Safeguards systems and measures are determined through diversion scenario analysis based on the facility design information submitted to the IAEA when a new nuclear facility is introduced. While the concept of safeguards-by-design (SBD), which considers the safeguards from the design phase for a facility operator to minimize unplanned changes or disruption to facility operations as well as for the IAEA to increase the efficiency and effectiveness in safeguards implementation, has been emphasized for more than a decade, there is no practical tool or guidance on how to apply it. In this study, we develop a diversion path analysis tool and introduce how to apply SBD using it. A diversion path analysis tool was developed based on the elements that constitute diversion and the algorithm generated based on the initial information of facility and nuclear material flow. The results of utilizing the analysis tool depending on a different level of facility information and the safeguards set-ups were compared through examples. Taking a typical light water reactor as an example, the test analyzed the automatic generation of dedicated routes, configuration of safeguards measures, and diversion path analysis. Through this, the application and limitations of the analysis tool are discussed, and ideas for utilization according to the SBD concept and necessary regulatory guidance are proposed. The results of this study are expected to be directly utilized to domestic nuclear control during the regulation process for a construction of new nuclear power systems, and furthermore, to enhance national credibility in the engagement with the IAEA for implementation of safeguards.

To evaluate the safeguards system or performance in a facility, it is crucial to analyze the diversion path for nuclear materials. However, diversion paths can range from the extremely simplified to the complicated depending on the level of knowledge and the specific person conducting the analysis. This study developed the diversion path analysis tools using an event tree and fault tree method to generating diversion paths systematically. The essential components of the diversion path were reviewed, and a logical flow was developed for systematically creating the diversion path. An algorithm was created based on the facility design components and logical flow, as well as the initial information of the nuclear materials and material flows. The event tree and fault tree analysis tools were used to test the path generation algorithm. The usage and limitations of these two logic methods are discussed, and ideas to incorporate the logic algorithm into practical program tools are suggested. The tests were analyzed on a typical light water reactor as an example, including automatic generation of dedicated pathways, configuration of safeguards measures, and analyzing paths with strategies for avoiding safeguard systems. The results led to the development of a draft pathway analyzer program that can be applied to general nuclear systems. The results of this study will be used to develop a program module that can systematically generate diversion paths using the event tree and fault tree method. It can help to guide and provide practical tools for implementing SBD.

The nuclide management technology for separating high-heat generating/high-mobility/long-lived nuclides from high-level wastes based on the chemical reactions is under development. In order to secure the reliability of nuclear non-proliferation and to implement the effective safeguards, it is necessary to consider the safeguards from the conceptual design phase of the novel technologies. However, there was no experience and research on safeguards for the chemical reaction based nuclide management technology. In order to development the available monitoring techniques for the safeguards of nuclide management technology, the possible diversion scenarios were developed and the material flows of major nuclear materials were analyzed according to the various diversion strategies for each unit process in this study. The diversion strategies in this study is limited to the diversion of nuclear materials according to the change of operational parameters (temperature, chemical reagents, pressures, etc). The nuclear material distribution behaviors under the abnormal conditions were analyzed and compared with normal conditions using the HSC Chemistry. The results will be used to determine the proper signals and feasible techniques to monitor the abnormal operations.

Even though it is emphasized to apply safeguards-by-design (SBD) concept in the early phase of the design of a new nuclear facilities, there is no clear guideline or tools for the practical SBD implementation. Generally known approach is trying to review whether there is any conflicts or shortcomings on a conceptual safeguards components in a design information. This study tries to build a systematic tools which can be easily applied to safeguards analysis. In evaluating the safeguards system or performance in a facility, it is essential to analyze the diversion path for nuclear materials. Diversion paths, however, can be either extremely simplified or complicated depending on the level of knowledge and purpose of specific person who do analyze in the field. In the context, this study discusses the applicability of an event tree and fault tree method to generating diversion paths systematically. The essential components constituting the diversion path were reviewed and the logical flow for systematically creating the diversion path was developed. The path generation algorithm based on the facility design components and logical flow as well as the initial information of the nuclear materials and material flows was test using event tree and fault tree analysis tools. The usage and limitation of the applicability of this two logic methods are discussed and idea to incorporate the logic algorithm into the practical program tools is suggested.The results will be used to develop a program module which can systematically generate diversion paths using the event tree and fault tree method.

The measurement activities to evaluate material balance of nuclear material are usually performed by operator. It is because that the IAEA does not have enough manpower to carry out nuclear measurement accountancy of all nuclear materials in the world. Therefore, the IAEA should consider scenarios which facility operator tries to divert nuclear material for misuse by distorting measurement record. It is required to verify the operator’s measurement data whether it is normal or not. IAEA measures inventory items using their own equipment which is independent of facility operator equipment for verification. Since all inventory lists cannot be verified due to limited resources, the number of items to be verified is determined through statistical method which is called as sample size calculation. They measure for the selected items using their own equipment and compares with operator’s record. The IAEA determines sample size by comprehensively considering targeted diverted nuclear material amount and targeted non-detection probability and performance of measurement equipment. In general, the targeted diverted nuclear material amount is considered significant quantity (plutonium: 8 kg, uranium-235: 75 kg). If the targeted non-detection probability or the performance of the verification equipment is low, the sample size increases, and on the contrary, in the case of high non-detection probability or good performance of verification equipment, even a small sample size is satisfied. It cannot be determined from a single sample size calculation because there are so many sample size combinations for each verification equipment and there are many diversion scenarios to be considered. So, IAEA estimates initial sample size based on statistical method to reduce calculation load. And then they calculate non-detection probability for a combination of initial sample size. Through the iteration calculation, the sample size that satisfies the closest to the target value is derived. The sample size calculation code has been developed to review IAEA’s calculation method. The main difference is that IAEA calculates sample size based on approximate equation, while in this study, sample size is calculated by exact equation. The benchmarking study was performed on reference materials. The data obtained by the code show similar results to the reference materials within an acceptable range. The calculation method developed in this study will be applied to support IAEA and domestic inspection activities in uranium fuel fabrication facility.

In order to effectively and efficiently apply safeguards to new nuclear facilities, it is recommended to apply safeguards-by-design concept. In evaluating the safeguards in the early stage of the design of a facility, it is essential to analyze the diversion path for nuclear materials. This study suggests a simple method which can generate diversion paths. The essential components constituting the diversion path were reviewed and the logical flow for systematically creating the diversion path was developed. The path generation algorithm is based on this components and logical flow as well as the initial information of the nuclear materials and material flows in a planned facilities. The results will be used to develop a program module which can systematically generate diversion paths using the event tree and fault tree method.

Pyroprocessing is a promising technology for managing spent nuclear fuel. The nuclear material accounting of feed material is a challenging issue in safeguarding pyroprocessing facilities. The input material in pyroprocessing is in a solid-state, unlike the solution state in an input accountability tank used in conventional wet-type reprocessing. To reduce the uncertainty of the input material accounting, a double-stage homogenization process is proposed in considering the process throughput, remote controllability, and remote maintenance of an engineering-scale pyroprocessing facility. This study tests two types of mixing equipment in the proposed double-stage homogenization process using surrogate materials. The expected heterogeneity and accounting uncertainty of Pu are calculated based on the surrogate test results. The heterogeneity of Pu was 0.584% obtained from Pressurized Water Reactor (PWR) spent fuel of 59 WGd/tU when the relative standard deviation of the mass ratio, tested from the surrogate powder, is 1%. The uncertainty of the Pu accounting can be lower than 1% when the uncertainty of the spent fuel mass charged into the first mixers is 2%, and the uncertainty of the first sampling mass is 5%.

본 조사는 채집방법에 따른 곤충군집을 비교하기 위해 공검지 습지보호지역 내에서 쓸어잡기, 함정트랩, 버킷트랩 세 가지 방법을 이용하였다. 조사 시기는 5월 15~16일, 8월 3~4일, 11월 6~7일 총 3회 실시하였으며, 조사는 보호지역 중심부에서 실시하였다. 본 연구결과 세 방법으로 총 7목 51과 110속 120종 14,717개체가 채집되었다. 채집방법별로 쓸어잡기에서 4목 25과 36속 37종 331개체, 함정트랩에서 3목 12과 18속 19종 30개체, 버킷트랩에서 6목, 38과 76속, 84종, 14,121개체가 조사되었다. 군집 분석결과 다양도 지수는 쓸어잡기가 3.63으로 가장 높게 나타났으며 풍부도 지수는 버킷트랩이 8.69로 가장 높게 나타났다. 유사도 지수는 세 방법이 서로 0.2이하로 매우 낮았다.

It has been said that amino acid transporters play an important role in supplying nutrition to normal and cancer cells and for cell proliferation. System L is a major nutrient transport system responsible for the Na+-independent transport of large neutral amino acids including several essential amino acids. In malignant tumors, a system L transporter L-type amino acid transporter 1(LAT1) is up-regulated to support tumor cell growth. In the present study, we have examined the function of LAT1 and its expression in the KB human oral epidermoid carcinoma cells. RT-PCR, western blot analysis and immunohistochemical analysis have revealed that KB cells express LAT1 in the plasma membrane together with its associating protein 4F2hc, whereas KB cells do not express the other system L isoform LAT2. The uptake of L-[14C]leucine by KB cells is Na+-independent and almost completely inhibited by system L selective inhibitor BCH. The profiles of the inhibition of L-[14C]leucine uptake by amino acids in the KB cells are comparable with those for the LAT1 expressed in Xenopus oocytes. The majority of L-[14C]leucine uptake is, therefore, mediated by LAT1 in the KB cells. These results suggest that the uptakes of neutral amino acids including several essential amino acids in the KB oral epidermoid carcinoma cells mediated by LAT1. In addition, specific inhibition of LAT1 by such agents as BCH in human oral squamous cell carcinomas will be a new rationale for anti-cancer therapy.

금속제련공학 및 환경과학 분야에 있어서 물질전체를 구성하고 있는 화학적 조성이 중요한 요소이나, 입자 표면의 화학조성과 미분화된 입자들의 표면 반응성을 제어함과 동시에, 입자 계면에서 일어나는 중금속과 유기물질등의 반응은 제련공정과 환경오염에 중요한 역할을 한다. 그러므로, 수용액상에 존재하는 여러 종류의 화학 물질과 광물입자 표면 사이에서 일어나는 계면반응 과정의 이해는 상당히 중요한 것이다. 일반적으로 입자 표면 분석에는 ex-situ 법을 사용하는 X-ray photo-electron spectroscopy (XPS) 분석 방법이 많이 적용되고 있으나, 이는 분석대상시료의 크기가 보통 100 마이크론에서 1 cm 정도의 범위 안에 혼재-혼합되어있는 고체 입자들을 분석하기 때문에 채취 분석된 X-ray의 원래 발산한 입자표면을 분석할 수는 없다. 그래서 본 연구에서는 Time-of-Flight Secondary-Ion Mass Spectroscopy (TOF-SIMS)를 응용하여 황화광물의 부유선광 공정 중 생성된 미세한 유화광물입자(30~75 microns) 표면에 형성된 무기, 유기물의 반응 관찰을 통해 이들의 정성분석 및 상대적 정량분석법을 연구하고자 하였다.