced. The design characteristics and design parameters are summarized and compared, in particular, the inherent safety characteristics and engineering safety design of the four types of heap are analyzed, providing ideas for the development of small reactors.
引文
[1] 晋风.新的时代赋予核能新期待——写在党的十九大闭幕之际[J].中国核工业,2017(10):1.
[2] KATO Y.Needs and Trends of Advanced Small Reactor Development[J].Journal of the Atomic Energy Society of Japan,2001,43(11):1054-1058.
[3] 陈仁宗,王冠.先进小型反应堆技术现状及未来发展趋势研究[J].科技视界,2018(3):15-18.
[4] MYCLE SCHNEIDER.国际清洁能源发展报告(2015)[R].国际清洁能源论坛(澳门),2015:97.
[5] 刘志铭,丁亮波.世界小型核电反应堆现状及发展概况[J].国际电力,2005,9(6):27-31.
[6] 刘晓壮.国内外部分小型压水堆安全特性比较分析[J].核安全,2015,14(1):56-59.
[7] 何剑.我国先进制造技术现状及发展趋势[J].科技创新与应用,2013(6):106.
[8] 陈培培,周赟.我国发展先进小型轻水反应堆的一些思考[J].中国核电,2012,5(1):88-93.
[9] 游战洪.世界首座模块式球床高温气冷堆[J].科学,2016,68(1):24-28;4.
[10] 佚名.球床模块式高温气冷堆[J].国防科技工业,2015(7):43.
[11] LEWIS E E,LEWIS H W.Nuclear Power Reactor Safety[M].New Jersey:Wiley,1977.
[12] 江绵恒,徐洪杰,戴志敏.未来先进核裂变能——TMSR核能系统[J].中国科学院院刊,2012,27(3):366-374.
[13] 黄光晓,郭奇勋.先进核电技术经济性分析[M].北京:清华大学出版社,2014.
[14] 钮新强.地下核电厂概论[M].北京:原子能出版社,2016.
[15] 王丽新.核反应堆安全性评述[J].科技创新与应用,2012(16):44.
[16] 李志容,陈立强,徐校飞,李源.模块式高温气冷堆的固有安全特性[J].核安全,2013,12(3):1-4.
[17] 吴中旺,曲静原,刘原中,奚树人.10 MW高温气冷实验堆事故分析的结果与对策[J].核科学与工程,2000,20(2):146-153.
[18] 安娜,黄建利.后福岛时代论高温气冷堆的优越性[C]//中国核学会核能动力分会2013年学术研讨会论文集,2013:97-101.
[19] 徐銤.钠冷快堆的安全性[J].自然杂志,2013,35(2):79-84.
[20] 徐銤.中国实验快堆的安全特性[J].核科学与工程,2011,31(2):116-126.
[21] 徐銤,杨红义.钠冷快堆及其安全特性[J].物理,2016,45(9):561-568.
[22] OGAWA M.Inherently-Safe High Temperature Gas-Cooled Reactor[M].Kyoto:Zero-Carbon Energy Kyoto,2012.
[23] 蔡翔舟,戴志敏,徐洪杰.钍基熔盐堆核能系统[J].物理,2016,45(9):578-590.
[2] KATO Y.Needs and Trends of Advanced Small Reactor Development[J].Journal of the Atomic Energy Society of Japan,2001,43(11):1054-1058.
[3] 陈仁宗,王冠.先进小型反应堆技术现状及未来发展趋势研究[J].科技视界,2018(3):15-18.
[4] MYCLE SCHNEIDER.国际清洁能源发展报告(2015)[R].国际清洁能源论坛(澳门),2015:97.
[5] 刘志铭,丁亮波.世界小型核电反应堆现状及发展概况[J].国际电力,2005,9(6):27-31.
[6] 刘晓壮.国内外部分小型压水堆安全特性比较分析[J].核安全,2015,14(1):56-59.
[7] 何剑.我国先进制造技术现状及发展趋势[J].科技创新与应用,2013(6):106.
[8] 陈培培,周赟.我国发展先进小型轻水反应堆的一些思考[J].中国核电,2012,5(1):88-93.
[9] 游战洪.世界首座模块式球床高温气冷堆[J].科学,2016,68(1):24-28;4.
[10] 佚名.球床模块式高温气冷堆[J].国防科技工业,2015(7):43.
[11] LEWIS E E,LEWIS H W.Nuclear Power Reactor Safety[M].New Jersey:Wiley,1977.
[12] 江绵恒,徐洪杰,戴志敏.未来先进核裂变能——TMSR核能系统[J].中国科学院院刊,2012,27(3):366-374.
[13] 黄光晓,郭奇勋.先进核电技术经济性分析[M].北京:清华大学出版社,2014.
[14] 钮新强.地下核电厂概论[M].北京:原子能出版社,2016.
[15] 王丽新.核反应堆安全性评述[J].科技创新与应用,2012(16):44.
[16] 李志容,陈立强,徐校飞,李源.模块式高温气冷堆的固有安全特性[J].核安全,2013,12(3):1-4.
[17] 吴中旺,曲静原,刘原中,奚树人.10 MW高温气冷实验堆事故分析的结果与对策[J].核科学与工程,2000,20(2):146-153.
[18] 安娜,黄建利.后福岛时代论高温气冷堆的优越性[C]//中国核学会核能动力分会2013年学术研讨会论文集,2013:97-101.
[19] 徐銤.钠冷快堆的安全性[J].自然杂志,2013,35(2):79-84.
[20] 徐銤.中国实验快堆的安全特性[J].核科学与工程,2011,31(2):116-126.
[21] 徐銤,杨红义.钠冷快堆及其安全特性[J].物理,2016,45(9):561-568.
[22] OGAWA M.Inherently-Safe High Temperature Gas-Cooled Reactor[M].Kyoto:Zero-Carbon Energy Kyoto,2012.
[23] 蔡翔舟,戴志敏,徐洪杰.钍基熔盐堆核能系统[J].物理,2016,45(9):578-590.