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Preliminary validation of ASTEC V2.2.b with the QUENCH-20 BWR bundle experiment

机译:Quench-20 BWR捆绑实验的ASTEC V2.2.B的初步验证

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摘要

ASTEC is an integral severe accident code which aims to simulate entire severe accident transients of the nuclear reactors. New BWR-related models are implemented in the new versions of European ASTEC integral code by IRSN for BWR-typical core structures such as absorber blades, canister, etc. during the In-vessel core degradation after a severe accident in a BWR. The goal is to improve the simulation of the whole severe accident sequence in a BWR, such as the Fukushima accidents. An important step is the validation of the new models (oxidation, molten material formation and melt relocation, etc.) before the code is used to simulate severe accident scenarios in BWRs. The QUENCH-20 BWR test was specifically performed to investigate the oxidation, hydrogen generation, melt formation and oxidation during the reflooding of the test section representing a quarter of a SVEA-96 Optima-2 fuel assembly. The data measured during the QUENCH-20 BWR test e.g. temperature of the fuel rod simulators, of the blade and of the canister as well as the hydrogen production, quench front movement is used for the validation of the code's prediction capability. In this work, the code ASTEC V.2.2.b is used to simulate the behavior of the QUENCH-20 test section. For this purpose, a detailed model of the QUENCH facility and test section was developed. This model was used to analyze the severe accident phenomena taking into account the same boundary conditions i.e. electrical power, mass flow rates, pressure, etc. as in the test. It was found out that the evolution of the temperature distribution in the bundle is reasonably evaluated by ASTEC for the entire duration of the transient. Besides, oxidation processes are also well reproduced. ASTEC predicts a total hydrogen generation of about 53 g while the measured value is around 57 g. In addition, ASTEC rather well predicted that about 15% of this hydrogen amount comes from the B4C-oxidation. Such good overall agreement between ASTEC and experimental measurements leads to further validation possibilities on BWR plant applications.
机译:ASTEC是一个不可或缺的严重事故代码,旨在模拟核反应堆的整个严重事故瞬变。新的BWR相关模型是在IRSN的新版本的欧洲ASTEC积分代码中实现了BWR - 典型的核心结构,例如吸收刀片,罐等在BWR中发生严重事故后的血管核心劣化期间。目标是改善BWR中整个严重事故序列的模拟,例如福岛事故。在代码用于模拟BWRS中的严重事故情景之前,这一重要步骤是对新模型(氧化,熔融材料形成和熔体重定位等)进行验证。具体进行猝灭-20BWR试验以研究代表SVEA-96 Optima-2燃料组件的四分之一的测试部分的氧化,氢气产生,熔体形成和氧化。在Quench-20 BWR测试期间测量的数据例如。燃料棒模拟器的温度,刀片和罐的刀具以及氢气产生,淬火前移动用于验证代码的预测能力。在这项工作中,代码ASTEC v.2.2.b用于模拟Quench-20测试部分的行为。为此目的,开发了淬火设施和测试部分的详细模型。该模型用于分析严重事故现象,考虑到相同的边界条件i.E.电力,质量流量,压力等。发现束中温度分布的演变是通过ASTEC进行的,在瞬态的整个持续时间内合理地评估。此外,氧化过程也良好再现。 ASTEC预测约53克的总氢气产生,而测量值约为57克。此外,ASTEC相当良好预测,该氢量的约15%来自B4C氧化。 ASTEC和实验测量之间的这种良好的总体协议导致BWR植物应用的进一步验证可能性。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2020年第12期|110931.1-110931.9|共9页
  • 作者单位

    Karlsruhe Inst Technol Inst Neutron Phys & Reactor Technol Hermann von Helmholtz Pl 1 D-76344 Eggenstein Leopoldshafen Germany;

    Karlsruhe Inst Technol Inst Neutron Phys & Reactor Technol Hermann von Helmholtz Pl 1 D-76344 Eggenstein Leopoldshafen Germany;

    Karlsruhe Inst Technol Inst Neutron Phys & Reactor Technol Hermann von Helmholtz Pl 1 D-76344 Eggenstein Leopoldshafen Germany;

    Karlsruhe Inst Technol Inst Appl Mat Mat Phys Hermann von Helmholtz Pl 1 D-76344 Eggenstein Leopoldshafen Germany;

  • 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
  • 中图分类
  • 关键词

    ASTEC; QUENCH; Severe accident; BWR; Reflooding;

    机译:astec;熄灭;严重事故;bwr;reshooding;

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