The Korea Research Institute of Standards and Science has developed certified reference materials (concrete, soil, and metal radioactive liquid) for measuring gamma-emitting radionuclides to improve and maintain the quality assurance and quality control of the radioactivity measurement in decommissioning nuclear power plants. The raw materials that make up each CRM were mixed in an appropriate ratio with radionuclides. For certification and homogeneity assessment, 10 bottles were randomly selected, two sub-samples were collected from each bottle, and radionuclides were measured via HPGe gamma spectrometry. The results of the homogeneity tests using a one-way analysis of variance on the radionuclides in the CRMs fulfilled the requirements of ISO Guide 35. Coincidence summing and self-absorption correction were performed on measurement results by introducing the Monte Carlo efficiency transfer code and Monte Carlo N-Particle transport code. In concrete analysis, the reference values for five radionuclides (60Co, 241Am, 134Cs, and 137Cs) in the CRM were in the range of 15-40 Bq/kg, and the expanded uncertainty was within 10% (k = 2). In soil analysis, the reference values for the 137Cs and 60Co were 118.7 and 124.4 Bq/kg, and the expanded uncertainty was within 10% (k = 2). In metal radioactive liquid analysis, the reference values for 134Cs, 137Cs and 60Co in the CRM were in the range of 200-270 Bq/kg, and the expanded uncertainty was within 7% (k = 2).

Spent nuclear fuel management is a high-priority issue in South Korea, and addressing it is crucial for the country’s long-term energy sustainability. The KORAD (Korea Radioactive Waste Agency) is leading a comprehensive, long-term project to develop a safe and effective deep geological repository for spent nuclear fuel disposal. Within this framework, we have three primary objectives in this work. First, we conducted statistical analysis to assess the inventory of spent nuclear fuel in South Korea as of 2021. We also projected future generation rates of spent nuclear fuels to identify what we refer to as reference spent nuclear fuels. These reference spent nuclear fuels will be used as the design basis spent fuels for evaluating the safety of the repository. Specifically, we identified four types of design basis reference spent nuclear fuels: high and low burnup from PLUS7 (with a 16×16 array) and ACE7 (with a 17×17 array) assemblies. Second, we analyzed radioactive nuclides’ inventory, activities, and decay heats, extending up to a million years after reactor discharge for these reference spent nuclear fuels. This analysis was performed using SCALE/TRITON to generate the burnup libraries and SCALE/ORIGEN for source term evaluation. Third, to assess the safety resulted from potential radioactive nuclides’ release from the disposal canister in future work, we selected safety-related radionuclides based on the ALI (Annual Limit of Intake) specified in Annex 3 of the 2019-10 notification by the NSSC (Nuclear Safety and Security Commission). Conservative assumptions were made regarding annual water intake by humans, canister design lifetime, and aquifer flow rates. A safety margin of 10-3 of the ALI was applied. We selected 56 radionuclides that exceed the intake limits and have half-lives longer than one year as the safety-related radionuclides. However, it is crucial to note that our selection criteria focused on ALI and half-lives. It did not include other essential factors such as solubility limits, distribution coefficients, and leakage processes. So, some of these nuclides can be removed in a specific analysis area depending on their properties.

근래들어 미중 간의 기술패권 경쟁이 심화됨에 따라 미국은 중국의 첨 단반도체 기술의 발전을 저지하기 위한 다양한 경제적, 기술적 제재를 부과하고 있다. 최근에는 반도체산업의 글로벌 밸류체인(GVC, 가치사슬) 의 변동성 증대와 더불어, 미국 주도로 주요 반도체 생산국가들인 한국, 대만, 일본을 포함한 칩포(Chip-4) 동맹을 결성하기 위한 논의를 하고 있다. 물론 이러한 미중 간의 첨단기술 경쟁은 우리나라의 산업전반 특 히, 중국에 생산기지를 가지고 중국의 수요에 많이 의존하고 있는 우리 나라 반도체 산업에도 큰 영향을 미치지 않을 수 없다. 따라서 미중 간 반도체산업 분야의 기술경쟁 실태를 면밀하게 분석하고, 이를 토대로 우 리의 국익을 극대화할 수 있는 방안을 모색하는 것이 절실하다. 이러한 배경 하에서, 본 논문은 반도체산업을 중심으로, 현재 미중 간에 벌어지 고 있는 기술패권 경쟁에서 미국과 중국은 각기 어떠한 위치를 점하고 어떠한 전략을 구사하고 있는지를 분석하고, 이를 토대로 이러한 미중 간 기술경쟁이 우리나라 반도체산업에 미칠 영향을 점검하고 적절한 대 응방안을 모색하고자 하는 것이다.

Internal reference price (IRP) is conceptualized as ‘a dynamic, internal price to which individuals compare the offered price of a product or service’. For this internal price, multiple conceptualizations and operationalizations have been proposed. This study finds heterogeneity in the use of reference price cues when consumers form an IRP and stablishes that seven distinct segments with different approaches can be can be distinguished.

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.

As if the wet storage of Spent Nuclear Fuel (SNF) becomes saturated, a transition from wet storage to dry storage could be required. The first process for dry storage is to move SNF from the wet storage into a canister for dry storage, and secondly perform a drying process to remove the moisture in the canister to prevent a potential impact such as deterioration of cladding or corrosion of the interior material. Nuclear Regulatory Commission (NRC) accepts the conditions describing the adequate dryness state that remain below the pressure of 3 Torr for 30 minutes in the drying process. That is, the most pressure of water vapor that may exist inside the canister is 3 Torr. If it is maintained below 3 Torr, it can be determined that the dryness criterion is satisfied. Based on this, relative humidity and dew point trends can be identified. Relative Humidity (RH) is calculated by dividing the vapor pressure by the saturated vapor pressure. Here, if the vapor pressure is fixed at 3 Torr, which is the dryness criterion value, the relative humidity has a value according to the saturated vapor pressure. Saturated vapor pressure is a value that varies with temperature, so relative humidity varies with temperature. On the other hand, the dew point temperature has a value according to the water vapor pressure. Therefore, when the internal temperature of the canister is 120°C and the water vapor pressure is 3 Torr, the relative humidity is 0.2% and the dew point temperature is -4.4°C. We will confirm the suitability of the dryness criterion through the drying tests, and secure a technology that can measure and evaluate the amount of moisture remaining inside the canister.

It is difficult to conduct an on-site investigation of Kaesung since it's located in North Korea. After the devastating Korean civil war we have lost a lot of authentic structures. At present, the statement of those who have seen the Kaesung during the time would be of great help in bringing out the significance of this study. According to Ma Hae-song, who was a local in Kaesung. He vividly remembered how his neighborhood looks like and he even mentioned the every single detail of his house in his essay. Moreover he also compared the traditional Han-ok in the former time from the household of other countries. There was an extraordinary interest and insight in Han-ok. This study estimated Ma hae-song's Gaesuong house based on Ma hae-song's personal and supplementary records. the contents by exchanging e-mails with his eldest son, poet Ma Jong-ki. Through the above process, it was confirmed that the writer Mahae Song's Gaeseong House was a typical wealthy merchant's house located in Donghaerang, a luxury residential area, and was engaged in commerce.

청동기시대 전기의 방형계 주거지는 당시 사회의 가족 구성의 결과물이며, 그 형태적 변이는 가족 의 발달과정에 기인하는 것으로 이해되기도 한다. 또한, (세)장방형 주거는 복수의 방형(단위)주거가 병렬적으로 연결된 형태이며, 그 단위주거는 핵가족의 주거공간이라는 추정 또한 널리 퍼져 있다. 그러나 많은 연구자들이 장단비가 시간성을 반영한다는 관행적 판단에 기초하여, 한 유적에서 공존 하는 장방형 주거지와 방형 주거지의 관계를 단지 시기적 차이로 해석함에 따라 주거의 변이에 대한 여러 요인―가족의 발달에 따른 주거 규모의 변화, 주거의 사용(신축과 증ㆍ개축)과 폐기 등―의 이 해를 저해하는 문제를 야기하게 되었다. 본고는 이러한 문제의 극복을 위해, 한강 하류역 청동기시대 전기 취락 유적들의 양상을 분석한 기 초자료를 바탕으로 가족 형태와 가구 양상 변화를 연결할 수 있는 고고학적 설명모형을 통해 가구발 달주기에 대한 인식이 한강 하류역 청동기시대 전기 주거 양상의 역동적 측면을 이해할 수 있는지를 살펴보았다. 주거지 간 중복양상이나 절대연대가 모호한 상황에서 주거지 평면 형태에 주목하는 기존의 편년관 안에서는 한강 하류역 청동기시대 전기 주거 양상을 역동적으로 설명하기 어렵다고 판단된다. 따라서 결합주거지를 고정된 문화적 실체로 파악하고 주거의 형태 차이를 양식적 차이로 이해하기보다는 가 족의 성장에 따른 주거 규모의 변이라는 기능적 측면을 상정해 보는 것이 합리적일 것으로 보인다.

The ovary undergoes substantial physiological changes along with estrus phase to mediate negative/positive feedback to the upstream reproductive tissues and to play a role in producing a fertilizable oocyte in the developing follicles. However, the disorder of estrus cycle in female can lead to diseases, such as cystic ovary which is directly associated with decline of overall reproductive performance. In gene expression studies of ovaries, quantitative reverse transcription polymerase chain reaction (qPCR) assay has been widely applied. During this assay, although normalization of target genes against reference genes (RGs) has been indispensably conducted, the expression of RGs is also variable in each experimental condition which can result in false conclusion. Because the understanding for stable RG in porcine ovaries was still limited, we attempted to assess the stability of RGs from the pool of ten commonly used RGs (18S, B2M, PPIA, RPL4, SDHA, ACTB, GAPDH, HPRT1, YWHAZ, and TBP) in the porcine ovaries under different estrus phase (follicular and luteal phase) and cystic condition, using stable RG-finding programs (geNorm, Normfinder, and BestKeeper). The significant (p < 0.01) differences in Ct values of RGs in the porcine ovaries under different conditions were identified. In assessing the stability of RGs, three programs comprehensively agreed that TBP and YWHAZ were suitable RGs to study porcine ovaries under different conditions but ACTB and GAPDH were inappropriate RGs in this experimental condition. We hope that these results contribute to plan the experiment design in the field of reproductive physiology in pigs as reference data.

As Kori-1 permanently shut down in Korea, it is expected that a large amount of radioactive waste will be generated during decommissioning of nuclear power plants. Radioactive concrete waste is contaminated up to depth of 100 mm with radionuclides such as 137Cs and 60Co. The radioactive waste should be accurately classified to reduce the cost of disposing of radioactive waste. Therefore, the specific radioactivity of waste must be precisely evaluated by gamma-ray measurements emitted from the radionuclides. In general, the effectiveness of the radioactivity measurement and process is confirmed using certified reference material (CRM) composed of water or agar. However, the decommissioning waste differs from this CRM in apparent density and chemical elements, so the specific radioactivity is underestimated or overestimated. Therefore, reference material composed of the same apparent density and chemical elements as the sample is required to improve the quality of radioactivity measurement. The purpose of this study is to develop a concrete reference material for the nuclear decommissioning waste. The concrete reference material composed of SiO2, CaO, and Al2O3 were manufactured in compliance with ISO Guide 35. 10 bottles were randomly selected for homogeneity test, and 2 samples for analysis were taken from each bottle. The specific radioactivity was measured using an HPGe detector with an efficiency of 30%. The results of the homogeneity test of 137Cs and 60Co satisfied the requirements of ISO Guide 35. Coincidence summing and selfabsorption effects were corrected using the Monte Carlo efficiency transfer code and Monte Carlo NParticle transport code. The reference values of 137Cs and 60Co in the concrete reference material were evaluated in the range of 1,000–1,100 Bq·kg−1 and extended uncertainty was around 7%.

The research for the safe management of high-level waste in Korea has been conducted by the Korea Atomic Energy Research Institute since 1997, and the results have formed the basis of the national basic plan for the high-level waste management and the revised national basic plan. In the future, it is evolving and developing R&D focusing on securing technologies for demonstration of the disposal technologies and R&D to develop disposal concepts that increase safety and improve efficiency. Efficient management of heat generated from high-level radioactive waste, including spent nuclear fuel, is an important factor in establishing the disposal concepts because it must be in harmony with key factors such as repository layout, waste disposal container specifications, and design and operation for the barriers of the disposal system. For safe and complete isolation of highlevel radioactive waste in the deep geology, the disposal systems 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. These disposal systems were based on low burn-up spent nuclear fuel characteristics generated in the early stages of nuclear power generation, and next, based on the high-level wastes from recycling process of the high burn-up spent nuclear fuels, and were the direct disposal systems for the high burn-up spent nuclear fuels. So, it is necessary to track and analyze the change process in the decay heat characteristics of the high-level waste to be disposed of in order to improve the disposal concept, which enhances the safety of disposal and the utilization of the national land. Therefore, in this paper, the process of change in decay heat of reference spent nuclear fuels for disposal applied to the disposal concepts from the initial stage of development of high-level waste disposal technology to the present in Korea is analyzed.

NFDC (Nuclear Fuel and materials Data Center) developed standard reference data for oxidation of HANA-6 cladding material. Thermo-gravimetric analyzer (TGA) was used to measure oxidation, and the measuring device was self-calibrated using standard materials. The oxidation amount of the HANA6 cladding was measured in an oxidizing atmosphere in the temperature range of 400 to 700°C. Through this, oxidation data, oxidation rate model equation, and graph were developed. The uncertainty factors were analyzed from the oxidation model. The expanded uncertainty of oxidation data was calculated by evaluating the uncertainty for each uncertainty factor. The oxidation data produced in this study was self-rated through deliberation by a specialized committee of NFDC and third experts. It was finally registered as a reference standard through the technical committee of the National Reference Standards Center. It is believed that the standard reference data developed in this study will be helpful for increasing reliability and stability evaluation of nuclear fuel and spent fuel.

The present research examines the fairness of the liability of ‘total’ in absentia trials within three specific circumstances. First: the accused is given sufficient notice of the trial and their right to decline to be present. Second: the accused must have a defence counsel advocating them in the trial. Third: the accused’s absolute right to re-trial should be protected once the judgment has been passed in absentia. The main research question to discern the hypothesis is that the accused can be tried in absentia under international criminal tribunals. Therefore, the focus is on answering which procedural scenarios could be counted as “an absence of the defendant.” The present research questions will be analyzed by examining the practice of the Special Tribunal for Lebanon (STL), its theoretical safeguards enshrined in the Statute, and the legal standards from human rights bodies’ jurisprudence.