중수는 경수와 다른 물리화학적 특징으로 다양한 생물화학적 변화를 유도할 수 있다. 기존 분리공정의 단점인 에 너지소비량을 줄이고자 전기방사 폴리아마이드 분리막을 이용하여 정삼투공정을 이용하였다. 유도용액으로 NaCl과 인산을 사용하였다. 중수농도를 정량화하기 위해 FT-IR 분광법을 활용하였다. 인산과 수소/중수소의 특별한 상호작용력을 분광학적 으로 확인하였으며, 정삼투공정으로 농축이 가능할 수 있다는 것을 관찰하였다.
In this study, four types of water-heavy fuel oil hybrid emulsion oil were manufactured depending on the moisture content ratio in order to reduce exhaust emissions of heavy fuel oil(Bunder-C), which is necessarily used in vessels, power plants and boilers. The components of the manufactured emulsion oil were analyzed using the ISO standard testing method. The analysis result showed that in the EM25 fuel with a maximum moisture content ratio of 25.0%, the moisture content was 25.0%, the sulphur content was 0.20%, the kinematic viscosity was 144.8mm2/s, the specific gravity was 0.9382, and the flash point was 100 Celsius degrees or above.
Heavy metals in stream water and sediments around industrial complex were studied in order to assess the contamination and to identify the potential source of metals. High variability has been observed for both dissolved and particulate phases in stream water with coefficient of variation (CV) ranging from 1.3 to 2.8. The highest metal concentrations in both phases were observed in Gunja for Ni and Cu, in Jungwang for Zn and Pb and in Shiheung for Cd, respectively. These results indicate that the different metal sources could be existing. The concentrations of the heavy metals in sediments decreased in the order of Cu>Zn>Pb>Cr>Ni>As>Cd>Hg, with mean of 2,549, 1,742, 808, 539, 163, 17.1, 5.8, 0.07 mg kg-1, respectively. Mean of metal concentrations (except for As) in sediments showed the highest values at Shiheung stream comparing with other streams. In sediments, the percent exceedance of class II grade that metal may potentially harmful impact on benthic organism for Cr, Ni, Cu, Zn, Cd, Pb was about 57%, 62%, 84%, 60%, 68%, 81% for all stream sediments, respectively. Sediments were classified as heavily to extremely polluted for Cu and Cd, heavily polluted for Zn and Pb, based on the calculation of Igeo value. About 59% and 35% of sediments were in the categories of “poor” and “very poor” pollution status for heavy metals. Given the high metal concentrations, industrial wastes and effluents, having high concentrations of most metals originated from the manufacture and use of metal products in this region, might be discharged into the stream through sewer outlet. The streams receive significant amounts of industrial waste from the industrial facilities which is characterized by light industrial complexes of approximately 17,000 facilities. Thus, the transport of metal loads through streams is an important pathway for metal pollution in Shihwa Lake.
한국고라니(Hydropotes inermis argyropus)는 우리나라의 고유종으로 가장 흔한 종의 하나이다. 이 종은 한반도 전역에 널리 분포하며 자연생태계에서 초식자로서 중요한 역할을 하는 것으로 알려져 있다. 따라서 고라니는 서식지의 질을 모니터링하는데 하나의 좋은 생물지표종으로 이용될 수 있을 것이다. 이 연구에서는 강원도 철원지역과 전라남도 동부지역에서 수집된 한국고라니의 서로 다른 3가지 조직(신장, 간, 지라)에서 5가지 중금속(Fe,
In general, water treatment sludge (WTS) had high concentration of heavy metal, thus it made the reuse or recycling of WTS difficult. The optimal solidification conditions for maximum suppression of heavy metal elution from WTS were decided in this study. Under the optimal solidification conditions (i.e., temperature, 320℃; ratio of WTS and MgO, 9:1; solidification time, 1hr), all of heavy metal including aluminum were not detected. Therefore there are no problems for reuse or recycling of WTS which was solidified under the optimal solidification conditions found in the study.
The adsorption of heavy metals in the waste water carried out on the various domestic clays and waste pottery. The effect of parameters such as pH, temperature, adsorption time and coexisting cations on the adsorption ability and characteristics were investigated to find out whether the clays could be used as adsorbents. Adsorption equilibrium was reached within 20 minutes on all the clays. The optimum pH was found to be above 5. When other cations such as Cu(II) or Zn(II) coexisted with Pb(II), the adsorption amount of Pb(II) decreased because of competing adsorption.
충남 서부 활석광산 주변의 수계에 대한 원소 함량특성에 대해 알아보고자 대흥 및 광천광산에 대해 수질 및 하상 퇴적물 시료와 함께 광산 주변 토양 및 모암 시료를 채취, 비교하였다. 대흥지역 퇴적물은 대부분 원소에서 SP가 GN에 비해 높았는데 이는 퇴적물 내 유색 및 무색광물 함량 차이로 판단된다. 절대 함량 비교에서 광물 결정구조 내 쉽게 Mg와 치환하는 원소는 낮은비율을, Fe와 치환하는 원소는 높은 비율을 보였는데 이는 퇴적물 내 주 구성광물내 원소 치환특성을 반영하기 때문으로 판단된다. 절대 함량의 감소 순서와 타원소들과 높은 상관관계(>0.85)의 빈도를 보이는 원소들 사이의 차이는 퇴적물 화학조성에 이차광물과 비정질 광물등의 조성도 반영되었음을 암시한다. 대흥지역 지표수는 대부분 원소에서 MSP가 SP와 GN의 중간값을, MSG는 LGN과 MSP의 중간값을 조여 수계의 혼합특성을반영하는 것으로 판단된다. 절대 함량관계에서는 SP는 GW1과 유사했고, GN은 LGN과 유사했으며, 절대함량은(Mg, Fe), (As, Sc), (Mo, V, Se) 순서로 낮아졌다. 광천지역은 갱내수가 천부 지하수에 비해 대부분 원소에서 높은 함량을 보였는데, 이는 갱내수가 더욱더 많은 물-암석반응을 거친 때문으로 판단된다. 절대 함량은 Mg, Br, Fe, (Sc, Cr), (An, Ni, V)순서로 감소하였다. 갱냉수의 지역간 원소 함량 차이는 사문암화가 우세한 광천지역과 활석화가 우세한 대흥지역 모암들 사이의물-암석 상화반응의 차이를 보여주는 것으로 판단된다 두 지역의 상부 토양 및 모암 조성에서 SP가 GN에 비해 높은 Mg 비, Ni, Cr, Co 등 함량을 보였는데, 이는 사문암 지역 내 Mg, Ni, Cr 등이 풍부한 광물들 탓으로 판단된다. 퇴적물과 수질 사이에서는 함량 경향을 뚜렷하지 않았고 원소에 따라 서로 다른 힘량 차이를 보였는데, 이는 퇴적물 원소 함량이 수계 조성을 반영하는 것이 아님을 나타낸다. 상부-토양-암석-수계의 조성관계에서 대흥지역 지표수 중 SP 조성이, 광천지역은 갱냉수가 지하수의 조성에 가까웠다.
충남 사문암 지역인 광천, 홍성, 백동, 대흥 및 유구지역의 토양, 식물체(참억새, 쑥, 리기다소나무) 및 지표수, 갱내수의 중금속 함량을 분석한 결과 사문암 토양의 Ni, Cr 및 Co 원소가 변성암 토양에 비하여 10~13배높았으며 이 원소들이 serpentine factor로 생각된다 사문암 지역간에는 이들원소의 차이가 뚜렷하지 않았다 변성암 토양식물에서보다 사문암 토양 식물에서 Ni, Cr, Co등이 높았다 리기다소나무의 원소 흡수량은 비교적 낮았고 3종 식물에서 대체로 뿌리의 원소 함량이 지상부 함량보다 높았으며 사문암 토양에서는 Ni, Cr, Co, Mo, Sc, As 및 Fe 원소들이 쑥보다 참억새에서 높았다 사문암 토양에서 생육하는 식물체 지상부의 생물학적 흡수계수는 Ni, Cr, Co, Zn, Sc, As 및 Fe 원소는 참억새에 높고Zn은 쑥에서 높았다,. 사문암 토양에서 뿌리로부터 지상부로의 원소 전이는 Ni, Cr, Co, Zn As 및 Fe 원소에 대해 쑥에서 높았고 Mo와 Sc 원소는 리기다소나무에서 높았다. 따라서 사문암 토양에서 참억새가 중금속의 흡수율은 높고 중금속에 대한 내성은 강할 것으로 사료된다 대흥지역에서 광산의 오염이 지표수 및 갱내수의 Ni. Cr, Co, Zn 및 Fe 등의 원소 농도를 높게 하였으며 비오염 계류는 오염계류의 원소 농도를 희석시켰다.
This study were conducted to estimate the values of the heavy metal in the fresh water fish and shellfish collected from fish market. The levels of the heavy metal were determined in a total of 319 samples of 11 species of the fresh water fish and 14 species of the shellfish by mercury analyzer and atomic absorption spectrophotometer. The results of this study were summerized as follows; The average contents of the heavy metal in the fresh water fish were Pb 0.075, Hg 0.053, Cd 0.002, Cr 0.135, Fe 8.695, Mn 1.078, Zn 9.491, Cu 0.548 mg/ kg. The average contents of the heavy metal in the shellfish were Pb 0.059, Hg 0.007, Cd 0.146, Cr 0.147, Fe 40.808, Mn 7.738, Zn 13.943, Cu 2.731 mg/kg. Being compared the average contents of the heavy metal of the fresh water fish with those of shellfish, the average contents of Cd, Fe, Mn, Cu in the shellfish were significantly higher than in the fresh water fish(P$lt;0.001). Depending on the sampling areas, the average contents of the heavy metal were different by districts. The contents of the heavy metal were changed with the seasons(P$lt;0.05).
Chitosan itself has been prepared using chitin, one of the most abundant compounds in nature, as a starting material. We have synthesized the water-soluble chitosan derivative, N-dithiocarboxy chitosan sodium salt, through the reaction of water-soluble chitosan with carbon disulfide in the presence of alkali metal hydroxide. To elucidate this natural polymer capacity of adsorbing heavy metal ions, we have performed adsorption experiments using the water-soluble chitosan derivative various average molecular weight and of different percent contents of sulfur. The effect of pH, adsorption time and temperature on adsorption efficiency was also studied. The adsorbent derived from water-soluble chitosan of average molecular weight ranging 9,000~120,000 was shown to have the highest capacity of adsorbing heavy metal ions. On the whole, adsorbing efficiency was increased as the reaction time goes longer and also increased as the reaction temperture goes higer in temperture range of 15℃~45℃. The adsorption capacity at various pH, however, was appeared to vary depending on the heavy metal ions studied Judging from these finding, water-soluble N-dithiocarboxy chitosan sodium salt, a derivative of a biodegradable nature polymer, is believed to be a potential adsorbent for heavy metal ions since it not only is shown to lower the concentration of heavy metal ions to below the drainage quality standard, but also it would not cause acidification and hardening of soil which is one of the detrimental effects of synthetic macromolecular adsorbents present.
Heavy water primary system decontamination technology is essential to reduce worker exposure and improve safety during maintenance and decommissioning of nuclear facilities. Advanced decontamination technology development aims to secure controlled decontamination technologies that can reduce the cost of radiation exposure and dramatically reduce the amount of secondary waste generated when decontaminating large equipment and large-area facilities. We conducted a study to identify candidate corrosion inhibitors through the literature and analyze the degree of corrosion of carbon steel samples. Countries with advanced nuclear technology have developed chemical decontamination technology for the entire nuclear power generation system and applied it to the dismantling and maintenance of nuclear power plants. In the decontamination process, the corrosion oxide film must be removed. If the base metal is corroded by the decontaminant in this process, additional secondary waste is generated and treatment costs increase. Therefore, it is necessary to develop a corrosion inhibitor that inhibits the corrosion of the carbon steel base metal in the decontamination process to generate a secondary waste liquid that is favorable for waste reduction and treatment. In this presentation, a study was conducted to analyze the extent of corrosion on a carbon steel base material and identify candidate materials for corrosion inhibition testing. Samples were analyzed using optical microscopy and EPMA analysis to determine the thickness of the corroded oxide film. EPMA analysis also allowed us to map the elemental distribution of the carbon steel corrosion layer, which we plan to quantify in the future. The candidate materials for organic-based corrosion inhibitor were also selected based on their inhibition mechanism; having high electronegative elements for coordinate covalent bonding at metal surface and hydrophobic nonpolar group for preventing access of corrosive substances.The selection of candidate materials for corrosion inhibition testing was based on the mechanism of the corrosion inhibitor. Organic-based corrosion inhibitors are adsorbed by donor-acceptor interactions between metal surfaces and highly electronegative elements. Corrosion can also be inhibited by arranging hydrophobic nonpolar groups on metal surfaces in the solution direction to prevent access of corrosive substances.
Pressurized Heavy Water Reactors (PHWR) have stored ion exchange resins, which are used in deuteration, dehydrogenation systems, liquid waste treatment systems, and heavy water cleaning systems, in spent resin storage tanks. The C-14 radioactivity concentration of PHWR spent resin currently stored at the Wolseong Nuclear Power Plant is 4.6×10E+6 Bq/g, which exceeds the limited concentration of low-level radioactive waste. In addition, when all is disposed of, the total radioactivity of C-14, 1.48×10E+15 Bq, exceeds the disposal limit of the first-stage disposal facility, 3.04×10E+14. Therefore, it is currently impossible to dispose of them in Gyeongju intermediate- and low-level disposal facilities. As to dispose of spent resins produced in PHWR, C-14 must be removed from spent resins. This C- 14 removal technology from the spent resin can increase the utilization of Gyeongju intermediate- and low-level disposal facilities, and since C-14 separated from the spent resin can be used as an expensive resource, it is necessary to maximize its economic value by recycling it. The development of C-14 removal technology from the spent resin was carried out under the supervision of Korea Hydro & Nuclear Power in 2003, but there was a limit to the C-14 removal and adsorption technology and process. After that, Sunkwang T&S, Korea Atomic Energy Research Institute, and Ulsan Institute of Science and Technology developed spent resin treatment technology with C-14-containing heavy water for the first and second phases from 2015 to 2019 and from 2019 to the present, respectively. The first study had a limitation of a pilot device with a treatment capacity of 10L per day, and the second study was insufficient in implementing the technology to separate spent resin from the mixture, and it was difficult to install on-site due to the enlarged equipment scale. The technology to be proposed in this paper overcomes the limitations of spent resin mixture separation and equipment size, which are the disadvantages of the existing technology. In addition, since 14CO2 with high concentration is stored in liquid form in the storage tank, only the necessary amount of C-14 radioactive isotope can be extracted from the storage tank and be used in necessary industrial fields such as labeling compound production. Therefore, when the facility proposed in this paper is applied for treating mixtures in spent resin tanks of PHWR, it is expected to secure field applicability and safety, and to reflect the various needs of consumers of labeled compound operators utilizing C-14.
According to IAEA PRIS, there is no record of dismantling commercial heavy water reactors among 57 heavy water reactors around the world. In Canada, which has the largest number of heavy water reactors, three of the 22 commercial heavy water reactors with more than 500 MW are permanently suspended, Gentilly unit 2 (2012), Pickering unit 2 (2007), and Pickering unit 3 (2008), all of which chose a delayed decommissioning strategy. On the other hand, Wolsong unit 1, which will be the world’s first heavy water reactor to be dismantled commercially, will be immediately carried out as a decommissioning strategy. KHNP has established various cooperation systems with advanced companies and international organizations related to overseas NPP decommission and is actively exchanging technologies. Among them, the most important focus is on research cooperation related to COG (CANDU owners Group). The first case is a joint study on Conceptual Calandria Segmentation. Four areas of process, waste management, ALARA, and cost for decommissioning reactors to be submitted to Canadian regulators for approval of Pickering and Gentilly-2’s preliminary decommissioning plan have been evaluated, and research on Wolsong unit 1 is currently underway. The second case is Decommissioning and long-term waste management R&D. Although the technical maturity is low, it studies the common interests of member companies in the decommissioning of heavy water reactor power generation companies and long-term waste management. Robotics for dismantling high-radiation structures, C- 14, H-3 measurement and removal methods, and concrete decontamination technology, which are characterized by heavy water, are being actively studied. KHNP is strengthening international cooperation with COG to prepare for the successful decommissioning of Wolsong unit 1. Based on previous studies by Pickering and Gentilly-2, an evaluation of the decommissioning of Wolsong unit 1 reactor is being conducted. In addition, it is preparing for decommissioning through experience analysis of the pressure tube replacement project.
KHNP is carrying out international technical cooperation and joint research projects to decommission Wolsong unit 1 reactor. Construction data of the reactor structures, experience data on the pressure tube replacement projects, and the operation history were reviewed, and the amount of dismantled waste was calculated and waste was classified through activation analysis. By reviewing COG (CANDU owners Group) technical cooperation and experience in refurbishment projects, KHNP’s unique Wolsong unit 1 reactor decommissioning process was established, and basic design of a number of decommissioning equipment was carried out. Based on this, a study is being conducted to estimate the worker dose of dismantling workers. In order to evaluate the dose of external exposure of dismantling workers, detailed preparation and dismantling processes and radiation field evaluation of activated structures are required. The preparation process can be divided into dismantlement of existing facilities that interfere with the reactor dismantling work and construction of various facilities for the dismantlement process. Through process details, the work time, manpower, and location required for each process will be calculated. Radiation field evaluation takes into account changes in the shape of structures by process and calculates millions of areas by process, so integrated scripts are developed and utilized to integrate input text data. If the radiation field evaluation confirms that the radiation risk of workers is high, mutual feedback will be exchanged so that the process can be improved, such as the installation of temporary shields. The results of this study will be used as basic data for the final decommissioning plan for Wolsong unit 1. By reasonably estimating the dose of workers through computer analysis, safety will be the top priority when decommissioning.
Under the Foreign Trade Act, an export license from the Nuclear Safety Commission is required to export items specified in Part 10 of Schedule 2 of the Public Notice of Exportation and Importation of Strategic Items (Trigger List Items). In the case of nuclear materials, deuterium, and heavy water, its cumulative amount determines whether it is trigger list item. An export license is required only if the cumulative amount exported to a single end-user country from January 1st to December 31st exceeds the regulation criteria. The reason for this cumulative control is to exclude small amounts of materials from the scope of control as they are considered less important in view of nuclear proliferation, but to prevent the possibility of acquiring large quantities of materials by importing small amounts several times. As a result, export control of nuclear material, deuterium, and heavy water requires different considerations than other Trigger List Items. First, materials exported by different companies must be consolidated to manage the cumulative amount. Second, it is necessary to continuously follow up the actual export status. If the material is not exported after it was classified as ‘non-Trigger List Items’, it should not be included in the cumulative amount. Third, there may be a difference between the accumulated quantities aggregated at the time of the classification and the time of the actual export. The classification should be changed if an export of the classified material is postponed or another export of same materials occurs before the export of the classified material. Fourth, the classification result of these materials should not be reused. Generally, the classification result could be reused within the expiration date (2 years) but in the case of substances. However, the reuse of classification result for materials should be limited as the classification results could be change depending on the cumulative amount. In addition, the sharing of classification results between different entities should also be restricted. The government approval procedures are required even for export of small amounts of nuclear materials which are less than the regulation criteria. The cumulative quantities of nuclear materials are systematically managed in the Nuclear Export & imPort control System (NEPS) through these procedures. NEPS is also linked to the custom clearance system of Korea Customs Service, which enables to track actual exports and the time of exports. However, cumulative quantities for the heavy water and deuterium are managed individually by classification reviewers. The annual export plans are received in advance from major entities which deal with the materials for nuclear uses, and the cumulative quantities for each application are managed manually. The systematic management has not been required as there were a few cases of exporting small quantities. However, systematic management may be required in the future as overseas expansion attempts from various companies in the nuclear field has been increasing. In addition, further study is needed on the criteria and system for calculating the cumulative amount. The time of aggregate the cumulative amount should be clarified by considering the difference between the time of classification and actual export. It is required to devise an efficient way to follow up the actual export.