• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.1
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• pp.9-17
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• 2007

In order to compare the correlation of radioactivity ratio between the radwaste streams and the primary coolant of PWR NPPs, A RCS sampling kit was installed to primary coolant system for the collection of the radionuclides during the normal operation of NPPs. RCS samples were collected from PWR type of domestic NPPs through 2004 to 2005, and pretreated with acid microwave digestion or leaching method to assay quantitatively of several interesting radionuclides. The radioactivity ratios of $^{137}Cs\;to\;^{60}Co$ in a filter cartridge and a resin cartridge were 2.3E-2 and 7.3E-1, respectively. At a same period of the reactor operating cycle, the radioactivity ratios of $^{137}Cs\;to\;^{60}Co$ were 6.3E-1 for a evaporator bottom, 6.7E-1 for a spent resin, and 5.6E-2 for a dry active waste, so that these radwaste streams were identified as having similar characteristics with the corresponding RCS samples.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.1
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• pp.37-43
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• 2012

Radioactive waste transport package was developed to transport eight drums of low and intermediate level waste(LILW) in accordance with the IAEA and domestic related regulations. The package is classified with industrial package IP-2. IP-2 package is required to undergo a free drop test and a stacking test. After free drop and stacking tests, it should prevent the loss or dispersal of radioactive contents, and loss of shielding integrity which would result in more than 20 % increase in the radiation level at any external surface of the package. The objective of this study is to establish the safety test method and procedure for stacking test and to prove the structural integrities of the IP-2 package. Stacking test and analysis were performed with a compressive load equal to five times the weight of the package for a period of 24 hours using a full scale model. Strains and displacements were measured at the corner fitting of the package during the stacking test. The measured strains and displacements were compared with the analysis results, and there were good agreements. It is very difficult to measure the deflection at the container base, so the maximum deflection of the container base was calculated by the analysis method. The maximum displacement at the corner fitting and deflection at the container base were less than their allowable values. Dimensions of the test model, thickness of shielding material and bolt torque were measured before and after the stacking test. Throughout the stacking test, it was found that there were no loss or dispersal of radioactive contents and no loss of shielding integrity. Thus, the package was shown to comply with the requirements to maintain structural integrity under the stacking condition.

• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.41 no.1
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• pp.79-84
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• 2013

DC/DC switching power converters are commonly used to generate a regulated DC output voltage with high efficiency. The DC/DC converter is composed of a PWM-IC (pulse width modulation-integrated circuit) controller, a MOSFET (metal-oxide semiconductor field effect transistor), inductor, capacitor, etc. It is shown that the variation of threshold voltage and the offset voltage in the electrical characteristics of PWM-IC increase by radiation effects in TID (Total Ionizing Dose) testing at the low energy ${\gamma}$ rays using $^{60}Co$, and 4 heavy ions applied for SEL (Single Event Latch-up) make the PWM pulse unstable. Also, the output waveform for the given input in the DC/DC converter is observed by the simulation program with integrated circuit emphasis (SPICE). TID testing on PWM-IC is accomplished up to the total dose of 30 krad, and the cross section($cm^2$) versus LET($MeV/mg/cm^2$) in the PWM operation is studied at SEL testing after implementation of the controller board.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.4
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• pp.351-357
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• 2007

The Japanese Government selected Mutsu, Aomori Prefecture as a provisional spent-fuel repository site. This comes as a result of the prefecture's five-year campaign to host the site since 2000. Korea stores spent nuclear fuel within sites of nuclear power plants, and expects the storage capacity to reach its limit by the year 2016. This compels Korea to learn the cases of Japan. Having successfully hosted Gyeongju as a site for low-to-intermediate-level nuclear waste repository, Korea has already learned the potential process of hosting spent fuel storage site. The striking difference between the two countries in the process of hosting the site is that the Korean government had to offer the local city a large amount of subsidy for hosting through competitive citizens' referendum among candidate cities while it was the leadership of the local municipality that enabled the controversial decision in Japan. It is also a distinguishable characteristics of Japan that not a huge subsidy is provided to the local host city. I hope this study offers an idea to Korea's future effort to select a spent-fuel host site.

• Journal of Radiation Protection and Research
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• v.16 no.1
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• pp.43-52
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• 1991

A comparison study is performed on dose assessment programs including DOSE, LIMCAL, and PABLM, DOSE is a program developed for preliminary safety assessments of the low- and intermediate- level radioactive waste disposal, and the others are existing programs applicable to similar calculations. The results show acceptable agreement within an order of magnitude(mrem/yr) except for C-14 and Pu-239. PABLM results higher dose for C-14 while lower value for Pu-239 in comparison with those from DOSE or LIMCAL. It is found that the discrepancy in C-14 is due to difference in transport model introduced and that in Pu-239 is from the different value of dose conversion factor to each program.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.173-174
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• 2009

"방사성폐기물 고화체의 물성시험"에 사용되는 시편을 실험실적으로 제조한 소규모 모의 고화체 시편과 고화공정에서 직접 채취한 소규모 시편, 200L 드럼으로부터 코아시편을 채취 가공하여 만든 시편과 같이 3종류가 있다. 고화공정에서 발생되는 고화체는 일반적으로 200 L 드럼에 주입되며, 고화체의 균일성 정도는 고화공정의 특성, 폐기물/고화매질 혼합비, 200 L 고화체 드럼의 냉각방식에 따라 다르다. 따라서, 실험실에서 제조한 시편과 공정에서 채취한 소규모 시편을 실제 고화공정을 대표할 수 없으며 또한 실제 발생된 고화체의 조성과도 동일하다고 볼 수 없다. 따라서 200 L 실드럼에서부터 코아시편을 채취하여 만든 시편이 고화공정과도 고화체를 대표할 수 있는 시편으로 볼 수 있다. 기 발생고화체(시멘트와 파리핀 고화체 및 잡고체 폐기물)의 영구처분을 위하여 과기부 고시 05-18호 "폐기물 인도기준" 규정과 한국방사성폐기물관리공단의 중 저준위 방사성폐기물 인수기주(안)의 준수 여부를 평가하기 위하여 각 원전의 대표 드럼에 대하여 특성평가시험인 압축강도, 침출, 침수, 열 순환, 내방사성 영향시험을 수행하기위해 실 드럼으로부터 원통형 코아시편을 채취하여 이를 시험검사에 필요한 시험시편으로 가공한 후 표준 특성시험법을 이용하여 물성들을 평가하며 특성평가시험을 위한 시편으로는 L/D=2, L/D=1인 두 종류의 시편을 가공하였으며 압축, 침수, 열순환 및 방사선조사시편은 L/D=2 시편을 제조하였고 침출시험시편은 L/D=1인 시편을 채취하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.18 no.2
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• pp.119-131
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• 2020

A numerical model was developed using COMSOL Multiphysics to evaluate groundwater flow that causes radionuclide migration in the unsaturated zone of a near-surface disposal facility, which is considered as a domestic low and an intermediate-level radioactive waste disposal facility. Each scenario was modeled by constructing a two-dimensional domain that included the disposal vault, backfill, disposal cover, and unsaturated aquifer. A comparison of the continuous and intermittent rainfall conditions exhibited no significant difference in any of the factors considered except the wave pattern of water saturation. The input data, such as porosity and residual water content of the unsaturated aquifer, were observed to not have a significant effect on the groundwater flow. However, the hydraulic conductivity of the unsaturated aquifer was found to have a significant effect on the groundwater flow. Therefore, it is necessary to assess the hydraulic conductivity of an unsaturated aquifer to determine the extent of groundwater infiltration into the disposal vault.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.25 no.1
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• pp.57-64
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• 2012

Since a seismic exceeding design load can result in exposing radioactive material during disposal process of radioactive wastes, the repository should be designed with enough seismic margin. In this paper, a seismic fragility analysis was performed to evaluate the seismic capacity of surface facility structures. According to the analysis results, since inspection & store facility and radioactive waste facility have a rectangle geometry, the seismic capacity was differently presented about 23%~43% according to the axis of structures. The HCLPF capacity of inspection & store facility and radioactive waste facility was 0.52g and 0.93g, respectively. And it was observed that seismic capacity of radioactive waste facility was similar to that of a containment for nuclear power plants.

• KOREAN JOURNAL OF PACKAGING SCIENCE & TECHNOLOGY
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• v.29 no.3
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• pp.203-209
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• 2023

The increasing saturation challenges in storage facilities for Low- and Intermediate-Level Radioactive Waste call for a more efficient storage approach. Consequently, we have developed a square-structured container that features a storage capacity approximately 20% greater than that of conventional drum-type containers. Considering the need to contain various radioactive wastes from nuclear power usage securely until they no longer pose a threat to human health or the environment, this study focuses on evaluating the sealing efficacy of the newly designed rectangular container using finite element analysis. Since radioactive waste containers typically do not experience external forces except under special circumstances, our analysis simulated the impact of an external force, assuming a fall scenario. After fastening the bolts, we examined the vertical stress distribution on the container by applying the calculated external force. The analysis confirms the container's stable seal.

• Proceedings of the Korean Vacuum Society Conference
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• 2012.02a
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• pp.383-383
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• 2012

전자소자 및 광전소자의 최적화 조건을 확립하기 위해 반도체 나노양자구조의 물리적 현상에 대한 연구가 활발히 진행되고 있다. 반도체 양자세선은 일차원 구조의 기초 물리 특성 관찰과 소자로서의 응용 가치가 높다. 양자세선을 사용한 단전자 트랜지스터, 공명터널 다이오드, 발광다이오드, 광탐지기 및 레이저 소자 제작과 관련한 연구가 활발히 진행 중에 있다. 나노양자구조들 중에서 양자우물과 양자점에 대한 실험적 및 이론적 연구가 많이 진행되었으나, 복잡한 공정 과정과 물리적 이론의 복잡함으로 양자세선에 대한 연구는 상대적으로 미흡하다. 양자세선을 이용한 전자소자와 광전소자의 효율을 증진하기 위해서는 양자세선의 전자적 성질에 대한 연구가 중요하다. 본 연구에서는 InAs/InP 양자세선에 대한 기저상태와 여기상태의 전하분포, 부띠천이 및 전자적 성질을 고찰하였다. 가변 메시 유한 차분법을 이용하여 양자세선의 이산적 모델을 확립하여 변형효과가 양자세선 구조에서 부띠에 영향을 주는지 조사하였다. 변형효과와 비포물선효과를 고려한 슈뢰딩거 방정식을 사용하여 변형 포텐셜을 계산하였으며 양자세선의 포텐셜 변화를 관찰하였다. 양자세선의 포텐셜 변화에 따라 전하구속분포, 에너지 준위 및 파동 함수를 계산하였다. 기저상태의 부띠 간에 발생하는 천이와 여기상태의 부띠 간에 발생하는 부띠 간의 엑시톤 천이 에너지 값을 계산하였다. 계산한 부띠 에너지 천이 값이 광루미네센스로 측정한 엑시톤 천이와 잘 일치하였다. 이 결과는 양자세센의 이차원적인 전자적 구조를 이해하고 양자세선을 사용하여 제작된 전자소자 및 광전소자의 전자적 성질을 연구하는데 도움을 주며, 저전력 나노양자소자를 제작하는 기초지식을 제공하는 중요한 역할을 할 것이다.