LIVE Experiments on Melt Behavior in the Reactor Pressure Vessel Lower Head

ALEXEI MIASSOEDOV; THOMAS CRON; XIAOYANG GAUS-LIU; ALEXANDER PALAGIN; SILKE SCHMIDT-STIEFEL; THOMAS WENZ

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LIVE Experiments on Melt Behavior in the Reactor Pressure Vessel Lower Head

机译：反应堆压力容器下盖融化行为的LIVE实验

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The main objective of the LIVE program at Karlsruhe Institute of Technology is to study the core melt phenomena both experimentally in large-scale three-dimensional (3D) geometry and in supporting separate-effects tests, and analytically using computational fluid dynamics (CFD) codes in order to provide a reasonable estimation of the remaining uncertainty band under the aspect of safety assessment. Within the LIVE experimental program several tests have been performed with water and with noneutectic and eutectic melts (mixtures of KNO_3 and NaNO_3) as simulant fluids. The results of these experiments, performed in nearly adiabatic and in isothermal conditions, allow a direct comparison with findings obtained earlier in other experimental programs (SIMECO, ACOPO, BALI, etc.) and will be used to assess the correlations derived for the molten pool behavior.

机译：卡尔斯鲁厄理工学院LIVE程序的主要目标是通过大型三维（3D）几何形状并支持单独效果测试，以及使用计算流体力学（CFD）代码进行分析来研究核心融化现象为了在安全评估方面对剩余的不确定带提供合理的估计。在LIVE实验程序中，已经使用水以及非共晶和共晶熔体（KNO_3和NaNO_3的混合物）作为模拟流体进行了一些测试。这些实验的结果是在几乎绝热和等温条件下进行的，可以直接与之前在其他实验程序（SIMECO，ACOPO，BALI等）中获得的发现进行直接比较，并将用于评估熔池的相关性行为。

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来源
《Heat Transfer Engineering》 |2013年第15期|1226-1236|共11页
作者
ALEXEI MIASSOEDOV; THOMAS CRON; XIAOYANG GAUS-LIU; ALEXANDER PALAGIN; SILKE SCHMIDT-STIEFEL; THOMAS WENZ;
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作者单位

Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (IKET), Karlsruhe, Germany;

Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (IKET), Karlsruhe, Germany;

Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (IKET), Karlsruhe, Germany;

Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (IKET), Karlsruhe, Germany;

Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (IKET), Karlsruhe, Germany;

Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (IKET), Karlsruhe, Germany;

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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
原文格式 PDF
正文语种 eng
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专利

1. LIVE-L4 AND LIVE-L5L EXPERIMENTS ON MELT POOL AND CRUST BEHAVIOR IN LOWER HEAD OF REACTOR PRESSURE VESSEL [J] . X. GAUS-LIU, A. MIASSOEDOV, J. FOIT, Nuclear Technology . 2013,第1期

机译：反应堆压力容器下端熔池和壳行为的LIVE-L4和LIVE-L5L实验
2. Features of heat and deformation behavior of a WER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification and in-vessel top cooling of corium pool on the thermal loads acting on WER-600 's reactor pressure vessel during a severe accident [J] . Loktionov Vladimir, Mukhtarov Erkin, Lyubashevskaya Irina Nuclear Engineering and Design . 2018,第JANa期

机译：在严重事故期间，WER-600反应堆压力容器在皮质池逆分层和恶化的外部容器冷却条件下的热和变形行为特征。第1部分。严重事故期间，反熔分层和皮质池的炉内顶部冷却对WER-600反应堆压力容器上作用的热负荷的影响
3. The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part I: Physical processes, modeling and model implementation [J] . Chi-Thanh Tran, Truc-Nam Dinh Progress in nuclear engergy . 2009,第8期

机译：用于模拟轻水反应堆压力容器下缸盖中熔池传热的有效对流模型。第一部分：物理过程，建模和模型实现
4. The Impact of Transient Behavior of Corium in the Lower Head of a Reactor Vessel for In- Vessel Melt Retention Strategies [C] . L. Carenini, F. Fichot International conference on nuclear engineering . 2016

机译：反应堆容器下部头部中的皮质瞬态行为对容器内熔体保留策略的影响
5. Effect of external cooling on the thermal and mechanical behavior of light water reactor vessel lower heads [D] . Park, Hyunjae 1992

机译：外部冷却对轻水反应堆容器下部水头热力学性能的影响
6. On the Elevated Temperature Thermal Stability of Nanoscale Mn-Ni-Si Precipitates Formed at Lower Temperature in Highly Irradiated Reactor Pressure Vessel Steels [O] . N. Almirall, P. B. Wells, H. Ke, -1

机译：高辐照反应堆压力容器钢中较低温度下形成的纳米Mn-Ni-Si沉淀物的高温热稳定性研究
7. The Effective Convectivity Model for Simulation and Analysis of Melt Pool Heat Transfer in a Light Water Reactor Pressure Vessel Lower Head [O] . Tran, Chi Thanh 2009

机译：轻水反应堆压力容器下部熔池传热模拟与分析的有效对流模型。

LIVE Experiments on Melt Behavior in the Reactor Pressure Vessel Lower Head

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