Laser scabbling has the potential to be a valuable technique capable of effectively decontaminating highly radioactive concrete surface at nuclear decommissioning sites. Laser scabbling tool using an optical fiber has a merits of remote operation at a long range, which provides further safety for workers at nuclear decommissioning sites. Furthermore, there is no reaction force and low secondary waste generation, which reduces waste disposal costs. In this study, an integrated decontamination system with laser scabbling tool was employed to test the removal performance of the concrete surface. The integrated decontamination system consisted of a fiber laser, remote controllable mobile cart, and a debris collector device. The mobile cart controlled the translation speed and position of the optical head coupled with 20 m long process fiber. A 5 kW high-powered laser beam emitted from the optical head impacted the concrete block with dimensions of 300 mm × 300 mm × 80 mm to induce explosive spalling on its surface. The concrete debris generated from the spalling process were collected along the flexible tube connected with collector device. We used a three-dimensional scanner device to measure the removed volume and depth profile.

Concrete radioactive waste is divided into surface-contaminated concrete and activated concrete, and although the generation rate varies depending on the operating conditions of the nuclear power plant, it is reported that the amount of surface-contaminated concrete generated is greater. It is reported in the ‘US-NRC Inventory Report’ that 99% of radionuclides in surface-contaminated concrete are distributed within 1 mm of the surface. Since concrete radioactive waste accounts for a large amount of generation after metal radioactive waste, it is necessary to reduce the amount of radioactive waste disposal by applying appropriate treatment techniques to surface-contaminated concrete. In this study, a similar contamination environment work space with the size of 5.4 (W) × 3.6 (L) × 2.5 (H) [m] in which concrete specimens can be fixed on the wall and floor was established. And an integrated decontamination equipment was verified the automation performance for ‘location accuracy’, ‘radioactive contamination level measurement’ and ‘concrete surface laser scabbling’. It was confirmed that the average was 8.3 [mm] in the evaluation of the ‘location accuracy’ for the remote control and movement of the integrated decontamination equipment. For performance verification of ‘radioactive contamination level measurement’ and ‘laser scabbling’, it were used that size of 30×30×8 [cm] ordinary concrete specimens and concrete radioactively contaminated with Co-60 below the regulatory exemption concentration. ‘Radioactive contamination level measurement’ is measured as much as the set range, divied and display the measured values in different colors on the map of the control program. Ordinary concrete specimens are 0.066~0.089 μ Sv/hr, and contaminated concrete specimens are 0.107~0.121 μ Sv/hr, and it was confirmed that they are expressed in different colors on the map. For ‘laser scabbling’, the performance according to the laser scabbling speed and reproducibility with ordinary concrete specimens was verified. As a result, a weight change of up to 1.48 kg was confirmed. Contaminated concrete specimens were subjected to a direct method using a surface contamination detector and an indirect method using a smear paper to measure surface contamination before and after scabbling, and the debris generated after scabbling was analyzed using HPGe.

A large amount of concrete radioactive waste is generated during the decommissioning of nuclear facilities, including nuclear power plants, and it is expected that the radioactive waste management expenses will be huge. In order to reduce the concrete radioactive waste, a decontamination or removal process is required, but working on concrete may present a risk of worker exposure in a high-radioactive space. Therefore, in this study, a remote control integrated decontamination equipment that can reduce concrete radioactive waste and ensure the safety of workers during the concrete decontamination process in a high-radioactive space was developed. The integrated decontamination equipment consists of remote movement, automatic surface contamination measurement, automatic surface decontamination and debris/dust removal systems. The remote movement system generates ‘mapping data’ of topographic features for the work space and ‘location data’ that coordinates the location of the integrated decontamination equipment through LiDAR (Light Detection and Ranging) sensor and SLAM (Simultaneous Localization And Mapping) technique. The user can check the location of the integrated decontamination equipment through ‘location data’ outside the work space, and can move it by remote control through wired/wireless communication. The automatic surface contamination measurement system uses a radiation detector and an automatic measurement algorithm to generate ‘surface measurement data’ based on the measurement distance interval and measurement time set by the user. ‘Surface measurement data’ is combined with ‘location data’ to create a visualized map of radioactive contamination, and users can intuitively realize the location and degree of contamination based on the map. The automatic surface decontamination system uses a laser and an automatic removal algorithm to decontaminate the concrete surface. Concrete debris and dust generated during this process were collected by the debris/dust removal system, minimizing waste generation and radiation exposure due to secondary pollution. The integrated decontamination equipment developed through this study was applied with technologies that reduced radioactive concrete waste and ensured the safety of workers. If technology verification and on-site applicability review are performed using concrete specimens simulating nuclear power plant or similar environments, it is reasoned to contribute to the domestic and overseas decommissioning industry.

The permanent shutdown of NPPs (nuclear power plants) has been growing steadily around the world. Also, permanent shutdown of old NPPs has been determined following to Kori-1 and Wolsong-1 in the Korea. Among issues of decommissioning of NPPs, especially, the management of radioactive waste is the most sensitive issue. According to IAEA, a large volume of radioactive concrete waste would be generated from decommissioning of nuclear facilities. Also, EC (European commission) expected that about 500 million tons of concrete will be produced in Europe by 2060 due to decommissioning of NPPs. It is known that the radioactive concrete consists of surface contaminated concrete and activated concrete. So, if contaminants from radioactive concretes can be removed using specific technologies, volume reduction of concrete can be achieved. Since there is no experience of decommissioning of NPPs in Korea, it is important to analyze previous cases. In this study, decontamination of radioactive concrete is analyzed through previous studies. Decontamination technologies of concrete are composed of mechanical methods, chemical methods, and thermal methods. Mechanical methods are physical technologies separating contaminants from concrete using scabbling, milling, and vacuum cleaning. In chemical methods, contaminants were removed from concrete using an oxidizing agent/reducing agent, acid/base. Thermal methods are removal technologies using lasers, microwaves, and pulsed power discharge. Some methods still have practical use cases, and further research is needed on the issue of generation of secondary waste. Review on the experience of decontamination of concrete show that waste of concrete generated during decommissioning of NPPs are expected to have effect of large volume reduction. However, many studies are needed because secondary waste and decontamination cost is sensitive issue of concrete generated during decommissioning of NPPs. In order to successful decommissioning of NPPs in Korea, various research of decontamination of concrete are need

Decontamination and Dismantlement (D&D) are of great interest to owner of decommissioning as a large number of old nuclear facilities around the world are either shutdown or soon to be decommissioned. D&D are key steps in the decommissioning of nuclear power plants (NPPs). These activities typically generate a significant volume of radioactively contaminated waste. However, as much as 90% or more of this waste is lightly contaminated metal and concrete that could potentially be cleared for recycle or beneficial reuse, rather than disposed of as radioactive waste. The objective of this study is to provide reference for the application of current technologies to cost-effectively reduce the volume of radioactive waste associated with decommissioning, through review of experiences with decontamination of NPPs materials for unrestricted release, recycle or reuse, Also, highlights the importance of ongoing efforts to harmonize regulations and standards for radioactive waste management globally to enable reuse and recycle of valuable materials generated during decommissioning. The presented results in the balance of this study are organized to align with the sequence of operations for executing reuse or recycle of material for a decommissioning project. Concrete from buildings has most commonly been used for backfill of voids onsite, while metal has most commonly been melted or cleared into the conventional scrap recycling industry. Copper and lead, commonly found in cables and shielding, have high residual value and are thus highly desirable for recycling. Steel and stainless steel, while not inherently valuable, are present in many large components, such that decontamination for recycling can be cost-effective compared to disposal as radioactive waste. The decontamination techniques range from simple, inexpensive methods to complex, aggressive methods, each with advantages in various scenarios and limitations in others. Treatment often involves the sequential application of two or more decontamination techniques (e.g., chemical decontamination followed by abrasive blasting). Strategies for the characterization of materials for recycling include analyzing material in place before dismantlement, analyzing removed samples before or after dismantlement, and evaluating bulk material removed after dismantlement. If clearance and recycling are permitted, metals can be released to the conventional scrap recycling market, and concrete rubble can be used as backfill material onsite. In general, successful reuse/recycle projects require consideration of reuse/recycling objectives and implementation of associated planning activities early in the decommissioning process. The practicality of reuse/recycle depends on a number of high level (country and region-specific) and component level (material and case specific) factors. Since this information is useful to those responsible for planning or implementing the decommissioning of nuclear facilities, it is expected that it will be of great help especially to those in charge of decommissioning plan and managers in charge of decommissioning projects.

Laser scabbling experiments were conducted with the aim of developing concrete decontamination technology. Laser scabbling system contains a 6 kW fiber laser (IPG YLS-6000, λ=1,070 nm) and optical head, which are connected with process fiber (core dia.: 600 μm, length: 20 m). Optical head consists of two lenses (f = 160 mm and 100 mm) to collimate and focus laser beam. The focused laser beam is passed through the small diameter of nozzle (throat dia.: 3 mm) to prevent the laser-produced debris into head. And then, the focused beam is directed toward concrete block as continuously diverging. The diverged laser beam was incident on the high-strength concrete with 300 mm (length) × 300 mm (height) × 80 mm (width) to induce explosive spalling on the concrete surface. The optical head was moved by X-Y-Z manipulate coupled with a computerized numerical control while scabbling. We have observed not only active spalling on the concrete surface but energetic scattering of laserproduced debris when scabbling on high-strength concretes. It indicates the need for a device capable of collecting the laser-produced debris. We newly designed and manufactured dust collector coupled with cylindrical tube to prevent scattering of laser-produced debris into ambient environment. The collecting system was evaluated by estimating the collecting efficiency for laser-produced debris while scabbling. The collecting efficiency was calculated on the basis of the information on the mass loss of concrete block after laser scabbling and the mass of collected debris in a container. The collecting efficiency was found to be over 85%.

현재 중국을 제외한 전세계에서 가동중인 원전중 50% 이상이 운전을 시작한지 30년 이상으로, 앞으로 해체가 진행될 원전이 대부분이다. 우리나라 역시 고리 1호기를 시작으로 수명연장이 없을 경우 10년 이내에 총 5기의 원전이 폐로될 것으로 예상되며 향후 해체를 진행해야 한다. 가장 먼저 해체가 진행될 고리 1호기에서 나오는 저준위 방사성폐기물의 양은 200L 드럼으로 14,500개에 해당할 것으로 예상되며, 이를 위한 처분 비용은 한수원이 제시한 원전 1기 해체 비용인 6,347억원의 40%에 해당된다. 이 비용을 줄이기 위해선 방사화된 콘크리트나 금속부분을 효율적으로 제거하는 제염기술이 필요하다. 연구용 원자로인 트리가마크-II 및 III와 우라늄변환시설을 해체한 경험이 있지만 소규모 저방사능 시설에만 국한되어 있을 뿐, 원전처럼 방사성물질 농도가 높은 대규모 시설에 대한 경험이 부족하다. 따라서 고리 1호기 해체 시 적용할 제염기술에 대해 다양한 방법으로 검토할 필요가 있다고 생각된다. 이에 본 연구에서는 현재 국내외에서 개발 및 실증된 제염기술에 대해 알아보았다.

원자력시설을 해체하는 과정에서 발행하는 방사성폐기물은 크게 금속, 콘크리트, 토양, 기타 잡고체로 구분되며 이중 콘크리트폐기물이 80% 이상을 차지한다. 상용 원자력발전소의 경우 콘크리트 폐기물은 약 50~55만톤 발생하는 것으로 알려져 있으며, 1기의 상용원전을 해체할 경우 원자로 가동 중 발생된 중성자 조사에 의한 구조물의 방사화 및 방사성 물질의 비산에 따른 오염으로 방사화된 콘크리트폐기물은 약 25,000톤이 발생한다. 발생된 폐기물을 드럼에 포장할 경우 수 만 드럼이 될 것으로 예상되며 그에따른 처분비 역시 천문학적인 비용이 들어갈 것으로 예상된다. 이를 줄이기 위해 방사성 콘크리트폐기물 발생량을 최소화하고 발생한 폐기물을 재활용하여 최종 처분되는 폐기물의 양을 줄이는 연구가 필요하다. 우리나라는 대규모 시설에 대한 해체 경험이 부족하기 때문에 고리 1호기에 적용할 효과적인 제염기술을 선정하기 위해선 상용원전을 해체한 경험이 있는 나라의 제염기술에 대해 알아볼 필요가 있다고 생각된다. 이에 본 연구에서는 상용원전 해체 경험이 있는 나라에서 적용한 제염기술에 대해 알아보고 기술의 장단점을 평가하여 적용 여부와 개선방안에 대해 알아보았다.

원자력발전소가 폐로 단계에 도달하게 될 경우, 다량의 방사성물질 및 폐기물이 발생한다. 특히, 해체 시 발생되는 콘크리트 폐기물은 경제적, 환경적 측면을 고려해서 재사용, 재활용, 처분 등이 관리방법 중 가장 적합한 방법을 선정해야 한다. 원자력시설의 해체 시 발생하게 되는 콘크리트 폐기물은 80%이상을 차지하고 있으며, EC(European Commission)의 보고서에 의하면 2060년까지 원자력 시설의 해체에 따라 유럽에서만 약 500만 톤의 콘크리트 폐기물이 발생할 것으로 예상하고 있다. 이러한 막대한 양의 콘크리트 폐기물에 대해 프랑스, 일본, 벨기에 등에서는 이미 콘크리트 폐기물의 제염 및 저감에 대한 연구가 심도 있게 진행 중에 있으며 프랑스의 경우에는 실험적인 연구를 거쳐서 상용화 수준에 다다른 실정이다. 콘크리트 폐기물은 원자력시설에 제한적으로 재활용이 가능하며, 방사성 폐기물의 저장 및 기반시설의 건설, 방사성 폐기물 처리에 사용되는 콘크리트 고화체, shielding block, backfiller 등으로 사용되고 있다. 해체 콘크리트 폐기물은 용적오염과 표면 오염으로 이루어져 있으며 대부분 표면으로부터 약 1∼10mm 두께로 오염되어 있어 기계적 처리 방법을 통해 방사성 폐기물로서 처리되어야 한다. 방대한 양으로 발생되는 콘크리트 해체폐기물을 자체처분 하거나 재활용한다면 처분 대상 폐기물량의 감소로 인한 처분 비용의 절감 및 처분 안전성의 증대뿐만 아니라 자원의 재활용성을 증대시킨다는 점에서 매우 긍정적인 측면을 나타낸다. 원자력시설의 콘크리트 제염기술로는 물리적 방법을 사용한 제염기술이 주로 사용되며 이를 다시 세분화 하면 표면제염기술과 표면파쇄제염으로 구분된다. 방사성 콘크리트의 물리적 표면제염 공정 및 장치 선정시에는 오염확산 및 작업자의 방사능 피폭 최소화, 제염 폐기물의 최종 처리방법, 제염 작업 최적화를 위한 최단, 최소 작업과 장소, 대상, 목적 등을 고려하여 제염기술이 선정되어야 한다. 이는 곧바로 방사능 구역에서의 작업자의 안전성 향상 및 해체비용 절감과 직결되기 때문이다. 그러나 원자력이라는 특수한 상황에서는 최적의 기술 선정시 경제적인 측면 보다는 안전성에 바탕을 두고, 주위 환경이 오염을 최대한 억제하는 방법에 초점을 맞추어야 할 것이다.