核燃料加工设施UF_6泄漏事故源强分析
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- 英文论文题名：Source term considerations of UF_6 leak at the nuclear fuel processing facilities
- 论文作者：阙骥 ; 杨晓伟 ; 张敏 ; 段红卫
- 英文论文作者：QUE Ji ; YANG Xiao-wei ; ZHANG Min ; DUAN Hong-wei ; Nuclear and Radiation Safety Center ; MEP.
- 年：2015
- 作者机构：环境保护部核与辐射安全中心;
- 论文关键词：UF_6泄漏 ; 事故源项 ; 核燃料 ; 安全分析
- 英文论文关键词：UF_6 leakage ; source term ; Nuclear fuel ; Safety analysis
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第10册（核安全分卷）
- 语种：中文
- 分类号：TL352.2
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：5
- 文件大小：433k
- 原文格式：O
- 会议级别：全国
摘要
本文建立了一个估算UF_6泄漏速率和残留UF_6的量及状态的源项模型。该模型基本假设为(1)容器内UF_6状态瞬时稳定、(2)UF_6液体不可压缩,气态UF_6释放为自由膨胀释放。本文使用此模型分析了美国NRC NUREG/CR-6410中UF_6泄漏事故情景。分析结果与NUREG/CR-6410分析结果比较表明,该模型计算得出的泄漏量小,但泄漏持续时间更长;与美国NRC应急响应后果评估程序RASCAL计算程序源项假设比较,结果表明RASCAL给出的最大泄漏份额和泄漏流量不具有保守性。
The paper establishes a source term model used to estimate the UF_6 leakage flow and the amount and status of residual UF_6 in a container. The model bases on two assumptions:(1) UF_6in container is instantaneous equilibrium;(2) UF_6 liquid is incompressible.UF_6 leakage accident scenarios assumed in NRC NUREG/CR-6410 is analyzed by using the model. Comparing with results in NUREG/CR-6410,it shows that the flow and duration of leakage obtained from the model is longer and smaller,respectively.Comparing with the maximum values of release fractions and flow proposed in RASCAL,which is used to estimate accident consequences for emergency response by NRC,it shows that those values is not conservative.
The paper establishes a source term model used to estimate the UF_6 leakage flow and the amount and status of residual UF_6 in a container. The model bases on two assumptions:(1) UF_6in container is instantaneous equilibrium;(2) UF_6 liquid is incompressible.UF_6 leakage accident scenarios assumed in NRC NUREG/CR-6410 is analyzed by using the model. Comparing with results in NUREG/CR-6410,it shows that the flow and duration of leakage obtained from the model is longer and smaller,respectively.Comparing with the maximum values of release fractions and flow proposed in RASCAL,which is used to estimate accident consequences for emergency response by NRC,it shows that those values is not conservative.
引文
[1]Guidance on the Application of Refined Dispersion Models for hazardous/toxic air releases,EPA-454/R-93-002,U.S.Environmental Protection Agency,1993.
[2]J.V.Ramsdell,Jr.G.F.Athey,S.A.McGuire,L.K.Brandon,RASCAL 4:Description of Models and Methods,NUREG-1940,Pacific Northwest National Laboratory,U.S.Nuclear Regulatory Commission,2012.
[3]Science Applications International Corporation,Nuclear Fuel Cycle Facility Accident Analysis Handbook,NUREG/CR-6410,U.S.Nuclear Regulatory Commission,1998.
[4]J.C.Anderson,C.P.Kerr,W.R.Williams,Correlation of the thermophysical properties of uranium hexafluoride over a wide range of temperature and pressure,ORNL/ENG/TM-51,Martin Marietta Energy Systems,INC.1994.
[5]American National Standards Institute,Packaging of Uranium Hexafluoride for Transport,ANSI N14.1,American National Standards Institute,1995.
[2]J.V.Ramsdell,Jr.G.F.Athey,S.A.McGuire,L.K.Brandon,RASCAL 4:Description of Models and Methods,NUREG-1940,Pacific Northwest National Laboratory,U.S.Nuclear Regulatory Commission,2012.
[3]Science Applications International Corporation,Nuclear Fuel Cycle Facility Accident Analysis Handbook,NUREG/CR-6410,U.S.Nuclear Regulatory Commission,1998.
[4]J.C.Anderson,C.P.Kerr,W.R.Williams,Correlation of the thermophysical properties of uranium hexafluoride over a wide range of temperature and pressure,ORNL/ENG/TM-51,Martin Marietta Energy Systems,INC.1994.
[5]American National Standards Institute,Packaging of Uranium Hexafluoride for Transport,ANSI N14.1,American National Standards Institute,1995.