• Title/Summary/Keyword: Nuclear Reactor Dismantlement

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IRRADIATION TEST OF MOX FUEL IN THE HALDEN REACTOR AND THE ANALYSIS OF MEASURED DATA WITH THE FUEL PERFORMANCE CODE COSMOS

  • WIESENACK WOLFGANG;LEE BYUNG-HO;SOHN DONG-SEONG
    • Nuclear Engineering and Technology
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    • v.37 no.4
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    • pp.317-326
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    • 2005
  • The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismantlement of nuclear weapons is recently emphasized due to the difficulties in securing the final repository for the spent fuel and the necessity to consume the ex-weapons plutonium. An irradiation test in the Halden reactor was launched by the OECD Halden Reactor Project (HRP) to investigate the in-pile behavior of plutonium-embedded fuel as a form of mixed oxide (MOX) and of inert matrix fuel (IMF). The first cycle of irradiation was successfully accomplished with good integrity of test fuel rods and without any undesirable fault of instrumentations. The test results revealed that the MOX fuel is more stable under irradiation environments than IMF. In addition, MOX fuel shows lower thermal resistance due to its better thermal conductivity than IMF. The on-line measured in-pile performance data of attrition milled MOX fuel are used in the analysis of the in-pile performance of the fuel with the fuel performance code, COSMOS. The COSMOS code has been developed for the analysis of MOX fuel as well as $UO_2$ fuel up to high burnup and showed good capability to analyze the in-reactor behavior of MOX fuel even with different instrumentation.

A Study on Contact Arc Metal Cutting for Dismantling of Reactor Pressure Vessel (원자로 해체를 위한 수중 아크 금속 절단기술에 대한 연구)

  • Kim, Chan Kyu;Moon, Do Yeong;Moon, Il Woo;Cho, Young Tae
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.21 no.1
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    • pp.22-27
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    • 2022
  • In accordance with the growing trend of decommissioning nuclear facilities, research on the cutting process is actively proceeding worldwide. In general, a thermal cutting process, such as plasma cutting is applied to decommissioning a nuclear reactor pressure vessel (RPV). Plasma cutting has the advantage of removing the radioactive materials and being able to cut thick materials. However, when operating under water, the molten metal remains in the cut plane and re-solidifies. Hence, cutting is not entirely accomplished. For these environmental reasons, it is difficult to cut thick metal. The contact arc metal cutting (CAMC) process can be used to cut thick metal under water. CAMC is a process that cuts metal using a plate-shaped electrode based on a high-current arc plasma heat source. During the cutting process, high-pressure water is sprayed from the electrode to remove the molten metal, known as rinsing. As the CAMC is conducted without using a shielding gas, such as Argon, the electrode is consumed during the process. In this study, CAMC is introduced as a method for dismantling nuclear vessels and the relationship between the metal removal and electrode consumption is investigated according to the cutting conditions.