In this research, a detailed analysis of the decay heat contributions of both actinides and non-actinides (fission fragments) from spent nuclear fuel (SNF) was made after 50 GWd·tHM−1 burnup of fresh uranium fuel with 4.5% enrichment lasted for 1,350 days. The calculations were made for a long storage period of 300 years divided into four sections 1, 10, 100, and 300 years so that we could study the decay heat and physical disposal ratios of radioactive waste in medium- and long-term storage periods. Fresh fuel burnup calculations were made using the code MCNP, while isotopic content and then decay heat were calculated using the built-in stiff equation solver in the MATLAB code. It is noted that only around 12 isotopes contribute more than 90% of the decay heat at all times. It is also noted that the contribution of actinides persists and is the dominant ether despite decreasing decay heat, while the effect of fission products decreases at a very rapid rate after about 40 years of storage.

MEPC 80차 회의에서 IMO는 더욱 강화된 온실가스 감축 전략을 제시하였다. 기존의 72차 회의에서 제시하였던 초기전략보다 구체적이고 강화된 감축 전략이다. IMO는 2050년 무렵까지 국제 해운으로부터 온실가스 배출을 ‘Net Zero’에 도달하도록 전략을 세웠다. 이 논문에서는 대표적인 친환경 연료로 구분되는 LNG, 수소, 메탄올, 암모니아의 위험도 평가를 진행하였다. 전문가들의 설문조사를 통한 결과를 퍼지 기법을 적용하여 주관적인 모호성을 해결하였다. 또한 TOPSIS 기법을 통해서 퍼지의 긍정적인 해와 부정적인 해를 도출하였 다. 이를 통해서 Vertex 방법을 이용하여 대체 연료의 근접계수 값을 최종적으로 구하여 결정하였다. 그 결과, 메탄올, LNG, 수소, 암모니 아 순으로 선호하였다. 이 연구는 제안된 접근 방식이 대체 연료를 결정을 위한 집단 의사결정 방법으로 이용할 수 있음을 보여준다.

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.

The objectives of this paper are: (1) to conduct the thermal analyses of the disposal cell using COMSOL Multiphysics; (2) to determine whether the design of the disposal cell satisfies the thermal design requirement; and (3) to evaluate the effect of design modifications on the temperature of the disposal cell. Specifically, the analysis incorporated a heterogeneous model of 236 fuel rod heat sources of spent nuclear fuel (SNF) to improve the reality of the modeling. In the reference case, the design, featuring 8 m between deposition holes and 30 m between deposition tunnels for 40 years of the SNF cooling time, did not meet the design requirement. For the first modified case, the designs with 9 m and 10 m between the deposition holes for the cooling time of 40 years and five spacings for 50 and 60 years were found to meet the requirement. For the second modified case, the designs with 35 m and 40 m between the deposition tunnels for 40 years, 25 m to 40 m for 50 years and five spacings for 60 years also met the requirement. This study contributes to the advancement of the thermal analysis technique of a disposal cell.

A transfer cask serves as the container for transporting and handling canisters loaded with spent nuclear fuels from light water reactors. This study focuses on a cylindrical transfer cask, standing at 5,300 mm with an external diameter of 2,170 mm, featuring impact limiters on the top and bottom sides. The base of the cask body has an openable/closable lid for loading canisters with storage modules. The transfer cask houses a canister containing spent nuclear fuels from lightweight reactors, serving as the confinement boundary while the cask itself lacks the confinement structure. The objective of this study was to conduct a structural analysis evaluation of the transfer cask, currently under development in Korea, ensuring its safety. This evaluation encompasses analyses of loads under normal, off-normal, and accident conditions, adhering to NUREG-2215. Structural integrity was assessed by comparing combined results for each load against stress limits. The results confirm that the transfer cask meets stress limits across normal, off-normal, and accident conditions, establishing its structural safety.

With South Korea increasingly focusing on nuclear energy, the management of spent nuclear fuel has attracted considerable attention in South Korea. This study established a novel procedure for selecting safety-relevant radionuclides for long-term safety assessments of a deep geological repository in South Korea. Statistical evaluations were performed to identify the design basis reference spent nuclear fuels and evaluate the source term for up to one million years. Safety-relevant radionuclides were determined based on the half-life criteria, the projected activities for the design basis reference spent nuclear fuel, and the annual limit of ingestion set by the Nuclear Safety and Security Commission Notification No. 2019-10 without considering their chemical and hydrogeological properties. The proposed process was used to select 56 radionuclides, comprising 27 fission and activation products and 29 actinide nuclides. This study explains first the determination of the design basis reference spent nuclear fuels, followed by a comprehensive discussion on the selection criteria and methodology for safety-relevant radionuclides.

In this study, the impact load resulting from collision with the fuel rods of surrogate spent nuclear fuel (SNF) assemblies was measured during a rolling test based on an analysis of the data from surrogate SNF-loaded sea transportation tests. Unfortunately, during the sea transportation tests, excessive rolling motion occurred on the ship during the test, causing the assemblies to slip and collide with the canister. Hence, we designed and conducted a separate test to simulate rolling in sea transportation to determine whether such impact loads can occur under normal conditions of SNF transport, with the test conditions for the fuel assembly to slide within the basket experimentally determined. Rolling tests were conducted while varying the rolling angle and frequency to determine the angles and frequencies at which the assemblies experienced slippage. The test results show that slippage of SNF assemblies can occur at angles of approximately 14° or greater because of rolling motion, which can generate impact loads. However, this result exceeds the conditions under which a vessel can depart for coastal navigation, thus deviating from the normal conditions required for SNF transport. Consequently, it is not necessary to consider such loads when evaluating the integrity of SNFs under normal transportation conditions.

The electrification of transportation is expected to greatly contribute to achieving the global climate change target. This study analyzed technological competitiveness in the fuel cell electric vehicle (FCEV) field based on patent family and citation index. Technology analysis was conducted by dividing FECV into six sub-technology areas based on IPC with fuel cell system, fuel cell technology, vehicle system, hydrogen storage and fueling, catalyst technology and etc. The largest number of patents are being filed in the fuel cell system technology field, and the fields with high growth rates over the past 10 years (2012-2022) were vehicle systems (12.4%) and hydrogen storage fuel field(11.5%). As of 2021, among global automakers, Toyota ranks the first in patent applications for FECV followed by Hyundai Motors in Korea, followed by Honda and Audi, with an average annual growth rate of 19.8%, the highest among competitors.

This study was conducted to analyze the effects of stand density on fire fuel (FF) changes in a Chamaecyparis obtusa forest. The study site was located in Mt. Munsu in Jeollabuk-do and consisted of a control, 30% thinning treatment (LT), and 50% thinning treatment (HT). Three-year-old seedlings were planted at a density of 3,000 trees ha-1 in 1976, and thinning was carried out in 2000. FF production was measured every 2 months by installing 3 circular litter traps 1.2 m above the ground. Litter bags containing 5 g of each leaf and branch were made and buried in the organic layer to investigate the FF decomposition rate. The decay constant was calculated after 18 months. FF accumulation was measured by collecting dry-weight organic matter from each plot using a square frame (0.09 m2) in September 2018. The FF production in LT and HT was significantly lower than that of the control (P<0.001). The leaf decay constant for HT was significantly lower than that of the control (P<0.05). The FF accumulation in HT was significantly lower than that of the control (P<0.01), but LT was not significantly different from the control. The results of this study showed that thinning decreased FF production.

본 연구에서는 산화 방지 특성이 있는 가리워진 아민기를 함유한 산화 그래핀(hindered amine grafted graphene oxide, HA-GO)을 합성하여 이를 도입한 나피온(Nafion) 기반의 복합 막을 제조한 후 고분자 전해질 막 연료전지 시스템에 응용하였다. HA-GO는 4-아미노-2, 2, 6, 6-테트라메틸-4-피페리딘(4-amino-2, 2, 6, 6-tetramethyl piperidine)에 존재하는 아민 기와 GO 표면에 존재하는 에폭시기의 개환 반응을 통해 제조하였으며, 합성된 HA-GO의 함량을 달리한 복합 막을 제조하여 순수 Nafion 막과 성능 특성을 비교하였다. HA-GO가 첨가된 복합 막은 Nafion 단일 막에 비해 기계적 물성, 화학적 안정성 및 수소이온 전도 특성이 향상되었다. 특히 HA-GO의 산화 방지 특성으로 인해 HA-GO가 첨가된 복합 막은 펜톤 평가 (Fenton’s test) 이후 수소이온 전도도의 유지 특성이 Nafion 단일 막에 비해 큰 폭으로 향상된 것을 확인할 수 있었다.

직접 메탄올 연료전지(direct methanol fuel cell, DMFC)는 연료의 개질 없이 메탄올 연료를 공급하여 수소이온과 전자 생성을 통해 전류를 생산하는 에너지 변환 장치이다. 현재 DMFC에 적용되고 있는 고분자 전해질 막(polymer electrolyte membrane, PEM)은 높은 수소이온 전도도와 물리화학적 안정성을 갖는 과불소화계 이오노머를 활용한 PEM이지만, 높 은 메탄올 투과율과 분해 시 발생되는 환경 오염 물질 등의 문제로 인해 신규 소재 개발이 요구되고 있다. 최근 들어, 과불소 화계 이오노머에 비해 낮은 연료 투과율 및 우수한 물리화학적 안정성을 갖는 탄화수소계 고분자 기반 PEM을 DMFC에 적 용하는 연구들이 보고되고 있다. 본 총설에서는 탄화수소계 고분자 기반 PEM 중 1) 친수성/소수성 영역의 뚜렷한 나노 상분 리 구조를 나타내는 가지형 공중합체를 합성하여 수소이온 전도성과 메탄올의 선택도를 향상시킨 연구, 2) 제막 단계에서 가 교 구조를 도입하여 메탄올 투과율을 감소시키고 치수 안정성을 향상시킨 연구, 3) 유/무기계 첨가제 및 다공성 지지체를 도 입하여 성능을 개선한 복합 막 개발 연구에 대해 소개하고자 한다.

폴리벤즈이미다졸(PBI) 기반의 막은 내구성이 우수한 네트워크 구조를 가지는 구조재료로서의 우수한 강성과 더 불어서 고온에서의 우수한 내열성, 우수한 기계적 및 인장 특성, 높은 유리전이온도(Tg), 물이 없는 무수 환경에서의 이온 전 도성능, 산화와 화학적 내구성으로 지난 20년 동안 다양한 용도의 대중적인 막 재료로 다양한 문헌에서 보고되어 왔다. 이온 전도성 PBI 기반 막은 고온용 양이온 교환막 연료 전지(HT-PEMFC)에서 광범위하게 사용되어왔다. 또한 PBI 기반 막은 독 특한 특성으로 인해 기체분리막 및 유기용매나노여과(OSN) 막 개발에서 광범위하게 사용되어왔다. 이번 리뷰에서는 고온용 연료전지, 기체분리 및 OSN 적용을 위한 다양한 유형의 PBI 기반 막의 최근 연구동향 및 적용가능성에 대해 설명하고자 한다.