Study on CsI release rate coefficient from fuel for source term evaluation

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-27 DOI:10.1016/j.anucene.2025.111288
Masami Taira , Takuma Fujiwara , Yuji Arita
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Abstract

Fission products released to the environment during severe accidents at nuclear power plants are evaluated using severe accident comprehensive analysis codes such as MELCOR. However, the codes cannot directly evaluate the release of CsI as molecular compound from fuel pellets. This is attributed that the release rate coefficient for molecular compounds such as CsI from fuel is not experimentally obtained yet. In this study, a method to experimentally derive the release rate coefficient of CsI from fuel was pursued. In the experiment, after simulated fuels containing CsI were fabricated using grain size as a parameter, CsI released from the simulated fuels was measured by a quadrupole mass spectrometer. Then the method to derive the release rate coefficients of CsI from fuel in the CORSOR-M model was developed converting experimental data into Arrhenius formula. The results demonstrated that the method can experimentally derive the molecular compounds release rate coefficients from fuel.
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源项评价中燃料CsI释放率系数的研究
使用MELCOR等严重事故综合分析代码对核电站严重事故中释放到环境中的裂变产物进行评估。然而,这些规范不能直接评价CsI作为分子化合物从燃料颗粒中释放的情况。这是由于分子化合物如CsI从燃料中释放的速率系数还没有实验得到。本文研究了一种通过实验推导出燃料中CsI释放速率系数的方法。在实验中,以颗粒尺寸为参数制备了含CsI的模拟燃料后,用四极杆质谱仪测量了模拟燃料释放的CsI。在此基础上,建立了CORSOR-M模型中CsI从燃料中释放速率系数的推导方法,将实验数据转化为Arrhenius公式。结果表明,该方法可以通过实验推导出燃料中分子化合物的释放速率系数。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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