보고서 정보
주관연구기관 |
한국원자력연구원 Korea Atomic Energy Research Institute |
연구책임자 |
김장열
|
참여연구자 |
김봉환
,
이종일
,
이정일
,
임길성
,
김태형
,
김상인
,
장인수
,
김종수
,
송민영
|
보고서유형 | 1단계보고서 |
발행국가 | 대한민국 |
언어 |
한국어
|
발행년월 | 2015-01 |
과제시작연도 |
2014 |
주관부처 |
미래창조과학부 Ministry of Science, ICT and Future Planning |
등록번호 |
TRKO201800009412 |
과제고유번호 |
1711011883 |
사업명 |
원자력기술개발사업 |
DB 구축일자 |
2018-05-26
|
키워드 |
선량회구평가.선량복원.광자극발광.휴대전화기.신 소화기모델 내부선량평가.저선량률 엑스선장.포털모니터 및 핵종판별기 시험 프로토콜.Retrospective dosimetry.Dose reconstruction.Optically stimulated luminescence.mobile phone.HATM.Internal dose assessment.Reference X-ray field.Field Performance Test of Portal and Hand-held monitor.
|
DOI |
https://doi.org/10.23000/TRKO201800009412 |
초록
▼
○ 방사선 사고 대응 방사선량 회구 평가(retrospective dosimetry) 기술 확보
- 개인 휴대형 전자기기 내부 소자를 이용한 방사선량 회구평가 기술 확보
․ 최소검출선량: 10 mGy 이하
․ 방사선량 회구 평가 절차서 개발
․ 휴대전화 이용 선량회구평가 실증 실험 실시: 기준선량대비 5%-40% 오차 이내로 회구평가 가능
- 건축물 구성 물질을 이용한 방사선량 회구 평가 기술 확보
․ 사고선량 평가를 위한 건축물 구성 물질의 분류 및 선정: 적벽돌,타일,변기
․ 사고선량 신속
○ 방사선 사고 대응 방사선량 회구 평가(retrospective dosimetry) 기술 확보
- 개인 휴대형 전자기기 내부 소자를 이용한 방사선량 회구평가 기술 확보
․ 최소검출선량: 10 mGy 이하
․ 방사선량 회구 평가 절차서 개발
․ 휴대전화 이용 선량회구평가 실증 실험 실시: 기준선량대비 5%-40% 오차 이내로 회구평가 가능
- 건축물 구성 물질을 이용한 방사선량 회구 평가 기술 확보
․ 사고선량 평가를 위한 건축물 구성 물질의 분류 및 선정: 적벽돌,타일,변기
․ 사고선량 신속 평가 프로토콜 개발: 최소검출선량 약 10 mGy
○ 방사성핵종 섭취 신모델 해석 및 적용체계 개발
- OIR 내부피폭 평가모델을 분석하고 자체 개발한 잔류함수산출 모듈을 이용하여 OIR을 적용한 핵종별 섭취 잔류 및 배설함수 산출 및 데이터베이스 구축
○ 방사선방호/방재/보안용 측정기 성능시험 체계구축
- 개인 및 주변 선량(률) 측정기 시험 및 교정을 위한 기준 엑스선장 확대 구축
- 방사능방재/보안용 방사선/능 측정시스템 현장 성능시험 시스템 구축
(출처 : 보고서 요약서 3p)
Abstract
▼
IV. Results
1. Establishment of retrospective dosimetry technology for radiation accident dosimetry
1) Development of retrospective dosimetry technology using personal electronic devices (smart phones)
- Dose dependence of OSL from resistors, inductors, and IC chips
⋅Linear in the tested
IV. Results
1. Establishment of retrospective dosimetry technology for radiation accident dosimetry
1) Development of retrospective dosimetry technology using personal electronic devices (smart phones)
- Dose dependence of OSL from resistors, inductors, and IC chips
⋅Linear in the tested dose range (8.7 mGy - 8909 mGy) on the whole
- Fading test of OSL from the samples
⋅Inducttors: about 50 % in 36 hours after the irradiation
⋅Resistors: about 80 % in 36 hours after the irradiation
- Estimation of minimum detectable dose for resistors and inductors
⋅Inducttors: 2.4 mGy; Resistors: 6.6 mGy
- Development of a protocol for retrospective dosimetry using electronic devices
⋅Procedures from sample preparation and dose estimation
- Field test of the developed procedures for retrospective dosimetry
⋅It was possible to estimated the irradiated dose respectively in deviation from 5 % to 40 % (depends on dose range)
2) Development of retrospective accident dosimetry technique using building materials
- Selection of building materials for retrospective accident dosimetry
⋅Fired bricks, tiles, roof tiles, toilet porcelain
- Sample extraction of quartz inclusion and core-disc method for TL/OSL/POSL measurement
- Reliability test of equivalent dose obtained from building materials
⋅Verification of SAR-OSL method using quartz grains(90-250 ㎛)
⋅Verification of SAAD-POSL method using core-disc sample(Ø8 mm)
- Development of accidental dosimetry as fast assessment using SAAD-POSL method
⋅Regeneration test of equivalent dose up to 7 Gy
⋅Minimum detectable dose of 10 mGy in SAAD-POSL method
⋅Measurement time as short as about 2 hours in SAAD-POSL method
3) Designing and assembling of OSL spectrum measurement equipment and development of required software for OSL/TL analysis
- Photon measurement devices: CCD and PMT
- Spectrum wavelength band: 325 nm - 800 nm
- Stimulation light sources: Green and Red LED, Green Laser
- Measurement of OSL spectrum from Al2O3:C and LiAlO2 materials
- Development of an algorithm for analysis of OSL, TL based on trap interaction model
2. Interpretation of new models for intake of radionuclides and it’s application to internal dosimetry system
1) Analysis and application of HATM
• Analysis of HATM
- Analysis of difference between HATM and GI tract model
- Establishment of database for transfer rates by age group and food type
- Analysis of transfer rate calculation methodology for absorption from alimentary regions other than small intestine
• Application of HATM
- Calculation of intake retention and excretion functions for 100 days after ingestion of 90Sr and comparison with existing functions
- Calculation of total disintegration number for 50 years (U50) in each alimentary tract compartment after ingestion of 90Sr and confirmation of agreement with the result in ICRP publication 100
- Calculation of intake retention and excretion functions with Cd retention on teeth and Fe retention on small intestine wall
2) Analysis of OIR and establishment of application system
• Analysis of revised HRTM
- Analysis of changed fractional deposition in extrathoracic region (ET)
- Analysis of changed particle transport compartment model and establishment of relevant database
• Development of intake retention functions calculation module using OIR
- Establishment of intake retention and excretion functions calculation methodology
- Development of transfer rate matrix and initial value vector creation module (matrix_creator)
- Development of retention and excretion calculation module (IRF_calculator)
- Application of Intel Kernel Library to improve calculation speed for matrix
- Development of expm module for C to calculate matrix exponential
3) Calculation of retention functions for each radionuclide using OIR
• Analysis of radionuclides in OIR part 2 and calculation of intake retention functions
- Analysis of systemic biokinetic model for 14 radionuclides (H, C, P, S, Ca, Fe, Co, Zn, Sr, Y, Zr, Nb, Mo, Tc)
- Establishment of transfer rates for systemic biokinetic model and relevant parameters
- Calculation of intake retention/excretion functions for each radionuclide and intake route
• Analysis of radionuclides in OIR part 3 and calculation of intake retention functions
- Analysis of systemic biokinetic model for 14 radionuclides (Ru, Sb, Te, I, Cs, Ba, Ir, Pb, Bi, Po, Rn, Ra, Th, U)
- Establishment of transfer rates for systemic biokinetic model and relevant parameters
- Calculation of intake retention/excretion functions for each radionuclide and intake route
3. Establishment of radiological performance testing scheme of radiation detection systems used for radiation protection, radiological emergency and security
1) Production of the reference X-ray fields (ISO LK qualities) and gamma ray field for test and calibration of personal electronic dosimeters and workplace monitors.
• Production of the reference X-ray fields (ISO LK qualities)
- ISO LK beam series : LK35, LK55, LK70, LK100, LK125, LK170, LK210, LK240.
- Quantification of the produced LK X-ray beams using the measurement method of half value layer (HVL).
- Homogeneity of LK X-ray beams were satisfied within 5% according to ISO4037.
- Air-kerma rates of eight LK X-ray beams were measured using ionization chamber calibrated at KRISS (Korea Research Institute Standard and Science) and JAEA (Japan Atomic Energy Agency).
- Air-kerma rates of KAERI’s LK X-ray (0.1-0.24 mGy.h-1.mA-1) were satisfied with ISO criterion (< 0.3 mGy.h-1.mA-1)
• Production of the low air-kerma rate gamma ray fields using a radiation source of 241Am
- Air-kerma rates of radiation fields of 241Am were 0.43 mGy.h-1 @5 cm, 0.11 mGy.h-1 @10 cm.
2) Establishment of field performance testing systems used for radiation protection, radiological emergency and security at workplace.
• Evaluation and preparation of performance test manuals and protocols of radiation detection portal monitors and hand-held radionuclide identifiers.
• Establishment of the radionuclide check source set for evaluation and performance test of portal and hand-held monitors.
- Gamma sources: 57Co, 133Ba, 137Cs, and 60Co, and radioactivities are 3.5, 0.7, 0.56, 0.12 MBq, respectively.
- Neutron source: 252Cf, neutron emission rate is 1.4×104 n/s.
• Production of a check source transfer equipment: moving speed and a height of source position can be adjusted and the function of automatic round-trip was provided.
(출처 : SUMMARY 13p)
목차 Contents
- 표지 ... 1
- 제 출 문 ... 2
- 보고서 요약서 ... 3
- 요 약 문 ... 4
- SUMMARY ... 11
- CONTENTS ... 20
- List of tables ... 22
- List of figures ... 25
- 목차 ... 31
- 표목차 ... 33
- 그림목차 ... 35
- 제 1 장 연구개발과제의 개요 ... 40
- 제 1 절 연구개발의 목적 ... 40
- 제 2 절 연구개발의 필요성 ... 40
- 제 2 장 국내․외 기술개발현황 ... 44
- 제 1 절 선진국 연구개발 동향 및 기술수준 ... 44
- 제 2 절 국내 연구개발 동향 및 선진국과의 기술격차 ... 45
- 제 3 장 연구개발수행 내용 및 결과 ... 47
- 제 1 절 방사선량 회구 평가 기술 개발 ... 47
- 1. 휴대형 전자기기 내부 소자의 광자극발광(OSL) 현상을 이용한 방사선량 회구평가 기술 개발 ... 47
- 2. 건축물 구성 물질을 이용한 사고선량 회구평가 기술개발 ... 85
- 3. 광자극발광/열발광 스펙트럼 측정 장치 및 분석 알고리듬 개발 ... 130
- 제 2 절 방사성핵종 섭취 신모델 해석 및 적용체계 개발 ... 158
- 1. 신 소화기모델 해석 및 체계 구축 ... 158
- 2. OIR 분석 및 적용체계 구축 ... 168
- 3. OIR Part 2,3 핵종 분석 및 잔류함수 산출 ... 182
- 제 3 절 방사선방호·방재·보안용 측정기 성능시험 체계 구축 ... 223
- 1. 전자개인선량계 성능시험용 기준 엑스선장 및 감마선장 제작 ... 223
- 2. 방사선 비상 운영장비 현장 성능시험 체계 구축 ... 230
- 제 4 장 목표 달성도 및 관련 분야에의 기여도 ... 242
- 제 1 절 연구개발 목표의 달성도 ... 242
- 제 2 절 관련 분야에의 기여도 ... 243
- 제 5 장 연구개발 결과의 활용계획 ... 246
- 제 6 장 연구개발과정에서 수집한 해외 과학기술정보 ... 249
- 제 7 장 참고문헌 ... 250
- 끝페이지 ... 257
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