초록

원전 방사성유출물 평가 및 관리기술 개발 연구는 총 3년에 걸쳐 수행되었으며 1차년도에서는 중수로원전(캐나다)의 유도방출기준 현황조사와 국내원전 유출물관련 규제 기관과 사업자간 현안사항에 대한 조사와 분석을 실시하였다. 이를 바탕으로 2차년도에서는 중수로원전의 유도방출기준을 반복계산하고 원전 유출물 관리에 대한 종합적인 검토를 수행하였다. 3차년도에서는 캐나다 유도방출기준을 검토하고 반영하여 월성원전의 유도방출기준 개선안을 제시하였으며 방사성유출물 관리 표준지침안을 작성하고 개선안을 제시하였다.

Abstract ▼

The study of the development of assessment and management technology for radioactive effluents at nuclear power plants was performed over a three year period. The investigation of problems pending between the regulatory agency and the utility and the analysis of the current Canadian derived release

The study of the development of assessment and management technology for radioactive effluents at nuclear power plants was performed over a three year period. The investigation of problems pending between the regulatory agency and the utility and the analysis of the current Canadian derived release limits (DRL) were conducted in the first year. In the second year, the recalculation of DRL for CANDU was carried out and a comprehensive investigation of radioactive effluent management was performed. Finally, an improvement plan for the Wolsong DRL reflecting the Canadian DRL was proposed and a standard regulation guide for radioactive effluents was developed in the third year. 1. Development of derived release limits (DRL) for CANDU nuclear power plants The analysis of the current DRL for CANDU and the calculation of the DRL were conducted in the first year. The re-establishment of DRL for CANDU had been demanded for long time as a pending problem of CANDU NPPs; thus, the Korea Electric Power Research Institute (KEPRI) held a technical seminar on tritium and C-14 and collected opinions from domestic experts and NPP specialists at the working level. First, the DRL for gaseous effluents was pre-calculated using the DRL method considering the problems of DRL for CANDU. An expert on radiation protection from the Canadian OPG (Ontario Power Generation) was invited to provide advice on the results of the calculation and information regarding the DRL revision and the trend of the regulatory agency. In the second year, the Canadian DRL method was analyzed and a reasonable DRL model for domestic NPPs was selected through an inter-comparison with the off-site dose calculation manual (ODCM). In addition, important parameters including social and environmental factors, atmosphere dispersion factors, and dilution factors were analyzed to estimate the input parameters used for the DRL calculation. The calculation process of a DRL for CANDU was developed using the analyzed data and the DRL was calculated by the development of a practical Wolsong DRL computer code. Finally, the Wolsong DRL computer code was improved, by considering the analyzed data of the Canadian DRL and a plan for improving the DRL corresponding with the ICRP-60 recommendation was proposed in the third year. Unnecessary pathways in the Wolsong DRL computer code were removed considering the characteristics of the Wolsong site based on the general transportation model of radionuclide to the environment. In addition, a pre-application test was performed for the practical use of the new DRL. The analyzed data was presented at a meeting for the revision of the Technical Specification (Tech. Spec.) for Wolsong unit 1 considering the pre-application results. Finally, the deletion of daily operating limits of Wolsong unit 1 and a revision of the Tech. Spec. were carried out. 2. Establishment of management measures of radioactive effluents released from NPPs An investigation of radioactive effluent problems pending between the regulatory agency and the utility was conducted in an attempt to find a solution in the first year. In particular, this research analyzed the current state of technical standards for radioactive effluent management in domestic NPPs and found that the management of radioactive effluents was slightly different for each plant since there were small differences in form and contents of the Tech. Spec. related to radioactive effluents in domestic NPPs and there are differences in devices used for the disposal of the radioactive wastes between NPPs. This research also suggested a plan for improving domestic technology compared with NUREG-1301 and developed a basic standard for management technology for radioactive effluents at nuclear power plants with the advice of domestic experts. In the second year, an analysis of the current state of the management standards for radioactive effluents in domestic NPPs was conducted continuously and an extensive investigation of the discharge standards for radioactive effluents in domestic and foreign NPPs was carried out and the domestic management standard guide for radioactive effluents was modified. In the standard guide, the terms related to the management of effluents were analyzed and better expressions were proposed. On the other hand, this research performed an analysis of the form and content of the management of radioactive effluents and suggested an improvement plan considering radioactivity analysis data and the classifications of the effluent. In addition, an auto-sampler was set up for three months to evaluate the suitability of the representative of samples for monitoring liquid radioactive waste. In the third year, the guidelines for the management of radioactive effluents at NPPs were written and the overall use of this guide was analyzed. The standard guide, revised for the more efficient management of effluents was suggested, considering past experiences with domestic NPP operations and the management of radioactive effluents, which were investigated in the first and second year. In addition, consultations with the domestic experts were scheduled to increase the possibility of the practical use of the improved management of effluents and a seminar on this subject was held for the utilities and regulatory agency. Practical discharge cases of radioactive effluents were investigated and assessed and the results of this research were used to address a radioactive contamination accident when it occurred in the demineralized water systems at Yonggwang unit 5.

목차 Contents

• 제 1 장 연구개발과제의 개요 ...45
• 제 2 장 국내외 기술개발 현황...48
• 제 3 장 연구개발 수행 내용 및 결과 ...51
• 제 1 절 중수로원전(월성) 유도방출기준 개발...51
• 1. 개요 ...51
• 2. 유도방출기준 방법론 분석 ...53
• 3. 국내원전의 유도방출기준 분석 ...57
• 4. 유도방출기준 분석 ...59
• 5. 유도방출기준 개선(안) 계산 및 제시...104
• 6. 논문 발표 및 기술간행물 발간 ...143
• 7. 결론 ...145
• 제 2 절 원전 유출물관리 종합대책 수립 ...147
• 1. 개요 ...147
• 2. 유출물관리의 기본개념 및 원칙 ...149
• 3. 국내원전 유출물 관리지침 분석 ...162
• 4. 해외원전 유출물 관리지침 분석 ...166
• 5. 방사성유출물 규제현안 분석 ...176
• 6. 국내원전 액체유출물 대표시료 분석 ...179
• 7. 논문 발표 및 기술간행물 발간 ...181
• 8. 결론 ...183
• 제 4 장 연구개발목표 달성도 및 관련 분야에의 기여도 ...185
• 제 5 장 연구개발결과의 활용계획 ...187
• 제 6 장 참고문헌 ...188