A person who performs or plans to conduct a physical protection inspection as stipulated by the law, the act on physical protection and radiological emergency, should obtain an inspector’s ID card certified and authorized by Nuclear Safety and Security Commission Order No.137 (referred to as Order 137). In addition, according to Order 137, KINAC has been operating some training courses for those with the inspector’s ID card or intending to acquire it. Also, strenuous efforts have been put to incrementally elevate their inspection related expertise. Since Republic of Korea has to import uranium enriched less than 20% in order to manufacture fuels of nuclear reactors in domestic and abroad, the physical protection for categorization III nuclear material in transit is significantly important along with an increase in transport. The expertise of inspectors should be constantly needed to strengthen as the increase in transport leads to an increase in inspection of nuclear material in transit. We have suggested a special way to improve the inspector’s capacities through Virtual Reality technology (VR). A 3-Dimensional virtual space was designed and developed using a 3-axis simulator and VR equipment for practical training. HP’s Reverb G2 product, which was developed in collaboration with VALVE Corporation and MicroSoft, was used as VR equipment, and the 3-axis motion simulator was developed by M-line STUDIO corp. in Korea for the purpose of realizing virtual reality. The training scenarios of transport inspection consist of three parts: preparation at the shipping point, transport in route including stops and handover at the receiving point. At the departure point, scenario of the transport preparation is composed with the contents of checking the transport-related documents which should be carried by shipper and/or carrier during transport and confirming who the shipper and/or carrier is. Second, scenario is designed for inspector to experience how carrier and/or shipper protect the nuclear material during transport or stops for rests or contingency and how they communicate with each other during transport. Lastly, scenario is developed focusing on key check items during handover of responsibilities to the facility operator at the destination. Those training scenarios can be adopted to strengthen the capabilities of those with inspector’s ID card of physical protection in accordance with Order 137 and to help new inspectors acquire inspectionrelated expertise. In addition, they can be used for domestic education to promote understanding of nuclear security, or may be used for education for people overseas for the purpose of export of nuclear facilities.

Nuclear Safety and Security Commission (NSSC) and KINAC review a Cyber Security Plan (CSP) by「ACT ON PHYSICAL PROTECTION AND RADIOLOGICAL EMERGENCY」. The CSP contains cyber security implementation plans for the licensee’s nuclear power plant, and it shall meet the requirements of KINAC/RS-015, a regulatory standard. The KINAC/RS-015 provides more detailed information on the legal requirements, so if licensees implement cyber security under the approved CSP, they can meet the law. To protect nuclear facilities from cyber-attacks, licensees should identify their essential digital assets, so-called “Critical Digital Assets” (CDAs). Then, they apply cyber security controls (countermeasures for cyber-attacks) on CDAs consisting of technical, operational, and management security controls. However, it is hard to apply cyber security controls on CDAs because of the large amounts of CDAs and security controls in contrast to the shortage of human resources. So, licensees in the USA developed a methodology to solve this problem and documented it by NEI 13-10, and US NRC endorsed this document. The main idea of this methodology is, by classifying CDAs according to their importance, applying small amounts of security controls on less important CDAs, so-called non-direct CDAs. In the case of non-direct CDAs, only basic cyber security controls are applied, that is, baseline cyber security controls. The baseline cyber security controls are a minimum set of cyber security controls; they consist of control a) from control g) a total of 7 controls. Although non-direct CDAs are less critical than other CDAs (direct CDAs), they are still essential to protect them from cyber-attacks. This paper aims to suggest a cyber security enhancement method for non-direct CDAs by analyzing the baseline cyber security controls. In this paper, baseline cyber security controls were analyzed respectively and relatively and then concluded how to apply small amounts of cyber security controls on non-direct CDAs rather than direct CDAs without scarifying cyber security.

An administrative agreement (AA) was signed between NSSC and UAE FANR in January 2023 under Article 5 of the ROK-UAE Nuclear Cooperation Agreement. The AA aims to enhance regulatory efficiency in safeguards and export control. This study reviewed the export control measures for the items subject to the agreement (ISA) and implementation procedures under ROK-UAE AA by comparing them with other countries cases. First of all, the ROK-UAE AA distinguishes between ISA and the inventory management target items. Technology is divided into two categories, one requiring consent for retransfer and the other, considering the characteristics of technology that is free to be copied and deleted, and thus less useful for inventory management. Only the former is included in the annual report, which differs from the ROK-Canada or ROK-Japan NCA, which includes all technologies subject to the agreements in the annual report. When ROK notifies export information, it is mandatory to specify whether the technology requires consent for retransfer. Furthermore, some technologies should be controlled as strategic information, even if excluded from the annual report, so efforts to prevent confusion are required. Secondly, the ROK-UAE AA covers all items in INFCIRC/254/rev.9/part1, unlike the ROK-U.S. and ROK-Canada NCA, which listed equipment subject to them. This is significant because it clarifies the criteria for regulation by increasing the consistency between the trigger list items in the domestic law and the ISA. However, the expanded ISA scope could result in some changes in export control procedures. For example, when importing nuclear material (NM) from the US, only uranium was controlled as ISA, and the packages were not considered. In contrast, when exporting fuel assemblies (FA) for UAE, both uranium and zirconium cladding should be treated as ISA. To this end, NEPS was improved to implement the features of the ROK-UAE AA. Consideration of the criteria and methods for imposing obligations under the agreement is essential because this is the first case of Korea concluded AA under exporting NPP and as a supplier of FA. Generally, the obligations for NM are imposed by the country of origin, conversion, and enrichment countries. Canada and EU recognize the fuel fabrication process as a substantial transformation and impose customs origin where the process takes place. Hence, NM fabricated from Canadian equipment is also subject to the same obligations as NM of Canadian origin. From this perspective, it would be appropriate to ensure ROK acts as a supplier and controls when exporting domestically manufactured FA. Moreover, a proper national obligation code system will be required to specify Korea’s control rights.

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.

A Study on the Discussion for the Indefendent Charater and the No-cause Character of the Real Rights Behavior The most controversial topic in the Korean civil law academic circle so far is the theory of Real Rights Behavior, which has centered on the the Indefendent Charater and the No-cause Character of Real Rrights Behavior. The core of the controversy over the No-cause Character of Real Rights Behavior is the legal interest of securing transaction safety, and the theoretical basis necessary to argue whether the No-cause Character of Real Rights Behavior is the recognition of the identity of Real Rights Behavior. In the end, the fierce debate, which has been held for the practical legal interest of securing transaction safety, is believed to be due to the lack of a realistic legal system and its regulations, and the unreasonable application of uncritical foreign theories. In other words, the Auflassung system to supplement the formalism examination system of registration in Germany secured transaction safety by strengthening the function of strengthening the credibility of registration. However, in the absence of such systems and related laws, the Korean civil law community borrowed German theories and applied them excessively, and constant debate reproduced them. In order to protect the realistic legal interests of transaction safety and to establish a consistent theoretical system in academia, it is necessary to supplement related systems through legislation

Currently, the most widely accepted disposal concept for long-term isolation of high level radioactive waste including spent nuclear fuels is to disposal in a deep geological repository designed and constructed with multiple barriers composed of engineered and natural barriers so that the waste can be completely isolated in a stable deep geological environment. In this concept, an important consideration is the heat generated from the waste due to the large amount of fission products present in the high level waste loaded in the disposal container. For safe and complete isolation of high level radioactive waste in the deep geology, the disposal concepts that meet the thermal requirements for the disposal system design have been developed by harmonizing the thermal characteristics of engineered and natural barriers in Korea. In this paper, the deposition hole configuration and the decay heat dissipation area (surface area) of disposal container were considered for the efficient thermal management in the deep geological disposal concept. Heat transfer through the waste form, its container and surrounding components and the rock will be mainly by conduction. Heat transfer by radiation and convection can be negligible after backfilling. When considering heat conduction, according to Fourier’s law, if the thermal conductivity of the repository components is the same, the greater the heat dissipation area and the adjacent temperature gradient, the greater the conduction effect. Therefore, rather than the conventional concept of loading 4 PWR spent fuel assemblies per disposal container and placing one disposal container in a deposition hole, it is better to load one assembly per disposal container and place 4 disposal containers in a deposition hole. In this case, it was found that the disposal area could be reduced through efficient thermal management. Considering this thermal management method as an alternative to the concept of deep geological disposal, additional research is needed.

Under the bilateral nuclear cooperation agreements (NCA) and its administrative arrangement (AA), Korea annually exchanges the inventory of subject items (including nuclear materials (NM), non-nuclear materials, equipment, and related information) with US, Canada and Australia. Also, the government performs export control procedures such as notification or prior consent during importing and exporting of relevant items. It makes NCA a means of realizing the nuclear non-proliferation regime. However, it raises difficulties in management because the entity that uses and treats those items are end-user, not the authorities of AA, the government agency of each country. Accordingly, to increase the accuracy and effectiveness of item management at the national level, it is required to establish a system for the individual company that has the NCA items, considering the characteristics of each company. In this study, significant companies are classified into more than three types, and the management system of the items subject to the agreement is analyzed. Each company’s item management status has different characteristics depending on its role (position) within the entire nuclear fuel cycle, the type of facility, its possessed items, the main form of national trade, and the frequency of domestic movement. Those differences lead to diversity in the management systems currently owned by each company. For example, from the perspective of nuclear materials, institutions requiring bulk management have systematically organized their management system and obligation code program compared to the ‘item institutions’ that can track batch history for all facility inventory changes. Although Domestic law imposes only the duty of origin management on NMs, fuel manufacturers or research institutes have established their standard obligation codes to manage multiple obligations. The non-nuclear materials and equipment can be easily tracked and controlled by individual items. However, the management of NCA items is a complicated task involving various processes, from importing goods to using, storing, managing inventory change, selling to others, or fulfilling the obligations of AA when exporting. In particular, when the movement of items within a company or international trade occurs frequently, or when the end-users are diverse, the management difficulties increase. So a system that can accurately convey and track items subject to the AA is needed. In addition, since various entities are related, it is necessary to improve understanding of NCA items to increase the system’s utilization and effectiveness. The comparison result and requirement for system improvement based on the review above will be reflected in the history management system for items subject to NCA under development.

When exporting nuclear power plants to a third country, the U.S. conditions import countries to join the International Atomic Energy Agency (IAEA) Additional Protocol. At the Korea-U.S. summit, Korea also agreed to maintain equal non-proliferation standards. This paper first analyzes how the U.S. applies the conditions for joining additional protocols to export control policies. The U.S. Atomic Energy Act is a general law in the field of nuclear power that governs both civilian and military use of nuclear power. Article 123 stipulates matters related to “cooperation with other countries.” According to Article 123, the United States must conclude a peaceful nuclear cooperation agreement with another country that stipulates nuclear non-proliferation obligations for nuclear cooperation to a “significant” extent. Article 123 of the Nuclear Energy Act presents nine conditions for signing the Nuclear Cooperation Agreement, and matters related to safeguards are stipulated in Nos. 1 and 2, and only IAEA’s Comprehensive Safeguards Agreement (CSA) is specified as requirements under the current law. As a result of analyzing the countries of the nuclear cooperation agreements currently signed by the United States, the United States is evaluating the AP in terms of the policy as an essential item. Among the nuclear agreements with the United States, three countries, Egypt, Brazil, and Argentina do not have AP in effect. Among them, Brazil and Argentina are recognized by the IAEA as replacing the ABACC with the AP, so only Egypt is not a member of the AP. The nuclear agreement between the U.S. and Egypt was signed in 1981 before the AP existed, and all recently signed agreements were identified as AP-effective countries. As a result of reviewing the U.S. export control laws, the U.S. did not legislate the AP as a condition for peaceful nuclear exports. Reflecting the NSG export control guidelines, AP was legislated as an export license requirement only in exporting sensitive nuclear technology (enrichment, reprocessing). However, it is confirmed that the U.S. policy applies AP entry into force as one of the main requirements for determining whether it is harmful to nuclear exports, along with the conclusion of the Nuclear Cooperation Agreement, the application of the Comprehensive Safeguards Agreement, and military alliance. The appropriate scope of application of the Additional Protocol in Korea and its application plan will be suggested through future research.

In 2004, in order to comply with UN Security Council Resolution 1540, the European Union (EU) came into force with Regulation 428/2009 for the export control of dual-use items, which has been working to prevent the proliferation of weapons of mass destruction (WMDs). In August 2021, it amended the EU 821/2021 to include mandating the introduction of ICPs for exporters in the member countries in order to strengthen controls over the transfer of tangible and intangible technologies. The main contents are as follows; 1) Mandatory introduction of Internal Compliance Program (ICP): Exporters within the EU countries should introduce a transaction review procedure through the ICP in consideration of their size and organization. 2) Export control on Cyber Surveillance Items to protect human rights: In order to protect human rights and comply with the obligations of international human rights law, EU countries should implement export controls on cyber-monitoring items exported from customs zones in the EU. Cyber surveillance items are specially designed to monitor, extract, collect or analyze data such as biometrics through intrusion of information and communication systems or deep packet hijacking. However, items used for purely commercial programs such as billing, marketing, quality service, user satisfaction or network security are excluded. 3) Expansion of the Catch-all system: EU countries should utilize the catch-all system to strengthen export controls on cyber-monitoring items, including dual-use items. 4) Strengthening control over the cloud: Exporters and EU countries should extend the scope of intangible technology transfer, such as electronic media, fax, and telephone, outside the EU’s customs territory, and apply export control regulations such as general or comprehensive licenses to cloud transmissions outside the EU territory. 5) Introduction of large-scale project authorization: To reduce the administrative burden on enterprises (especially small and medium-sized enterprises) and authorities when exporters with individual or collective licenses export to one or more specific end-users for the purpose of large scale projects, provided that they ensure the implementation of an appropriate level of export controls; EU countries may introduce large-scale project license systems in the form of general authorization. Recently, there is a possibility that the ROK would export its nuclear technologies including APR1400 to the EU member countries in the midst of the EU adoption of carbon-zero policy. In this paper, we have analyzed the EU export control regulations and suggested the future direction of nuclear export control programs in the ROK.

In August 2021, in response to the rapidly changing trade environment, including the advancement of Information Communication Technology (ICT) and its services, the European Union (EU) implemented the Dual-Use Items Control Regulation 821/2021 to introduce an Internal Compliance Program (ICP) to the EU countries. Accordingly, the exporters should comply with the regulation to strengthen their transactions review systems. Sweden, Germany, France, and the United Kingdom have implemented ICPs and outreach activities for dual use items. In particular, France explicitly stipulates the introduction of ICP in the law to manage and supervise it. While Sweden, Germany, and the United Kingdom strengthen the supervisory authority of regulatory agencies then companies are encouraged to autonomously introduce ICPs. Before introducing the ICP for the trigger list items (the items) to the Republic of Korea (ROK), a comprehensive export license system for them should be firstly considered based on EU Regulations. Also the comprehensive export license might be implemented by expanding the subject for the existing license on technology export of nuclear plant into the items. The ROK does not introduce an ICP as it does not recognize a self-classification on the items in accordance with the nuclear export control law. However, in preparation for the export to the EU countries that have intentions to introduce nuclear plants, it is necessary to analyze the export control programs of Sweden, Germany, France, and the United Kingdom. Like the programs of Sweden, Germany and the United Kingdom, the EU regulations might be adopted to reduce the regulation burden in the ROK. With the reference of Sweden, the authority could support the Export Control Manager Certification (ECMC) system accredited by civil association then its outreach activities could be diverse and extended. Basically, the ECMC system could consist of Part I, II, III and IV and an applicant could be accredited by a civil association as the ECM after completing the courses of Part I and II. The ECMC courses might be as follow; 1) Part I: the Basic common course for beginner 2) Part II: the National export control system for the items 3) Part III: the International export control regulations 4) Part IV: Re-Certification within the certain period In this paper, we analyzed the export control programs in Sweden, Germany, France, and the United Kingdom and suggested the ECMC system that might be applied to the ROK as above.

KINAC has regulated cyber security of nuclear facilities based on「Act on Physical Protection and Radiological Emergency」and KINAC/RS-015 “Security for Computer and Information System of Nuclear Facilities”, a regulatory guide. By that law and regulatory guide, nuclear licensees shall protect digital assets so-called CDAs, which are conducting safety, security, and emergency preparedness functions from cyber-attack. First of all, to protect CDAs from cyber-attack, licensees should identify CDAs from their assets according to the RS-015. The identification methods are provided in another regulatory guide, RS-019. To research the best practice, a reference case is selected as a U.S. case. In this study, a comparison analysis was conducted especially focused on EP CDAs identification methodology between R.O.K. and U.S., because the regulation basis is relatively insufficient in R.O.K., and improvement plans for the cyber security regulations in R.O.K were proposed. From the analysis, it was identified that detailed methods to identify EP function are provided in NEI 10-14 “Identifying Systems and Assets Subject to the Cyber Security Rule” published by Nuclear Energy Institute (NEI), an institute of nuclear power reactor licensees. Also identified that the definition of EP function is provided clearly in NEI 10-04 based on related regulation, 10 CFR 50.47 “Emergency Plans”. In that regulation, licensees shall follow and maintain the effectiveness of an emergency plan that meets the sixteen planning standards of 10 CFR 50.47(b). So, these sixteen planning standards correspond to the emergency preparedness functions. In NEI 10-04, scoping considerations for emergency preparedness function are provided referring to sixteen planning standards. Moreover, in that scoping considerations, planning standards, planning standard functions and 10 CFR 73.54 “Protection of digital computer and communication systems and networks” scoping guidance are provided, so, licensees identify EP CDA in their assets conveniently. In case of R.O.K., because these sixteen planning standards are not established, there is an ambiguity in identifying EP CDAs. The only related provision is “Detailed Standards for Establishment of Emergency Plan”. To resolve the ambiguity, it is needed to analyze sixteen planning standards in 10 CFR 50.47(b) and “Detailed Standards for Establishment of Emergency Plan”. Then, should be developed ‘scoping considerations for emergency preparedness function’ based on the analysis as provided in NEI 10-04.

Sabotage on nuclear power plants are of great national and social significance and long-term damage, the IAEA’s “Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Rev.5) provides a standard direction for physical protection of their nuclear facilities in almost all member countries, including Korea and the United States. In the United States, Federal Law 10 CFR Part 73, Sections 73.40 to 73.57 specify requirements for physical protection of nuclear power plants, performance criteria, physical protection systems and components thereof, core information, and physical protection for key activities related to nuclear power plant operations. Accordingly, the USNRC carefully examines whether the plant meets the physical protection objectives and criteria set out in SRP 13.6.2, whether the core area/protection area is properly set up to protect against internal and external physical attacks, sabotage threats, and what design measures and facilities are being set up for these areas. The Department of Homeland Security (DHS), established in 2002 following the 2001 World Trade Center attacks, authorized federal, local governments, and authorities National Infrastructure Protection Plan (NIPP) to protect facilities from terrorist attacks and man-made physical attacks in 2007. NIPP clarifies the great principles and governance of the physical protection of national infrastructure in the United States presented by DHS. There are many physical protection design guidelines and technical standards for preventing attacks from terrorists or internal and external sabotage attackers, improving the viability of mitigating the damage in case of emergency, and achieving efficient recovery from such damage. Particularly important, small-scale damage/damage at a particular location of a major facility is extended to the entire facility, resulting in asymmetrical large-scale damage, so-called “Progressive Collapse” under initial attack loads, minimizing local damage, and protecting the building’s integrity through isolation from other structural components. Consequently, this paper deal with physical protection system design on Unite states standards and practices for applying to physical protection system design in Republic of Korea.

Since the reform and opening up, China has maintained rapid economic growth for nearly 40 years, and is the country with the fastest economic growth in the world. However, the rapid economic growth has also paid a huge social price, which is directly related to the unreasonable economic structure and extensive growth mode. Traditional engines of economic growth began to fade. This paper through the analysis to the theory of ancient and modern Chinese and foreign economists study on economic growth: economic growth is an extremely complex process, many factors influence the economic growth, correctly grasp the role of these factors in economic growth, to grasp the law of economic growth, the correct understanding of modern economic growth is very important. Sustained economic growth in China, on the basis of dynamic analysis, combined with the current economic situation at home and abroad, as you can see, in the high-speed economic growth since reform, various factors have been attenuation or mutation, the major developed countries and regions for the adjustment of the external imbalance in pressure, the depth of the global economic growth and recovery of the factors of uncertainty, It is difficult to maintain and improve the driving force and source of China’s economic growth in the future. The current industrialization process has reached a historical and international high level and is nearing the end. The growth rate of industrial investment will slow down significantly in the future. The demographic dividend is gradually depleting, and the savings rate will gradually decrease in the future. The era of rapid economic growth brought by demographic dividend and high savings rate in a long period of time will change. Therefore, based on the perspective of supply side demand and the development of new industries, the paper analyzes the driving force of traditional economic growth in China in the past, and holds that the driving force of consumption upgrading and digital economy are the important driving force of economic growth, and strives to improve the consumption structure of residents, increase the consumption rate and vigorously develop digital economy. Shifting China’s economic growth from relying on external demand to relying on domestic demand will provide strong support for high-quality development.

Climate change has recently become a serious global issue, and carbon emissions and energy consumption are increasing, particularly in cities where economic activities and populations are concentrated. Accordingly, various countries worldwide are promoting the Green New Deal and promoting urban-centered climate change response policies with the aim of carbon neutrality. In Korea, following the “smart green city” project that creates a city where humans and the environment coexist, a similar “carbon neutral green city” policy is set to be introduced. Therefore, in this study, implications and directions for the sustainable introduction of the carbon neutral green city policy will be derived by comparing and analyzing the State and Tribal Assistance Grants of the U.S. bipartisan infrastructure law and the smart green city of the Korean new deal.

As the plan for the nuclear dismantlement due to the permanent shutdown of Kori-1 and Wolseong- 1 nuclear power plants has been concretized, a “movable radionuclide analysis system” is being developed that can quickly and accurately analyze large amounts of radioactive waste generated on the sites during dismantling. This system has various advantages from the perspective of strict regulations on the radioactive waste movement and social acceptability, such as preventing unexpected accidents while moving on the national highway or expressway, reducing various documents and immediate response to dismantling plans. Currently the system is being developed to be equipped with previously developed sample pretreatment and radioactivity measuring equipment and automated volatile and nonvolatile nuclide separation equipments, but to ensure mobile stability, it needs to analyze factors and establish stability standards. In the KS Q ISO/IEC 17025:2017 standard, the requirements for “facilities and environmental conditions” are a very important factor in building reliability for consumers as part of the quality guarantee for this facility. In order to meet the requirements, the technical standards of various test equipment to be installed in this facility were investigated. The physical, chemical, and radiological hazards that could affect the safety of the equipment and workers in the process of moving the equipment between nuclear power plants or between nuclear dismantling sites were derived from vibrations, rapid changes in temperature and humidity, and the spread of contamination from radioactive waste samples. Therefore, the scope of application of the law, which is the basis for securing stability during movement, was classified into two situations: movement from facility manufacturer to installation site (non-contaminated) and movement from primary to secondary use (contaminated). And in order to investigate the Nuclear Safety Act, enforcement ordinances, and radiation safety management, and to establish standards for packaging and transportation of radioactive materials, the results of transportation tests and transport details were compared and analyzed. Finally, the air suspension systems and the automatic temperature and humidity control devices were analyzed to establish standards for securing stability against the vibration and the sharp changes in the temperature and humidity, and countermeasures such as accident measures in accordance with the Enforcement Decree of the Nuclear Safety Act were also investigated.

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.

Gases such as hydrogen can generate from the disposal canister in high-level radioactive waste disposal systems owing to the corrosion of cooper container in anoxic conditions. The gas can be accumulated in the voids of bentonite buffer around the disposal canister if gas generation rates become larger than the gas diffusion rate of bentonite buffer with the low-permeability. Continuous gas accumulations result in the increase in gas pressure, causing sudden dilation flow of gases with the gas pressure exceeding the gas breakthrough pressure. Given that the gas dilation flow can cause radionuclide leakage out of the engineered barrier system, it is necessary to consider possible damages affected by the radionuclide leakage and to properly understand the complicated behaviors of gas flow in the bentonite buffer with low permeability. In this study, the coupled hydro-mechanical model combined with the damage model that considers two-phase fluid flow and changes in hydraulic properties affected by mechanical deformations is applied to numerical simulations of 1-D gas injection test on saturated bentonite samples (refer to DECOVALEX-2019 Task A Stage 1A). To simulate the mechanical behavior of microcracks which occur due to the dilation flow caused by increase in gas pressure, a concept of elastic damage constitutive law is considered in the coupled hydro-mechanical model. When the TOUGH-FLAC coupling-based model proposed in this study is applied, changes in hydraulic properties affected by mechanical deformations combined with the mechanical damage are appropriately considered, and changes in gas injection pressure, pore pressures at radial filters and outlet, and stress recorded during the gas injection test are accurately simulated.

In April 2015, the government of the Republic of Korea and the United States of America signed a new Nuclear Cooperation Agreement (NCA). Subsequently, in April 2016, the Nuclear Safety and Security Commission (NSSC) of the ROK and the Department of Energy (DOE) of the US signed the Administrative Agreement (AA) under the new Nuclear Cooperation Agreement. Accordingly, when Korea imports items subject to the Korea-US agreement, it is required to determine the inventory of imported agreement items and notify the United States of the inventory amount every year. In addition, when re-exporting an agreement item to a third country, prior consent of the original exporting country (USA) must be obtained. Nuclear companies that import items subject to the Korea-US Atomic Energy Cooperation Agreement must report their inventory to the government every year, but the standards and procedures for managing the inventory are not clearly stipulated in the national law. This makes it difficult for the government to verify the adequacy of the report submitted by nuclear companies, adding to the administrative burden on both the government and the companies. Accordingly, it is required for the government to establish and operate a system for history management system for import and export items subject to the agreement so that related information can be recorded and managed at each stage, such as first import of items to Korea, generation, disposal, and exports to third countries. This system provides history management functions such as initial import information record for items imported through import/export procedures according to administrative agreements, change of owned company due to domestic movement, deletion of inventory due to loss/disposal, deletion of inventory due to export or addition of inventory due to derived materials. Through this system, operators can easily manage agreement items, and the government can obtain reliable information on agreement items in close to real-time. In addition, when this system applies to exports of items subject to the agreement, the number of items subject to the agreement exported by Korea can be provided first so that the importing country can more quickly check the items subject to the agreement. It is expected to contribute to securing control of the items subject to the agreement and reducing concerns over nuclear proliferation.

중국이 사회 전환기에 접어든 큰 맥락에서, 시장 경제는 충분히 성장했고, 시장 경제 주체들의 활동도 전례 없이 활발해졌고, 하지만 뇌물 수수도 함께 생겨났고, 점점 더 심해지고, 공정한 시장 질서를 파괴할 뿐만 아니라, 또한 중국 시장경제의 건전한 발전에 엄중한 영향을 끼쳤으며, 따라서 대중들이 이러한 행위에 대하여 형벌의 강도를 높여야 한다는 강력한 목소리를 불러일으켰으며, 중국의 입법자는 이에 효과적으로 응답하여 2006년 7월 전국인민대표대회 상무위원회에서 "형법개정안(6)"을 개정하여 통과시켰으며, 상업수수의 범위를 확대하였다. 학계에서도 상수뇌에 대한 관심을 소홀히 하지 않고 있다, 그러나 기존의 연구는 대부분 형법적인 관점에서 상수뇌에 대한 개념, 구성 특징 및 사법적 인정에 대한 분석과 해석에 치중하고 있다. 이러한 연구는 사후처벌의 보완을 위한 지도적인 역할을 하고 있다. 그러나 범죄학적으로 사업상 뇌물 수수에 대한 사전 예방과 통제에 관한 연구는 아직 미약하다. 본문은 사실학의 각도에서 상업 수수의 정의와 위해를 상술하고, 그 현존하는 특징과 유형을 귀납하며, 체계적으로 현재 중국 사회에 만연한 주요 원인을 고찰하고, 마지막에는 비교적 체계적인 예방 대책을 제출하여 상업 수수의 현상을 통제하기 위해 조금이나마 미약한 힘을 다하고자 한다.

독도교육은 독도의 영유권확보를 위한 선결적 수단 가운데 하나로서, 그 중요성은 따로 강 조하지 않더라도 자명하다고 할 것이다. 본 논문은 지난 3년 동안의 영남대학교 법학전문대학원에서의 독도교육의 운영사례를 중 심으로, 법학전문대학원의 학생을 대상으로 한 가장 효과적인 독도교육의 모델을 찾는데 목 표가 있다. 이러한 목표 하에서, 본 논문에서는 아래의 몇 가지 측면을 살펴보고자 한다. 먼저 영남대 학교를 비롯한 지역대학에서의 독도교육의 현황을 간략하게 소개하고자 한다. 둘째 영남대학교에서 수행해온 독도교육의 내용을 검토하고, 그 한계를 분석하고자 한다. 셋째 법학전문대 학원의 학생을 대상으로 한 가장 효과적인 독도교육의 모델을 구하고자 한다. 끝으로 결론에 갈음하여 법학전문대학원의 학생을 대상으로 한 독도교육의 나아갈 방향을 기술하고자 한다. 이상과 같은 검토와 분석을 통해 본 논문은 다음과 같은 몇 가지 결론을 제시하고 있다. 첫째 법학전문대학원에서의 독도교육은 독도 관련 법률전문가의 양성 및 국가의 전략적 차원에서의 기여라는 점에서 크게 환영할 일이라는 점이다. 둘째 법학전문대학원에서 독도교육을 성공적으로 수행하기 위해서는 초・중・고교에서 의 독도교육과 연계성을 가지고 체계적으로 교육되어야 한다는 점이다. 셋째 독도문제를 포괄적으로 다룰 수 있는 전문가양성프로그램이 요청된다는 점이다. 넷째 독도교육을 위해 정부나 지방자치단체의 적극적 역할이 필요하다는 점이다. 다섯째 가칭 ‘독도교육공동연구회’와 같은 민간 주도의 위원회를 설치하여, 독립적이고 중 립적인 틀 속에서 관련 논의를 지속적으로 이어가야 한다는 점이다. 결론적으로 독도에 관한 국민의 사랑과 관심이 지속된다면, 독도는 ‘아름다운 금수강산’으 로 영원히 남을 것이다. 국민의 사랑과 관심이 필요한 때이다.