• Journal of the Korean Society of Systems Engineering
• /
• v.17 no.1
• /
• pp.65-75
• /
• 2021

When the decommissioning of South Korea nuclear power plants is promoted in earnest with the permanent shutdown of Kori Unit 1 in 2017, a large amount of various types of radioactive waste will be generated. For minimal generation and safe management of decommissioning waste, the waste should be made by appropriate classification of the dismantling waste characteristics in accordance with physical, chemical and radiological characteristics to meet the acceptance criteria of disposal facilities. Replacing the preliminary inspection at the site for the compliance of the waste acceptance criteria (WAC) of medium and low-level radioactive waste with the generator's own radioactive waste certification program (WCP), from the perspective of disposal, the optimization of waste management at the national level contributes to the efficient availability of disposal, such as the processing of non-conforming radioactive wastes at the site. To this end, it is important to evaluate radioactivity in each system and area such as nuclear reactors before decommissioning is carried out in earnest, and the prior removal of harmful wastes is important. From waste collection to waste disposal, decommissioning waste should be managed at each stage in consideration of the acceptance criteria of disposal facilities to minimize the generation of non-conforming waste.

• Proceedings of the Korea Information Processing Society Conference
• /
• 2013.11a
• /
• pp.1382-1385
• /
• 2013

본 논문에서는 로봇의 움직임 특성을 추출하여 로봇 시스템의 신뢰성을 평가하는 방법을 제안한다. 원자력 발전소 증기 발생기 전열관의 비파괴 검사에 사용되는 ECT 검사용 Probe 가이드 로봇 (이하 증기발생기 로봇으로 기술)을 대상으로 하였다. 증기발생기 로봇의 동작 상태를 감시하기 위해 관측 카메라가 설치된다. 증기발생기 수실은 로봇 설치 및 해체를 위한 원형의 출입구 (Man Way)를 제외하고는 밀폐된 공간이다. 증기 발생기 전열관의 비파괴 검사 중에는 로봇과 로봇의 동작을 감시하는 관측 카메라만 설치된다. 관측 카메라가 고정되어 있다면, 배경의 변화를 야기하는 외란은 없다고 가정할 수 있다. 시간적으로 이웃하는 2 개의 관측 영상을 미분 (차 영상) 처리하면, 로봇 시스템의 이동 성분만 추출된다. 이러한 이동성분의 크기를 계산하여 로봇의 전체 행정거리 (ECT Probe를 검사위치에 안내하기 위해 로봇 기구부가 움직이는 범위)에 대해 영상 프레임 단위로 전개하면 특정의 고유 궤적이 나타난다. 이러한 고유 궤적과 다른 패턴을 보이는 로봇의 움직임 궤적은 에러로 간주한다. Burn-in 시험 (원자력 발전소 현장에 투입하기 전에 실험실에서 현장 적용의 타당성을 검증하기 위해 수행하는 시험) 중에 있는 증기발생기 로봇에 대해 본 논문에서 제안한 방법으로 신뢰성 평가를 수행하였으며, 그 결과 및 문제점 등에 대해 기술한다.

• Nuclear Engineering and Technology
• /
• v.22 no.4
• /
• pp.416-422
• /
• 1990

현재 추진중인 중,저준위 방사성폐기물 영구 처분장은 현시점에서 적용중인 처리기술외에는 더 이상의 기술개발을 고려치 않고 폐기물 발생량을 추정하여 이를 근거로 하였는데, 당 연구소에서 개발중인 감용처리기술이 적용된다는 가정아래 향후 방사성 폐기물 관리계획을 검토하였다. 국내에서 발생되는 방사성 폐기물의 대부분을 차지하는 원자력 발전소 운전으로 인해 발생되는 폐기물에 대해서만 감용처리기술을 적용해도 해체폐기물이 본격적으로 발생되는 2018년 이전까지는 그 발생량이 55%까지 감소함을 알 수 있었다. 따라서 초기건설용량 25만 드럼규모의 처분장에 대해 그 운영기간은 7년이상 연장할 수 있을 것으로 예상되었다.

• Journal of the Korean Recycled Construction Resources Institute
• /
• v.6 no.2
• /
• pp.115-122
• /
• 2018

In this paper, the feasibility of recycling concrete waste as a method to reduce final disposal amount of wastes generated through decommissioning of nuclear power plant has been analyzed based on experimental results of existing literature. When recycled concrete waste was used as recycled aggregate, it was investigated through literature that the concrete strength decreased by 30~40% depending on the mixing ratio. It was also investigated that concrete with recycled aggregate can be used as a structural material when the quality of recycled aggregate is well managed since no significant problem was found. When recycled cement produced from concrete waste was used, the strength of concrete or mortar decreased considerably as the recycled cement content increased. Therefore, it can be concluded that concrete or mortar with recycled cement can be used as a filling material for final disposal of large radioactive waste rather than for structural use. This paper is expected to be useful for reduction on disposal volume and decommissioning cost for nuclear power plants such as Kori 1.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.17 no.1
• /
• pp.121-126
• /
• 2019

The radionuclide inventory prediction of a nuclear power plant can help establish decommissioning plan by providing information of radiation environment. Accumulated radionuclides in reactors and related facilities after reactor shutdown can be divided into neutron activated materials and contaminated materials. Among the neutron activated radionuclides, $^{36}Cl$ and $^{41}Ca$ are important from the viewpoint of disposal because of its long half-life and physiochemical characteristics. In this research, we calculated the radionuclides of $^{36}Cl$ and $^{41}Ca$ in bioshielding concrete by estimating the neutron flux and cross section using the MCNPX. And we evaluated the inventories of $^{36}Cl$ and $^{41}Ca$ using the activation calculation code ORIGEN2.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.13 no.1
• /
• pp.21-34
• /
• 2015

Source term analysis should be carried out to prepare the decommissioning of the nuclear power plant. In the planning phase of decommissioning, the classification of decommissioning wastes and the cost evaluation are performed based on the results of source term analysis. In this study, the verification of MCNP/ORIGEN-2 model is carried out for preliminary source term calculation for Wolsung Unit 1. The inventories of actinide nuclides and fission products in fuel bundles with different burn-up were obtained by the depletion calculation of MCNPX code modelling the single channel. Two factors affecting the accuracy of source terms were investigated. First, the neutron spectrum effect on neutron induced activation calculation was reflected in one-group microscopic cross-sections of relevant radio-isotopes using the results of MCNP simulation, and the activation source terms calculated by ORIGEN-2 using the neutron spectrum corrected library were compared with the results of the original ORIGEN-2 library (CANDUNAU.LIB) in ORIGEN-2 code package. Second, operation history effect on activation calculation was also investigated. The source terms on both pressure tubes and calandria tubes replaced in 2010 and calandria tank were evaluated using MCNP/ORIGEN-2 with the neutron spectrum corrected library if the decommissioning wastes can be classified as a low level waste.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.14 no.2
• /
• pp.123-134
• /
• 2016

Decommissioning of nuclear power plants has become a big issue in South Korea as some of the nuclear power plants in operation including Kori unit 1 and Wolsung unit 1 are getting old. Recently, Wolsung unit 1 received permission to continue operation while Kori unit 1 will shut down permanently in June 2017. With the consideration of segmentation method and disposal containers, this paper evaluated final disposal amount of radioactive waste generated from decommissioning of the reactor pressure vessel in Kori unit 1 which will be decommissioned as the first in South Korea. The evaluation results indicated that the final disposal amount from the top and bottom heads of the reactor pressure vessel with hemisphere shape decreased as they were cut in smaller more effectively than the cylindrical part of the reactor pressure vessel. It was also investigated that 200 L and 320 L radioactive waste disposal containers used in Kyung-Ju disposal facility had low payload efficiency because of loading weight limitation.

• Fire Science and Engineering
• /
• v.34 no.3
• /
• pp.134-140
• /
• 2020

Nuclear power plants (NPPs) in Korea are required to be maintained using a defense in-depth approach to prevent leakage of radioactive substances outside the plant and allow safe shutdown in the event of a fire. Periodic testing must be conducted to ensure that the fire protection facilities perform as required by the laws for various nuclear reactor types. In June 2017, for the first time in Korea, a nuclear plant, Kori Unit 1, was permanently shut down. It was prepared for decommissioning in accordance with the fire protection regulations imposed by the regulatory body. However, a standard protocol is necessary for systematically establishing the fire protection program for decommissioning of NPPs in the future. Therefore, the nuclear legal systems of countries with many operating nuclear power plants, such as the United States, Japan, Canada, and various European countries, were reviewed and guidelines for establishing a fire protection program for decommissioning NPPs was suggested; the fire protection requirements stated by Reg Guide 1.191 (Decommissioning fire protection program for NPPs during decommissioning and permanent shutdown) were used as a model. Suggestions for establishing legal regulations to optimize fire protection programs and secure basic technology for decommissioning NPPs were also made.

• Journal of the Korean Society of Radiology
• /
• v.15 no.6
• /
• pp.795-801
• /
• 2021

The designed drone-based unmanned remote radiation detection module was developed according to the needs of the nuclear power plant decommissioning workshop. Using the Geiger-Mueller tube sensitive to low-level radiation measurement, It was manufactured to measure the amount of radiation leaking into and out of the containment vessel. The drone-based radiation detection module weighs less than 200g, It can be operated inside and outside the containment vessel of a nuclear power plant. To check the performance of the designed equipment, a performance evaluation test was conducted with reference to the international standard (IEC-60864). The stability of the radiation detection module designed to meet the needs of the field the statistical rate of change by repeated measurements in the rate of change experiment to evaluate the measurement accuracy was ±4.6%. The accuracy ±7.3% in the linearity experiment to evaluate the dose rate dependence, the linear The figure satisfies the international performance evaluation standard of ±3.5%. The radiation detection module developed in this study is a customized equipment for a nuclear power plant dismantling workshop. It will be helpful for accurate measurement of space dose rate and safety management of radiation worksites in sites with a lot of radiation dust.

• Proceedings of the Korean Vacuum Society Conference
• /
• 2015.08a
• /
• pp.116.1-116.1
• /
• 2015

원자력 발전소 고리 1호기의 해체가 결정됨에 따라 발전소를 구성한 금속기기의 제염처리가 대두되고 있다. 금속 방사성폐기물 중 상당수는 그 자체가 방사성 오염 물질이라기보다는 오염 핵종이 표면에 부착하고 있는 경우가 많아 제염 공정을 거쳐 폐기한다면 보관해야 하는 양을 획기적으로 줄일 수 있을 것이다. 이에 따라 본 연구실에서는 플라즈마트론을 이용한 방사성 폐기물 건식제염처리에 대하여 연구하였다. 본 실험에서는 방사성을 띄지 않는 동위원소 Co sheet와 DC 플라즈마트론을 사용하였다. Ar 1000 sccm을 고정으로 비율(10:0, 9:1, 8:2, 7:3, 6:4), 거리(20 mm, 30 mm 40 mm), 시간(60 sec, 120 sec, 180 sec)을 변수로 두어 실험하였다. 결과적으로 기체의 혼합비가 4:1일 때 최대 식각율 $9.24{\mu}m/min$을 확인했다.