This note summarizes the application of zooplankton indices for water quality management and estimation based on main research topics of articles focusing on wetland ecosystems, topics that are remained poorly investigated in S. Korea. The aquatic ecosystem-based consists of indices that respond to different target environmental factors, including environmental disturbance. Among the major indicator species and biota, we reviewed that management strategy for the wetland environment has to be focused more on small-sizes, in terms of zooplankton ecology and indices. The ecology of zooplankton communities in freshwater ecosystem has been the focus of an increasing number of studies since 2019, and considerable progress has been made in understanding the major mechanisms involved in regulating their abundance, diversity and spatio-temporal patterns. Even though studies on the freshwater ecosystem in Korea have a long history, a few of studies on zooplankton biota were conducted at wetlands. We suggested the candidate zooplankton indices proposed by the U.S. EPA and EU to suit Korean conditions. In the step of selecting metrics, the best available metrics are species-related variables, such as composition and abundance, as well as richness and diversity. Overall, in spite of several limitations, the development of a plankton-based multivariate assessment method in Korea wetlands is possible using mostly field research data. Later, it could be improved based on qualitative metrics on zooplankton, and with the emergence of further survey data. The present information can be used as basic information for researchers who are dealing with aquatic environments and its interaction with organisms.

북한 산림황폐화의 원인 중 하나는 1990년대 에너지 위기 이후로 목재에너지를 지나치게 많이 사용한 것으로 지목되고 있다. 그럼에도 불구하고 여전히 땔감문제 해결이 요구되며, 경작지 부족으로 인하여 강하천과 저수지 등 주변 습기가 높은 비경작지에서도 생산성과 발열량이 높은 수종을 식재하여 땔감문제를 해결하려는 노력들이 시도되고 있다. 본 총설에서는 북한의 연료림 조성에 적용 가능한 수종을 대상으로 남북한 기술 현황 검토를 통해 향후 남북산림협력 및 기술 교류 등을 위한 기초자료를 제공하는 것을 목적으로 한다. 북한에서 땔나무림으로 조성되었거나 활용되고 있는 수종으로는 아까시나무, 포플러, 버드나무 및 오리나무 등이 있다. 아까시나무(북한명: 아카시아나무)는 연료림 조성을 위한 주요 수종으로 조림 및 품종 육성 등이 지속적으로 연구되고 있는 것으로 조사되었다. 최근 언론보도 등 문헌을 살펴보면 산림 내 연료림(땔나무림) 조성만으로는 부족한 실정으로 강하천과 저수지 등 비경작지에 식재 가능한 포플러와 버드나무 등 속성수의 육성 품종(상원뽀뿌라나무, 참대버드나무 등)을 활용하고 있는 것으로 나타났다. 남한에서도 포플러류와 버드나무류는 탄소흡수원 확충, 바이오매스 생산 등을 위한 형질개량 및 품종 육성 연구가 수행된 바 있다. 포플러류 중 분포범위가 넓은 사시나무는 근맹아에 의한 번식방법을 이용하여 북한내 많은 지역에서 연료림으로 활용가능할 것이다. 또한 버드나무류의 바이오매스 증진을 위해 종간교잡을 시도한 사례 등 유전개량 및 품종육성을 통한 연료림 조성 기술협력이 가능할 것이다. 속성수를 주거지 인근 비경작지 식재를 위하여 북한에서 원림조성에 활용되고 있는 포플러류와 버드나무류를 활용할 수 있으며, 수확 갱신을 통한 이용방안은 추가적으로 모색되어야 할 것이다.

Molten Salt Reactor (MSR) is one of the 4th generation nuclear power systems which is its verified technology in physically and chemically. Among the various salts used for MSR system, the eutectic composition of NaCl-MgCl2 system maintains the liquid state at around 450°C, in the same time, it has high solubility for nuclear fuel chlorides. This characteristic has high advantage for lowering the operating temperature for the MSR, which could reduce the problem of hightemperature corrosion by salt for structural materials significantly. In particular, since MgCl2 has the similar standard reduction potential with nuclear fuel, is used as a surrogate for, many basic researches have been conducted for verifying characteristic of MgCl2. It is well-known that main short-advantage of MgCl2 is hygroscopic properties. MgCl2 changes to MgCl2-xH2O state easily by absorbing moisture in air condition. The hydrated MgCl2 is producing MgOHCl by thermally decomposing at high temperature, the formed MgOHCl corrodes structural materials, even small amount of MgOHCl gives significant damage. Therefore, the purification of MgCl2 has been required for long-term operation of MSR using MgCl2 as a base salt. In this study, the purification of eutectic composition salt for NaCl-MgCl2 has been mainly performed by considering its thermodynamic properties and electrochemical characteristic, and the experimental results have been discussed.

According to IAEA GSR Part.6, Decommissioning is carried out on the basis of planning and evaluation to ensure safety, protection of workers, public, and environment. Then, the decommissioning project of nuclear facility includes a radiation protection plan that reflects the regulatory requirements and international recommendations of each country and the internal regulations of the licensee. The scope of the radiation protection plan covers all radiation activities related to the dismantling and disposal of contaminated facilities subject to decommissioning. Radiation protection applications in the United States, a country with previous experience in decommissioning nuclear facilities, include 10 CFR 20 for NRC management facilities and 10 CFR 835 for facilities under DOE. In this study, we analyzed two cases of decommissioning plans to which NRC regulations are applied. In 1992, Yankee Atomic Electric Company (YAEC), the licensee of Yankee Nuclear Power Station (YNPS), notified NRC of the permanent shutdown of YNPS and submitted decommissioning plan accordingly. This decommissioning plan consists of a total of 9 chapters, and section 3.2 describes the radiation protection of decommissioning workers. The contents of the radiation protection program consist of 16 subsections. Another case is the decommissioning work plan of U.S. Navy Surface Ship Support Barge (SSSB), which used in Virginia to support the refueling of the U.S. Navy’s reactor vessel. This document was developed based on the NUREG-1757 and was revised in 2021 after receiving NRC comment. SSSB’s project radiation protection plan is described in appendix 1, and the contents consist of a total of 28 sections except for reference. In Korea, decommissioning plan is developed in accordance with “Standard Format and Content of the Decommissioning Plan for Nuclear Facilities”. According to this regulation, the radiation protection plan for licensing documents submitted at the time of application for approval of decommissioning execution shall describe the organization and functions for implementing of plan, methods, cycles and procedures for performing radiation protection and radiological monitoring. Also, the safety review guidelines of regulatory body also require radiation protection plans and procedures to ensure ALARA activities during decommissioning. In the case of the final decommissioning plan of Kori-1, which is currently submitted to regulatory body for licensing review, the decommissioning radiation protection plan is divided into 8 sections. Although the classification criteria for the radiation protection plan categories described above facilities are different, it could be seen that the following 7 contents are included in common: (a) ALARA application and organization for implementation, (b) Management of radiation control area, (c) Process of radiation work, (d) Radiation and contamination control, (e) Personnel radiation exposure monitoring, (f) Radioactive material management, (g) Radiation protection training.

SMR, which has recently been in the spotlight, has several advantages. However, it poses additional challenges in the areas of new design, digitalization, security, safety and safeguards. Among them, security refers to measures to protect nuclear materials and facilities from unauthorized access, theft, or destruction. Safeguards refer to measures to prevent the spread of nuclear weapons. The relationship between security and safeguards is complex and constantly evolving. In general, security measures are designed to protect nuclear materials and facilities from physical attack, while safeguards are designed to track and monitor the movement of nuclear materials and prevent them from being used to create nuclear weapons. In some areas security and safeguards work in complementary ways, and in other areas they conflict. But ultimately, finding a balance is what is effective and efficient. In conclusion, although the security and safeguards of SMRs have different key objectives, they are closely related and must be implemented comprehensively and consistently to ensure the safety of nuclear facilities, the public, and the environment. In this paper, we investigate how the safety and safeguards of SMR are currently being researched and analyze what difficulties there are when assuming that they are operated as a single interface.

본 연구는 유럽 식민주의 영향으로 형성된 아프리카 교육체계를 분석하고, 사교육에 대한 수요 발생 과정을 분석하고 자 하였다. 우리나라는 공적개발원조(ODA)를 통해 아프리카에 대한 교육 지원을 한국의 개발경험 공유라는 기저를 근간 으로 확대해나가고 있다. 특히, COVID-19 펜데믹으로 인해 교육산업이 변화하고 에듀테크 산업이 성장하면서 교육에 대 한 지속적인 발전과 양질의 교육 욕구는 사교육과 매우 밀접한 관계를 갖고 확장하고 있다. 이러한 아프리카 대륙의 교 육변화 이해는 아프리카 교육지원과 교육산업 해외시장 진출을 위해 선행되어야 한다. 이에, 아프리카 대륙의 교육변화 를 체계적 문헌연구 방법으로 통해 분석하여 고찰하였다. 한국의 사교육은 입시제도에 대응하는 처방적 차원에서 발생한 것이지만, 아프리카 대륙의 사교육은 교육의 질 저하로 인한 보완적 차원에서 발생하였다. 아프리카 대륙의 교육체계는 교육의 보편성과 형평성을 추구하고 있으나, 교육의 수월성을 지향하는 사교육을 적극적으로 활용하여 전반적인 교육의 효율성과 양질의 교육 접근성 향상을 높일 필요가 있다.

본 연구의 목적은 오수견의 구전적 설화를 중심으로 돌비의 출토 및 현 오수면 원동공원과의 연계성을 통해 오수의 지명적 가치를 분석하는 것이 다. 아울러 오수면에 위치한 의견공원, 김개인 생가 등 풍수적인 물형가치 를 찾아 구전에 합당한 공간을 설정하고, 이 설정이 구전적 오수의견(義犬) 과 부합하는 지리적 형상을 이해하고자 하였다. 오수의견은 구전이나 나름 의 역사성을 갖추고 있는 문헌적 사료(史料)가 있으며 그와 관련하여 오늘 날까지도 이 지역주민들의 사랑을 받고 있는 공간이기도 하다. 그러므로 오수면의 의견스토리가 담긴 공간성은 반려견문화 세계화에 따라서 더욱 그 의미의 확장성을 보일 수 있다. 이러한 관점에서 오수면의 정체성과 지 명 그리고 전반적인 인문학적 연구가 더욱 필요할 것이다. 또한 의견의 구 전적 이야기와 합치하는 풍수적 의견물형(義犬物形)을 더하고 구전적 오수 견 이야기의 토대를 돌비출현과 연관 지어 스토리의 완성적 공간을 확장하 였다. 본 연구는 단순히 구전적 이야기로만 전해오던 인간과 반려견(의견) 과의 인격적 애정관계를 통해서 그들 간의 생명관을 고찰함과 동시에 오수 의견 이야기의 실제적 역사로서 그 가능성을 살펴보고자 하였다. 또한 오 수의견 이야기의 주 무대로 알려진 오수면의 지명적 정체성을 알아보고 그 의미를 바탕으로 오수의견과의 연결성 있는 스토리를 찾아보고자 하였다.

Since time immemorial company’s interaction with its customers plays a vital role in co-creation of values and shared lifestyle. Similarly, for Japanese department stores passing through the declining stage of the life cycle, strategy based on maintaining relationships is important for renovating their business models. This study examines the importance of “Retail Brand Community” for Japanese department stores, considering from the perspective of Brand community and Social Identity Theory.

After permanent shutdown, contamination existing in nuclear facilities must be removed according to decontamination and dismantling procedures to achieve the target end state. In Korea, Korea Research Reactor (KRR) Units 1, 2 are being decommissioned, and Kori Unit 1 is in the process of reviewing the final decommissioning plan for the start of decommissioning. In order to complete decommissioning of nuclear facilities, it is necessary to satisfy the dose criteria according to the residual radioactivity remaining in the site and buildings. In the United States, which has a lot of experience in decommissioning, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) is used as a procedure for measuring and analyzing residual radioactivity. In MARSSIM, survey units are classified according to the level of contamination, and the radiation survey procedure and effort can be determined according to the survey unit level. After the radiological analysis and statistical verification of the survey unit, it is decided whether to release the site. At this time, the geographical area to be used as the background level is called the reference area. Therefore, selection of an appropriate reference area is important for accurate residual radioactivity analysis and for the release of the site. In this study, reference area evaluation cases and domestic decommissioning procedures were analyzed to derive considerations for selecting an appropriate reference area. For example, Zion NPP in the US selected a place outside the boundary of the restricted area unaffected by nuclear power plant operation as a reference area by referring to the meteorological monitoring report. Among Korea’s decommissioning procedures, the appropriateness of the reference area can be confirmed through the final status report submitted upon completion of decommissioning. However, since the selection and application of the reference area needs to be reflected during decommissioning, relevant information must be updated through periodic communication between operator and regulatory agency. The results of this study will be used as considerations for selecting a reference area.

The U.S. Nuclear Regulatory Commission (NRC) states that every environmental report prepared for the licensing stage of a Pressurized Water Reactor shall contain a statement concerning risk during the transportation of fuel and radioactive wastes to and from the reactor. Thus, the licensee should ensure that the radiological effect in accidents, as well as normal conditions in transport, do not exceed certain criteria or be small if cannot be numerically quantified. These are specified in 10 CFR Part 51 and applied in NUREG-1555 Supplement 1 Revision 1, which deals with Environmental Standard Review Plan. Corresponding regulations in Korea would be the Nuclear Safety and Security Commission Notice No. 2020-7. In Appendix 2 of the Notice, guides on the radiological environmental report for production and utilization facilities, spent nuclear fuel interim storage facilities, and radioactive waste disposal facilities. In this guide, unlike the regulations in the U.S., there are no obligations for radiological dose assessment for workers and public during the transportation. Therefore, overall regulations and their legal basis related to risk assessment during transportation conducted for the environmental report in the U.S. were analyzed in this study. On top of that, through the comparison with regulations in Korea, differences between the two systems were figured out. Finally, this study aims to find the points in terms of assessing transport risk to be revised in the current regulatory system in Korea.

As the amount of on-site Spent Nuclear Fuel (SNF) in storage increases due to the continued operation of Nuclear Power Plants (NPPs) in Korea, the on-site wet storage pool is expected to become saturated. Therefore, a facility for safely storing the spent nuclear fuel is required so that there is no problem with operation of the NPP until permanent disposal of SNF. Prior to the construction of such a facility, the safety analysis of the interim storage facility and verification of the safety of the spent fuel storage system (e.g. cask, silo) to be used are required according to Article 63 of the Nuclear Safety Act. In this process, analysis of the Structures, Systems, and Components (SSCs) of the storage system is needed. Based on the analysis, it is necessary to efficiently classify SSCs that are important to safety in order to differentiate management that more thoroughly manages those important to safety. In Korea, according to the notice of the Nuclear Safety and Security Commission, the components performing essential safety functions for the safe storage of spent fuel storage system are to be classified as “important safety equipment”. 10 CFR Part 72, a federal regulation related to interim storage facilities in the United States, also requires the identification of SSCs that fall under “Important to Safety (ITS)”, which is like domestic case. In addition, it has been confirmed that there are cases in which detailed classification according to Reg Guide 7.10 and NUREG-CR/6407 is added in Safety Analysis Report. However, these existing classification methods are not only classified as a single grade except for the method according to the Reg guide, but all are classified according to a qualitative standard. Qualitative criteria may cause ambiguity in judgment, resulting in subjective judgment of the person who proceeds in the classification process. Therefore, in this study, a new classification method is proposed to solve the problem according to the qualitative classification method. Assessing the level of radiological harm to the general public due to the assumption of failure of SSC in the spent fuel storage system is used as a quantitative evaluation standard.

The purpose of this study is to examine how the Japanese word, ‘omakase’, is used in Korean newspaper articles and analyze its inflow and settlement in the sociolinguistic background. The word, ‘Omakase’, is frequently used in newspaper articles in the areas of culture, economy, international, and local. It is commonly used in the area of food and beverage, and in some cases, it extends to other areas, such as the economy. The cases of uses in the existing category are sushi omakase, sashimi omakase, and Japanese food omakase. The cases of extensive uses in the food and beverage category are Korean beef omakase, native chicken omakase, seafood omakase, homemade meal omakase, and lamb chops omakase. Examples of use in other categories or creating hybrid w ords include o makase e conomy, omakase n ail, imokase, and Haenyeo-kase. The use of omakase in newspaper articles has gradually increased since 2002, and it has been increasing dramatically since 2013. The reason of its extensive use is considered the influence of various social backgrounds, for instance, the opening of Japanese pop culture or the entryof Japanese franchises into Korea.

Two stage-corpora of the newspaper LianHe ZaoBao from 2005-2008 (6678,6564 characters) and from 2018-2020 (3308,2690 characters) were collected and were used for Chinese characters statistics by the Huayu Research Center at Jinan University. Chinese character Species used in the two stage-corpora are 7004 and 6166 respectively. Chinese characters beyond the General Standard Chinese Character List in the mainland are 952 and 621 respectively, and the proportions of off-list characters are 13.59% and 10.07% respectively. The proportion of non-universal standardized Chinese characters decreased by 3.52 percentage points, indicating that Chinese characters used in the rear stage of LianHe ZaoBao are more consistent with those in mainland China. The Statistics, recording and sorting of the Chinese characters used in LianHe ZaoBao will help us understand the current Chinese characters ecology in Singapore and understand the commonalities and differences of Chinese characters between China mainland and Singapore. Based on the survey, we can explore the feasibility, methods and scope of the Chinese characters differences between Singapore and the mainland, as well as the strategies of compiling global Chinese dictionaries and further thinking about cross-border Chinese characters coordination.

매년 우리나라 연안해역에서 항해 중인 소형선박 및 소형어선과 연안에 어 로작업을 위해 설치된 시설물과의 접촉 사고가 빈번하게 발생한다. 이러한 사 고들은 주로 연안해역에 설치된 양식장, 정치망, 자망 등으로 인해 발생하며,선박 사고의 일반적인 원인으로는 항해 중인 선박에서 선원의 상무인 경계 소 홀, 침로 유지 및 선위 확인의 미충실, 항해 일반원칙과 국제해상충돌방지규칙 의 미준수 등 여러 가지가 될 수 있다. 본 논문에서는 어구손상사고와 관련된 사고의 원인을 검토하기 위해 해양안전심판원 재결서를 통해 분석하였으며, 그 결과 사고의 원인으로 경계 소홀, 설치된 어구와 적절한 거리 미확보, 항해 계 획 수립 미비 등이 사고의 원인으로 작용한 것을 알 수 있었다. 이러한 인적요 인으로 발생하는 사고를 줄이기 위해서는 선원의 꾸준한 안전교육이나 선박 안 전관리체제의 시스템 변경과 같은 오랜 시간과 많은 비용이 필요하다. 본 논문 에서는 어구를 조금 더 빨리 직관적으로 발견하여 인적요소를 제외한 다른 사 고요인을 제거하는 방법으로 사고 발생을 줄일 수 있는 방안을「수산업법」, 「어업면허의 관리 등에 관한 규칙」,「양식장ㆍ어장 표지시설의 설치 기준」, 「양식산업발전법」 등에서 문제점을 파악하고 개선하여 어구손상사고를 줄일 수 있는 방법을 모색해보고자 한다.

It has been discovered that the isosaccharinic acid (ISA) formed in a cellulose degradation leachate were capable of forming soluble complexes with thorium, uranium (IV) and plutonium. Since 1993, the ISA has received particular attention in the literature due to its ability to complex a range of radionuclides, potentially affecting the migration of radionuclides. ISA is formed as a result of interactions between cellulosic materials within the waste inventory and the alkalinity resulting from the use of cementitious materials in the construction of the repository. In an alkaline cementitious environment, cellulose degrades mainly via a peeling-off reaction. The main degradation product is ISA, a polyhydroxy type of ligand forming stable complexes with tri- and tetravalent radionuclides. ISA can have an adverse effect on the sorption of radionuclides to an extent which depends on its concentration in the cement pore water and potentially enhance their mobility. The concentration of ISA is governed by several factors such as cellulose loading, cement porosity, extent of cellulose degradation, etc. The sorption of ISA on cement, however, is the process which governs the concentration of ISA in the pore water. According to the experimental result from a literature, the ISA concentration in facilities with a cellulose loading of 5% is calculated to be of the order of 10−4 M. At this level, the effect of cellulose degradation products on radionuclide sorption is negligibly small. Recently in Korea, cellulous limits as waste acceptance criteria is studying and planning to prepare the detailed requirement for near surface radioactive waste disposal facilities. It is desirable to suggest consideration on cellulose disposal limits around the time that the regulatory body and concern organizations establish the cellulose disposal limits as follows. Firstly, identify the cellulose effect on the sorption of the nuclides as cementitious disposal environments such as affected nuclides, threshold value and contribution to radiological risks under domestic disposal environment. Secondly, make sure and consider the difference between lab-scale experimental conditions and probability occurring in real disposal conditions such as probability for generation and persistence of pH in cellulosic material disposal conditions and cellulosic material disposal methods. Finally, consider characterization of cellulosic material such as polymerization, contents of cellulose in law material and time of degradation process. As a result, desirable cellulose limits are to set up for both safety and economic aspect.

This paper intends to present considerations on the question of what is the “load standard” or “design load” for integrity evaluation under normal transportation conditions and what type of design load is good for users. This suggests a direction for subsequent research on producing design loads that transport business companies can utilize without difficulty. Several studies have been conducted to evaluate the integrity of spent nuclear fuel during normal transportation. A representative study recently conducted is the Multi-modal Transportation Test (MMTT) conducted using a commercial spent nuclear fuel cask by US DOE in 2017. In Korea, additional transport tests were planned to acquire sufficient test data under the conditions of road and sea transport considering the Korean situation. As a result, road transport tests were carried out in 2020 and sea transport tests were carried out in 2021. In the road transport test, a driving test that simulates various road conditions and a test that cycled a 4.5 km road eight times were performed. In most cases, the maximum acceleration of less than 1 g occurred, and the maximum strain was less than 48 με. For the sea transport test, the magnitude of both the maximum acceleration and the maximum strain were lower than those in the road transport test. We concluded tentatively that the integrity of spent fuel under normal conditions of transport was satisfactory with a large margin. However, when the storage business is realized and the transport of spent fuel becomes visible, the storage and transport business companies will have to prove the maintenance of the integrity of the spent fuel under normal transport conditions at the request of the regulatory agency. The transport business companies can transport the spent nuclear fuel by using different types of transport casks and different types of trucks and ships from those used in the tests mentioned above. However, it is absurd to have to prove the integrity of spent nuclear fuel by performing expensive tests again. Therefore, in this study, the design load that can be used by transport business companies is to be presented. The design load to be presented should satisfy the following requirements. The design load should be applicable including some differences in the transport cask or transport system, or different design loads should be presented according to the differences. The location where this design load is applied is to be specified (e.g. fuel rod, basket, internal structure). Requirements according to the operating speed of the transport system should be presented together. The type of design load is to be presented (e.g. PSD, SRS, FDS etc.). Other types of standards may be presented. For example, a speed limit for a vehicle carrying spent nuclear fuel may be suggested, or a speed limit for a vehicle passing through a speed bump may be suggested. In order to present such a reliable design load, a multi-axis vibration excitation shaker table test will be carried out. Though this shaker table test, the behavior of the nuclear fuel assembly is closely evaluated by applying the data obtained from the road and sea transport tests previously performed as an input load. In addition, FDS (Fatigue Damage Spectrum) will be produced and applied to experimentally evaluate the durability of fuel assemblies under normal transport conditions.

최근 빅데이터, 인공지능 등 눈부신 기술 발전으로 인해 자율운항선박이 현 실화되고 있으며, 산업계를 중심으로 육상에서 선박을 조종하기 위한 기술 개 발이 활발히 진행되고 있다. 이러한 자율운항선박 도입을 위한 관련 법적 검토 를 통해 국제해사협약의 필요한 개정 및 명확화 작업이 이루어질 수 있도록 함 으로써 향후 자율운항선박이 원활하게 운항될 수 있는 여건 조성에 기여할 수 있을 것이다. 이 논문에서는 11개의 법률위원회 소관협약에 한정하여 연구를 진행하였다. 우선 협약내용별 해당 조항이 자율운항선박 운용에 아무 문제없이 적용되는지, 아니면 적용되려면 개정 및 명확화 등이 필요한지 여부를 검토하 였다. LEG 협약에 대한 규정검토작업 결과, 별도의 작업이 필요하지 않거나, 일부 규정의 경우 통일해석 및 협약의 개정을 통해 자율운항선박의 운용이 가 능한 것으로 판단되었다. LEG 협약 상 도출된 주요 쟁점 사항은 정의 및 용어, 선장의 역할과 책임, 원격운항자의 역할과 책임, 법적책임, 증서, 기타사항으로 정리할 수 있다. 자율화 등급 1단계 및 2단계에서는 선박에 선원이 탑승하기 때문에, 대부분 통일해석의 개발을 통해 자율운항선박에 적용이 가능할 것으로 보인다. 선원이 승선하지 않는 자율화 등급 3단계 및 4단계에서는 현재 협약을 개정하거나 자 율운항선박에 관한 새로운 협약의 제정이 필요할 것이다. 아울러 아직 정립되 지 않은 자율운항선박, 자율화 등급 등에 대한 용어의 정의가 공통적으로 필요 하다. 그리고 선장 등에 대한 명확한 개념 및 역할도 검토가 필요하다. 일반적 으로 선장은 선박소유자를 대신하여, 선박운항 책임자로 그 역할이 상당히 중 요하다고 할 수 있다. 그러나, 자율화 등급 1단계를 제외하고 2단계, 3단계 및 4 단계에서는 선박에 선장이 승선하지 않기에 이러한 전통적인 선장의 역할 및 책임을 명확히 하는 것이 필요할 것이다. 또한, 자율운항선박 도입으로 인해 새 롭게 등장하는 원격운항자의 역할과 책임에 대한 명확화가 필요하다. LEG 협 약의 법적 검토를 통해 원격운항자 관련 부분이 상당 부분 식별되었으며, 원격 운항자의 정의, 개념, 역할 및 책임 등에 대한 부분을 명확하게 할 필요가 있다. 아울러 새로운 자율운항선박의 자율시스템 및 원격조종시스템 등이 출현하게 됨에 따라 제조업자, 시스템 개발자 등에 대한 책임 여부에 대해 명확화가 필 요하다. 그리고 항만국통제 수검을 위해 선내 비치해야 하는 보험증서를 선원 이 승선하지 않는 자율운항선박에 어떻게 처리해야하는 지에 대해 추가적인 통 일해석이나 개정이 필요할 수 있다.

근대 고등교육 사립 연희전문학교의 설립·운영에서 실무자로 직접적인 영향력을 보여준 에비슨(Oliver R. Avison)의 교육행정가적 인 특징과 상호문화성의 관련성을 고찰하여 현대적 시각에서 조명해 보고자 하였다. 에비슨의 교육행정가적인 네 가지 특징은 상호소통 능력, 협업능력, 추진력, 통합능력이다. 이들은 상호문화성의 중핵적 요소들이 내재되어 실제적으로 교육 현장에서 개방성, 가능성, 공공성, 현재성의 네 가지 상호문화성으로 발현되었다. 따라서 에비슨의 교육행 정가적인 특징들은 곧 상호문화성으로 호환 가능한 자기 번역 능력을 가졌으며, 그 상호문화성이 곧 사립 연희전문학교 설립·운영을 주도한 숨은 공로자였음을 확인할 수 있었다. 상호문화성이 내재된 에비슨의 교육행정가적인 특징들에 관한 연구는 한국의 다층적 삶을 살아가는 모든 구성원의 상생적 삶을 위한 대안적 모색임과 동시에 선교현장에서 교육행정가의 모범으로써 선용할 만한 또 하나의 모델을 발굴하는 일이 될 것이다.