There is a large amount of radioactive waste in waste storage in the Korea Atomic Energy Research Institute. Some of the radioactive waste was generated during the dismantling process due to Korea Research Reactor 1&2 and it accounts for 20% of the total waste. Radioactive waste must be reduced by appropriate disposal methods to secure storage space and to reduce disposal costs. Research Reactor wastes include wastes that are below the acceptable criteria for selfdisposal and non-contaminated wastes, so they can be treated as wastes subject to self-disposal through contamination analysis and reclassification. In order to deregulation radioactive waste, it is necessary to meet the self-disposal standards stipulated in the Domestic Nuclear Act and the treatment standards of the Waste Management Act. The main factors of deregulation are surface contaminant, radionuclide activity and dose assessment. To confirm the contamination of waste, surface contaminant and gamma nuclide analysis were performed. After homogenizing the waste sample, it was placed in 1 L Mariinelli beaker. When collecting waste samples, 1 kg per 200 kg of waste was collected. The concentrations of the major radionuclides Co-60, Cs-134, Cs-137, Eu-152, and Eu-154 were analyzed using HPGe detector. To evaluate radiation dose, various computational programs were used. A dose assessment was performed with the analyzed nuclide concentration. The concentrations of representative nuclides satisfied the deregulation acceptance criteria and the results of the dose assessment corresponding to self-disposal method was also satisfied. Based on this results, KAERI submitted the report on waste self-disposal plan to obtain approval. After final approval, Research Reactor waste is to be incinerated and incineration ash is to be buried in the designated place. Some metallic waste has been recycled. In this study, the suitability of deregulation for self-disposal was confirmed through the evaluation of the surface contaminant analysis, radionuclide concentration analysis and dose assessment.

Since the National R&D Innovation Act was enacted in 2022, it became a crucial issue how to qualify or improve R&D activities and disseminate their outcomes. Many organizations have referred to various quality management standards such as the American National Standards Institute/American Society for Quality (ANSI/ASQ) Z1.13, International Organization for Standardization (ISO) 9001, and the American Society of Mechanical Engineers Nuclear Quality Assurance-1 (ASME NQA-1), as a means to set up their own quality system. ISO is the international standard for implementing a quality management system (QMS), which provides a framework and principles for managing an organization’s QMS, with the aim of ensuring that the organization consistently provide products or services that meet regulatory requirements. ISO 9001 can cover all aspects of an organization’s operations, and it can also be expanded to include R&D areas. The introduction of ISO 9001 to R&D aims to improve R&D practices and establish a standardized process framework for conducting R&D. ANSI/ASQ Z1.13 provides quality guidelines for research and consists of 10 sections covering various aspects of research quality, emphasizing ethical conduct, clear objectives, reliable data collection, and analysis. ASME NQA-1 is one of quality assurance standards for nuclear facility applications, but it has been extended and applied to R&D activities in the nuclear fields. It just focuses on planning, procedures, documentation, competence, equipment, and material control. KINAC has conducted extensive research on verifying and regulating nuclear activities while providing support for national nonproliferation technologies and policies. In addition to the quantitative growth achieved so far, efforts are being made to establish a qualitative and integrated management system. As a first step to achieve this goal, this study reviewed international standards and methodologies for research quality and derived the key components for R&D quality management. Moreover, the appropriate outline of quality management system framework was proposed for R&D as a regulatory support process, based on the ISO 9001. The implementation of quality management standards and procedures for R&D in KINAC, which could lead to improved research practices, more reliable data collection and analysis and increased efficiency in conducting R&D activities.

In KAERI, Waste storage facility in the radiation management area has stored a large amount of wood waste. The amount of waste is approximately 27,000 kg, it accounts for 17% of the total waste in waste storage facility. Proper disposal of wood waste improves the fire resistance performance, secure storage space and reduce disposal costs. In order to self-disposal of wood waste, it is necessary to satisfy the self-disposal standards stipulated by the domestic Atomic Energy Act and the treatment standards of the Waste Management Act. The main factors of standards are surface contaminant, radionuclide activity and radiation dose effects. To confirm the contamination of wood waste, direct indirect measurement methods and gamma nuclide analysis were performed. To evaluate radiation dose, various computational programs were used. The results of the analysis were satisfied with domestic regulations on the classification and self-disposal of radioactive wastes. Based on this results, KAERI submitted the report on wood waste self-disposal plan to obtain approval. After final approval, wood waste is to be incinerated and incineration ash is to be buried in the designated place. The objective of this study is to provide total procedure of wood waste self-disposal and effective representative sampling method.

본 연구는 병풀의 초음파 추출 시 용매에 따른 면역활성 증진 효과를 탐색하고자 수행되었다, 각 추출공정의 수율 비교에서 초음파 공정을 병행한 60℃ 에탄올 추출이 일반 100℃ 물 추출에 비해 15% 높은 수율을 나타냈으며, 에탄올을 용매로 한 추출이 동일한 조건의 물 추출에 비해 모두 높은 수율을 나타냈다. 이는 용매의 극성과 용출되는 병풀 내 성분의 극성에 기인하는 것으로 사료된다. 인간 정상 섬유아세포인 CCD-986sk를 이용한 세포독성 측정을 통해 모든 병풀 추출물이 32% 이하의 세포독성을 나타냈다. 인간 면역 B, T세포의 생육도 측정에서 초음파를 병행한 60℃ 에탄올 추출물이 무첨가 대조구에 비해 10%의 증진 효과를 나타내었으며, 면역세포의 cytokine 분비량 측정에서도 IL-6, TNF-α의 분비를 각각 4.86 × 10-4 pg/cell과 5.73 × 10-4 pg/cell로 나타내 증진 효과를 나타냈다. 또한, 초음파 병행 에탄올 시료를 첨가한 면역 T세포의 분비물에 의한 NK 세포 활성에서도 10%의 생육증진효과를 나타내었다. 이를 통해 병풀의 에탄올 추출물이 면역 활성을 가지고 있으며 초음파 공정을 통해 활성의 증진이 나타날 수 있음을 확인하였다. 이는 에탄올 용매를 통해 병풀 유용성분의 용출이 증진되고, 초음파 공정을 통해 병풀 유용 성분의 수율 향상 및 유용성분의 변화, 신규물질 용출 등이 일어나기 때문인 것으로 사료된다.

본고에서는 초고압 추출 공정의 활성 증진 효과를 알아보기 위해 복분자의 면역활성 실험을 실시하였는데 그 결과는 아래와 같다. 인간의 정상 신장세포인 HEK293을 이용한 세포 독성은 추출물은 1.0 mg/ml의 농도에서 최고 19.5%의 세포독성을 나타냈다. 항암활성은 AGS와 A549 암세포를 이용하였는데, 초고압을 실시할 경우 1.0 mg/ml의 농도에서 80%이상의 높은 억제활성을 보였으며, 암세포의 생육활성에 대한 정상 세포의 세포독성의 비로 나타낸 선택적 사멸도는 모든 고농도에서 모두 3 이상으로 나타났다. 모든 처리구 중 15분간 초고압 추출한 것이 가장 높은 활성을 보였으나 5분간 초고압 추출한 것과 큰 차이가 나지 않아 5분간 초고압 추출을 실시하는 것이 효율적인 것으로 보인다. B cell과 T cell을 이용한 면역세포의 생육은 배양 6일째에 15분간 초고압으로 추출한 처리구에서 각각 13.5×104cells/ml, 14.6×104cells/ml로 가장 높은 세포농도를 나타냈다. 면역세포를 이용한 cytokin의 분비량 측정실험에서는 HPE15 추출물이 배양 시간에 따른 cytokine의 분비가 가장 높게 나타나는 것을 확인할 수 있었다. 각 세포의 TNF-α와 IL-6의 분비량은 6일째 최고의 분비량을 나타내었다. 또한 NK cell의 면역활성은 모든 추출물에서 배양 시간에 따라 유의적으로 증가하는 것을 확인하였다. 그 중 HPE15 추출물에서 B cell의 경우 15.8×104cells/ml, T cell의 경우 14.8×104cells/ml으로 가장 높은 생육 활성을 나타내었다. 본 실험 결과를 통하여 초고압으로 인해 기존의 추출 방법으로는 추출되지 않았던 유용생리활성 물질들이 초고압으로 조직과 세포막 파괴로 인해 유용성분의 용출량이 증가하고 새로운 물질의 용출로 인해 높은 활성을 나타낸 것으로 판단되었다.