期刊文献+

船用压水堆核泄漏事故工作舱室辐射场绝对分布研究

Study on the absolute distribution of the radiation field in the work cabins in case of radioactive leakage involving the shipboard pressurized water reactor
原文传递
导出
摘要 目的 建立船用压水堆核泄漏事故工作舱室辐射场实时绝对分布的研究方法.方法 通过分析船用压水堆运行规律、辐射源项与释放机理,研究船用压水堆变工况运行条件下堆芯主要放射性核素积存量计算方法,进而利用核动力船舶内131I探测装置实时监测数据建立工作舱室辐射场实时绝对分布确定方法.结果 利用Matlab软件建立了船用压水堆变工况运行条件下堆芯主要放射性核素积存量以运行功率和运行时间为变量的最小二乘法拟合函数,初步确定了船用压水堆核泄漏事故工作舱室辐射场实时绝对分布确定流程,船用压水堆变工况运行条件下堆芯主要放射性核素积存量与运行功率、运行时间的函数拟合值与真实值的拟合度可达到95%以上.结论 所建立的船用压水堆核泄漏事故工作舱室辐射场实时绝对分布技术方法,可将船上相关装置设置输入接口,并可实现船用压水堆核泄漏事故工作舱室船员剂量即时快速估算,对船用压水堆核泄漏事故应急救援意义重大. Objective To establish the method of real-time absolute distribution of the radiation field in the work cabins when radioactive leakage occurred involving the shipboard pressurized water reactor (PWR).Methods By analyzing operating modes of the shipboard PWR,radioactive source items and release mechanism,the calculation method for the determination of cumulative amount of main radionuclides in the PWR-core under variable conditions was investigated.Then,by using the real time monitoring data of the iodine-131 detection devices onboard the nuclear-powered ship,the method of radiation field absolute distribution in the work cabins was established.Results By using Matlab software kit,the least square fitting to the function in the accumulation quantity of the main radionuclides in the reactor core and operating power and running time was thus established,and the procedures for the real-time absolute distribution of the radiation field in the work cabins when radioactive leakage occurred were initially identified.The goodness-of-fit between the fitting value of function for the accumulation quantity of the main radionuclides in the reactor core and operating power and running time,and true fitting value reached over 95% under variable operating conditions of the shipboard pressurized reactor core.Conclusions The determining procedures for the real-time absolute distribution of the radiation field in the work cabins on shipboard the PWR will facilitate input interface with the related device of the ship,and can help to realize instant and fast dose-estimation of the crew in case of radioactive leak accident.It is of great significance for the emergency rescue of the radioactive leak accident that might occur in the PWR on board the ship.
机构地区 海军医学研究所
出处 《中华航海医学与高气压医学杂志》 CAS CSCD 2015年第2期92-95,共4页 Chinese Journal of Nautical Medicine and Hyperbaric Medicine
基金 海军后勤部科研项目(BHJ09JD06) 海军装备部科研项目(09A201)
关键词 船用压水堆 核泄漏事故 工作舱室 辐射场 绝对分布 Shipboard PWR Radioactive leak accident Work cabin Radiation field Absolute distribution
  • 相关文献

参考文献6

二级参考文献27

  • 1[9]Eckerman K F, Ryman J C. (Oak Ridge National Lab. ,TN. ). External Exposure to Radionuclides in Air, water and Soil Exposure-to-Dose Coefficients for General Application. PB94-114451,1993
  • 2[10]Canadian Standards Association. Guidelines for Calculating Radiation Doses to the Public from a Release of Airborne Radioactive Material under Hypothetical Accident Conditions in Nuclear Reactor. CAN/CSA-N288.2-M91, 1991
  • 3[1]IAEA. Techniques and decision making in the assessment of off-site consequences of an accident in a nuclear facility [J]. Safety Series,1987,86:20-23.
  • 4防化研究院.核电厂严重事故场外应急辐射(放射学)监测[J].核安全技术研究,1990,(10):2-5.
  • 5[3]Geiss H, Nestery K, Thoma P, et al. In der Bundesrepublik Deuschland experimentell ermittelte Ansoreitungspa-rameter fur 100 m Emissionshone [R]. Kernforschungsanlage Julich/Kernforschungszentrum Karlsruhe Reps.,1981.
  • 6[4]Vogt K J, Geiss H. Newe Ausbreiturgskoeffizienten f u* * r 50 und 100 m Emissionshone [R]. Kernforschurgsanlage Julich Internal Rep.,1980.
  • 7[5]Hubschmann W, Nester K, Thomas P. Ausbreitungsparameter f u* * r Emission-shohen von 160 m und 195 m [R]. Kernforschungszentrum Karlsruhe Rep.,1980.
  • 8[6]IAEA Technical Reports Series. Evaluation of radiation emergencies and accidents [J]. Selected Criteria and Data,1974,(3):31-35.
  • 9SASAHARA A,MATSUMURA T,NICOLAOU G,et al.Neutron and gamma ray source evaluation of LWR high burn-up UO2 and MOX spent fuels[J].Nuclear Science and Technology,2004,41(4):448-456.
  • 10DEVELL L,JOHANSSON K.Specific features of cesium chemistry and physics affecting reactor accident source term predictions[M].Sweden:[s.n.] ,1994:8-11.

共引文献35

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