초록 ▼

본 연구에서는 우리나라의 방사선방호, 방사선이용 및 방사능방재분야의 규제기술을 한 단계 더 높은 수준으로 발전시키기 위하여 다음 항목에 대한 연구를 수행하였다.
▪ 방사선방호 선진화체계 기반기술 개발
- ICRP 신권고 반영 내부피폭선량평가 규제검증 시스템 구축
- 외부피폭선량 평가 및 성능검증 기술 개발
- 원자력사고영향 확률론적 평가코드 개발
▪ 방사선원 안전성검증 선진기술 개발
- 비파괴검사 종사자 전혈구 검사기록 이력관리 시스템 개발
- 사이클로트론 시설해체 안전성 평가기술 개발
-

본 연구에서는 우리나라의 방사선방호, 방사선이용 및 방사능방재분야의 규제기술을 한 단계 더 높은 수준으로 발전시키기 위하여 다음 항목에 대한 연구를 수행하였다.
▪ 방사선방호 선진화체계 기반기술 개발
- ICRP 신권고 반영 내부피폭선량평가 규제검증 시스템 구축
- 외부피폭선량 평가 및 성능검증 기술 개발
- 원자력사고영향 확률론적 평가코드 개발
▪ 방사선원 안전성검증 선진기술 개발
- 비파괴검사 종사자 전혈구 검사기록 이력관리 시스템 개발
- 사이클로트론 시설해체 안전성 평가기술 개발
- 첨단의료용 선형가속기 차폐설계 및 안전성 평가기술 개발
▪ 기존피폭 최적화 이행체계 구축
- Mobile 기반 지각방사선량 평가시스템 구축
- 국내 주요 라돈 유의지역에 대한 정밀 조사
- 라돈 및 토론 자핵종 평가기술 개발 및 국외 이행체계 구축동향 분석
▪ 원자력비상대응 최적화 기술 개발
- 방사선비상계획구역 및 주민보호조치 국제기준 분석
- 국내 방사선비상계획구역의 재정립 방안 고찰
- 다수호기 동시사고에 따른 방사선영향평가 방안 수립

Abstract ▼

IV. Research Results
1. Development of basic regulatory technology for advanced system of radiation protection.
• The revised provisions in the nuclear safety law and its enforcement ordinance concerning the internal dosimetry were suggested that the related articles add an internal dose asses

IV. Research Results
1. Development of basic regulatory technology for advanced system of radiation protection.
• The revised provisions in the nuclear safety law and its enforcement ordinance concerning the internal dosimetry were suggested that the related articles add an internal dose assessment on the current dose assessment for external exposure using a TLD reading system. The new notifications related to internal dosimetry are proposed in accordance with the revised provisions in the law and its enforcement as in the followings; 1) registration criteria of business affairs for internal dosimetry and dose assessment, 2) regulatory guidance for preparation and presentation on technical basis report of internal dosimetry depending on treating radionuclides and/or characteristics of facilities, 3) regulatory guidance for quality assurance of internal dosimetry and dose assessment, 4) acceptance criteria and procedures for blind test of internal dosimetry.
• It was concluded that all of laws, notifications, technical standards, regulatory criteria and guidances related to internal dosimetry should consider commonly technical details for the followings; 1) optimized methods for individual monitoring considering a physical and/or chemical state of the radioactive isotopes handled by a facility and its usage, 2) frequency of individual monitoring, 3) estimation method of intake and uncertainty, 4) applications of dose coefficient, tools for dose assessment, and uncertainty, 5) selection and verification methods of subjects for dose assessment.
• A total of 30 organs including radiosensitive organs except for muscle and lymphnode were converted to polygon models. The conversion results showed that the converted polygon models can describe more realistic shape of organs than the conventional voxel models. Especially, the polygon models can overcome the limitations of wall organs such as skin, gall bladder, stomach, and urinary bladder due to the finite voxel resolution. In addition, it was possible to realistically model micrometers thick organs including oral mucosa and ET region using the polygon conversion technique. The polygon skeleton can be modeled divided into 19 parts and each part consists of cortical, spongiosa, and medullary cavity.
• The personal dosimetry criteria for tesing of the American National Standard, ANSI/HPS N13.11 published in the year of 2009, was reviewed in terms of newly revised details. As the result, it was concluded that the 8 categories of performance test was reduced to 5, the beta source of Tl-204 was replaced with Kr-85, the performance criteria was reinforced by revising acceptable errors of 0.3∼0.4 to 0.24∼0.3, the maximum dose of 100 mSv at radiological accidents was reduced to 50 mSv. The revised provisions in the related regulations were suggested in order to reflect the ANSI/HPS, N13.11(2009).
• The specific calculating model of MACCS2 code was reviewed and then items for its improvement were produced. Also the modification method was prepared for the purpose of including a new scientific data related to radiation protection. The assessment module of atmospheric dispersion was developed, which is a basic engine of assessment for environmental impacts of radioactive materials released from accidents. Dose conversion coefficients in case of external exposure due to boundless contamination of air matrix were calculated under considering the ICRP's 103, 107, 110 and 116.
2. Development of advanced technology for verification of radiation source safety.
• The web based electrical program for RW's the CBC result database has been established (http://kiramsbd.org). For the practical application of the database, we have registered 25,532 of the CBC examination table result of RWs in total, which has sent to KIRAMS from 52 of NDT company and the result is including the accumulated data(minimum 1 year, maximum 10 years) of 8,059 of radiation worker. The result of data analyzation showed that the "CBC Off-Scale Case" was 174(2.2%) of the total registered RWs in the database, 8,059.
• As a result, in this project the introduction of optimized management system for health examination is necessary, and it is urgent to set up the legal system to force the re-examination of CBC and additional examination whenever is needed by the decision of separate medical expert's investigation, and also to manage the health examination result effectively.
• In this study, we investigated the cyclotron operation status in Korea. And then we analyzed practical information on the decommissioning of cyclotron in ANL(Argonne National Laboratory) and Belgium(EU) and abroad decommissioning requirements(IAEA, NRC). By the analysis the cyclotron operation status and decommissioning procedure, we collected the data of activation characterization and decommissioning costs From the decommissioning requirements of IAEA and NRC, we checked on the application of DFP(decommissioning funding plan) and the preparation of cyclotron decommissioning. Also we proposed to develop adequate reuse or recycling standard on the very low level radioactive waste for the economic feasibility.
• We analyzed 161 radiation safety reports. 64-80% of the report is considering of IMRT treatment technique, and 5 is usually used for IMRT factor. By analyzing two years treatment methods in a hospital, about 10% of treatment was IMRT. The traditional treatment room with maze, it was measured 150 uSv/h inside of the shielding door and 15 uSv/h outside.
3. Establishment of the implemental bases for the optimization of radiation protection for existing exposures.
• Vehicle based terrestrial radiation monitoring devices was developed, its operating protocol was linked with the SIREN (System for Identifying Radiation in Environments Nationwide) as a sub-module (CREAMS : Crustal Radiation Evaluation And Monitoring System) of it, and all data measured in the vehicle was able to be automatically sent via 3G CDMA and accumulated in the SIREN. The preliminary survey for performance evaluation was also carried out.
• Detailed indoor radon survey was carried out for about 3% dwellings of Bongwha-Gun, Gyeongbuk, the one of radon prone areas in Korea during two quarters (Autumn and Winter Seasons).
• The attributal risk assessment of lung cancer caused by Radon was performed base on the geographical distributions of previous indoor radon survey results in order to build a foundation for the epidemiological studies in Korea.
• The Standard Radon Chamber was developed to meet the requirement for STAR(System for Test Atmospheres with Radon) to develop the Radon and Thoron daughter evaluation.
• In addition, the current status of implementation of the optimization for existing exposure of USA and UK after ICRP103 recommendations was investigated.
4. Development of optimized technology for nuclear emergency response.
• Trend analysis on international guidance and major countries practice was performed to revise emergency planning zone (EPZ) concept and to evaluate suggested range for domestic nuclear power plants.
• Technical study was done to estimate EPZ size from the view of optimized protection. Emergency preparedness system and emergency response ability was considered and deterministic method and PSA method were employed.
• A scenario for a simultaneous accident at multiple units such as station blackout and loss of UHS by extreme natural disasters such as earthquake, tsunami, typhoon and flood were developed.
• Also, recent trend on the radiological consequence assessment for a simultaneous accident at multiple units was analyzed, and the result was reflected into the method on the radiological consequence assessment.
• PCTRAN (Personal Computer TRANsient analyzer) APR1400 module which is a PC-based nuclear power plant simulator was developed in order to assess the source terms of the scenario for SKN Unit 3&4.
In addition, RadPuff module which is a simulation program for the radioactive effluent dispersion was introduced, so that the prompt radiological consequence assessment system for a simultaneous accident at multiple units was established.

목차 Contents

• 표지 ... 1
• 제출문 ... 2
• 보고서 요약서 ... 3
• 요약문 ... 4
• SUMMARY ... 12
• Contents ... 20
• 목차 ... 21
• 제 1 장 연구개발과제의 개요 ... 22
• 제 2 장 국내.외 기술개발 현황 ... 24
• 제 1 절 국내 기술개발 현황 ... 24
• 제 2 절 국외 기술개발 현황 ... 25
• 제 3 절 연구결과가 차지하는 위치 ... 27
• 제 3 장 연구개발 수행내용 및 결과 ... 28
• 제 4 장 목표달성도 및 관련분야에의 기여도 ... 32
• 제 5 장 연구개발 결과의 활용계획 ... 33
• 제 6 장 연구개발과정에서 수집한 해외과학기술정보 ... 34
• 제 7 장 참고문헌 ... 37
• 끝페이지 ... 47