To ensure the maintenance of the nuclear emergency response system, it is important to periodicaly conduct hazard assessments using up-to-date input variables. The results of this review are apllied to drills and exercises, enabling the inspection of emergency plan and response procedures. Therefore, this study aims to analyze off-site consequences according to the occurrence time of the Design Basis Accident (DBA) for the Hanaro Fuel Fabrication Facility (HFFF) by using the recent site-specific meteorological data and to review the appropriateness of urgent protective measures. MELCOR and SafeHanaro computer codes were used for radiation source-term estimation and environmental impact assessment, respectively. It was assumed that radioactive materials are released into environment for 2 hours due to the fire during the nuclear fuel sieving process. The following 12 scenarios for each occurrence time period was selected (0 am, 2 am, 4 am, 6 am, 8 am, 10 am, 12 pm, 2 pm, 4 pm, 6 pm, 8 pm, 10 pm) and the effective dose and thyroid dose in earlyand intermediate-phase were assessed. As a result, the most severe exposure-induced accident scenario is found to be as occurring at 0 am on July 15th, with the Most Exposed Individual (MEI) positioned 200 meters downwind from the facility. The committed effective dose for MEI is identified as to be 2.97E-02 mSv which has a significant margin against the IAEA's (Generic Intervention Level) GIL and (Generic Criteria) GC. During the passage of the radio-active plume, the estimated effective dose and thyroid dose due to inhalation were 2.97E-02 mSV (99.99%) and 5.06E-05 mSv (99.77%), respectively. External exposure appeared to be negligible. Meanwhile, the thyroid dose is noticeably below the criteria for decision-making for distribution of Potassium Iodide (KI). Accordingly, in order for local residents to participate in the exercise and drills, it is essential to develop scenarios considering simultaneous emergencies at multi-facilities and latenight accidents. In conclusion, this results will be used to improve the exercise plans for enhancing the nuclear or radiological emergency competencies of the KAERI.

The objective of this study is to investigate the safety awareness and effectiveness of the education and training for employees engaged in radiological emergency organization of the Korea Atomic Energy Research Institute (KAERI). In 2022, the questionnaire for the education satisfaction survey was revised to regulary evaluate the effect of edcation on perceptions of importance on emergency preparedness for nuclear research facilities. In line with, a standard questionnaire was created which covers 3 factors and 9 attributes, and the evaluation indicatior is based on a 5-point Likert scale. In 2023, the education on radiological emergency preparedness was conducted for 235 emergency staff. From May 24 to July 13, 2023, data was collected from a total of 235 emergency response personnels, including 28 new staffs and 207 maintenance staffs. Aa a result of response analysis, it was identified that education for radiological emergency response had a significant correlation with the promoting safety culture. It was found that senior emergency personnel with more years of experience are highly interested in radioactive disaster prevention and actively participate in and training. On the other hand, it was presented that new and less experienced groups tend to have a relatively high scored of the risk perception of nuclear research facilitites. Therefore, it is necessary to improve the practical curriculum in order to increase the participation of junior disaster prevention personnel in education and training, ensuring that they correctly recognize the risk of research facilities. This results are expected to be used to improve the quality of education and drills for radiological emergency response at KAERI.

The nuclear licensee must ensure that the nuclear or radiological emergency preparedness and response organization is explicitly defined and staffed with adequate numbers of competent and assessed personnel for their roles. This paper describes the responsibilities of medical and support personnel for the medical action of casualties in the event of a radiological emergency at the KAERI. Currently, there is one medical personnel (nurse) in KAERI, and a total of eight medical support personnel are designated for medical response in the event of a radiological emergency. These medical support personnel are designated as one or two of the on-site response personnel at each nuclear facility, operating as a dedicated team of A, B (4 people each). In the event of a radiological emergency, not all medical support personnel are mobilized, but members of the dedicated medical team, which includes the medical support personnel of the nuclear facility where the accident has occurred, are summoned. Medical and support personnel will first gather in the onsite operational support center (OSC)/technical support center (TSC) to prepare and stand by for the medical response to injured when a radiological emergency is declared. They should take radiation protective measures, such as wearing radiation protective clothing and dosimeters, before entering the onsite of a radiological emergency, because injuries sustained during a radiological emergency may be associated with radioactive contamination. In the event of an injury, direct medical treatment such as checking the patient’s vitals, first aid, and decontamination will be carried out by medical personnel, while support personnel are mainly responsible for contacting the transfer hospital, reporting the patient’s condition, accompanying the ambulance, filling out the emergency medical treatment record, and supporting medical personnel. In order to respond appropriately to the occurrence of injuries, we regularly conduct emergency medical supplies education and medical training for medical support personnel to strengthen their capabilities.

In response to a regulatory mandate, all nuclear licensees are obligated to establish an information system that can provide essential information in the event of a radiation emergency by connecting the monitoring data of the Safety Parameter Display System (SPDS) or equivalent system to the Korea Institute of Nuclear Safety (KINS). Responding to this responsibility, the Korea Atomic Energy Research Institute (KAERI) has established the Safety Information Transmission System (SITS), which enables the collection and real-time monitoring of safety information. The KAERI monitors and collects safety information, which includes data from the HANARO Operation Work Station (OWS) and the HANARO & HANARO Fuel Fabrication Plant (HFFP) Radioactivity Monitoring System (RMS), and the Environmental Radiation Monitoring System (ERMS) & meteorological data. Currently, the transmission of this safety information to the AtomCARE server of the KINS takes place via the SITS server located in the Emergency Operations Facility (EOF). However, the multi-path of transmission through SITS has caused problems such as an increase in data transmission interruptions and errors, as well as delays in identifying the cause and implementing system recovery measures. To address these issues, a new VPN is currently being constructed on the servers of nuclear facilities that generate and manage safety information to establish a direct transmission system of safety information from each nuclear facility to the AtomCARE server. The establishment of a direct transmission system that eliminates unnecessary transit steps is expected to result in stable information transmission and minimize the frequency of data transmission interruptions. As of the improvement progress, a security review was conducted in the second and third quarters of 2022 to evaluate the security of newly introduced VPNs to the nuclear facility server, and based on the results of the review, security measures were strengthened. In the fourth quarter of 2022, the development of a direct transmission system for safety information began, and it is scheduled to be completed by the fourth quarter of 2023. The project includes the construction of the transmission system, system inspection, and comprehensive data stability testing. Afterward, the existing SITS located in the EOF will be renamed as the Safety Information Display System (SIDS), and there are plans to remove any unused servers and VPNs.

Employees of nuclear licensees have to take the education for radiological emergency preparedness, as prescribed by presidential Decree. The Korea Atomic Energy Research Institute (KAERI), as an educational institution designated by the Nuclear Safety and Security Commission (NSSC), has been conducting field-oriented workplace education. This aims to enhance understanding of radiological emergencies that may occur in nuclear facilities and to strengthen response capabilities to prevent and deal with accidents in the event of radiation emergencies or radioactive disasters. To accomplish these educational goals, a paradigm shift from the previous theory-oriented curriculum to a participatory curriculum with high field applicability is needed to strengthen the ability to respond to nuclear or radiological emergencies. In addition, a feedback system is required to manage the quality of education and improve the curriculum. In this regard, KAERI sought ways to revitalize the education to strengthen the emergency response competencies. Based on the concept of the Systematic Approach to Training (SAT) methodology, which is recommended by the International Atomic Energy Agency (IAEA) for the development and implementation of education and training for NPP personnel, an educational model and its feedback system were developed. Then, a field-oriented participatory curriculum operation and satisfaction survey were conducted to evaluate the educational effectiveness. Lastly, the survey results were discussed in a critique session to point out weaknesses and indicate areas for improvement, and then were used as data for educational quality assurance. This paper introduces the composition and effectiveness of KAERI’s SAT-based education model based on its recent three years of experience.

Radioactive materials depositied after nuclear accident or radiological emergency result in radiation exposure to individuals living in long-term contaminated territories. Therefore, the remedial actions should be taken on affected areas for the evacuated residents to return to their homes and normal lifestyle. Meanwhile, radiation exposure occurs through various pathways by work types during the site clean-up. Therefore, dose assessment is crucial to protect emergency workers and helpers from the potential radiological risk. This study estimated the exposure dose to individuals decontaminating the areas contaminated with 60Co, 63Ni, 90Sr, 134Cs, 137Cs, and then calculated the maximum workable soil concentration to comply with the reference level of 20 mSv/y for transition to existing exposure situations. For the realistic assessment, the detailed exposure scenarios depending on the types of work (excavation, collection, transportation, disposal, landfill), and the relevant exposure pathways were used. In addition, with the LHS (Latin Hypercube Sampling) - PRCC (Partial Rank Correlation Coefficient) method, sensitivity analysis was performed to identify the influence of the input parameters and their variation on the model outcomes. As a result, the most severe exposure-induced type was identified as the excavator operation with an annual individual dose of 4.75E-01 mSv at the unit soil concentration (1 Bq/g), from which the derived maximum workable soil concentration was 4.21E+01 Bq/g. Dose contribution by isotopes were found to be 60Co (55.63%), 134Cs (32.01%), and 137Cs (12.28%), and the impact of 63Ni and 90Sr were found to be negligible. Dose contribution by exposure pathways decreased in the following order: ground-shine, soil ingestion, dust inhalation, and skin contamination. Furthermore, the most high sensitive input parameters and their PRCC were found to be as the dilution factor (0.75) and as the exposure time (0.63). In conclusion, the results are expected to contribute to optimize radiation protection strategeis for recovery workers and to establish appropriate response procedures to be applicable in areas with high deposition density after a radiological or nuclear emergency.

Background : Platycodon grandiflorum is a perennial plant and a member of Campanulaceae family. Since ancient times, they have been using P. grandiflorum as an important medicinal plant in Korea. Platycodin D is the most abundant saponin derived from P. grandiflorum and pharmacologically active component. Cytochrome P450s (CYPs) are important enzymes in the saponin biosynthesis. CYP is, in general, the terminal oxidase enzymes and essential roles in saponin biosynthesis pathway by hydroxylation or oxidaition of triterpene skeletons. Methods and Results : We tried to identify CYP genes related to saponin biosynthesis of P. grandiflorum through RNA-seq analysis. The sequencing was performed using Illumina Hi-Seq platform after cDNA library preparation. The produced reads were assembled using CLC Genomics Workbench software (CLC Bio, Inc.). We obtained 122,663 contigs and found 191 putative CYP genes. Familes of CYP716, CYP708, CYP93 and CYP51 were selected as putative saponin biosynthesis related gene families using phylogenetic relationship analysis. Conclusion : The results in this study could help to find the CYPs related to saponin biosynthesis pathway of P. grandiflorum.

Background : Platycodon grandiflorum is a perennial plant and a member of Camanulaceae family. Since ancient times, they have been using P. grandiflorum as an important medicinal plant in Korea. Platycodin D is the most abundant saponin derived from P. grandiflorum and pharmacologically active component. UDP-glycosyltransferases (UGTs) are important enzymes in the saponin biosynthesis. UGT is a glycosyltransferase and act on the final step of the secondary metabolite biosynthesis. Methods and Results : We tried to identify UGT genes related to saponin biosynthesis of P. grandiflorum through RNA-seq analysis. The sequencing was performed using Illumina Hi-Seq platform after cDNA library preparation. The produced reads were assembled using CLC Genomics Workbench software (CLC Bio, Inc.). We obtained 122,663 contigs and found 137 putative UGT genes. Familes of UGT71, UGT73, and UGT74 were selected as putative saponin biosynthesis related gene families using phylogenetic relationship analysis. qPCR condition about UGT73 is preheating 94℃ 180 sec, denaturation 94℃ 60 sec, annealing 53℃ 60 sec, extension 72℃ 90 sec, final extension 72℃ 600 sec, 45 cycles repeated. Conclusion : The results in this study could help to find the UGTs related to saponin biosynthesis pathway of P. grandiflorum.