초록 ▼

1세부 파이로 PR/PP 강화기술개발
• ‘적시경보’ 및 ‘전용탐지확률’ 기반의 신(新) PR 평가방법 개발 및 시설 3D 모델 연계 PPS 유효성 평가 프로그램 모듈 개발
• PR 강화를 위한 모니터링 기술 및 공정연계 옵션을 도출하고, 파이로시설의 PPS 예비설계 및 성능기반 PPS 평가방법론을 기반으로 파이로시설의 PPS 유효성 평가 수행
• 성공적인 INPRO PROSA 프로젝트 수행 완료를 통해 안전조치성 평가방법 개발에 기여

2세부 파이로 안전조치 기술개발
• 공학규모 파이로 시설의 안전

1세부 파이로 PR/PP 강화기술개발
• ‘적시경보’ 및 ‘전용탐지확률’ 기반의 신(新) PR 평가방법 개발 및 시설 3D 모델 연계 PPS 유효성 평가 프로그램 모듈 개발
• PR 강화를 위한 모니터링 기술 및 공정연계 옵션을 도출하고, 파이로시설의 PPS 예비설계 및 성능기반 PPS 평가방법론을 기반으로 파이로시설의 PPS 유효성 평가 수행
• 성공적인 INPRO PROSA 프로젝트 수행 완료를 통해 안전조치성 평가방법 개발에 기여

2세부 파이로 안전조치 기술개발
• 공학규모 파이로 시설의 안전조치에 필요한 핵물질 계량장비 개발
• 핵물질 모니터링용 원격 LIBS, 감마선 영상장비 개발 및 성능 평가
• 공학규모 파이로시설에 대한 안전조치 요건 및 주요 이슈 도출
• 기준파이로시설(REPF) 모델 업데이트한 REPF+1 모델 도출 및 안전조치시스템 업데이트

3세부 파이로 핫셀 설계 및 안전성 향상 기술개발
• 파이로시설에서 발생 가능한 유형별 가상사고(방사선 피폭, 핵임계, 화학적 위해물질, 화재/폭발 등) 시나리오를 개발하고 사고평가를 포함한 안전성 평가기법을 정립함.
• 사고유형별 가상사고 시나리오를 고려한 파이로시설의 계통·분야별 안전설계기준요건 확립하고 안전시스템 설계요건을 개발함.
• 파이로시설의 인허가를 위한 안전성 평가체계를 정립함.

(출처 : 보고서 요약서 3p)

Abstract ▼

Ⅳ. Result of the Project
○ Development of Pyroprocessing PR/PP Enhancement Technology
1. Analysis of Pyroprocessing system characteristics
● Analyzing and comparing the characteristics of several major pyroprocess options from JFCS, KAERI, ANL
- Building a database of pyroprocess materia

Ⅳ. Result of the Project
○ Development of Pyroprocessing PR/PP Enhancement Technology
1. Analysis of Pyroprocessing system characteristics
● Analyzing and comparing the characteristics of several major pyroprocess options from JFCS, KAERI, ANL
- Building a database of pyroprocess material characteristics, which is important to PR such as radiation, heat emission, criticality, of a different combination of process options
● Identifying pyro fuel cycle facility concept
- Defining pyro fuel clcye facility concept and developing 3D facility model for diversion pathway and vital area analysis for PR and PP analysis

2. Enhancement of PR of pyro fuel cycle facility
● Analyzing the elements of nuclear material diversion and its detection
- Defining detecting element of nuclear material diversion categorized diverted materials and diversion activities, and reviewing available detecting technologies applicable general nuclear facility
- Identifying detection technologies and analyzing its applicability to pyroprocess facility, categorized detecting material (mass, volume, element, radiation, etc.) and detecting diversion activities (operation change, material transfer, tempering record, etc.)
● Developing and identifying PR enhancing options and technology
- Suggesting and reviewing the technologies of alarming abnormal operation using image processing and/or infrared imaging to detect nuclear material transfer
- Reviewing applicability of various technologies such as calorimetry, LIBS, RIMS, voltametry and densitometry technologies into near real time accounting and or process monitoring for pyroprocess as well as a new C/S devices such as glass seal, remote monitoring seals array, under water sonic monitor
- Developing process linkage options to enhance proliferation resistance, such as (1) salt transfer option, (2) Dross removed U/TRU product, (3) representative sampling from a mechanical de-cladding process

3. Enhancement of PP of pyro fuel cycle facility
● Developing preliminary design requirement for physical protection system based on the design information of ‘preliminary design of engineering pyroprocess facility’
- Including pyroprocessing facility characteristics, protection target identification based on diversion scenarios and vital area analysis, identifying threats
● Preliminary designing of PPS for pyroprocessing facility and assessing PPS effectiveness based on performance-based evaluation method
- Preliminary designing PPS reflecting basic functions of detection, delay, and response divided in controled area, protected area, and vital area
- Performing adversary pathway analysis, developing adversary sequence diagram, and evaluating probabilities of interruption and neutralization and PPS effectiveness for the five most vulnerable vital areas to the sabotage threats

4. Development of pyro PR/PP evaluation method
● Reviewing and analyzing evaluation methods
- Reviewing and comparing almost every conventional PR evaluation methodologies and methods, and summarizing and re-organizing their indicators, measures, and metrics to deduce PR indicators for pyro
● Developing a new PR evaluation method based on a early detection of diversion concept using detection probability
- Developing a systematic procedure to build diversion pathways and detection measures with probability values, and evaluation method for PR measures in quantitative manner along with the diversion pathway analysis
● Developing 3D facility model and evaluation program modules for PPS effectiveness and 6 PR measures
- Building a PR/PP evaluation platform using 3D modeling and DB technology, the PPS effectiveness evaluation program, which can analyze adversary pathways, drawing Adversary Sequence Diagram, evaluate the system performance
- Developing a PR evaluation program modules which can systematically develop and manage diversion pathways and safeguards measures and theirs probability values, calculate 4 PR metric values to quantitatively evalute PR measures

5. International collaboration for PR/PP enhancement of pyro-fuel cycle
● Safeguards and Sedurity By Design work in the JFCS Phase 2 R&D
- Analyzing the review result of safeguards system of engineering scale pyroprocessing facility from the Phase 1 R&D, and identifying detailed tasks for the phase 2
- Comparing various major process flowsheet and identifying a representative flowsheet for a safeguards and physical protection system designing
● Joining and conducting GIF PRPP working group and INPRO PROSA project
- Collecting information from international collaboration community such as INRRO and GIF, and reflecting PR/PP enhancing approach
- Completing the PR and safeguardability assessment method through-out IAEA INPRO PROSA project and drafting the IAEA technical document (to be published in 2015)

○ Development of Pyroprocessing Safeguards Technology
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

○ Development of Pyroprocessing Hot Cell Facility Design and Safety Enhancing Technology
1. Development of Hypothetical Accident Evaluation Technology for Pyroprocessing Hot Cell Facility
● Nuclear safety regulations, standards and requirements for development of pyroprocessing facility safety basis document was reviewed and hazard and accident analysis procedure for pyroprocessing facilities was established. The hazard and accident analysis method for the reference facilities was analyzed, which are HCF(Hot Cell Facility) designed by Sandia National Laboratory, and FCF(Fuel Conditioning Facility) at Idaho National Laboratory. Also, the hazard evaluation procedure developed in this research for pyroprocessing facilities. Potential accident scenarios was developed and some case study was performed.

2. Development of Design Requirements of Safety System for Pyro Hot Cell Facility
● We investigated and analyzed the category of domestic and international status of safety design for pyro-related hot cell facilities; and safety function and characteristics of each major equipment in pyro facility according to the safety design standards and regulations from DOE and NRC; safety analysis reports and design reports for hot cell facilities. Based on it, we presented the fundamental requirements for major safety design requirements to be applicable to the Pyro hot cell facility. In addition, based on the 10-tHM scale pyroprocessing facility for the spent fuel treatment, draft P&I diagrams and configurations were presented regarding the requirement and concept of layouts for hot cell facility; major utilities for the facility such as HVAC, argon supply, emergency electricity supply, control, cooling water, compressed air, radiation and criticality protections, fire protection, electrical, instrumentation, and control systems, and toxic material protection. Finally, design requirements were specifically established.

3. Safety Evaluation Study of Pyro Hot Cell Facilities
● The objective of this safety evaluation study for Pyro Hot Cell Facilities is to analyze and evaluate the national and overseas standards for pyroprocess hot cell facilities. And the models of safety evaluation for pyro hot cell facilities are also established and suggested for adaptation of future pyro hot cell facilities. National nuclear safety laws and standards related to spent fuel pyroprocess hot cell facilities were analyzed to survey and establish technical standards of pyroprocess facilities. The technical standards of Japan and USA related with the advanced spent fuel reprocessing facilities were also analyzed and the IAEA safety standards for fuel cycle facilities were also analyzed for adaptation to the pyroprocess facilities developed and developing by KAERI. The models of safety evaluation for pyro hot cell facilities are also suggested and established for the KAERI’s future pyro hot cell facilities.

(출처 : SUMMARY 21p)

목차 Contents

• 표지 ... 1
• 제 출 문 ... 2
• 보고서 요약서 ... 3
• 요 약 문 ... 5
• SUMMARY ... 17
• CONTENTS ... 31
• 목차 ... 33
• 표목차 ... 36
• 그림목차 ... 38
• 제1장 연구개발과제의 개요 ... 43
• 제 1절 연구개발의 목적 및 필요성 ... 43
• 1. 연구개발 목적 ... 43
• 2. 연구개발의 필요성 ... 43
• 제 2절 연구개발 범위 ... 46
• 제2장 국내외 기술개발 현황 ... 49
• 제1절 국내 기술개발 현황 ... 49
• 1. 파이로 PRPP 강화기술개발 ... 49
• 2. 파이로 안전조치 기술개발 ... 49
• 3. 파이로핫셀 설계 및 안전성향상 기술개발 ... 51
• 제2절 국외 기술개발 현황 ... 51
• 1. 파이로 PRPP 강화기술개발 ... 51
• 2. 파이로 안전조치 기술개발 ... 54
• 3. 파이로 핫셀 설계 및 안전성향상 기술개발 ... 55
• 제3절 연구결과의 국제적 위상 ... 57
• 1. 파이로 PRPP 강화기술개발 ... 57
• 2. 파이로 안전조치 기술개발 ... 59
• 3. 파이로 핫셀 설계 및 안전성향상 기술개발 ... 60
• 제 3장 연구개발수행 내용 및 결과 ... 61
• 제 1 절 파이로 PR/PP 강화 기술개발 ... 61
• 제 1.1 절 파이로 순환핵주기 시스템 특성 분석 ... 61
• 제 1.2 절 파이로 순환핵주기시설의 PR 강화 방안 분석 ... 68
• 제 1.3 절 파이로 순환핵주기시설의 PP 강화 방안 분석 ... 93
• 제 1.4 절 파이로시설 PR/PP 평가방법론 개발 ... 111
• 제 1.5 절 파이로 순환핵주기 PR/PP 강화를 위한 국제협력 ... 133
• 제 2 절 파이로 안전조치 기술개발 ... 143
• 제 2.1 절 파이로 핵물질 계량관리 기술개발 분석 ... 143
• 제 2.2 절 파이로 시설의 격납/감시 및 모니터링 기술개발 ... 171
• 제 2.3 절 파이로 안전조치 모델링 및 시뮬레이션 ... 190
• 제 2.4 절 공학규모 파이로시설의 안전조치 시스템 개념 설계 ... 206
• 제 2.5 절 사용후핵연료 Pu 측정 고도화 기술개발 ... 226
• 제 3 절 파이로 핫셀 설계 및 안전성향상 기술개발 ... 248
• 제 3.1 절 파이로시설 사고시나리오 개발 및 평가 ... 248
• 제 3.2 절 파이로 핫셀시설 안전시스템 설계요건 개발 ... 287
• 제3.3절 파이로시설 안전성평가기법 개발 ... 320
• 제4장 목표달성도 및 관련분야에의 기여도 ... 339
• 제 1 절 목표 달성도 ... 339
• 제 2 절 관련 분야 기여도 ... 345
• 제5장 연구개발결과의 활용계획 ... 347
• 제 1 절 파이로 PRPP 강화기술개발 ... 347
• 제 2 절 파이로 안전조치 기술개발 ... 349
• 제 3 절 파이로 핫셀 설계 및 안전성향상 기술개발 ... 351
• 제6장 연구개발과정에서 수집한 해외과학기술정보 ... 352
• 제 1 절 파이로 PRPP 강화기술개발 ... 352
• 제 2 절 파이로 안전조치 기술개발 ... 353
• 제 3 절 파이로 핫셀 설계 및 안전성향상 기술개발 ... 354
• 제7장 참고문헌 ... 356
• 끝페이지 ... 362