Kori Unit 1, the first commercial nuclear power plant (NPP) in Korea, was permanently shut down in 2017 and was scheduled for decommissioning. Various programs must be planned early in the decommissioning process to safely decommission NPPs. Radiological characterization is a key program in decommissioning and should be a high priority. Radiological characterization involves determining the decommissioning technology to be applied to a nuclear facility by identifying the radiation sources and radioactive contaminants present within the facility and assessing the extent and nature of the radioactive contaminants to be removed from the facility. This study introduces the regulatory requirements, procedures, and implementation methods for radiological characterization and proposes a methodology to link the results of radiological characterizations for each stage. To link radiological characteristics, this study proposes to conduct radiological characterization in the decommissioning phase to verify the results of radiological characterization in the transitional phase of decommissioning NPPs. This enables significantly reducing the scope and content of radiological characterization that must be performed in the decommissioning phase and maintaining the connection with the previous phase.

Radiation workers receive exposure during radiation works such as decontamination or cutting of metals and concrete in decommissioning nuclear power plants. To reduce occupational exposure, various radiation protection measures should be prepared by estimating the exposure dose in advance. RESRAD-RECYCLE, the computer code, is generally used for estimating occupational dose due to handling metals contaminated with radioactive materials. However, RESRAD-RECYCLE used the dose conversion factors (DCF) of EPA FGR No. 11 based on ICRP Publications 30 and 48 published in the 1980s for internal exposure estimation. This study compared the DCFs of RESRAD-RECYCLE with those of the relatively recently published ICRP Publications 119 and 141. In addition, the internal exposure dose was evaluated by changing the value of the DCFs of RESRAD-RECYCLE. As a result of the comparison, ICRP Publication 119 showed that the DCF values of most nuclides were significantly lowered. On the other hand, in the case of nuclides emitting gamma rays, there was generally no significant change in the value of DCFs. In addition, in the case of 65Zn and 94Nb, the DCF increased compared to the previous ICRP publications. The exposure dose of the decommissioning workers of Hanul Units 1 and 3 and Hanbit Unit 4 was also calculated in this study. The expected radioactivity concentration of the steam generator chamber of each unit was used as the source term. The concentration of metal dust in the air generated during cutting was calculated and applied to evaluate the internal exposure dose. As a result of the dose evaluation, there was a difference in exposure dose up to 0.2 mSv in the scrap cutter scenario of Hanbit Unit 4, which generated a lot of dust and had a high radioactivity concentration. On the other hand, in the case of the slag worker, there was no difference in the dose because the working time was very short, and the inhalation of metal dust was small, even if the latest DCF was applied.

본 연구는 폐탄광에서 산림으로 복구된 지역의 임목, 낙엽층, 토양, 그리고 산림의 총 탄소 저장량을 추정하고, 수종별 탄소 저장량 차이를 비교하기 위해 수행되었다. 이를 위하여 강원도, 경상북도, 전라남도의 폐탄광 산림복구지에서 자작나무, 잣나무, 소나무류 (소나무, 리기다소나무, 곰솔)가 서로 다른 시기에 식재된 산림과 주변의 일반 산림을 조사하였다. 일반 산림에 비하여 폐탄광 산림복구지 내 낙엽층 및 토양 (ton C ha-1; 자작나무: 3.31±0.59 및 28.62±2.86, 잣나무: 3.60±0.93 및 22.26±5.72, 소나무류: 4.65±0.92 및 19.95±3.90), 그리고 산림의 총 탄소 저장량 (ton C ha-1; 자작나무: 54.81±7.22, 잣나무: 47.29±8.97, 소 나무류: 45.50±6.31)은 낮게 나타났으며, 임목 탄소 저장량 (ton C ha-1; 자작나무: 22.57±6.18, 잣나무: 21.17±8.76, 소나무류: 20.80±6.40)은 자작나무가 식재된 곳에서만 낮은 결과가 나타났다. 수종별로 토양 탄소 저장량을 제외한 임목, 낙엽층, 산림의 총 탄소 저장량에서 차이가 나타나지 않았으며, 임목 및 산림의 총 탄소 저장량은 복구 후 경과 시간에 따라 증가하는 경향을 보였다. 한편, 폐탄광 산림복 구지의 자작나무와 소나무류에서 토양 pH 및 CEC가 낮게 나타났으며, 수종별 불안정탄소, 유효인산, 미생물 바이오 매스 탄소가 일반 산림토양보다 2배 이상 낮은 결과를 보 였다. 폐탄광 산림복구지에 석회 및 유기질 비료의 시비와 경운을 통해 토양 성질을 개선하고, 가지치기 및 간벌 등 과 같은 산림관리로 임목 생육을 증진시키면 폐탄광 산림 복구지 내 탄소 저장량을 증가시킬 수 있을 것으로 기대된다.

인도네시아의 열대 이탄지는 황폐화되고 농경지 및 조림지로 전용되어왔다. 수로는 열대 이탄지의 지하수위를 관리하고 작물의 생산성을 높이기 위해 설치되었으나, 열대 이탄지의 구조를 파괴하고 침하 및 산불 발생 위험을 증가시켰다. 이에 따라, 인도네시아 정부는 수로로 인한 문제를 막기 위한 정책과 모라토리엄을 마련하였다. 그리고 해당 정책들에 따라 이탄지 재습지화에 관한 시범사업들이 일부 수행되었다. 우리나라가 열대 이탄지를 재습지화 한다면 추후 탄소배출권을 확보할 수 있는 가능성이 있으므로, 적절한 재습지화에 관한 자료가 필요하다. 이에 따라, 본 연구에서는 열대 이탄지에 적용되는 정책의 흐름을 조사하고 이 시범사업들의 설치 계획, 고려사항, 댐 설계, 재료, 설치 방법, 모니터링 방법, 그리고 소요 시간 및 비용 등에 대해 분석하였다. 이탄층의 깊이가 3 m 이상인 지역은 개발이 제한되고 개발 허가 발급이 중단되었으며, 복원을 위한 수로차단이 설치되었다. 이 지역에서는 댐의 지속성과 지역 이해당사자들의 참여를 독려하는 것이 우선순위로 여겨졌다. 개발 허가지역의 경우에는 개벌과 화전이 금지되었으며, 지하수위를 유지하기 위한 수로차단에 목적을 두었고, 수로차단을 설치할 때에는 작업 및 비용의 효율성이 우선적으로 고려되었다. 조사 결과를 바탕으로 본 연구에서는 인도네시아 열대 이탄지의 규제 적용 및 수로차단 설치 시 적용할 수 있는 방안들을 제시하였다. 이러한 결과는 동남아시아 지역의 배수된 열대 이탄지에 적합한 수로차단을 계획하는 데 기여할 수 있을 것으로 사료된다.

Bhutanese forests have been well preserved and can sequester the atmospheric carbon (C). In spite of its importance, understanding Bhutanese forest C dynamics was very limited due to the lack of available data. However, forest C model can simulate forest C dynamics with comparatively limited data and references. In this study, we aimed to simulate Bhutanese forest C dynamics at 6 plots with the Forest Biomass and Dead organic matter Carbon (FBDC) model, which can simulate forest C cycles with small amount of input data. The total forest C stock (Mg C ha-1) ranged from 118.35 to 200.04 with an average of 168.41. The C stocks (Mg C ha-1) in biomass, litter, dead wood, and mineral soil were 3.40-88.13, 4.24-24.95, 1.99-20.31, 91.45-97.90, respectively. On average, the biomass, litter, dead wood, and mineral soil accounted for 36.0, 5.5, 2.5, and 56.0% of the total C stocks, respectively. Although our modeling approach was applied at a small pilot scale, it exhibited a potential to report Bhutanese forest C inventory with reliable methodology. In order to report the national forest C inventory, field work for major tree species and forest types in Bhutan are required.

본 실험에 사용한 신생아 분변을 BL-NPNL 배지와 MRS(pH 5.4) 배지로 생균수를 조사한 결과, 각각 2.09×108 CFU/g feces와 1.06×109 CFU/g feces로 조사되었으며, 통성혐기성 유산균을 선발하여 내담즙산성과 내산성을 비교한 결과, SJ3, SJ6, SJ7, SJ-10균주들이 높은 활성을 보였다. 이들 유산균은 모두 E. faecalis로 동정되었으며, 향후 항생제 내성과 virulence factor에 대한 연구가 진행된다면 유산균 정장제와 사료 첨가제와 같은 probiotics 제품에 적용이 될 수 있을 것으로 판단되었다.

For efficient introgression of the downy mildew resistance gene from a resistant cultivar into domestic breeding lines, molecular markers used for marker-assisted backcrossing (MAB) were developed in onion (Allium cepa L.). The resistance gene (Pd) was originally introgressed from a wild species, A. roylei, by interspecific hybridization, and the resistant gene was known to be positioned at the end of chromosome 3. Therefore, cDNA sequences of loci located at the ends of chromosome 3 of two linkage maps were obtained from a transcriptome database. Primer pairs were designed on exon sequences of eight loci. Among them, the PCR products of the i25255 locus showed length polymorphism between A. roylei and onions, and both large and small-sized PCR products were observed in the resistant cultivar. Sequence analysis showed that a 67-bp indel existed in the intron sequences. Based on this indel polymorphism, a simple PCR marker, designated DMR1, was developed. Analysis of diverse onion accessions showed that no accessions contained the A. roylei-specific marker genotype except for the resistant cultivar. These results indicated that the DMR1 marker was successfully tagging the A. roylei fragment harboring the downy mildew resistance gene, and the resistant cultivar was heterozygous for the resistance gene. After further analysis of multiple loci positioned at chromosome 3, a range of the A. roylei fragment introgressed in the resistant cultivar was determined in two linkage maps. On the basis of the range of the A. roylei fragment, three molecular markers used for recombinant selection in MAB were also developed.