期刊文献+

海洋环境条件下浮动堆安全壳设计 被引量:3

Design of floating nuclear power plant containment under marine environment conditions
下载PDF
导出
摘要 [目的]浮动堆经过在军用舰船上几十年的发展和运行经验积累,反应堆的安全性得到了很大提高,在民用领域的推广应用逐渐被认可,目前亟需解决反应堆装船的适配性问题。安全壳是浮动堆与船体结合的接口,是反应堆装船的船体舱室,其设计不仅要适应船舶的海洋环境条件,还要满足反应堆运行的核安全要求。[方法]首先,从浮动堆安全壳的适应性要求出发,分析安全壳压力与船舶主尺度和重量之间的主要矛盾关系,提出一种浮动堆安全壳分析设计流程。然后,参考陆上核电站和核动力舰船安全壳的特点,以及国外核动力船舶和民用核设施设计规范要求,从安全壳构型与压力控制维度的角度出发,提出一种方形双层抑压安全壳方案。[结果]对安全壳压力特性以及结构强度的分析显示,在设计基准事故工况下,安全壳结构安全,重量和空间指标可控,安全壳的船堆适配性较好。[结论]参考工程经验表明,基于该方案的浮动堆总体指标较好,可为工程人员设计提供参考。 [Objectives] After several decades of the development and operation experience of military ships, the safety of floating reactors has been greatly improved. Their promotion and application in the civilian field has been gradually recognized, and it is urgently necessary to solve the problem of adaptability in reactor loading on ships. The containment is the interface between the reactor and the hull, and consists of the compartment of the reactor loading on a ship. The containment design must be adapted to the marine environment conditions of the ship, as well as to the nuclear safety requirements of reactor operation.[Methods]First, based on the adaptability requirements of floating reactor containment, the main contradiction between the pressure of the containment and the dimensions and weight of the ship is analyzed. A design and analysis process for floating reactor containment is proposed. With reference to the characteristics of onshore nuclear power plants and nuclear power ship containment, as well as the design requirements of foreign nuclear power ships and civil nuclear facilities, a square double-shell suppression containment is proposed in the dimensions of the containment configuration and pressure control program.[Results]Through an analysis of the pressure characteristics and structural strength of the containment, the structure of the containment under designbased accident conditions is found to be safe, with controllable weight and space indicators, and a good ship’s reactor fit.[Conclusions]With reference to engineering experience, the overall index of a floating nuclear power plant based on this scheme is reasonable, and it can provide reference for engineering personnel.
作者 谭美 李鹏凡 郭健 张进才 陈艳霞 TAN Mei;LI Pengfan;GUO Jian;ZHANG Jincai;CHEN Yanxia(Wuhan Second Ship Design and Research Institute,Wuhan 430205,China)
出处 《中国舰船研究》 CSCD 北大核心 2020年第1期107-112,144,共7页 Chinese Journal of Ship Research
基金 国家能源应用技术研究及示范工程项目(NY20150201)。
关键词 浮动堆 安全壳 海洋环境 总体设计 Floating Nuclear Power Plant(FNPP) containment marine environment overall design
  • 相关文献

参考文献5

二级参考文献19

  • 1鲁勤武,郝坚,张淑霞,郭俊营,蔡晖.阳江核电厂安全壳钢衬里模块化施工方案研究及应用[J].核动力工程,2011,32(S2):44-46. 被引量:3
  • 2国家核安全局.HAF102,核动力厂设计安全规定[S].北京:周家核安全局,2004.
  • 3U.S. Nuclear Regulatory Commmsion Regulations. 10CFR50. Code of Federal Regulations [S]. U. S. NRC, 2006.
  • 4US Nuclear Regulatory Commissions, RG 1. 157, BestEstimate Calculations of Emergency Core Cooling System Performance[S]. U.S. NRC, May 1989.
  • 5Westinghouse LLC, Westinghouse AP1000 Design Control Document[ R]. Westinghouse Electirc Company LLC, 2008.
  • 6U.S. NRC. Final Safety Evaluation Report: Related to certification of the AP1000 standard design[R]. U.S. NRC, 2004.
  • 7T Wicket, et al. Report of the Uncertainty Methods Study for Advanced Best Estimate Thermal Hydraulic Code Applications[M]. 2 vols, Rep. NEA/CSNI R(97) 35. Paris: OECD, 1998.
  • 8Reyes J N, Hochreiter Jr L. Scaling Analysis for the OSU AP600 Test Facility (APEX) [J]. Nuclear Engineering and Design, 1998, (186): 53-109.
  • 9ASME, Boiler and Pressure Vessel Code, Section m, Rules for Construction of Nuclear Facility Compo- nents, Division 1 -Subsection NE--Class MC Compo- nents[ S]. 2001.
  • 10丁连征,王刚,王海龙.安全壳用低合金调质钢SA738B的焊接工艺评定[c]//中国核能行业协会中国核能可持续发展论坛,2010:162-164.

共引文献66

同被引文献32

引证文献3

二级引证文献2

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部