首页> 外文会议>49th annual meeting on nuclear technology >Simulation of the Bundle Test QUENCH-07 with the Severe Accident Analysis Codes ASTEC V2.1 and AC~² - ATHLET-CD
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Simulation of the Bundle Test QUENCH-07 with the Severe Accident Analysis Codes ASTEC V2.1 and AC~² - ATHLET-CD

机译:用严重事故分析代码ASTEC V2.1和AC〜²模拟捆绑测试QUENCH-07-ATHLET-CD

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During a severe accident in a light water reactor (LWR) the likely production of hydrogencan cause oxyhydrogen reactions with serious consequences. In order to gain abetter understanding of the thermal behavior, oxidation kinetics and the resulting hydrogengeneration of core materials like Zircalloy-4 (Zry-4), the QUENCH tests wereconducted.In the framework of the QUENCH-07 bundle test, the impact of absorber rod failure onhydrogen, carbon monoxide, carbon dioxide and methane generation can be determined.From the beginning of the test a mixture of overheated steam and argon with amass flow of 3 g/s each, streams through the bundle. The latter consisting of 20 heatedfuel rod simulators and one central unheated boron carbide absorber rod simulatorwith a stainless steel cladding and a Zircalloy-4 guide tube. Validation work presentedin the following shows the simulation of the bundle test QUENCH-07 with the severeaccident analysis codes ASTEC V2.1 and AC~² - ATHLET-CD. An objective of the simulationsconducted is the analysisand assessment of thecode capabilities to simulatethe most relevant phenomenain particular related to boroncarbide during the QUENCHtest. For the simulations conductedwith ASTEC an existinginput deck by L. Laborde andF. Igier for QUENCH-03 andQUENCH-11 was used as abasis and modified forQUENCH-07 [LAB14]. For thesimulations conducted withAC² - ATHLET-CD an existingversion by T. Drath was updatedto the latest code version[DRA07].
机译:在轻水反应堆(LWR)发生严重事故期间,可能产生的氢气会引起氢氧反应,并产生严重后果。为了更好地了解Zircalloy-4(Zry-4)等核心材料的热行为,氧化动力学和所产生的氢,我们进行了QUENCH测试。\ r \ n在QUENCH-07管束试验的框架内,可以确定吸收器杆失效对氢,一氧化碳,二氧化碳和甲烷生成的影响。\ r \ n从试验开始时,就是过热蒸汽和氩气的流量分别为3 g / s,流过束。后者由20个加热的燃料棒模拟器和一个中央不加热的碳化硼吸收棒模拟器组成,带有不锈钢包层和Zircalloy-4导管。下面介绍的验证工作显示了使用严重的\ n \ n事故分析代码ASTEC V2.1和AC〜²-ATHLET-CD对捆绑测试QUENCH-07的仿真。进行模拟的目的是分析\ r \ n并评估\ r \ n代码的能力,以模拟\ r \ n最相关的现象\ r \ n特别是与QUENCH期间的硼\ r \ n碳化物有关的\ r \ n测试。对于用ASTEC进行的模拟,L。Laborde和\ r \ nF使用了一个现有的\ r \ n输入平台。将QUENCH-03和\ r \ nQUENCH-11的Igier用作\ r \ n基础,并针对\ r \ nQUENCH-07进行了修改[LAB14]。对于用\ r \nAC²-ATHLET-CD进行的模拟,T。Drath已将现有的\ r \ n版本\ r \ n更新为最新的代码版本\ r \ n [DRA07]。

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    Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics, Ruhr-Universität Bochum (RUB) jan.peschel@rub.de;

    Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics, Ruhr-Universität Bochum (RUB) gremme@lee.rub.de;

    Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics, Ruhr-Universität Bochum (RUB) koch@lee.rub.de;

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