Deep borehole drilling is essential not only to select the host rock type for deep geological disposal of high-level radioactive waste (HLW), but also to identify the characteristics of the disposal site during the site selection process. In particular, since the disposal depth of HLW is considered to be over 300 m, deep borehole drilling must be performed. In deep borehole drilling, drilling design, excavation, and operation may vary depending on the rock type, drilling depth, and drilling purpose etc. This study introduced cases in which Korea was divided into four geotectonic structures and four representative rock types and conducted with a goal of 750 m drilling depth. Prior to this, a review of deep drilling cases conducted at domestic and abroad was presented. If sufficient time and cost are available, several drilling holes can be excavated for various purposes, but if not, one or two drilling holes should be used to achieve the objectives of various fields related to HLW disposal. The presence of bedding, strata or fault zones depending on the type of rock, etc. may affect drilling deviation or circulating water management. In addition, unlike drilling in general geotechnical investigation drilling, the use of polymers or grouting agents is limited to determine hydraulic and geochemical characteristics. This report introduces the experience considered during the design and drilling process of deep drilling in granite, gneiss, sedimentary rock, volcanic rock, etc., and is expected to be used as basic data when carrying out future HLW projects.

Despite the increasing interest in Deep Borehole Disposal (DBD) for its capability of minimizing disposal area, detailed research about DBD operation system design should be conducted before the DBD can be implemented. Recently, DBD operation system applying wireline emplacement (WE) technique is under study due to its high flexibility and capability of minimizing surface equipment. In this study, a conceptual WE system, and operation procdure is introduced. The conceptual WE system consists of 3 main stations, which from the top are hoisting station (HS), canister connection station (CCS) and basement (BS). In HS, WE is controlled and monitored. The WE is controlled using wireline drum winch and sheaves, and load on wireline is measured using a load cell. HS also has a pressure control system (PCS), which monitors internal pressure of the system, and a lubricator, which act as housing for joint device, allowing the joint device to be easily inserted into the borehole. The joint device is used to connect the disposal canister to wireline for emplacement/retrieval. In CCS, a rail transporter brings a transport cask containing disposal canisters, then the transport cask is connected to the hoisting system and a PCS in the BS. The main component located at canister station are a sliding shielding door (SSD), and a slip. The SSD is used to prevent canister from falling into borehole during the connecting operation and prevent radiation from BS to affect the workers. The slip is located beneath the SSD and is used to hold the disposal canister before it is lowered into the borehole. In BS, PCS is installed to prevent overflow and blowout of borehole fluid. The PCS consists of wireline pressure valve, christmas tree and BOP, which all are a type of pressure valve to seal the borehole and release pressure inside the borehole. The WE procedure starts with transporting transport cask to CCS. The transport cask is connected to lubricator, and PCS. Joint device is lowered down to be connected with disposal canisters, then pulled up to check the load on the wireline. After the check-up, SSD is opened, and disposal canister is lowered into the borehole. When desired depth is reached, joint device is disconnected and retrieved for next emplacement. In this study, the conceptual deep borehole disposal system design implementing WE technique is introduced. Based on this study, further detailed design could be derived in future, and feasibility could be tested.

Deep geological disposal (DGD) of spent nuclear fuels (SNF) at 500 m–1 km depth has been the mainly researched as SNF disposal method, but with the recent drilling technology development, interest in deep borehole disposal (DBD) at 5 km depth is increasing. In DBD, up to 40SNF canisters are disposed of in a borehole with a diameter of about 50 cm, and SNF is disposed of at a depth of 2–5 km underground. DBD has the advantage of minimizing the disposal area and safely isolating highlevel waste from the ecosystem. Recently, due to an increasing necessity of developing an efficient alternative disposal system compared to DGD domestically, technological development for DBD has begun. In this paper, the research status of canister operation technology and plans for DBD demonstration tests, which subjects are being studied in the project of developing a safety-enhancing high-efficiency disposal system, are introduced. The canister operation technology for DBD can be divided into connection device development and operation technology. The developing connection device, emplacing and retrieving canisters in borehole, adopted the concept of a wedge thus making replacement equipment at the surface unnecessary. The new connection device has the advantage of being well applied with emplacement facilities only by simple mechanical operation. The technology of operating a connection device in DBD can be divided into drill pipe, coiled tubing, free-drop, and wireline. The drill pipe is a proven method in the oil industry, but requiring huge surface equipment. The coiled tubing method uses a flexible tube and shares disadvantages as the drill pipe. The free-drop is a convenient method of dropping canister into a borehole, but has a weakness in irretrievability in an accident. Finally, the wireline method can be operational on a small scale using hydraulic cranes, but the number of operated canisters at once is limited. The test facility through which the connection device is to be tested consists of dummy canister, borehole, lifting part, monitoring part, and connecting device. The canister weight is determined according to the emplacement operation unit. The lifting part will be composed following wireline consisting of a crane, a wire and a winding system. The monitoring part will consist of an external monitoring system for hoists and trolleys, and an internal monitoring system for the connection device’s location, pressure, and speed. In this project, a demonstration test will be conducted in a borehole with 1km depth, 10 cm diameter provided by KAERI to verify operation in the actual drilling environment after design improvement of the connecting device. If a problem is found through the demonstration test, the problem will be improved, and an improved connection device will be tested to an extended borehole with a 2 km depth, 40 cm diameter.

현재 기준개념으로 개발하여 상용화 단계에 있는 심층 동굴 처분기술에 대한 대안으로서 지질학적 조건이 더 안정적인 지하 3~5 km의 심도에 사용후핵연료를 포함한 고준위폐기물을 처분하는 심부시추공 처분기술의 국내 적용 가능성을 예비 평가 하였다. 이를 위하여 심부시추공 처분개념의 기술적 적용성 분석에 필요한 국내 기반암 분포특성 및 심부시추공 처분부 지적합성 평가 기술 분석과 대구경 심부시추기술을 평가하였다. 이들 분석결과를 바탕으로 심부시추공 처분시스템 설계 기준 및 요건에 적합한 심부시추공 처분용기 및 밀봉시스템 개념을 설정하여 예비 기준 심부시추공 처분 개념을 도출하였다. 그리고 도출된 예비 기준 처분시스템에 대하여 열적 안정성 및 그래픽 처분환경에서의 처분공정 모사 등 다양한 성능평가를 수행하고 이들을 종합하여 심부시추공 처분시스템의 국내 적용성에 대하여 다양한 관점에서의 예비평가를 수행하였다. 결론적으로, 심부시추공 처분시스템은 처분심도와 단순한 방법으로 인하여 안전성 및 경제적 타당성 측면에서 많은 장점이 있지만, 불확실성을 줄이고 인허가를 획득하기 위해서는 이 기술에 대한 현장실증이 필수적이다. 본 연구결과는 사용후핵연료 관리 국가정책 수립을 위한 공학적 근거자료로 활용이 가능하며, 심부시추공 처분기술에 관심을 갖는 방사성폐기물 관리 이해당사자들에게 필요한 정보자료로 제공될 수 있다.

본 연구에서는 심부시추공 처분을 위한 밀봉시스템으로서 Gibb’s Group에 의해 제안된 화강암 용융 및 재결정화에 의한 시 추공 밀봉 방안에 대해 KURT 화강암을 대상으로 실현 가능성을 확인하였다. 화강암 용융 실험은 첨가제를 이용한 상압용 융시험과 물의 기화에 의한 수증기 고압용융시험 2가지로 수행되었다. 상압 용융시험 결과, KURT 화강암 분말에 NaOH를 첨가하여도 기본 융점보다 낮은 1,000℃에서 부분용융이 시작되었으며, 냉각된 용융물에서 침상결정의 형성을 확인하였다. 수증기 고압시험은 물의 첨가량에 따라 수증기압을 달리하며 최대 400 bar의 수증기압까지 용융 시험이 진행되었다. KURT 화강암은 낮은 수증기압에도 1,000℃에서 부분 용융이 시작되었으나, 물이 많이 첨가된 높은 수증기압에서 화강암의 부분 용융은 보이지 않았다. 따라서 소량의 수증기가 있는 고압상태가 화강암의 용융에 적합한 것으로 판단되었다. 한편, 고온고압의 수증기는 내부식성의 반응기 벽을 부식시켜, 고온의 수증기에 의한 처분용기의 부식 문제가 발생되었다.

In this study, to replace the ‘J-slot joint’, a joint device between a disposal canister and an emplacement jig in Deep Borehole Disposal process, a novel joint device was designed and tested. The novel joint device was composed of a wedge on top of a disposal canister and a hook box at the end of a winch system. The designed joint device had merits in that it can recombine an emplaced canister freely without the replacement of the joint component. Moreover, it can be applied to various emplacement jigs such as drill pipes, wire-lines, and coiled tubing. To demonstrate the designed joint device, the joint device (Φ 110 mm, H 148 mm), a twin canister string (Φ 140 mm, H 1,105 mm), and a water tube (Φ 150 mm, H 1,500 mm) as a borehole model were manufactured at 1/3 scale. As deployment muds, Na-type bentonite (MX-80) and Ca-type (GJ II) bentonite muds were prepared at solid contents of 7wt% and 28wt%, respectively. The manufactured joint device showed good performance in pure water and viscous muds, with an operation speed of 10 m·min-1. It was concluded that the newly developed joint device can be used for the emplacement and retrieval of a deep disposal canister, below 3~5 km, in the future.

To overcome the low mechanical strength and corrosion behavior of a carbon steel canister at high temperature condition of a deep borehole, SiC ceramics were studied as an alternative material for the disposal canister. In this paper, a design concept for a SiC canister, along with an outer stainless steel container, was proposed, and its manufacturing feasibility was tested by fabricating several 1/3 scale canisters. The proposed canister can contain one PWR assembly. The outer container was also prepared for the string formation of SiC canisters. Thermal conductivity was measured for the SiC canister. The canister had a good thermal conductivity of above 70 W·m-1·K-1 at 100℃. The structural stability was checked under KURT environment, and it was found that the SiC ceramics did not exhibit any change for the 3 year corrosion test at 70℃. Therefore, it was concluded that SiC ceramics could be a good alternative to carbon steel in application to deep borehole disposal canisters.

The concept of deep borehole disposal (DBD) for high-level nuclear wastes has been around for about 40 years. Now, the Department of Energy (DOE) in the United States (U.S.) is re-examining this concept through recent studies at Sandia National Laboratory and a field test. With DBD, nuclear waste will be emplaced in boreholes at depths of 3 to 5 km in crystalline basement rocks. Thinking is that these settings will provide nearly intact rock and fluid density stratification, which together should act as a robust geologic barrier, requiring only minimal performance from the engineered components. The Nuclear Waste Technical Review Board (NWTRB) has raised concerns that the deep subsurface is more complicated, leading to science, engineering, and safety issues. However, given time and resources, DBD will evolve substantially in the ability to drill deep holes and make measurements there. A leap forward in technology for drilling could lead to other exciting geological applications. Possible innovations might include deep robotic mining, deep energy production, or crustal sequestration of CO2, and new ideas for nuclear waste disposal. Novel technologies could be explored by Korean geologists through simple proof-of-concept experiments and technology demonstrations.

원자력발전소에서 전기를 생산하고 난 후 발생하는 사용후핵연료 또는 이들 사용후핵연료의 재처리/재활용 공정으로부터 발생하는 고준위폐기물은 인간환경으로부터 안전하게 장기간 격리시켜야 한다. 최근 심부시추공 굴착기술의 획기적인 발전 으로 인하여, 방사성폐기물의 심부시추공 처분기술에 대한 연구가 의미 있게 진행되고 있다. 본 논문에서는 이러한 심부시추 공을 활용하여 고준위 방사성폐기물을 지하 3~5 km 심도에 격리시키는 심부시추공 처분기술의 국내 적용 가능성을 분석하 기 위하여 국내 심부 지하환경 특성에 대하여 예비분석 하였다 이를 위하여, 미국 및 유럽권 국가 연구사례와 기술개발 현황 을 검토하고, 실제 국내의 심부 지질조건을 검토하기 위하여 고지열 분포지역에 개발 중인 지열 탐사공을 대상으로 3~4 km 심도까지의 암석, 지온 등 특성 자료를 수집, 분석하였다. 결정질 암반 심도 및 지온경사 등 분석 결과와 국내 발생 사용후 핵연료를 바탕으로 심부시추공 처분시스템 구성요소인 처분용기, 밀봉시스템 등에 대하여 예비단계의 개념을 제안하였다.

사용후핵연료를 포함하는 고준위 방사성폐기물을 지질학적 조건이 안정적인 지하 3~5 km의 심도에 처분할 수 있다면 다음 과 같은 많은 장점이 있는 것으로 평가되고 있다. 즉, (1)암반 수리전도도가 매우 낮아 지하수가 생태계까지 도달하는데 속 도가 현저히 감소되며, (2)상부층 두께로 인하여 생태계와의 이격거리 확보에 유리하고, (3)지하수가 환원상태이므로 핵종 의 용해도가 매우 낮을 뿐만 아니라 (4)오랜 연령의 지하수에서는 핵종이 흡착된 콜로이드 생성과 이동이 극히 제한된다는 점이다. 이와 관련하여 심부시추공 처분(Deep Borehole Disposal) 연구는 심층 처분(Deep Geological Disposal) 시스템에 대한 이상적인 처분 대안기술로서 꾸준하게 진행되어 왔다. 본 논문에서는 최근 심부 시추기술이 비약적으로 발전됨에 따 라 의미있게 연구가 진행되고 있는 심부시추공 처분시스템을 국내 적용하기 위한 초기 단계로서 해외의 심부시추공 처분시 스템 기술개발 사례를 분석하였다. 이를 통하여 심부시추공 처분에 대한 일반적인 개념과 심부시추공 처분시스템 개념을 도 출한 연구사례를 국가별로 정리하였다. 이들 분석결과는 향후 심부시추공 처분기술의 국내 적용을 위한 입력자료로서 유용 하게 활용될 수 있을 것이다.

방사성폐기물의 처분연구와 관련하여 대전 유성지역 화강암내 심부시추공 시추코아의 단열 광물들에 대한 광물학적 특성을 연구하였다. 유성지역의 심부시추공들에는 다수의 단열대가 발달해 있으며 국지적인 열수변질작용이 중첩되어 있다. YS-01 시추코아에 대한 전암분석결과 -90 m∼-130 m 구간과 -230 m ∼-250 m 구간에서 급격한 SiO2 함량 감소와 Al2O3, CaO, L.O.I 값의 증가가 관찰되며 이는 단열충전광물의 생성과 관련이 있다. 이러한 단열충전광물에 대한 XRD분석결과 불석광물(로몬타이트, 휼란다이트), 방해석, 일라이트(2M1과 1Md 다형), 녹니석, 녹염석, 카올리나이트 등이 확인되었으며, 산출되는 양은 방해석 불석광물 〉 일라이트 〉 녹염석 녹니석 〉 카올리나이트의 순이다. SEM관찰 및 EPMA 분석결과, 단열충전광물들의 심도에 따른 조직 및 화학특성의 변화는 관찰되지 않는다. 연구지역은 화강암반내에 발달된 단열대가 지하수의 유동로로 작용하여 오랜 기간에 걸친 물-암석 반응이 진행되었고, 또한 저온의 열수변질작용이 중첩되었기 때문에 이들에 의한 단열충전광물의 생성기원 연구가 필요하다.