To safely dispose of highly radioactive spent resin and concentrate waste generated through nuclear power plant operations, it is essential to meet the physicochemical properties requirements of the packages and ensure the accuracy and reliability of radiological characteristics determination. Both spent resin and concentrate are packaged in high-integrity containers (HICs) after drying and are homogeneous waste products generated in the primary system and liquid radioactive waste treatment system. Meeting the physicochemical properties requirements does not appear to be difficult. However, to achieve reliable radiological characterization of high-integrity container packages, it is necessary to take a representative sample and perform accurate radiological analysis. Therefore, this paper discusses the methodology for evaluating the radionuclide inventory of high radioactive resin and concentrate packages, as well as the essential element technology and considerations. For relatively high radioactive resin and concentrate packages, the radionuclide inventory for each package should be evaluated with high reliability through direct radiological analysis of the representative samples collected for each package. This can contribute to the efficient operation of radioactive waste disposal facilities. Radionuclide-specific concentrations directly analyzed for each package will be managed in a database. As analytical data accumulates and direct measurements of high-integrity container package such as the radwaste drum assay system (RAS) become feasible, statistical techniques such as correlation analysis between easy-tomeasure (ETM) nuclides and difficult-to-measure (DTM) nuclides can lead to the development of efficient and reasonable indirect evaluation methods, such as scaling factor and the mean activity concentration method. As for the element technology, a remote representative sampling technique should be developed to safely and effectively take representative samples of highly radioactive materials, including granulated or hardened concentrate waste. Considerations should also be given to determining the sample quantity representing each package, as well as establishing radiation calibration and measurement methods appropriate to the radiation levels of the representative samples.

Licensing for the application of the Polymer Concrete High Integrity Container (PC-HIC) to nuclear power plants has been completed or is in progress. Approval for the expanded application to all domestic nuclear power plants has been completed to utilize the 860 L PC-HICs for the 2nd stage surface repository, and the regulatory body is reviewing the license application to use the 510 L PCHICs for the 1st stage underground repository in the representative nuclear power plants. The 860 L PC-HICs, which have been licensed for all domestic nuclear power plants, will be used for safe storage management and disposal of low-dose dried concentrate waste and spent resin, and a total of 100 units is expected to be supplied to representative nuclear power plants that have been licensed first. The 510 L PC-HICs are planned to be used for underground disposal of high-dose spent resin and dried concentrate waste. Prior to the application of PC-HICs to nuclear power plants and disposal to the repository, it is necessary to establish realistic and reasonable requirements through close consultations between waste generator and disposal operators to ensure the suitability for disposal of PC-HIC packages and to carry out disposal delivery and acceptance work. Since the Polymer Concrete High Integrity Container (PC-HIC) has long-term integrity of more than 300 years and the barrier does not temporarily collapse, spent resin and dried concentrate waste, which are radioactive wastes to be solidified, can be disposed of much more safely in PC-HIC packages than solidified types. Acceptance criteria for the PC-HIC packages should be prepared fully reflecting the advantages of PC-HIC, and quality assurance methods for physical/chemical/radiological characterization results based on the Waste Certification Program (WCP) should be supported. In addition, infrastructure should be secured for safe transportation, handling, and storage of the PC-HIC packages. In this paper, we have tried to find a reasonable acceptance criteria, quality assurance method, and infrastructure level according to the dose and disposal conditions of PC-HIC packages.

Transport packages have been developed to transport the decommissioning waste from the nuclear power plant. The packages are classified with Type IP-2 package. The IAEA requirements for Type IP-2 packages include that a free drop test should be performed for normal conditions of transport. In this study, drop tests of the packages were performed to prove the structural integrity and to verify the reliability of the analysis results by comparing the test and analysis results. Half-scale models were used for the drop tests and drop position was considered as 0.3 m oblique drop on packages weighing more than 15 tons. The strain and impact acceleration data were obtained to verify the reliability of the analysis results. Before and after the drop tests, radiation shielding tests were performed to confirm that the dose rate increase was within 20% at the external surface of the package. Also, measurement of bolt torque, and visual inspection were performed to confirm the loss or dispersion of the radioactive contents. After each drop test, slight deformations occurred in some packages. However, there was no loss of pretension in the lid bolts and the shielding thickness was not reduced for metal shields. In the package with concrete shield, the surface dose rate did not increase and there was no cracks or damage to the concrete. Therefore, the transport packages met the legal requirements (no more than a 20% increase of radiation level and no loss or dispersion of radioactive contents). Safety verifications were performed using the measured strain and acceleration data from the test, and the appropriate conservatism for the analysis results and the validity of the analysis model were confirmed. Therefore, it was found that the structural integrity of the packages was maintained under the drop test conditions. The results of this study were used as design data of the transport packages, and the packages will be used in the NPP decommissioning project in the future.

Radioactive spent resin and concentrate waste powder generated from the primary system of nuclear power plants (NPPs) should be treated and disposed of in the form of solidified products or high integrity container (HIC) packages. We are preparing for the application of polymer concrete high integrity containers (PC-HICs) that has been approved for disposal and field application after going through the disposal suitability review of the repository operator and the license review process of the regulatory body. A reliable assessment of nuclide inventory in waste drum is required for the disposal of the radioactive waste drums, and the representative samples should be collected for both the indirect (non-destructive assessment based on the scaling factor, average radioactivity concentration, etc.) and direct (destructive analysis) evaluation of the difficult-to-measure (DTM) nuclides. It is important to secure the representativeness of samples for reliable and accurate evaluation of radionuclide inventory and approval of methodologies for highly radioactive waste such as spent resin and concentrate waste poser, and in order to secure the radiation safety of the sampling workers and representativeness of the samples, a remote sampling method is required with excellent convenience and safety and sufficient representativeness of the sample. The simple sampling device used in the past to collect samples for the scaling factor does not have a remote control function, so high-radiation samples must be collected within a very short time and it is difficult to obtain sufficiently representative samples due to structural characteristics that cannot collect the entire sample in the axial direction of the package. Therefore we developed concept designs for a remote sampling device that can satisfy both sample representativeness, operator convenience and safety.

High Integrity Container (HIC) made of polymer concrete was developed for the efficient treatment and safe disposal of radioactive spent resin and concentrate waste in consideration of the disposal requirements of domestic disposal sites. Permission for application of Polymer Concrete High Integrity Container (PC-HIC) to the domestic nuclear power plants (NPPs) has been completed or is under examination by the regulatory agency. In the case of 860 L PC-HIC for very-low-level-waste (VLLW) or low low-level-waste (LLW), the application of four representative NPPs has been approved, and the license for extended application to the rest NPPs is also almost completed. A licensing review is also underway to apply 510 L PC-HIC for intermediate and low-level-waste (ILLW) to representative nuclear power plants. In order to handle and efficiently store and manage PC-HICs and high-dose PCHIC packages, a gripper device that can be remotely operated and has excellent safety is essential, and the introduction of NPPs is urgent. The conventional gripper device developed by the PC-HIC manufacturer for lifting test to evaluate the structural integrity of PC-HIC requires a rather wide storage interval due to its design features, and does not have a passive safety design to handle heavy materials safely. In addition, work convenience needs to be reinforced for safety management of high radiation work. Therefore, we developed a conceptual design for a gripper device with a new concept to minimize the work space by reflecting on-site opinions on the handling and storage management conditions of radioactive waste in NPPs, and to enhances work safety with the passive safety design by the weight of the package and the function of checking the normal seating of the device and the normal operation of the grip by the detector/indicator, and to greatly improves the work efficiency and convenience with the wireless power supply function by rechargeable battery and the remote control function by camera and wireless monitoring & control system. Through design review by experts in mechanical system, power supply and instrumentation & control fields and further investigations on the usage conditions of PC-HICs, it is planned to facilitate preparations for the application of PC-HIC to domestic NPPs by securing the technical basis for a gripper device that can be used safely and efficiently and seeking ways to introduce it in a timely manner.

Marketers increasingly develop strategies to benefit from the potentials of the mobile internet and related technologies. Digitally enhanced product packaging is one prominent example for this evolution and QR (quick response) codes currently give this trend an appearance. QR codes enable manufacturers to provide consumers - despite the limited space on the product package - with comprehensive product information. And consumers increasingly request additional product information, for instance, to monitor environmental factors before purchasing products. Hence, while marketers nowadays regularly use QR codes on product packages to provide consumers with additional product information, they complain about the low usage rates and finally about the effectiveness of QR codes. Extant literature provides little guidance on consumer responses towards these marketing stimuli and, in particular, on how the mere presence of QR codes on product packages affects consumer behavioral and behavior-related responses. Existing research unexceptionally explores how marketers can motivate consumers to scan QR codes (Okazaki et al., 2012; Okazaki et al., 2017) and thus draws a one-sided picture of how marketers can benefit from QR codes. To enrich extant knowledge, this research uses information processing and environmental theory to offer insights into whether and how QR codes on product packages affect consumer product purchasing. The findings of an experimental study illustrate that QR codes affect consumer product purchases by inducing product- and vendor-related cognitive beliefs. In particular, the presence of QR codes on product packaging strengthens consumers’ perceptions about product quality and vendor innovativeness which then positively translate into purchase intentions. Hence, QR codes displayed on product packaging indirectly shape product purchasing. In sum, this research broadens the previous focus on usage-related outcomes by considering how and why QR codes affect consumer purchasing.

본 연구는 포장방법과 저장기간에 따른 국산대두와 연해주 대두의 이화학적인 특성을 조사하기 위하여 TBA test, 산가, POV, fluorescence spectrum test를 실시하였다. 저장 기간이 경과함에 따라 TBA test는 국산대두와 연해주 대두 모두 실험기간 내 포장방법에 따른 유의적인 차이는 있었으나 전체적인 경향은 차이가 없었다. 산가는 국산 대두에서 16일차에 유의미한 차이를 보였으나 20일차에서는 모두 유의차를 보이지 않는 것을 알 수 있었다. 연해주 대두의 경우 저장기간 동안 포장방법에 따른 차이가 없었다. POV의 경우 국산대두에서 저장 16일차까지 유의한 차이가 없었으나 진공포장 20일차에서 1.85 meq/kg oil로 값이 증가하였다. 연해주 대두에서는 초기값과 저장 20일차의 측정값이 10%내의 변화를 보이고 함기포장과 진공포장, 질소충진포장과의 유의차를 나타내지 않아 포장법에 의한 산패도의 차이를 찾아내지 못하였다. Fluorescence spectrum test를 이용한 측정에서는 국산 대두의 경우 같은 경향을 나타내었다. 연해주 대두의 경우도 저장방법 별 산패도 값의 차이는 존재하였지만 같은 경향을 나타내는 것을 알 수 있었다. 연구결과를 토대로 fluorescence spectrum test를 이용하여 산패도를 측정하는데 적합하다고 판단된다. 또한 요오드가, 검화가, 비중 측정을 통해 포장방법과 저장기간을 통한 변화를 측정하였으나 유의할 만한 차이를 나태내지 못하였다. 결과적으로 국산대두와 연해주대두의 저장기간 20일 동안의 산패도의 증가는 나타나지 않았고 포장방법에 따른 산패도의 차이는 없었다. 본 연구의 결과는 연해주산 대두를 수입할 경우 유통기한 중 질소충진과 같은 고비용의 포장법을 적용하지 않더라도 수입 시에 품질변화가 거의 이루어 지지 않음을 보여 주어 실질적으로 국내 소비자에게 연해주산 non-GMO 대두를 경제적으로 공급이 가능함을 보여주었다. 또한 20일의 저장기간 동안 변화가 매우 적음은 현재 대두의 분말가공에 시도되고 있는 집결지 최소가공방식의 최소가공량을 2-3배 확장하여 집결지에서 보다 많은 양을 가공 저장하여 수송함이 가능함을 보여 주고 있다. 이는 연해주대두의 경제적 활용가능성을 보다 높여 줄 것이라 판단된다.

IP-2형 운반용기는 정상운반조건에서의 자유낙하시험 및 적층시험을 수행한 후에 운반내용물의 분산 및 유실이 없어야 하며 외부표면에서의 방사선량률이 20%이상 증가할 수 있는 차폐능력의 상실이 없어야 한다. 본 연구에서는 두꺼운 철판을 구조재로 사용하며 볼트체결방식의 뚜껑을 가진 IP-2형 운반용기에 대한 구조 안전성을 평가하기 위한 해석적인 방안을 제안하였다. 해석적인 방법을 통하여 원자력발전소에서 발생된 방사성폐기물 드럼을 폐기물 처리시설에서 임시저장고까지 운반하기 위한 두 종류의 IP-2형 방사성폐기물 운반용기에 대하여 자유낙하조건에서 운반내용물의 분산 및 유실과 차폐손실이 없음을 확인하였다. 자유낙하조건에서 운반내용물의 분산 및 유실을 평가하기 위하여 최대 볼트단면 평균응력값과 최대 뚜껑열림량을 볼트의 인장강도와 뚜껑부에 존재하는 단차와 비교 평가하였다. 또한 최대 차폐두께 감소량을 이용하여 차폐손실을 평가하였다. 자유낙하조건에 대한 동적충돌해석을 검증하고 구조 안전성을 시험적으로 평가하기 위하여 자유낙하시험을 다양한 방향으로 실시하였다. 자유낙하시험에서는 운반내용물의 분산 및 유실은 볼트체결방식의 뚜껑에서 볼트의 파손 및 플랜지의 변형 등을 검사하여 평가하였으며, 차폐손실은 초음파 두께 측정기를 이용한 차폐두께를 측정하여 평가하였다. 해석에 대한 검증을 위하여 시험에서 취득한 변형률과 가속도를 동일한 위치에서 얻어진 해석결과와 비교하였다. 해석결과는 시험결과에 비하여 보수적인 결과를 보여주므로 해석에서 입증한 IP-2형 방사성폐기물 운반용기의 안전성은 보수적인 결과이다. 마지막으로 유한요소해석을 통하여 적층조건에 대한 IP-2형 방사성폐기물 운반용기는 안전함을 입증하였다. 적층해석에서 차폐체의 응력은 항복응력에 비하여 1/3정도의 작은 값을 보였다. 두 종류의 IP-2형 방사성폐기물 운반용기는 정상운반조건에서의 자유낙하시험 및 적층시험에 대하여 안전함을 입증하였다.

This paper investigates the importance and satisfaction levels according to factors on commercial Enterprise Resource Planning(ERP) packages in the view of end users when the ERP system is employed especially in SMEs, Considering the characteristics and f

This paper addresses the financial performance effect according to the implementation of SCM packages. Eight financial performance measures were selected based on the literature review. KIS-FAS2004 data on the fifteen companies that implemented SCM packages before December, 2003 were collected to test the effect of SCM implementation. The obtained experimental results show that there are some differences on financial performance measures between before and after the SCM implementation.

This paper proposes an evaluation methodology of commercial Enterprise Resource planning(ERP) packages in the view if end users when the ERP system is employed especially in SMEs. Considering the characteristics and functions of ERP packages, five factors(vendor, technology, function, A/S, price) are obtained based on the review of literature. The proposed evaluation procedure consists of several evaluation items and processes which support the selection of ERP packages for a certain SME. When a company tries to implement the ERP system, the proposed method suggests the suitable ERP package for its own business environment.

마이크로 머신 소자는 일반전자 소자와 달리 소자 자체에 미세한 기계적 구조물을 갖고 있으며, 이의 구동을 통하여 센서 또는 엑츄에이터의 기능을 갖게 된다. 이 소자들은 그 작동 요구특성에 따라 패키지의 기계적, 환경적 격리를 요구하거나 분위기조절이 요구되는 등 까다로운 패키지 특성을 필요로 한다. 또한 미세한 작동소자들로 인하여 열 및 열응력에 매우 민감하며, 패키지방법에 따라 구동부위의 작동 특성이 크게 변화할 수 있다. 본 연구에서는 마이크로 머신 소자가 패키지 상에 접촉되어 패키지 될 때, 소자의 접촉 재료 및 공정온도, 크기 등이 마이크로 머신 소자에 미치는 열응력을 연구하였다. 유한요소해석법을 사용하여 소자에 미치는 열응력과 이로 인한 마이크로머신 소자의 물리적 변형을 예측하고, 이를 통하여 마이크로 머신 소자 패키지에 최소한의 열응력을 미치는 소자접속 재료의 선별과 패키지 설계의 최적화를 이루고자 하였다.