This case report describes the pathological features of pulmonary alveolar proteinosis(PAP) in mouse. Grossly, multiple irregular yellow-grey patches were observed on the lung surface of a C57BL/6 mouse. Histopathologically, the alveolar walls were thickened by type II cell hyperplasia and cellular infiltrates, and the bronchioles and alveolar lumens were filled with amorphous eosinophilic lipoproteinaceous material. This material was positive for Periodic acid-Schiff stain. Gomori methenamine silver staining was negative. Immunohistochemical staining showed that cells in the alveolar wall and lumen were positive for surfactant protein B, chitinase-like protein-3, and CD68. As a result, PAP was diagnosed. This is a rare case of spontaneous PAP in mice, and we report the histopathological characteristics along with the literature.

PURPOSES : This study aims to analyze the impact of demand risk on two public-private partnership (PPP) projects, namely BTO and BTO-a. The main aspects covered in this study are: i) identification of key risk issues considering the structure of PPP projects, and ii) game theory-oriented scenario building and simulation of demand risk allocation from participants’ perspectives. METHODS : Using the institutional analysis and development (hereafter IAD) framework, a hypothetical structure is formulated to examine the interactions of demand risk. It develops a series of demand risk allocation models for PPP projects (i.e., BTO and BTO-a). The risk structures from the IAD step are the demand risk allocation issues. Using game theory-oriented simulation, this study evaluates demand risk based on scenario building. RESULTS : First, this study highlights the imbalanced rate problems of returns between the BTO and BTO-a projects proposed by the market. This may lead to improvement measures geared towards problematic methods for determining the rate of return among domestic PPP projects. Second, compared with the BTO type, this study expects that the BTO-a type may exhibit more effectiveness, which can increase the probability of project success in both the public and private sectors. Third, judging from game-theory-oriented approaches, this study confirms the function of the BTO-a as a method to adjust moral hazard in the private sector. CONCLUSIONS : Government management standards for BTO-a projects were derived based on the simulation results. It is necessary to select an appropriate project method based on rationality by balancing the IRR for each project method. Legal regulations should be applied separately to each part of the government guarantee. In addition, this study emphasizes that the introduction of ex-post value-for-money (VFM) analysis is essential for the efficient management of government expenses.

Graphene-derived materials are an excellent electrode for electrochemical detection of heavy metals. In this study, a MnO2/ graphene supported on Ni foam electrode was prepared via ultrasonic impregnation and electrochemical deposition. The resulting electrode was used to detect Pb(II) in the aquatic environment. The graphene and MnO2 deposited on the Ni foam not only improved active surface area, but also promoted the electron transfer. The electrochemical performance towards Pb(II) was evaluated by cyclic voltammetry (CV) and square wave anodic stripping voltammetry (SWASV). The prepared electrode exhibited lower limit of detection (LOD, 0.2 μM (S/N = 3)) and good sensitivity (59.9 μAμM−1) for Pb(II) detection. Moreover, the prepared electrodes showed good stability and reproducibility. This excellent performance can be attributed to the strong adhesion force between graphene and MnO2, which provides compact structures for the enhancement of the mechanical stability. Thus, these combined results provide some technical considerations and scientific insights for the detection of heavy metal ions using composite electrodes.

In this study, in relation to the demolition of the building as a research reactor, in order to establish a basic design for preparation for relocation and installation of the TRIGA Mark-II, the present conditions such as actual measurements and structural safety were investigated, as well as technologies and cases related to the relocation and installation of cultural properties. Based on this, the basic design for the relocation and installation of cultural assets was established by reviewing the disassembly and transport design of the TRIGA Mark-II and the basic plan for the relocation site. Although the structural safety of the current self-weight of the structure is judged to be reasonable, when lifting the structure, it is necessary to consider a method of lifting the foundation by reinforcing the foundation so that the tensile force can be minimized in the structure. As for the technology to be applied before TRIGA Mark-II, the technology before non-transplacement was confirmed as the most reasonable method in terms of preserving the original form, securing safety, and securing economic feasibility. Among the non-replacement technologies, the methods that can be applied before reactor 1 can be largely classified into three types. The three methods to be reviewed can be largely classified into the traditional rail movement method, the movement method using transport equipment, and the crane movement method. Each required period was calculated from the basic design results, and the modular trailer method was judged to be the most efficient. From the basic design results, the required period for each stage according to the mobile construction method was calculated. Depending on the calculation result, the modular trailer method is judged to be the most efficient. However, the final construction method should be selected according to the detailed design results. Overall, the results obtained through this study suggest that it is possible to create a memorial hall without the previous installation of TRIGA Mark-II if the structure foundation is composed independently of the building foundation after conducting a detailed characteristic investigation on the foundation of the TRIGA Mark-II structure.

Heat-generating nuclides such as Cs-137 and Sr-90 should be separated from spent nuclear fuel to reduce the short-term thermal load on the repository facility. In particular, Sr-90 must be separated because its decay process generates high temperatures. Recently, the Korea Atomic Energy Research Institute (KEARI) has been developing a waste burden minimization technology to reduce the environmental burden resulting from the disposal of spent nuclear fuel and maximize the utilization of the disposal facility. The technology incorporates a nuclide management process that maximizes disposal efficiency by selectively separating and accumulating key nuclides from spent nuclear fuel, such as Cs, Sr, I, TRU/RE, and Tc/Se. Sr nuclides dissolve in the chloride phase during the chlorination process of spent nuclear fuel and are recovered as carbonate or oxide through reactive distillation or reactive crystallization. Due to their chemical similarity, Ba nuclides are recovered along with Sr nuclides during this process. In this study, we prepared a ceramic waste form for group II nuclides, Ba(x)Sr(1-x)TiO3 (x=0, 0.25, 0.5, 0.75, 1), using the solid-state reaction method, taking into account the different ratios of Sr/Ba nuclides produced during the nuclide management process. Regardless of the Sr/Ba ratio, the established waste form fabrication process was able to produce a stable waste form. Physicochemical properties, including leaching and thermal properties, were evaluated to determine the stability of group II waste forms. In addition, the radiological properties of waste forms of Ba(x)Sr(1-x)TiO3 with varying Sr/Ba ratios were evaluated. These results provided fundamental data for the long-term storage and management of waste forms containing group II nuclides.

The US NRC developed a program called NRCDose3 to evaluates the environmental impact of radiation around nuclear facilities. The NRCDose3 code is a software suite that integrates the functionality of three individual LADTAP II, GASPAR II, and XOQDOQ Fortran codes that were developed by the NRC in the 1980’s and have been in use by the nuclear industry and the NRC staff for assessments of liquid effluent and gaseous effluent, and meteorological transport and dispersion, respectively. Through the integrated program, it is possible to conduct safety assessment and environmental impact assessment from liquid and gaseous effluent when operating permits are granted. In addition to a more user-friendly graphic user interface (GUI) for inputting data, significant changes have been made to the data management and operation to support expanded capabilities. The basic calculation methods of the LADTAP II, GASPAR II, and XOQDOQ have not been changed with this update to the NRCDose3 code. Several features have been added. The previous program used only ICRP-2 dose conversion factor, but the new program can additionally use dose conversion factor of ICRP-30 and ICRP-72. In the previous program, 4 age groups (infant, child, teen, and adult) were evaluated during dose evaluation, but when ICRP-72 was selected, 6 age groups (infant, 1-year, 5-year, 10-year, 15-year, and adult) could be evaluated. In addition, when selecting ICRP-72, many user-modifiable parameters such as food intake and exposure time were added. It will be referred to E-DOSE60, a program currently under development.

The ability to both assay the presence of, and to selectively remove ions in a solution is an important tool for waste water treatment in many industrial sectors, especially the nuclear industry. Nuclear waste streams contain high concentrations of heavy metals ions and radionuclides, which are extremely toxic and harmful to the environment, wildlife and humans. For the UK nuclear industry alone, it is estimated that there will be 4.9 million metric tonnes of radioactive waste by 2125, which contains a significant number of toxic radionuclides and heavy metals. This is exacerbated further by increased international growth of nuclear new build and decommissioning. Efforts to remove radionuclides have been focused on the development and optimisation of current separation and sequestering techniques as well as new technologies. Due to the large volumes of waste the techniques must be economical, simple to use and highly efficient in application. Magnetic nanoparticles (MNPs) offer a powerful enhancement of normal ion exchange materials in that they can be navigated to specific places using external magnetic fields and hence can be used to investigate challenges such as, pipework in preparation of decommissioning projects. They also have the potential to be fine-tuned to extract a variety of other radionuclides and toxic heavy metals. It has been demonstrated that with the right functional groups these particles become very strongly selective to radionuclides, such as Uranium. However, this new technology also has the potential to effectively aid nuclear waste remediation at a low cost for the separation of both radionuclides and heavy metals. In this work, we investigate the origin of the selectivity of superparamagnetic iron oxide nanoparticles (SPIONs) to Uranium by making systematic changes to the existing surface chemistry and determining how these changes influence the selectivity. Identifying the mechanism by which selected common nuclear related metals, such as Na(I), K(I), Cs(I), Ca(II), Cu(II), Co(II), Ni(II), Cd(II), Mg(II), Sr(II), Pb(II), Al(III), Mn(II), Eu(III) and Fe(III), are sorbed will allow for specific NP-target (nanoparticle) ion interactions to be revealed. Ultimately this understanding will provide guidance in the design of new targeted NP-ligand constructs for other environmental systems.

IAEA safety standards document and international programs (such as BIOMASS) related to the assessment of the biosphere around High Level Radioactive Waste (including Spent Nuclear Fuel) repositories require the assessment of the biosphere to use the assumption that the current natural environment and human society will be maintained, and at the same time, the evolution of the distant future changes also need to be taken into account. In Korea, which has not designated candidate disposal sites, it is necessary to investigate and predict the current state and future changes of the natural environment throughout Korea and apply it practically to Biosphere assessment (for BDCF derivation) for candidate disposal sites suitability assessment and Safety Case (for performance assessment) preparation for design, construction, operation, and post-closure management. To this end, the natural environment in the fields of Topography, Geology, Soil, Ecology, Weather and Climate, Animals and Plants, Hydrology, Ocean, Land-use, etc. and human society in the fields of Population Distribution, Spatial-Planning, Urban Form, Industrial-Structure, Lifestyle etc. are being investigated in the context of current status, past change records, and future change potential in the Korean Peninsula. This paper summarizes those investigations to date. This study referred Biomass-6 [IAEA] and National Atlas I (2019)/II (2020)/III (2021) [National Geographic Information Institute of the Korea Ministry of Land, Infrastructure and Transport].

The safe disposal of high-level radioactive waste is a critical concern in many countries, especially in the context of the increasing use of nuclear power to overcome climate change. To provide a comprehensive understanding of the behavior of the radionuclides in the crystalline natural barrier, sorption of the artificially synthesized high-level radioactive waste (HLW) leachate was conducted. Granite (-1,000 m from ground level) and biotite gneiss (-100 m from ground level) rock cores were collected from Gyeongju and Gwacheon, respectively. The rock cores were milled with a jaw crusher and steel disk mill and then sieved. The crushed rocks with a diameter of 0.6 – 1.0 mm were selected, washed three times with deionized water, and then dried. To synthesize the simulated HLW leachate, representative elements (U(VI), Se(IV), Mo(VI), and Ni(II)) were added to natural groundwater collected from Gyeongju. The kinetic sorption experiment was performed in a polypropylene bottle with a solid-to-liquid ratio of 100 g/L in the orbital shaking incubator (200 rotations per min, 25.0°C). After the sorption, the supernatants were filtered by a 0.2-μm polytetrafluoroethylene syringe filter and subsequently analyzed by inductively coupled plasma-mass spectrometry (ICP-MS). Through the kinetic change of aqueous concentration, the contact time has been determined to be 7 days. Ni(II) showed the highest distribution coefficients (Kd = 0.81 L/m2 for granite and 8 – 16 L/m2 for biotite gneiss), followed by U(VI) (Kd = 0.03 – 0.04 L/m2 for granite and 0.04 – 0.05 L/m2 for biotite gneiss). Highly mobile nuclides such as Se(IV) (Kd = 0.02 L/m2 for granite and 0.03 L/m2 for biotite gneiss) and Mo(VI) (Kd = 0.01 – 0.02 L/m2 for granite and 0.01 L/m2 for biotite gneiss) showed the lowest distribution coefficient. Our study provides insights into the migration-retention behaviors of the HLW leachate with granite and biotite gneiss in geological systems and verifies the sorption parameters, e.g., distribution coefficients, experimentally produced by other groups to ensure the safe disposal of HLW.

When a loss of coolant accident which causes a partial or a full drainage in the SFP would happen, Zircaloy-4 spent fuel cladding begin to react with high temperature air, and the heat generates by exothermic reaction between Zircaloy-4 cladding and surrounding air. Due to the heat, the ignition may occur in the surface of Zircaloy-4 cladding. If the Zr-fire phenomenon occurs during the accident in a SFP, the spent fuel cladding and pellets would be severely fragmented and powdered and it may bring about a massive release of radioactive source terms. Therefore, it is crucial to prevent the zirconium fire phenomenon for the spent fuel pool safety. However, a main cause to trigger the zirconium fire was not identified. In order to identify a possible mechanism of the Zr-fire phenomenon, OECD-NEA SFP Project I, II was initiated. In this paper, we reviewed the Zr-fire phenomenon which may occur in the spent fuel pool for complete loss of coolant accident scenario. The Spent Fuel Pool Project (hereinafter SFP project) is the experimental program to investigate the phenomena of spent fuel pool complete loss of coolant accident using a 17×17 PWR fuel assembly. In this section, the zirconium fire phenomenon which was observed from the SFP project is briefly investigated. This paper presented the fuel assembly temperature (i.e. zirconium alloy cladding temperature) and oxygen concentration profile of the SFP project phase-1 ignition test. At around 12.7 hour, the temperature abruptly increased and the oxygen concentration also dramatically decreased. This abrupt temperature escalation is the zirconium fire phenomenon. In order to investigate the mechanism of this zirconium fire phenomenon, behaviors of both temperature and oxygen concentration were fully compared. This paper reviewed the results of OECD-NEA SFP project experiment and then a mechanism of Zr-fire phenomenon was dscussed. It seems that the Zr-fire phenomenon might be a consequence of thermal mismatch between heat generation and dissipation. A large amount of heat might be generated by the air oxidation of Zircaloy-4 spent cladding immediately after the kinetic transition which is a breakaway phenomenon. This paper discussed the relationship between the breakaway phenomenon and the Zr-fire phenomenon in case of air oxidation of Zircaloy-4 spent cladding. This paper presents preliminary findings on the Zr-fire phenomenon from the open experiment data of the prototypic spent fuel severe accident scenario. These findings would enhance the understanding of Zircaloy-4 spent cladding air oxidation and severe accident scenario progression in a SFP.

According to the “Law on protection and response measures for nuclear facilities and radiation”, Nuclear Power Plant (NPP) licensees should conduct periodic exercises based on hypothetical cyberattack scenarios, and there is a need to select significant and probable ones in a systematic manner. Since cyber-attacks are carried out intentionally, it is difficult to statistically specify the sequences, and it is not easy to systematically establish exercise scenarios because existing engineering safety facilities can be forcibly disabled. To deal with the above situation, this paper suggests a procedure using the Probabilistic Safety Assessment (PSA) model to develop a cybersecurity exercise scenario. The process for creating cyber security exercise scenarios consists of (i) selecting cyber-attack-causing initiating events, (ii) identifying digital systems, (iii) assigning cyber-attack vectors to a digital system, (iv) determining and adding type for operator’s response, (v) modifying a baseline PSA model, and (vi) extracting top-ranked minimal cut sets, and (vii) selecting a representative scenario. This procedure is described in detail through a case study, an expected cyber-attack scenario General Transient-Anticipated Transient Without Scram (GTRN-ATWS). It refers to an accident scenario for ATWS induced by GTRN. Since ATWS is targeted for cyber training in some NPPs, and GTRN is one of the most common accidents occurring in NPPs, GTRN-ATWS was chosen as an example. As for the cyber-attack vector, portable media and mobile devices were selected as examples based on expert judgment. In this paper, only brief examples of GTRN-ATWS events have been presented, but future studies will be conducted on an analysis of all initiating events in which cyber-attacks can occur.

Background: Despite the fact that aquatic exercise is one of the most popular alternative treatment methods for children with cerebral palsy (CP), there are few research regarding its effectiveness. Objects: The purpose of this study was to examine the effects of aquatic exercise on upper extremity function and postural control during reaching in children with CP. Methods: Ten participants (eight males and two females; 4–10 years; Gross Motor Function Classification System levels II–IV) with spastic diplegia were recruited to this study. The aquatic exercise program consisted of four modified movements that were selected from the Halliwick 10-point program to enhance upper extremity and trunk movements. The participants attended treatment two times a week for 6 weeks, averaging 35 minutes each session. The Box and Block Test (BBT), transferring pennies in the Bruininks-Oseretsky Test (BOT), and pediatric reaching test (PRT) scores were used as clinical measures. Three-dimensional motion analysis system was used to collect and analyze kinematic data. Differences in BBT and BOT values among pre-treatment, post-treatment, and retention (after 3 weeks) were analyzed using a Friedman test. In addition, the PRT scores and variables (movement time, hand velocity, straightness ratio, and number of movement units) from the three-dimensional motion analysis were tested using a Wilcoxon signed-rank test. The significance level was established at p < 0.05. When the results appeared to be statistically significant, a post-hoc test for multiple comparisons was performed with the Wilcoxon signed-rank test. Results: All clinical measures, which included BBT, transferring pennies of BOT, and PRT, were significantly increased between pre-intervention and post-intervention scores and between pre-intervention and retention scores after treatment (p = 0.001). Three-dimensional motion analysis mostly were significantly improved after treatment (p = 0.001). Conclusion: Aquatic exercise may help to improve body function, activity, and participation in children with varying types of physical disabilities.

Chu Bamboo Book in Anhui University (vol.2) published in August 2022 (hereinafter referred to as “Anda II” or “An Da Jian”) is the latest collation of the bamboo slips of the Warring States Period in Anhui University by the Research Center for the Development and Application of Chinese Characters of Anhui University, which includes two parts: Zhongni Yue and Cao Mo Chen. Through a preliminary comparison and analysis of the writing phenomena corresponding to the purposes of such articles as Cao Mo Zhi Chen and Zhong Ni Yue in An Da Jian, Cao Mo Zhi Zhen in Shang Bo Jian (Chu Bamboo Book in Shanghai Museum), the author found some special phenomena related to He Wen. For example, although the writing of Cao Mo by An Da Jian seems to have various ways of writing, this way of writing may contain a profound interpretation of the meaning of the text by the scribes at that time. This writing phenomenon is of great value for in-depth consideration: 1.When the two words “Shang Xia (上下)” and “Zhi Suo (之所)” can be taken apart or not, the words that cannot be taken apart are often written as He Wen, and the words that can be taken apart are often not written as He Wen; 2.When the original two words “Jun Zi (君子)” and “Xiao Ren (小人)” cannot be separated, the written form of He Wen may represent a special emphasis. At the same time, through a comparative study of the use of Chinese characters in Cao Mo and Zhongni Yue, we may speculate that although Cao Mo and Zhongni Yue may not belong to the same style of writing, at least in the arrangement of He Wen, There may be some similar writing logic in these two chapters - the speculation about this writing logic may be used in the analysis of other difficult texts in Zhongni Yue.

본 연구는 식물군집구조 분석을 통해 천관산도립공원의 식생 특성을 파악하여 천관산도립공원의 지속적인 관리와 보호에 필요한 자료를 구축하고자 진행되었다. 천관산도립공원의 63개 조사구에 대한 식물군집구조 분석 결과, TWINSPAN과 DCA분석을 통해 삼나무군락(Ⅰ), 편백-소나무군락(Ⅱ), 리기다소나무-소나무군락(Ⅲ), 침활혼효군락(Ⅳ), 소나무군락(Ⅴ), 낙엽성참나무류군락(Ⅵ), 신갈나무-소나무군락(Ⅶ), 곰솔군락(Ⅷ)의 총 8개 군락으로 나뉘었다. 이는 조림수종인 삼나무와 편백, 리기다소나무가 우점하는 인공림 군락(Ⅰ, Ⅱ, Ⅲ)과 자생수종이 우점하는 자연림 군락(Ⅳ, Ⅴ, Ⅵ, Ⅶ, Ⅷ)으로 나눌 수 있다. 천관산도립공원은 자연생태계나 경관을 대표할 만한 도립공원 지역임에도 다른 도립공원에 비해 인공림의 출현비율이 높게 나타나고 있다. 인공림 군락은 조림수종이 인위적으로 식재된 형태로 대부분 현재의 상태를 유지할 것으로 판단되지만, 주변 자연림을 통해 유입된 난온대 수종인 후박나무와 참식나무 등과 낙엽활엽수 등의 자생종이 하층에 출현하고 있어 관리를 통해 기후적 특성에 맞는 자연림으로의 천이 유도가 가능할 것으로 판단되며, 지속적인 관리를 위한 모니터링 또한 필요할 것으로 판단된다. 자연림 군락은 대부분 낙엽성참나무류와 소나무가 경쟁하고 있는 상태로 한국 난온대 지역의 식생천이계열상 천이 초기단계로 보여지며, 천이계열상 침엽수 다음으로 출현하는 졸참나무나 신갈나무로의 천이가 진행 중인 것으로 판단된다. 그러나 난온대 지역의 천이 중간단계에서 출현하는 후박나무, 참식나무 등이 출현을 시작하고 있으며, 기후 특성을 고려하면 장흥군은 난온대 지역에 속해있어 최종적으로 상록활엽수가 우점하는 난온대림으로의 천이도 기대할 수 있을 것으로 예상된다. 본 연구를 통해 식생에 대한 연구가 부족한 천관산도립공원의 식생자료를 구축하였다. 하지만 천관산도립공원의 식생연구는 아직 부족한 실정으로 산림식생자료 구축과 식생변화 관찰 등을 위한 추가적인 연구가 지속해서 이루어져야 할 것으로 사료된다.

금당천의 어류군집 특징과 멸종위기종 한강납줄개(Rhodeus pseudosericeus)의 서식양상을 파악하기 위해 2021년 3월부터 10월까지 조사를 실시하였다. 조사기간 동안 7개 지점에서 5과 25종 1,698개체의 어류가 채집되었다. 우점종은 피라미(Zacco platypus, 상대풍부도 46.5%), 아우점종은 긴몰개(Squalidus gracilis majimae, 16.7%) 였으며, 그 외 버들치 (Rhynchocypris oxycephalus, 12.0%), 참갈겨니(Z. koreanus, 5.7%), 돌고기(Pungtungia herzi, 3.2%), 한강납줄개 (2.0%), 떡납줄갱이(R. notatus, 1.9%), 납지리(Acheilognathus rhombeus, 1.8%) 등의 순으로 우세하였다. 출현종 중 한국고유종은 돌마자(Microphysogobio yaluensis), 한강납줄개, 각시붕어(R. uyekii), 참중고기(Sarcocheilichthys variegatus wakiyae), 긴몰개, 참갈겨니, 점줄종개(Cobitis nalbanti), 참종개(Iksookimia koreensis), 얼록동사리 (Odontobutis interrupta) 9종(고유화율 36.0%)이었고, 외래종은 생태계교란 생물로 지정된 배스(Micropterus salmoides) 1종이 하류부에서 채집되었다. 법정보호종으로 환경부지정 멸종위기 야생생물 II급인 한강납줄개의 서식양상을 조사한 결과, 서식범위는 금당천 중류부(RP-1~RP-4) 약 6~7km 구간이며, 주로 수심 0.3~1.0m의 유속이 느리고 수생식물이 많은 소의 수변부에 서식하고 있었다. 어류군집 분석 결과, 전체적으로 우점도와 균등도가 낮고 다양도와 풍부도는 높게 나타났으며, 군집구조는 크게 상류와 중하류로 구분되었다. 하천 건강성은 좋음(3지점)과 보통(3지점), 나쁨(1지점)으로 평가되었고, 수질은 상류와 하류 모두 좋음으로 평가되었다. 선행연구와 비교한 결과, 종수는 큰 차이를 보이지 않았으며, 과거에는 출현하였으나 본 조사에서 출현하지 않은 종은 13종이었고, 반면 본 조사에서 처음으로 출현한 종은 6종이었다. 교란요인은 하천공사와 많은 보, 외래어종 배스의 서식 등이 확인되었다. 금당천은 멸종위기종 한강납줄개를 비롯한 납자루아과(Acheilognathinae) 어류가 많이 서식하여 보존가치가 높은 지역이기 때문에, 지속적인 관심과 체계적인 보존방안이 요구된다.

최근 기후변화로 가뭄, 홍수 등 재해의 빈도와 강도가 높아지고 있다. 이러한 재해의 피해를 줄이기 위해서는 시공간적 현황 파악을 통한 대비가 필요하다. 본 연구에서는 가뭄의 피해를 최소화하고자 지역별 밭작물의 필요수량과 공급량을 고려하여 밭가뭄 지역 등급화 실시하였고, 월별 비교를 통해 가뭄 취약 시기를 파악하였다. 전국 148개 지역 중 안전지역(Ⅰ), 안전지역(Ⅱ), 우려지역, 상습지역으로 구분한 25개 지역을 선정하였으며, 이 지역의 월별 필요수량 대비 공급량 분석을 하였다. 필요수량 산정의 재배작물은 콩으로 선정하였으며, 공급량은 공공관정, 민간관정, 상수도 자료를 분석하였다. 필요수량 대비 공급량이 봄철은 안전지역(Ⅰ), 안전지역(Ⅱ), 우려지역, 상습지역에서 각 1,281.5%, 667.6%, 729.5%, 316.3%, 가을철에는 각 436.0%, 212.8%, 213.9%, 105.3%로 공급이 충분할 것으로 분석되었으나 여름철에는 각 82.4%, 40.6%, 42.6%, 20.0%로 용수공급 이 부족한 것으로 분석되었다. 콩의 재배 기간인 5~9월에 관정(공공+민간)으로의 공급량은 대부분 지역에서 부족한 것으로 분석되었다. 이러한 분석을 통해 용수 부족이 발생하는 재배기간 동안 용수확보 방안이 필요하다.

The emergence of micropollutants in natural water sources due to the overuse of anthropogenic chemicals in industry and households has threatened the production of clean and safe tap water in drinking water treatment plants. Conventional physicochemical processes such as coagulation/flocculation followed by sand filtration are not effective for the control of micropollutants, whereas chemical oxidation processes (applying chlorine, permanganate, ozone, etc.) are known to be promising alternatives. Determining the optimum oxidant dose is important issue related to the production of disinfection by-products as well as unnecessary operating cost, and is made possible by simulations of target-micropollutant abatement based on kinetic model equation consisting of second-order rate constant (between the oxidant and the target) and oxidant exposure. However, the difficulty in determining oxidant exposure as a function of complex water quality parameters limits the field application of kinetic model equation. With respect to representative oxidants used in drinking water treatment plants, this article reviews two main approaches for determining oxidant exposure: i) direct measurement in situ and ii) prediction by empirical models based on key water quality parameters. In addition, we discussed research requirements to improve the predictive accuracy of the empirical models for oxidant exposure and to develop a rational algorithm to determine optimal oxidant dose by considering the priority of the target pollutants to be treated.

남강 유역에 위치한 진주 대평리, 평거동, 초장동 등 대규모 유적의 분묘 경관을 통해 취락 안팎의 구조와 상호작용에 대해 살펴보았다. 먼저 분묘의 가시 경관과 취락 영역 간의 관계를 추론하였다. 이 는 분묘에서 바라본 시각적 체험 경관은 사회구성원들이 일상에서 인식하고 있었던 영역이며, 취락의 정치적·경제적·이념적 영역과 직접 관련이 있다는 것을 전제로 하였다. 가시권분석 결과, 대규모 취락의 가시권은 대체로 반경 5km에 해당하며, 서로 가시권을 공유하지 않는 배타적 경관을 이루고 있었다. 이를 통해 국지적 단위공동체는 각기 독립적인 영역을 유지하며 상호작용하는 등질적인 구조 를 형성하고 있었다고 생각된다. 취락 내부의 경관은 분묘군을 중심으로 차별적이고 역동적인 양상을 보이고 있었다. 이는 분묘의 군집 유형을 통해 살펴볼 수 있다. Ⅰ유형은 대형 묘역지석묘 주변에 분묘군이 조영된 것으로, 선대 권력을 상징하는 지석묘 주변에 분묘를 환상이나 열상으로 배치하여 전통적 사회 질서를 유지하고자 하였던 경관 조성 전략이 작용한 결과로 이해된다. 특히 이 분묘군은 취락 안팎에서 상시 체험 가능한 현저한 곳에 축조되어 있어 구성원들의 시선과 움직임을 통제할 수 있는 지배적 경관을 구성하고 있 었다. Ⅱ-1유형은 생활 공간에 분묘를 열상으로 배치하여 이를 매개로 공동체성을 강화하려는 의도 가 반영된 것으로 보인다. Ⅱ-2유형은 농경지 경계면에 분묘를 축조하여 마을의 안녕과 풍요를 기원 하는 수단으로 활용되었다. Ⅲ유형은 분묘들의 장축이 상호 교차하는 군집으로, 무덤의 공간 순서 변 경을 통해 사회 질서의 변화를 추구하였던 행위자의 표현으로 보인다. 이와 같은 군집 유형은 모든 대규모 취락에서 일률적으로 확인되지 않았다. 취락 내부의 공간적 맥 락을 통해 볼 때, 분묘는 단순히 매장시설이 아니라, 유력자들이 권력 관계를 합리화하거나 재조정하 고 구조화하는 사회적 행위 공간이었다. 이러한 공간 조성은 각 취락의 물리적 환경과 구성원들의 경 관 해석에 영향을 받았으며, 분묘 축조를 주도하였던 주체들의 공간 구현 전략에 따라 각기 다른 형태 로 나타났다. 남강 유역 대규모 취락의 분묘는 각 사회-공간의 상호작용에 의해 형성된 차별적 경관 을 구성하고 있었으며, 권력과 공동체성을 대표하는 의미화된 장소로서 역할을 하고 있었다.