• Title/Summary/Keyword: Reactor Dismantling

Search Result 35, Processing Time 0.027 seconds

Assessing the Feasibility of Diver Access During Dismantling of Reactor Vessel Internals

  • Kukhyun Son;Chang-Lak Kim
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.22 no.1
    • /
    • pp.37-44
    • /
    • 2024

  • In 2017, a decision was made to permanently shut down Kori Unit 1, and preparations began to be made for its decontamination and decommissioning. The dismantling of the biological shields concrete, reactor vessel (RV), and reactor vessel internals (RVI) is crucial to the nuclear decommissioning process. These components were radiologically activated by the neutron activation reaction occurring in the reactor during its operational period. Because of the radioactivity of the RV and RVI of Kori Unit 1, remotely controlled systems were developed for cutting within the cavity to reduce radiation exposure. Specialized equipment was developed for underwater cutting operations. This paper focuses on modeling related to RVI operations using the MAVRIC code and the dose calculation for a diver entering the cavity. The upper and lower parts of the RVI are classified as low-level radioactive waste, while the sides that came into contact with the fuel are classified as intermediate-level radioactive waste. Therefore, the modeling presented in this paper only considers the RVI sides because the upper and lower parts have a minimal impact on the radiation exposure. These research findings are anticipated to contribute to enhancing the efficiency and safety of nuclear reactor decommissioning operations.

  • https://doi.org/10.7733/jnfcwt.2024.002 인용 PDF

Design of a virtual dismantling facility for research reactor (연구로 가상 해체 시설 설계)

  • Park Hui-Seong;Kim Seong-Gyun;Lee Geun-U;O Won-Jin;Park Jin-Ho
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2005.11a
    • /
    • pp.47-55
    • /
    • 2005

  • A design of a dismantling mock-up system have been established based on the result that analyzed a characteristic of modules which need to design a virtual dismantling facility. A unit program composed of a various module such as a decommissioning database system. 3D dosimetric mapping that represents a distribution of a radionuclide contamination, a evaluation module for a dismantling schedule and cost A research of software architecture was carried out in order to Integrate these components that have been independently operated. The result was established an architecture that consis of a visualization module which could be visualized D&D activities and a simulation module which tan he evaluated a dismantling schedule and decommissioning cost.

  • PDF

Quantitative Comparison and Analysis of Decommissioning Scenarios Using the Analytic Hierarchy Process Method and Digital Mock-up System (계층화 분석과정법과 디지털 목업을 이용한 정량적 해체 시나리오 평가)

  • Kim, Sung-Kyun;Park, Hee-Sung;Jung, Chong-Hun;Lee, Kune-Woo
    • Journal of Energy Engineering
    • /
    • v.16 no.3
    • /
    • pp.93-102
    • /
    • 2007

  • This paper presents a scenario evaluation model of the AHP (Analytic Hierarchy Process) to evaluate dismantling scenarios considering quantitative and qualitative considerations. And decommissioning information producing modules which can obtain a dismantling schedule, quantify radioactive waste, visualize a radioactive inventory, estimate a decommissioning cost, and estimate a worker's exposure was developed to assess qualitatively decommissioning information. The digital mock-up (DMU) system was developed to verify dismantling processes and find error of scenarios in virtual space. It combines and manages the decommissioning information producing modules, the decommissioning DB, and the dismantling evaluation module synthetically. By using AHP model and DMU system, the thermal column in KRR-1 was evaluated on plasma arc cutting scenario and nibbler cutting scenario using the developed decommissioning DMU system.

  • PDF KSCI

Assessment of the Radiological Inventory for the Reactor at Kori NPP Using In-Situ Measurement Technology (In-Situ 측정법을 이용한 고리 원자로 방사선원항 평가)

  • Jeong, Hyun Chul;Jeong, Sung Yeop
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.12 no.2
    • /
    • pp.171-178
    • /
    • 2014

  • After the expiration of operating license of a plant, all infrastructures within the plant must be safely dismantled to the point that it no longer requires measures for radiation protection. Despite the fact that Kori 1 and Wolsong 1 are close to the expiration of their operating license, sufficient technologies for radiological characterization, decontamination and dismantling is still under development. The purpose of this study is to develop one of methods for radiological inventory assessment on measuring object by using direct measure of large component with In-Situ measurement technique. Radiological inventory was assessed by analyzing nuclide using portable gamma spectroscopy without dismantling reactor head, and the result of direct measurement was supplemented by performing indirect measurement. Radiochemical analysis were performed on surface contamination samples as well. During the study, radiological inventory of reactor vessel calculated expanding the result. Based on the result and the radioactivity variation of each radionuclides time frame for decommissioning can be decided. Thus, it is expected that during the decommissioning of plants, the result of this study will contribute to the reduction of radiation exposure to workers.

  • https://doi.org/10.7733/jnfcwt.2014.12.2.171 인용 PDF KSCI KPUBS