Long-Term Behaviors of Oxide Layer in Liquid Lead–Bismuth Eutectic (LBE), Part II: Model Applications

Zhang, Jinsuo

doi:10.1007/s11085-014-9469-4

Cited by 19 publications

(4 citation statements)

References 12 publications

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“…The Russian experience on LBE-cooled nuclear reactors indicates that the oxygen concentration and the flow velocity are the two most important factors that affect the oxide layer properties (Zhang 2013), which restrict the CiADS subcritical reactor design. The FUTURE code adopted the long-term behaviors model of the oxide layers in an oxygencontrolled system developed by (Zhang 2013(Zhang , 2014 to evaluate the status of the cladding's interface on the LBE side. This model predicts the thickness of the double oxide layers (magnetite layer and spinel layer, which are observed in experiments) due to growth and removal.…”

Section: Coolantmentioning

confidence: 99%

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Wang

Yun

2021

Front. Energy Res.

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The China initiative Accelerator Driven System (CiADS) and the corresponding lead-bismuth eutectic (LBE) cooled subcritical reactor, as the research subject of one of the major national science and technology infrastructure projects, are undertaken by the Institute of Modern Physics-Chinese Academy of Sciences (IMP-CAS). And in the first phase, UO2 fuels will be loaded in the subcritical core to test the coupling technology and achieve a long-term steady operation. A brief description of CiADS subcritical reactor, fuel assembly and fuel element are presented here, and a multi-physics performance analysis and design evaluation of CiADS UO2 fuel are carried out by means of the FUTURE code. FUTURE is a fuel performance analysis code to evaluate the synergy of phenomena occurring in the fuel element and their impact on the fuel design improvement for the liquid metal fast reactor, which was developed jointly by IMP-CAS and Xi’an Jiaotong University (XJTU). In this paper, the FUTURE code was modified and updated focusing on characteristics of CiADS fuels. Relocation and densification models were added. Results of the hottest fuel element, mainly concerning the thermo-mechanical behaviors, are discussed concerning both fuel and cladding performance on the basis of indicative design limits. According to the preliminary design, the CiADS UO2 fuel exhibits good performance, and the main safety parameters are far below the indicative limits. The Fuel Cladding Mechanical Interaction (FCMI) is not very serious, and the permanent cladding strains and Cumulative Damage Fraction (CDF) are small and even negligible thanks to the low level of fuel temperature and corresponding stress. However, some critical issues may still exist, especially on LBE corrosion near the coolant inlet, where protective oxide layers are very thin from BoL to EoL. The modeling is useful for providing feedback to the conceptual design of the CiADS LBE-cooled subcritical reactor and the update of FUTURE code.

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Section: Coolantmentioning

confidence: 99%

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Wang

Yun

2021

Front. Energy Res.

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“…After the magnetite reaches a limiting thickness, it starts to dissolve upon further exposure and the dissolution rate depends on the HLM flow velocity, temperature, and oxygen concentration. The model also suggests that the corrosion rate of HT-9 and T91 steels decreases by about three orders of magnitude after the outer magnetite scale is completely removed by flow-accelerated corrosion [166]. It should be noted, however, that this model does not consider the IOZ, which is often observed after sufficiently long exposures.…”

Section: Mechanistic Understanding and Modelling Of Oxidation Behaviourmentioning

confidence: 96%

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Gong

Short

Auger

et al. 2022

Progress in Materials Science

195

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“…The oxygen concentration and the flow velocity are the two most important factors that affect the oxide layer properties. The long-term behavior of the oxide layers model with an oxygen-controlled system has been developed to evaluate the status of claddings [101,102]. This model predicts the thickness of the double oxide layers (Fe 3 O 4 magnetite layer and spinel layer) considering growth and removal.…”

Section: Corrosionmentioning

confidence: 99%

Cladding Failure Modelling for Lead-Based Fast Reactors: A Review and Prospects

Wang,

Yun

2023

Metals

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Lead-cooled fast reactors (LFRs) are considered one of the most promising technologies to meet the requirements introduced for advanced nuclear systems. LFRs have higher neutron doses, higher temperatures, higher burnup and an extremely corrosive environment. The failure studies of claddings play a vital role in improving the safety criteria of nuclear reactors and promoting research on advanced nuclear materials. This paper presented a comprehensive review of the extreme environment in LFRs based on the fuel performance analyses and transient analyses of reference LFRs. It provided a clear image of cladding failure, focusing on the underlying mechanisms, such as creep, rupture, fatigue, swelling, corrosion, etc., which are resulted from the motions of defects, the development of microcracks and accumulation of fission products to some extent. Some fundamental parameters and behavior models of Ferritic/Martensitic (F/M) steels and Austenitic stainless (AuS) steels were summarized in this paper. A guideline for cladding failure modelling was also provided to bridge the gap between fundamental material research and realistic demands for the application of LFRs.

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Long-Term Behaviors of Oxide Layer in Liquid Lead–Bismuth Eutectic (LBE), Part II: Model Applications

Cited by 19 publications

References 12 publications

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

Cladding Failure Modelling for Lead-Based Fast Reactors: A Review and Prospects

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