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Kafe 바로가기주관연구기관 | 한국원자력연구원 Korea Atomic Energy Research Institute |
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연구책임자 | 박세환 |
참여연구자 | 김호동 , 서중석 , 신희성 , 송대용 , 오종명 , 이용덕 , 박현민 , 고광훈 , 안성규 , 한보영 , 이동훈 , 서희 , 원병희 , 안상준 , 이채훈 , 박광준 , 최홍엽 , 김정동 , 이승규 , 김세윤 , 나상호 , 최대웅 , 이현수 , 김영국 , 김찬형 , 구자용 |
보고서유형 | 1단계보고서 |
발행국가 | 대한민국 |
언어 | 한국어 |
발행년월 | 2015-05 |
과제시작연도 | 2014 |
주관부처 | 미래창조과학부 Ministry of Science, ICT and Future Planning |
등록번호 | TRKO201800009475 |
과제고유번호 | 1711011405 |
사업명 | 원자력기술개발사업 |
DB 구축일자 | 2018-05-26 |
키워드 | 파이로 핵물질 계량관리.파이로시설의 격납/감시.파이로 안전조치 시스템.준실시간 계량관리 시스템.파이로공정 모니터링.안전조치 분석용 전산코드.Pu 직접 측정.감마선 영상화 기술.레이저 유도파쇄 분광 분석법.Nuclear material accountancy.Containment and surveillance.Design of Safeguards system for pyroprocessing.Near real-time accountancy system.facility.Process Monitoring technology for pyroprocessing facility.A computer code for analyzing safeguardability.Direct measurement of Pu.Gamma ray imaging technology.Laser Induced Breakdown Spectroscopy. |
DOI | https://doi.org/10.23000/TRKO201800009475 |
○ 파이로 핵물질 계량 기술개발
- U/TRU 계량용 융합형 NDA 시스템 기술개발
- 한미핵주기 공동연구를 통한 핵물질 계량방안 분석
- 파이로 전처리 물질 계량을 위한 ASNC 적용성 분석
○ 파이로 시설의 격납/감시 및 모니터링 기술개발
- 파이로시설의 격납/감시 시스템 설계
- PRIDE 공정 모니터링 통합분석 프로그램 개발
- 감마 감시시스템 적용성 분석 및 감마영상장치 시제품 개발
- LIBS를 이용한 핵물질 모니터링 기술개발
○ 파이로 안전조치 모델링 및 시뮬레이션
○ 파이로 핵물질 계량 기술개발
- U/TRU 계량용 융합형 NDA 시스템 기술개발
- 한미핵주기 공동연구를 통한 핵물질 계량방안 분석
- 파이로 전처리 물질 계량을 위한 ASNC 적용성 분석
○ 파이로 시설의 격납/감시 및 모니터링 기술개발
- 파이로시설의 격납/감시 시스템 설계
- PRIDE 공정 모니터링 통합분석 프로그램 개발
- 감마 감시시스템 적용성 분석 및 감마영상장치 시제품 개발
- LIBS를 이용한 핵물질 모니터링 기술개발
○ 파이로 안전조치 모델링 및 시뮬레이션
- 파이로 안전조치 모델링 및 시뮬레이션 요건 도출
- 파이로 안전조치 모델링 및 시뮬레이션 방안 수립
- 파이로 안전조치 모델링 및 시뮬레이션 기술 개발
○ 공학규모 파이로시설의 안전조치 시스템 개념 설계
- PRIDE 준실시간계량관리 시스템 개발
- 공학규모 파이로시설의 안전조치시스템 요건 분석 및 안전조치시스템 개념설계
○ 사용후핵연료 Pu 측정 고도화 기술개발
- 비파괴분석을 통한 사용후핵연료집합체의 Pu 직접 측정기술개발
- 사용후핵연료 X-선/감마선 분석 기술개발
- Pu분석 고도화 기술 평가
- 파이로 입력물질 계량방안 분석 및 입력물질 계량 시스템 개념 도출
(출처 : 보고서 요약서 3p)
Ⅳ. Result of the Project
1. Development of nuclear material accountancy technology for pyroprocessing
• Analysis on approach for nuclear material accountancy (NMA) of pyroprocessing
- Analysis and upgrade of NMA approach of REPF
• Development of hybrid-type NDA equipment for U/TRU NM
Ⅳ. Result of the Project
1. Development of nuclear material accountancy technology for pyroprocessing
• Analysis on approach for nuclear material accountancy (NMA) of pyroprocessing
- Analysis and upgrade of NMA approach of REPF
• Development of hybrid-type NDA equipment for U/TRU NMA
- Design of PNAR-based equipment based on Monte Carlo simulation for U/TRU ingot accounting
- Establishment of novel NMA technique, such as Fast Neutron Energy Multiplication (FNEM), and design of prototype equipment based on Monte Carlo simulation
- Design optimization and Development of hybrid U/TRU accounting equipment based on PNAR and FNEM, HIPAI (Difference between measurement and simulation: <1.48%)
• Analysis on nuclear material accounting methods through JFCS collaboration
- NDA and DA measurement of samples taken from g-scale hot test at INL (15 samples from various steps of g-scale hot test)
- Analysis on applicability of Cm ratio based on DA/NDA data from g-scale hot test
- Analysis on applicability of Cm ratio and Pu accounting error as a function of variation of Cm ratio (Satisfied criteria on MUF uncertainty (Pu error of 5%) when Cm ratio varies within 5%)
- Draft the experiment plan of NMA and monitoring in kg-scale hot test
• Analysis on applicability of ASNC for NMA of head-end process material
- Upgrade for improvement of remote maintenance
- Remote assembly and disassembly test at mock-up facility
- Installation of ASNC in hot cell and basic performance test
2. Development on containment/surveillance(C/S) and monitoring technology for the pyroprocessing facility
• Design of containment and surveillance system for the pyroprocessing facility
- Review of containment and surveillance system for the pyroprocessing related facilities
- Analysis of the result of preliminary conceptual design of the engineering-scale pyroprocessing facility
- Conceptual design of the containment and surveillance system for the engineering-scale pyroprocessing facility based on result of the preliminary conceptual facility design
• Development of the integrated computer program for the process monitoring at PRIDE
- Analysis of the characteristics of the process equipments and process material, process flow, facility structure, the factors of process monitoring of PRIDE
- Development of the DAQ module of image data for the surveillance of nuclear material transfer at PRIDE
- Development of the NaI(Tl) gamma-ray detector system for tracing the position of nuclear material in the argon cell
• Development of the compton camera for PRIDE facility
- Analysis on applicability of the compton camera for radiation monitoring in PRIDE facility
- Design of the compton camera for radiation monitoring in PRIDE facility
- Development of the compton camera prototype and performance evaluation
• Development of nuclear material monitoring technology using LIBS
- Fabrication of remote 2 LIBS systems (Stand-Off LIBS, Fiber-Optic LIBS)
- Fabrication of Stand-Off Telescopic LIBS system and basic performance test
- Installation of Fiber-Optic LIBS system(ALMN) at ACPF
- Installation of pyro mockup system including globe box and electrorefiner to test the LIBS performance
3. development of pyroprocesing safeguards modeling and simulation
• Requirement analysis of pyroprocessing safeguards modeling and simulation
- Requirement analysis of modeling and simulation about pyro facility/pyro process/safeguards system
- Requirement analysis of process material flow and MUF uncertainty simulation in PYMUS code
• Establishment of method of pyroprocessing safeguards modeling and simulation
- Establishment of process flow and safeguards system in REPF+1 model
- Method analysis of MUF uncertainty simulation in REPF+1 model
• Technical development of pyroprocessing safeguards modeling and simulation
- Establishment of dynamic nuclear material flow technique and nuclear measurement simulation technique based on monte-carlo method
- Establishment of statistical method to detect nuclear material diversion based on NRTA
4. Conceptual design of safeguards system for an engineering-scale pyroprocessing facility
• Development of near real-time accountancy system for PRIDE
- Analysis of nuclear material accountancy approach and the design of near real-time accountancy system for PRIDE
- Development of DAQ modules and nuclear material accounting module for the near real-time accountancy system
• Requirement analysis and conceptual design of safeguards system for an engineering-scale pyroprocessing facility
- Analysis of safeguards system status of Rokkasho Rreprocessing Plant and Tokai Reprocessing Plant in Japan, and establishment of concept and requirement of engineering-scale pyroprocessing facility
- Analysis of OSL technology status, and key technology establishment of NMA for engineering-scale pyroprocessing facility
- Establishment of verification requirements according to pyroprocessing nuclear material types based on safeguards requirements of reprocessing facility
- Preliminary plan of NRTA for timely detection goal, material balance/year satisfying the requirement of nuclear material accountancy
- Primary issue selection and solution establishment for nuclear material accountancy
5. Measurement technology development of Pu in spent fuel
• Development of direct Pu measurement technology development of spent fuel using NDA
- Performance evaluation of SINRD and CIPN at KAERI
• Development of spent fuel analysis technology using X-ray/gamma ray
- Development of X-ray/gamma spectroscopic analysis simulation code based Compton suppression, and establishment of prototype system and basic performance test
- Installation of Compton suppression X-ray/gamma spectroscopic analysis system for spent fuel measurement at PIEF of KAERI
• Evaluation of Pu measurement technology
- Development of RIMS for measurement of Pu isotope ratio in spent fuel. Investigation of laser ablated Gd atom, and design/production with consideration for optical fiber and power of UV source
- Installation and test of microcalorimeter for applicability to pyroprocessing safeguards
• Analysis on input nuclear material accountancy of pyroprocessing and conceptual design
- Less than 1 % inhomogeneity by 4 hours mixing using Turbular mixer in spent fuel homogenization test at DFDF (analyzed with IDMS/TIMS and gamma)
- Establishment of sieving condition with simfuel(U3O8) powder to verify the feasibility of homogenization
- Introduction of RS for sampling test with head-end process material, and Nauter mixer for homogeneity evaluation using simfuel.
- establishment of NMA approach depending on grain size
(출처 : SUMMARY 14p)
과제명(ProjectTitle) : | - |
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연구책임자(Manager) : | - |
과제기간(DetailSeriesProject) : | - |
총연구비 (DetailSeriesProject) : | - |
키워드(keyword) : | - |
과제수행기간(LeadAgency) : | - |
연구목표(Goal) : | - |
연구내용(Abstract) : | - |
기대효과(Effect) : | - |
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