본 연구는 철도교 노후화에 따른 열차운행 중 신속 교체 및 재난·재해에 대한 급속 시공을 통하여 공기단축 및 시공성 확보로 국민의 사회적·경제적 피해를 최소화하고자 한다. 철도교 개량 등에서 필 수적인 8철도하로교 시공고도화 및 성능향상9을 위하여 신속 교체와 성능향상이 가능한 강합성 철도하 로교 설계·제작·시공 기술을 개발하고자 한다. 또한, 개발하고자 하는 강합성 하로교의 경우 철도교뿐 만 아니라 도로교에서 적용하고자 하며, 철도교는 상부구조가 단경간 형식으로 이루어지고 있어 철도 교 사용성 검토에 큰 문제가 없으나 도로교의 경우 바닥판 연속화를 고려 중에 있어, 이에 대한 온도 및 부모멘트 등 여러 문제점을 검토하였다. 상로교의 경우 다수의 거더에 의해 바닥판이 지지되므로 PS의 중요성이 부각될 수 없지만, 하로교의 바닥판은 양단 거더에 의한 고정지지이므로 RC구조 적용 이 어려워, 강합성 또는 PSC 공법을 일반적으로 적용한다. 기존 강합성 구조는 비용, 공기 측면에서 지양하고 PSC 구조의 가로보 및 바닥판과 강재 거더를 합성한 하로교를 개발하고자 한다.

The initial development plans for the six reactor designs, soon after the release of Generation IV International Forum (GIF) TRM in 2002, were characterized by high ambition [1]. Specifically, the sodium-cooled fast reactor (SFR) and very-high temperature reactor (VHTR) gained significant attention and were expected to reach the validation stage by the 2020s, with commercial viability projected for the 2030s. However, these projections have been unrealized because of various factors. The development of reactor designs by the GIF was supposed to be influenced by events such as the 2008 global financial crisis, 2011 Fukushima accident [2, 3], discovery of extensive shale oil reserves in the United States, and overly ambitious technological targets. Consequently, the momentum for VHTR development reduced significantly. In this context, the aims of this study were to compare and analyze the development progress of the six Gen IV reactor designs over the past 20 years, based on the GIF roadmaps published in 2002 and 2014. The primary focus was to examine the prospects for the reactor designs in relation to spent nuclear fuel burning in conjunction with small modular reactor (SMR), including molten salt reactor (MSR), which is expected to have spent nuclear fuel management potential.

Recently, as carbon-neutral energy sources become increasingly important worldwide, SMRs (Small Modular Reactors), which offer significantly enhanced safety, versatility, and mobility compared to conventional nuclear reactors, are gaining attention as a viable alternative. SMR generally refers to small modular reactors with a power output of 300 MWe or less. Unlike conventional reactors, SMRs are characterized by an all-in-one design where peripheral systems and equipment are all integrated into the reactor itself, leading to enhanced reliability and durability. Additionally, the nuclear fuel reloading cycle is significantly extended compared to traditional reactors, resulting in a substantial reduction in maintenance difficulty and costs. Researchers have taken note of these characteristics of SMRs, particularly the extended fuel reloading cycle. Therefore, we have initiated the initial design of an ultra-small Micro Modular Reactor with an electricity generation capacity of 10 MWe and a fuel cycle of up to 55 years, with the goal of using it as a propulsion power source for various transportation modes, especially ships. Our design of MMR, called ‘ARA,’ is primarily distinguished by its use of U233 and Th232 fuels instead of conventional UO2 fuel. Due to various features of ‘ARA,’ including different fuel compositions, ARA is predicted to exhibit several characteristic features compared to conventional PWRs. In this study, among these characteristics, we focused on predicting changes in material composition within the fuel rod during the extended cycle operation of high-enriched fuel, rather than short-cycle operation using low-enriched fuel, unlike conventional reactors. The primary goal of this research is to observe the behavior of the composition of the materials used in the fuel cycle of the MMR, which utilizes U233 and Th232 fuels instead of UO2. Considering the difficulties in the spent nuclear fuel disposal process, many different trials were made to minimize the fission products of ARA, which differs from conventional reactors in terms of fuel type, size, and fuel cycle, in relation to waste generation.

The process basket assembly is an important module in pyroprocess, because pyroprocess is a batch process, so process materials are contained in a basket assembly and transferred with the basket. The basket assembly is composed of upper and lower assembly. The lower assembly is a basket or crucible which contains process materials, and it can have electrodes. The upper assembly mainly consists of heat shields, a flange, and connectors for supplying currents to electrodes of the lower assembly. During the electrolytic recovery process, the lower part is submerged into molten salt, whose temperature is about 500°C at least and the heat from salt is transferred to the upper assembly. And the heat affects the performance or durability of parts on the top of equipment and can raise cell temperature, which is an undesired situation. In addition, the handling equipment can pick the assembly when it is hottest, and during the transfer, the gripped part is under thermal and mechanical stresses. Because of this, the thermal effects from the heat should be required during equipment design stage. In this study, the thermal analyses of process basket assembly were conducted for 3 cases: the steady state of the basket assembly when it submerged in molten salt, the thermal and mechanical stresses when gripped by remote handling device, and the temperature changes under natural convection. These analyses were performed using Solidworks with flow simulation package, and the results will apply to improve the thermal resistant performance of the basket assembly.

Modular construction is an economical and efficient construction that reduces time and costs by manufacturing units in factories and constructing them on site. Currently, the demand for modular construction is increasing not only abroad but also domestically. As the demand for modular construction increases, a lot of development and research on connections between modular units are being conducted. Connections between modular units should be quick and simple to assemble when assembling units on site, and should be in a form that allows each unit to be connected regardless of direction. In addition, it must be able to exert sufficient strength against external loads. In this study, a connection between modular units using connecting steel plates and bolts was proposed, and the nonlinear behavior of the connection to external lateral force was analyzed through finite element analysis, and resistance performance was evaluated.

Since SMR’s reduced reactor radius results in higher neutron leakage, SMR operates at a relatively lower discharge burnup level than traditional Light Water Reactors (LWRs). It may result in larger spent fuel amounts for SMRs. Furthermore, recent studies demonstrated that NuScale reactor will generate a significantly higher volume of low- and intermediate-level waste owing to components located near the active core including the core barrel and the neutron reflector. For spent nuclear fuel simulation, FRAPCON-4.0 was updated. Major modifications were made for fission and decay gas release, pellet swelling, cladding creep, axial temperature distribution, corrosion, and extended simulation time covering from steady-state to dry storage. In this study, typical 17×17 PWR fuel (60 MWd/kgU) and NuScale Power Module (36 MWd/kgU) was compared. NuFuel-HTP2™ fuel assembly, which has a half-length of proven LWR fuel, was employed. Owing to the lower discharge burnup and operating temperature, the maximum hydrogen pickup was 73 wppm and the maximum hoop stress was ~25 MPa. Therefore, hydride reorientation issue is irrelevant to SMR spent fuel. In this context, the current regulatory limit for dry storage (i.e. 400°C and 90 MPa) can be significantly alleviated for LWR-based SMRs. The increased safety margin for SMR spent fuel may compensate high spent fuel management cost of SMRs incurred by an increased amount. The comprehensive analysis on SMR spent fuel management implications are discussed based on simulated SMR fuel characteristics.

In addition to Korea, various countries such as the United States, the United Kingdom, France, and China are designing small module-type reactors. In particular, a small modular reactor is the power of 300 MWe or less, in which the main equipment constituting the nuclear reactor is integrated into a single container. Depending on the purpose, small modular reactors are being developed to help daily life such as power, heating supply, and seawater desalination, or for power supply such as icebreakers, nuclear submarines, and spacecraft propellants. Small modular reactors are classified according to form. It can be classified into light-water reactors/ pressurized light-water reactors based on technology proven in commercial reactors, and non-lightwater reactors based on fuel and coolant type such as Sodium-cooled Fast Reactor, High temperature gas-cooled reactor, Very high temperature reactor and Moltenn salt reactor. SMRs, which are designed for various purposes, have the biggest difference from commercial nuclear reactors. The size of SMRs is as small as 1/5 of that of the commercial reactors. Several modules may be installed to generate the same power as commercial reactors. Because of the individually operation for each module, load follow is possible. Also, The reactor can be cooled by natural convection because the size is small enough. It is manufactured as a module, the construction period can be reduced. Depending on the characteristics of these SMRs, application for safeguards is considered. There are many things to consider in terms of safeguards. Therefore, it is IAEA inspection or other approaches for SMRs installed and remotely operated in isolated areas, data integrity for remote monitoring equipment to prevent the diversion of nuclear materials, verification method and material accountancy and control for new fuel types and reactors. Since SMR is more compact and technical intensive, safeguards should be considered at the design stage so that safeguards can be efficiently and effectively implemented, which is called the Safeguards by design (SBD) in the IAEA. In this paper, according to the characteristics of SMR, we will analyze the advantages/disadvantages from the point of view of safeguards and explain what should be considered.

The purpose of this study is to evaluate seismic performances of a modular house system developed by a simple 4-clip fastening method and double metal assembly made of lightweight metals. In order to evaluate structural and non-structural seismic performances of the system. Shaking table test was carried out with full-scale modular units, and a nonlinear pushover analysis was performed to obtain suitable seismic responses for story drifts, displacements, force resistances and dynamic properties of the system. Through 3D analysis and shaking table test, the current method of lightweight modular metal unit assembly and systems with seismic performance of a 4-clip fastening type modular house were demonstrated safe and effective to seismic design.

다양한 수종의 묘목을 고밀도로 심는 모듈군락식재가 기존의 성목식재보다 자연림 복원 효과성이 뛰어난지 알고자 야외 실험을 했다. 또 모듈군락식재의 식재밀도 차이에 따라 생장이 촉진되는지, 또 식피율이 높아지는지를 알아보았다. 큰나무를 넓게 띄어 심는 성목식재구(대조구)와 다종의 묘목을 고밀도로 심는 모듈군락식재구(처리구)로 구분했고, 다시 식재밀도에 따른 3주/㎡와 1주/㎡ 모듈군락식재구로 나눠 실험을 설계했다. 2019년 5월부터 26개월간 공시재료의 생존율, 생장량(수고, 수관폭, 근원직경), 식피율을 측정했고, 측정 수고값을 활용하여 장래 수고생장을 예측했다. 모듈 군락식재구의 생존율과 상대생장량이 성목식재구보다 높았다. 모듈군락식재구의 식피율은 23개월 이전에 지표면을 완전히 덮었지만, 성목식재구는 이식스트레스로 인해 오히려 식피율이 낮아졌다. 고밀도로 심은 모듈군락식재구의 묘목이 자라서 식재 후 5∼6.5년 만에 성목식재구보다 더 높이 자랄 것으로 예측됐다. 이런 결과를 이끈 원인은 다종(多 種)·묘목·고밀도 식재와 토양개량·멀칭 등의 식재기반 개선 때문이라 본다. 즉, 모듈군락식재구에 심은 묘목은 큰나무를 심은 성목식재구보다 식재 후 환경 적응력이 뛰어나 생존율이 높고, 초기 생장량이 많았을 것이다. 다양한 자생수종의 고밀도 혼식은 상호보완적 환경압을 완화하는 동시에 개체간 경쟁을 유발해 생장 촉진을 이끌었다. 더불어, 식재기반 개선은 묘목의 활착율 상승과 생장량 증가에 유효했다고 본다. 식재밀도가 높을수록 식피율이 급격히 늘어나, 제초 등의 사후관리비 절감 효과가 있을 것이다. 모듈군락식재구(3주/㎡, 1주/㎡)의 식재밀도가 높았을 때 수고생장이 촉진되 었고, 수관폭·근원직경은 식재밀도가 낮았을 때 높아지는 경향을 보였지만, 통계적 차이가 없었다.

IAEA, in preparation for possible commercial operation of small modular reactors (SMR), is pursuing the early development of safeguards approaches for these reactors along with the publication of the safeguards technical report (STR) to make verification activities easier for inspectors. For this purpose, the IAEA, through the MSSP, is developing various approaches for the application of safeguards by design for SMRs in collaboration with five countries that along with the ROK includes Russia, China, and U.S. etc. In order to review the specific design information of the ROK’s only SMR facility, SMART, and to establish safeguards methods from the initial design stage, collaborations were made with the Korea Atomic Energy Research Institute, which researched and developed the SMART. As a result, the design information questionnaire (DIQ) and STR was created and sent to the IAEA. The DIQ is a collection of crucial questions regarding the application of safeguards to understand the characteristics of the reactor facility, and STR is a document referred to by IAEA inspectors during safeguards verification activities. The main contents of the STR consist of introduction, technological description of SMR, safeguards approach, conclusions and annexes. Through this study, it is anticipated to understand the technical requirements for safeguards implementation of SMRs in the design stage, and through the completion of the final report applying SBD with regards to the design of the SMART facility, it could be used as information material for future safeguard verification activities by IAEA inspectors.

본 논문에서는 유한요소해석을 통한 모듈러 구조물 접합부의 힌지접합부 연구에 관하여 소개한다. 모듈러 구조물은 모듈과 모듈을 적층하는 방식으로 공사를 진행하여 단위 모듈간의 기둥 및 보의 일체성을 기대하기 어려운 특성을 가지고 있다. 그러나 현 모듈러 설 계 시 이러한 구조적 특성을 무시하고 횡력에 대한 모멘트전달을 고려하여 기존 강구조와 동일한 방식으로 해석하고 있다. 더구나 모 멘트접합을 체결하기위해 모듈러 외부뿐만 아니라 내부에서 볼트 체결이 이루어져 조립 후 마감을 추가하는 불합리한 상황도 발생한 다. 이러한 일체성을 기대하기 어려운 특성을 고려하기 위하여 힌지접합을 활용한 모듈러구조시스템을 제안하였다. 논문에서는 기존 의 모멘트접합부에서 힌지접합부로 변경하였을 때 하중의 전달을 확인하기 위하여 이전 다른 연구에서 활용되었던 가위 모델을 변형 한 변형 가위 모델을 고안하여 접합부의 기본 이론을 제안·검토하였고, 기본을 바탕으로 계산된 결과는 구조해석 프로그램인 마이다 스 젠과 비교하여 검증하였다. 추가적으로 기존 모멘트접합부로 설계되었던 모듈러구조물을 힌지접합부로 변경하여 부재내력 및 사 용성을 검토하였다.

The Precast concrete(PC) modular structures are a method of assembling pre-fabricated unit modules in the construction site. The essential aim of modular structures is to introduce a connection method that can ensure splicing performance and effectively resist shear strength. This study proposed PC module using a connecting plate that can replace splice sleeves and shear keys used in the conventional PC modular structures. To evaluate the splicing performance and shear capacity of the proposed method, the shear test was conducted by fabricating one monolithic reinforced concrete(RC) beam and two PC modular beams with a shear span-to-depth ratio as variables. The experimental results showed that the shear capacity of the PC modular beam was about 89% compared to that of the RC beam, and showed a failure of the RC beam according to the shear span-to-depth ratio. Therefore, it was considered that the connecting plate effectively transferred the stress between each PC module through the joint and ensure integrity. In addition, the applicability of shear strength equation of ACI 318-19 and Zsutty's equation to PC modular beams were evaluated. Results demonstrated that the improved shear strength equations are needed to consider reduction of shear strength in PC modules.