• Title/Summary/Keyword: Nuclear Fuel

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Effect of central hole on fuel temperature distribution

  • Yarmohammadi, Mehdi;Rahgoshay, Mohammad;Shirani, Amir Saied
    • Nuclear Engineering and Technology
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    • v.49 no.8
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    • pp.1629-1635
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    • 2017

  • Reliable prediction of nuclear fuel rod behavior of nuclear power reactors constitutes a basic demand for steady-state calculations, design purposes, and fuel performance assessment. Perfect design of fuel rods as the first barrier against fission product release is very important. Simulation of fuel rod performance with a code or software is one of the fuel rod design steps. In this study, a software program called MARCODE is developed in MATLAB environment that can analyze the temperature distribution, gap conductance value, and fuel and clad displacement in both solid and annular fuel rods. With a comparison of the maximum fuel temperature, fuel average temperature, fuel surface temperature, and gap conductance in solid and annular fuel, the effects of a central hole on the fuel temperature distribution are investigated.

  • https://doi.org/10.1016/j.net.2017.07.022 인용 PDF KSCI

PROGRESS IN NUCLEAR FUEL TECHNOLOGY IN KOREA

  • Song, Kun-Woo;Jeon, Kyeong-Lak;Jang, Young-Ki;Park, Joo-Hwan;Koo, Yang-Hyun
    • Nuclear Engineering and Technology
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    • v.41 no.4
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    • pp.493-520
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    • 2009

  • During the last four decades, 16 Pressurized Water Reactors (PWR) and 4 Pressurized Heavy Water Reactors (PHWR) have been constructed and operated in Korea, and nuclear fuel technology has been developed to a self-reliant state. At first, the PWR fuel design and manufacturing technology was acquired through international cooperation with a foreign partner. Then, the PWR fuel R&D by Korea Atomic Energy Research Institute (KAERI) has improved fuel technology to a self-reliant state in terms of fuel elements, which includes a new cladding material, a large-grained $UO_2$ pellet, a high performance spacer grid, a fuel rod performance code, and fuel assembly test facility. The MOX fuel performance analysis code was developed and validated using the in-reactor test data. MOX fuel test rods were fabricated and their irradiation test was completed by an international program. At the same time, the PWR fuel development by Korea Nuclear Fuel (KNF) has produced new fuel assemblies such as PLUS7 and ACE7. During this process, the design and test technology of fuel assemblies was developed to a self-reliant state. The PHWR fuel manufacturing technology was developed and manufacturing facility was set up by KAERI, independently from the foreign technology. Then, the advanced PHWR fuel, CANFLEX(CANDU Flexible Fuelling), was developed, and an irradiation test was completed in a PHWR. The development of the CANFLEX fuel included a new design of fuel rods and bundles.. The nuclear fuel technology in Korea has been steadily developed in many national R&D programs, and this advanced fuel technology is expected to contribute to a worldwide nuclear renaissance that can create solutions to global warming.

  • https://doi.org/10.5516/NET.2009.41.4.493 인용 PDF KSCI

Fretting Wear of Fuel Rods due to Flow-Induced Vibration

  • Kim, Yong-Hwan;Jeon, Sang-Youn;Kim, Jae-Won
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05c
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    • pp.21-26
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    • 1996

  • Recently several PWR Nuclear Plant experienced fuel rod fretting wear failures due to Flow Induced Vibration. When such multi-span supported fuel assembly has vibration excitation, it is important to know how fretting wears are progress and when the fuel rods are start to failure. In this study, we estimate the amount of wear depth using Archard theory when the fuel rod starts to relative motion against spacer grid dimples.

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