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In-containment Source Term Evaluation for apr1400

In-containment Source Term Evaluation for APR1400

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第13届太平洋地区核能大会

作者： Y.M.Song S.Y.Park Thermal Hydraulic and Safety Research Team Korea Atomic Energy Research Institute 150 Yusong Dukjin Daejon Korea 305-353 Thermal Hydraulic and Safety Research Team Korea Atomic Energy Research Institute 150 Yusong Dukjin Daejon Korea 305-353

＜正＞TID-14844, which was issued in 1962, has been used for regulatory applicationsof source term under design basis accidents. But recently, USNRC issuedNUREG-1465 for regulatory purposes, which represented more realistic source termthan TID-14844 did. NUREG-1465 was based upon research results and insights foraccident source terms obtained over 40 years in PWRs. In order to keep up with thesetrends, in-containment source term calculations for TLOFW （Total Loss of Feed Water）and LLOCA （Large Loss of Coolant Accident） at 1400 MW PWRs is calculated andcompared with NUREG-1465 source term. In case of TLOFW,maximum atmosphericconcentration of Xe/I/Cs/Te radionuclide groups appeared to be smaller thanNUREG-1465 source term by one order of magnitude. In case of LLOCA withemergency safety injection recovery at 30 minutes into the accident, maximumatmospheric concentration of I/Cs/Te radionuclide groups appeared to be a little largerthan NUREG-1465 source term while Xe is smaller. This study provides not only newsource term data using MELCOR1.8.4 and its state-of the-art models but alsoevaluating basis for mitigation capability under severe accidents at 1400 MW PWR.

关键词： In-containment source term apr1400 TID-14844 NUREG-1465 MELCOR1.8.4 Realistic source term

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Hydrodynamic Loads Induced by Air Clearing During Rapid Depressurization through a Unit Cell Sparger in apr1400

Hydrodynamic Loads Induced by Air Clearing During Rapid Depr...

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第13届太平洋地区核能大会

作者： Choon-KyungPARK SeokCHO Chul-HwaSONG Korea Atomic Energy Research Institute Yuseong P.O. Box 105 Daejeon 305-600 Korea Korea Atomic Energy Research Institute Yuseong P.O. Box 105 Daejeon 305-600 Korea Korea Atomic Energy Research Institute Yuseong P.O. Box 105 Daejeon 305-600 Korea

＜正＞A series of sparger tests have been conducted to investigate the performance of asteam sparger, which will be used in a apr1400. The tests have been conducted at theBlowdown and Condensation （B＆C） Loop in Korea Atomic Energy Research Institute（KAERI） using a prototypic steam sparger. The major test parameters include amountof air mass and air temperature in the discharge line, valve opening time, steam massflow rate, and water temperature and level in the IRWST. The hydrodynamic loadsinduced by air clearing during typical operation conditions seems to be weeklydependent on air mass in the piping for a given range of air masses. The valve openingtime and steam mass flow rate had significant effects on the loads. The load increases asthe valve opening time decreases, and the steam mass flow rate increases. However, theload induced by the prototypic steam sparger was less than those expected in a in BWRand the steam sparger tested in this program can be used satisfactorily for the apr 1400.

关键词： Air clearing apr1400 Hydrodynamic load IRWST Steam sparger

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Design Development of Advanced Power Reactor 1400

Design Development of Advanced Power Reactor 1400

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第13届太平洋地区核能大会

作者： Y.S.Choi S.J.Cho D.W.Jerng Center for Advanced Reactors Development Nuclear Environment Technology Institute Korea Hydro ＆ Nuclear Power Co. Ltd. 103-16 Munji-Dong Yuseong-Gu Daejon 305-380 Korea Center for Advanced Reactors Development Nuclear Environment Technology Institute Korea Hydro ＆ Nuclear Power Co. Ltd. 103-16 Munji-Dong Yuseong-Gu Daejon 305-380 Korea Center for Advanced Reactors Development Nuclear Environment Technology Institute Korea Hydro ＆ Nuclear Power Co. Ltd. 103-16 Munji-Dong Yuseong-Gu Daejon 305-380 Korea

＜正＞Advanced Power Reactor 1400 （apr1400） has been developed since 1992 asone of long-term national R＆D projects in Korea. apr1400 is an evolutionary typenuclear power plant of a 1400 MWe class, which upgrades the safety and economiccompetitiveness of nuclear power incorporating up-to-date advanced technologywhile stands on the proven basis of the experience from currently operating nuclearpower plants. Major advanced features were focused on the safety enhancement andthe incorporation of digital technology was made in the control room design. To verifysome of the new design features of apr1400, experimental programs were ***, the system and layout were optimized for cost reduction through the reflectionof the construction and operation experiences of currently operating plants in *** accordance with the design development, the licensing review of the standarddesign was performed and design certification was issued. The first of apr1400 is inthe construction plan to be commissioned in September 2010. The site is preparednext the Kori site, the east-south seashore of Korea, where the first nuclear powerplant in Korea was installed.

关键词： ALWR apr1400 KNGR URD

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两出口压水堆上腔室流动特性数值模拟

两出口压水堆上腔室流动特性数值模拟

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作者：刘嘉维哈尔滨工程大学

学位级别：硕士

上腔室内的流场对反应堆的安全运行有着不可忽视的影响。AP1000作为当下主流的核电技术,一个主要的创新即是将压力容器出口管数目由三个改成两个。本文利用数值计算的方法对两出口压水堆上腔室内流动特性进行研究,并将AP1000与apr1400... 详细信息

上腔室内的流场对反应堆的安全运行有着不可忽视的影响。AP1000作为当下主流的核电技术,一个主要的创新即是将压力容器出口管数目由三个改成两个。本文利用数值计算的方法对两出口压水堆上腔室内流动特性进行研究,并将AP1000与apr1400上腔室进行了比较。通过本文的研究,分析了冷却剂在上腔室的搅混特性和热管段内的热分层现象,对比了两种不同内部结构的两环路上腔室流体特性,本文为上腔室内部构件的优化以及相关研究,提供了重要的参考。本文的数值模拟在Linux系统上进行,通过Salome软件进行前处理,建立计算模型,划分网格,利用Python将模型及网格代码化。通过Codeaturne进行计算,并用Paraview进行数据后处理。根据计算结果,探究了两出口上腔室内的流动特性,得到了导向筒的设计对于流体搅混的作用,对比了不同内部结构下,上腔室流场的变化。并分析了中子低泄漏燃料排布情况下,热管段流体的热震荡现象。计算结果表明,冷却剂在上腔室主要有三条流道,中央区冷却剂首先竖直向上流到堆顶,再进行90折流,流向热管段。近壁区冷却剂距离出口喷嘴较近,则直接流入热管段,若距离出口喷嘴较远,则会以漩涡形式流过控制棒与上腔室内壁形成的环形区域,流入热管段。AP1000接近出口喷嘴处横向流速较高,存在较大压降。而apr1400,冷却剂刚进入上腔室流速较快,在上腔室轴向较低位置存在较大压降。在近壁区环腔90及270 存在漩涡。造成该处较大压降。对比分析得到,上腔室内部构件菱形排布方式优于方形排布。另外,在热管段,冷却剂的混合主要出现在起始段。传热特性计算则表明出口对于上腔室内的温度分布有重要影响,中央区的温度分布轴向变化不大,而近壁区的温度分布则随着高度逐渐均匀。在径向上,中央区的温度随时间的波动不明显。而近壁区冷却剂,呈现较为强烈的温度波动。轴向上,中央区在接近堆顶处,有较为明显的温度波动。冷却剂最大温差由堆芯出口处40C减小到出口喷嘴处15C,说明上腔室内冷却剂搅混并不充分。在热管段起始段,AP1000最大温差小于apr1400最大温差。因此apr1400的上腔室搅混不如AP1000。造成该现象的主要原因为apr1400上栅格板多孔流通面积小,且控制棒为方形排布。

关键词： AP1000 apr1400 上腔室流动特性传热特性搅混

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