• Journal of Korean Tunnelling and Underground Space Association
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• v.25 no.2
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• pp.175-186
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• 2023

The buffer materials in disposal hole are exposed to the decay heat from spent nuclear fuels and groundwater inflow through adjacent rockmass. Since understanding of thermal-hydro-mechanical-chemical (T-H-M-C) interaction in buffer material is crucial for predicting their long-term performance and safety of disposal repository, it is necessary to investigate the heating-hydration characteristics and consequent T-H-M-C behavior of the buffer materials under disposal conditions considering geochemical factors. In response, the Korea Atomic Energy Research Institute developed a laboratory-scale 'Lab.THMC' experiment system, which characterizes the T-H-M behavior of buffer materials under different geochemical conditions by analyzing heating-hydration process and stress changes. This technical report introduces the detail design of the Lab.THMC system, summarizes preliminary experimental results, and outlines future research plans.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.589-594
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• 1996

도서지역에서의 해수침입에 의한 해수-담수 경계면의 예측은 담수의 이용측면에서 뿐만 아니라 방사성폐기물 영구처분장과 같은 시설을 지하동굴을 이용하여 건설할 경우 설계개념의 설정 및 처분시설의 성능평가 측면에서도 중요한 사항이다. 해수침입의 예측에 널리 사용되어 온 Ghyben-Herzberg 근사식을 자연수위면의 경사가 급한 도서 지하매짙에 적용할 경우 야기되는 문제점을 지적하고, 보다 신뢰성이 향상된 방법인 염분 이동식에 근거한 수치해를 이용하여 해수-담수 경계면을 예측하였다. 경사도가 다른 두 가지 가상 처분시스템에 대한 정상상태에서의 해수침입 해석 결과, Ghyben-Herzberg 근사식은 담수지역에서의 수직 수두구배가 작은 경우에만 적용되며 국내에서 방사성폐기물 처분부지로 고려하였던 굴업도와 같은 작은 도서의 지하매질에서의 해수-담수 경계면 예측시 오류를 범할 수 있으므로 단순 적용은 피해야 할 것으로 판단되었다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.4
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• pp.263-272
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• 2012

A GoldSim template program for a safety assessment of a hybrid-typed repository system, called A-KRS, in which two kinds of pyro-processed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyro-processing of PWR nuclear spent fuels are disposed of, has been developed. This program is ready both for a deterministic and probabilistic total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios. The A-KRS has been probabilistically assessed with 9 selected input parameters, each of which has its own statistical distribution for a normal release and transport scenario associated with nuclide release and transport in and around the repository. Probabilistic dose exposure rates to the farming exposure group have been evaluated. A sensitivity of 9 selected parameters to the result has also been investigated to see which parameter is more sensitive and important to the exposure rates.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.4
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• pp.281-294
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• 2012

The current status of the computer codes for the analysis of coupled thermal-hydrological-mechanical behavior occurred in a high-level waste repository was investigated. Based on the reported results on the comparison between the predictions using the computer codes and the experimental data from the in-situ tests, the reliability of the existing computer codes was analyzed. The presented codes simulated considerably well the coupled thermal-hydrological-mechanical behavior in the near-field rock of the repository without buffer, but the predictions for the engineered barrier system of the repository located at saturated hard rock were not satisfactory. To apply the current thermal-hydrological-mechanical models to the assessment of the performance of engineered barrier system, a major improvement on the mathematical models which analyze the distribution of water content and total pressure in the buffer is required.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.1
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• pp.63-75
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• 2012

This paper gives some basic requirements and preferences of various geological environmental conditions for the final deep geological repository of spent nuclear fuel (SNF). This study also indicates how the requirements and preferences are to be considered prior to the selection of sites for a site investigation as well as the final disposal in Korea. The results of the study are based on the knowledge and experience from the IAEA and NEA/OECD as well as the advanced countries in SNF disposal project. This study discusses and suggests preliminary guideline of the disposal requirements including geological, mechanical, thermal, hydrogeological, chemical and transport properties of host rock with long term geological stabilities which influence the functions of a multi-barrier disposal system. To apply and determine whether requirements and preferences for a given parameter are satisfied at different stages during a site selection and suitability assessment of a final disposal site, the quantitative criteria in each area should be formulated with credibility through relevant research and development efforts for the deep geological environment during the site screening and selection processes as well as specific studies such as productions of safety cases and validation studies using a generic underground research laboratory (URL) in Korea.

• Tunnel and Underground Space
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• v.32 no.2
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• pp.107-119
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• 2022

Excavation-Disturbed Zone (EDZ) is an important design factor in constructing final disposal facilities for spent nuclear fuel, since EDZ affects mechanical stability including a spacing between disposal holes, and the hydraulic properties within EDZ plays a significant role in estimating in-flow rate of groundwater as well as a subsequent corrosion rate of a canister. Thus, it is highly required to characterize in-situ EDZ with precision and control the EDZ occurrence while excavating disposal facilities and constructing relevant underground research facilities. In this report, we not only reviewed EDZ-related researches carried out in the ONKALO facility of Finland but also examined appropriate methods for field inspection and quality control of EDZ occurrence. From the review, GPR can be the most efficient method for in-situ characterization of EDZ since it does not demand drilling a borehole that may disturb a surrounding environment of caverns. And the EDZ occurrence was dominant at a cavern floor and it ranged from 0 to 70 cm. These can provide useful information in developing necessary EDZ-related regulations for domestic disposal facilities.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.349-349
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• 2004

차세대관리 종합공정(Advanced spent fuel Conditioning Process)은 사용후핵연료의 안전하고 효율적인 관리를 위하여 제시된 건식처리공정으로 사용후핵연료를 금속으로 전환하고, 고발열성 핵종(Cs, Sr)을 효율적으로 제거하여 사용후핵연료의 부피, 발열량 및 방사선의 세기를 최대 1/4까지 감소시키고, 처분용기의 소요량과 처분장의 소요면적을 1/2 이상으로 축소함으로서 처분 안전성과 경제성을 높일 수 있는 장점으로 인해 연구개발 중에 있으며, 이의 실증시험 수행을 위하여 ${\alpha}-{\gamma}$ type의 핫셀을 건설 중에 있다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.290-299
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• 2003

고준위 방사성 폐기물 처분장으로부터 유출된 핵종이 인간 생태계에 도달하여 어느 정도의 선량률로서 피폭을 일으키는가를 보이기 위한 생태계 피폭 모델링 및 평가 연구는 처분안전성 평가의 최종 단계로서 핵종 유출의 결과가 인간에게 어느 정도의 방사선 피폭을 주는가를 보이는 것이 그 주요한 내용이 된다. 이 연구를 통하여 도출된 시나리오 중에서 가장 기본이 될 수 있는 생태계에 대하여 AMBER를 사용하여 피폭 계산을 수행하여 선량 환산 인자 평가를 계산해 보았다. AMBER 코드는 핵종 이동 계산을 위해 여러 개의 구획을 설정하고 구획간의 핵종 이동은 핵종 전이 계수(mass transfer coefficient)를 이용하여 계산한다.

• Journal of Energy Engineering
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• v.20 no.3
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• pp.236-241
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• 2011

In this study, considering a degree of proliferation resistance and sustainability, development status of perspective recycling systems for spent nuclear fuels (SNF) is comprehensively reviewed on the basis of the urgent needs of sustainable management measures for high level radioactive wastes such as spent nuclear fuels (SNF).

• Journal of the Korean Geotechnical Society
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• v.33 no.10
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• pp.25-31
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• 2017

The buffer is one of the major components of an engineered barrier system (EBS) for the disposal of high-level radioactive waste (HLW). As the buffer is located between a disposal canister and host rock, it is indispensable to assure the disposal safety of high-level radioactive waste. It can restrain the release of radionuclide and protect the canister from the inflow of groundwater. Since high quantity of heat from a disposal canister is released to the surrounding buffer, thermal properties of the buffer are very important parameters for the analysis of the entire disposal safety. Especially, temperature criteria of the compacted bentonite buffer can affect the design of HLW repository facility. Therefore, this paper investigated thermal properties for the Kyungju compacted bentonite buffer which is the only bentonite produced in South Korea. Hot wire method and dual probe method were used to measure thermal conductivity and specific heat capacity of the compacted bentonite buffer according to the temperature variation. Thermal conductivity and specific heat capacity were decreased dramatically when temperature variation was between $22^{\circ}C{\sim}110^{\circ}C$ as degree of saturation decreased according to the temperature variation. However, there was little variation under the high temperature condition at $110^{\circ}C{\sim}150^{\circ}C$.