• Title/Summary/Keyword: Nuclear Fuel Cladding

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Out-of-pile Characteristics of Advanced Fuel Cladding (HANA alloys)

  • Park, Jeong-Yong;Park, Sang-Yun;Lee, Myung-Ho;Choi, Byung-Kwon;Baek, Jong-Hyuk;Kim, Jun-Hwan;Kim, Hyun-Gil;Jeong, Yong-Hwan;Kim, Gyu-Tae;Jung, Youn-Ho
    • Proceedings of the Korean Nuclear Society Conference
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    • 2005.05a
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    • pp.423-424
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    • 2005

  • The performance of HANA claddings was evaluated in out-of-pile conditions. All the performance test results revealed that HANA claddings were superior to the reference claddings such as Zircaloy-4 and A-cladding. Corrosion resistance was improved by 60 to 70% compared to the commercial claddings. Creep, burst, tensile, LOCA, wear and microstructural properties were shown to be as good as the commercial claddings.

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Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment

  • Gao, Pengcheng;Zhang, Bin;Li, Jishen;Shan, Jianqiang
    • Nuclear Engineering and Technology
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    • v.54 no.1
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    • pp.138-151
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    • 2022

  • Cladding ballooning and rupture are the important phenomena at the early stage of a severe accident. Most severe accident analysis codes determine the cladding rupture based on simple parameter models. In this paper, a FRTMB module was developed using the thermal-mechanical model to analyze the fuel mechanical behavior. The purpose is to judge the cladding rupture with the severe accident analysis code. The FRTMB module was integrated into the self-developed severe accident analysis code ISAA to simulate the PHEBUS FPT3 experiment. The predicted rupture time and temperature of the cladding were basically consistent with the measured values, which verified the correctness and effectiveness of the FRTMB module. The results showed that the rising of gas pressure in the fuel rod and high temperature led to cladding ballooning. Consequently, the cladding hoop strain exceeded the strain limit, and the cladding burst. The developed FRTMB module can be applied not only to rod-type fuel, but also to plate-type fuel and other types of reactor fuel rods. Moreover, the FRTMB module can improve the channel blockage model of ISAA code and make contributions to analyzing the effect of clad ballooning on transient and subsequent parts of core degradation.

  • https://doi.org/10.1016/j.net.2021.07.029 인용 PDF KSCI

Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes

  • Kiraly, Marton;Horvath, Marta;Nagy, Richard;Ver, Nora;Hozer, Zoltan
    • Nuclear Engineering and Technology
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    • v.53 no.9
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    • pp.2990-3002
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    • 2021

  • The mechanical interaction between the fuel pellet and the cladding tube of a nuclear fuel rod is a very important for safety studies as this phenomenon could lead to fuel failure and release of radioactivity. To investigate the ductility of cladding tubes used in WWER type nuclear power plants, several mandrel tests were performed in the Centre for Energy Research (EK). This modified mandrel test was used to model the mechanical interaction between the fuel pellet and the cladding using a segmented tool. The tests were conducted at room temperature and at 300 ℃ with inactive as-received and hydrogenated cladding ring samples. The results show a gradual decrease in ductility as the hydrogen content increases, the ductile-brittle transition was seen above 1500 ppm hydrogen absorbed.

  • https://doi.org/10.1016/j.net.2021.03.019 인용 PDF KSCI

MODAL TESTING AND MODEL UPDATING OF A REAL SCALE NUCLEAR FUEL ROD

  • Park, Nam-Gyu;Rhee, Hui-Nam;Moon, Hoy-Ik;Jang, Young-Ki;Jeon, Sang-Youn;Kim, Jae-Ik
    • Nuclear Engineering and Technology
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    • v.41 no.6
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    • pp.821-830
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    • 2009

  • In this paper, modal testing and finite element modeling results to identify the modal parameters of a nuclear fuel rod as well as its cladding tube are discussed. A vertically standing full-size cladding tube and a fuel rod with lead pellets were used in the modal testing. As excessive flow-induced vibration causes a failure in fuel rods, such as fretting wear, the vibration level of fuel rods should be low enough to prevent failure of these components. Because vibration amplitude can be estimated based on the modal parameters, the dynamic characteristics must be determined during the design process. Therefore, finite element models are developed based on the test results. The effect of a lumped mass attached to a cladding tube model was identified during the finite element model optimization process. Unlike a cladding tube model, the density of a fuel rod with pellets cannot be determined in a straightforward manner because pellets do not move in the same phase with the cladding tube motion. The density of a fuel rod with lead pellets was determined by comparing natural frequency ratio between the cladding tube and the rod. Thus, an improved fuel rod finite element model was developed based on the updated cladding tube model and an estimated fuel rod density considering the lead pellets. It is shown that the entire pellet mass does not contribute to the fuel rod dynamics; rather, they are only partially responsible for the fuel rod dynamic behavior.

  • https://doi.org/10.5516/NET.2009.41.6.821 인용 PDF KSCI