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 Wolseong 1, PHWR (Pressurized Heavy Water Reactor) was decided. Accordingly, there is need for C-14 treatment technology to spent resin generated by PHWR in classified Medium Level Radioactive Waste by C-14 specific activity. However, spent resin by PHWR is mixed and stored with activated carbon and zeolite (mixture), not a single storage, and separation from the mixture must be carried out in advance for C-14 treatment in the spent resin. This study developed a C-14 treatment facility that combined with the technology of separating spent resin from spent resin mixture by PHWR NPP and the technology of C-14 treatment for disposal. The C-14 treatment facility consists of spent resin separation (Part 1) and treatment of separated spent resin. (Part 2) Part 1 is applied with a process of separating the mixed and stored spent resin from the spent resin mixture by applying a drum screen method. In the case of Part 2, spent resin treatment process for desorbing and collecting C-14 nuclides in the separated spent resin using microwave reactor was applied. Except for the adsorbent used to collect C-14 detached in the process of separating and treating spent resin, no additional material is introduced into the facility, and thus secondary waste is significantly reduced. In addition, pollution prevention banks at the bottom of the facility and a sealed automated circulation system were applied to prevent unexpected leakage and diffusion of radioactive materials and ensure stability of workers. Currently, the C-14 treatment facility has been verified for spent resin separation and spent resin treatment using simulated spent resin mixture, and the facility will be demonstrated and verified for field applicability. According to derived results, it is believed that it will be possible to apply the C-14 treatment facility when decommissioning of PHWR.

본 연구는 유기 벼 재배시 주로 이용되는 유기질비료가 토양화학성과 벼의 생장 및 수량에 미치는 영향을 구명하기 위해 수행되었다. 전남지역 벼 유기재배지에서 많이 이용되고 있는 유기질비료를 Organic fertilizer(이하 OF) I, 식물성 성분이 많이 함유된 비료(쌀겨 위주)를 OF II, 동물성 성분이 많이 함유된 비료를 OF III, 그리고 식물성과 동물성이 혼합된 비료를 OF IV로 나누어서, 벼 이앙 전에 전층시비로 토양에 골고루 처리하였다. 유기질비료내의 탄질율이 상대적으로 낮았던 OF I과 III이 OF II와 IV에 비교하여 시기별로 유기질비료의 질소 무기화가 빠르게 진행되었다. 토양의 시기별 유기물 함량은 유기질비료 투입량이 많았던 OF II와 IV에서 높게 나타났으며, 수확 후 토양의 화학성은 대체적으로 OF II와 IV에서 높게 나타났다. 벼 생장특성은 처리에 따른 차이는 나타나지 않았다.

함정에 사용되는 선체재료로는 연강, 고장력강, 고강도강, 알루미늄 합금 및 복합재료 등이 있다. 그 중 함정의 선체는 수밀과 강도 의 유지 및 탑재장비의 지지 등 기본적인 기능을 위하여 철강 재료를 주로 사용하고 있다. 함정의 주 임무는 해양에서 작전을 수행하는 것이 므로 해수에 의한 선체 부식이 필연적으로 발생하게 된다. 선체의 부식을 방지하기 위하여 도장 방법, 희생양극법 및 강제 전류 방식이 사용 되고 있다. 특히 Al 및 Zn을 활용한 희생양극법의 경우 부식특성 개선을 위하여 인듐(In), 카드뮴(Cd) 및 납(Pb) 등의 중금속이 첨가되어 있 다. 하지만 이러한 중금속은 인체 및 환경에 매우 유해하므로 전 세계적으로 사용이 점차 규제되고 있다. 이에 본 논문에서는 인체 및 환경에 무해한 미세원소(Ma, Ca, Ce 및 Sn)를 첨가하여 Al 및 Zn 합금을 제조하였다. 제조된 함정용 Al 및 Zn 희생양극의 효율 특성 측정을 위하여 SEM, XRD, 동전위 분극실험 및 전류효율 평가를 실시하였으며, 실험결과 Al-3Zn-0.6Sn 및 Zn-3Sn 합금의 양극 성능이 다른 합금 보다 효 율성이 우수하였다.