초록

○ 제4세대 소듐냉각 고속로 고유개념 개발
- 고유 노심 및 계통 개념 설정
- 핵변환로 노심 예비개념 설정
- 고유개념 실증로 개념설계

○ 선진기술 개발 및 검증
- 경제성 향상 기술 개발
- 안전성 입증 실험 기반 구축
- 금속연료 기본기술 개발

○ 기반기술 검증
- 고유전산코드 개발 및 예비검증
- 소듐기술 개발
(출처: 보고서 요약서 7p)

Abstract ▼

Ⅳ. Results of the Research and Development
○ Development of Advanced Concepts for Gen IV SFR
• Conceptual Design of Demonstration Reactor
- Establishment of design criteria: To achieve Gen IV SFR technology goals such as sustainability, safety and proliferation resistance, top- tier design

Ⅳ. Results of the Research and Development
○ Development of Advanced Concepts for Gen IV SFR
• Conceptual Design of Demonstration Reactor
- Establishment of design criteria: To achieve Gen IV SFR technology goals such as sustainability, safety and proliferation resistance, top- tier design requirements of demonstration reactor were defined. Also, the codes and standards were established and applicability review of the general and safely design criteria were performed. Design criteria were estabilished, eliminating the uncertain future technologies and using the available licensing technology, to understand clearly between the design areas.

- Conceptual design of core : A conceptual core design is developed for TRU burner in which an initial core is driven by less than 20wt% enriched U²³⁵, and finally transformed to a self-recycled TRU core. The demonstration core concept that can minimize the hard ware change and maximize the core functions in spite of loading different fuels in a single core configuration was finalized through extensive analyses of core performance parameters for various core conceptual design candidates.

- Conceptual design of metal fuel: The influences of the key fuel design parameters such as fuel composition, cladding thickness and temperature, and plenum length upon fuel in-pile behavior were evaluated. It was verified by fuel performance analysis that the fuel would maintain its integrity up to discharge burnup. Based on these results, conceptual design specification, design drawing and design report were produced.

- Conceptual design of fluid system: Through the development and evaluations of
various fluid design concepts, SFR fluid system design concept was developed which satisfy Gen IV design requirements. The design concept has lower value of core damage frequency of 10⁶/R.Y year by orignal passive decay heat removal ciruit and design diversity. And the system has better economics than foreign sodium fast reactor by high net system efficiency of 38.8% and design simplifications

- Conceptual design of mechanical structures: In phase 2 conceptual design of the demonstration fast reactor, degree of accomplishment has been improved by conducting arrangements of buildings and systems, minimization of reactor vessel (OD 12m), simplification of reactor internals and interface design of reactor head based on experience in phase 1 conceptual design of large capacity reactor. In addition, optimizations in arrangements of I1HX, DHX and sodium pump, minimization of pipe length (l44m per loop) by adopting Mod.9Cr-1Mo steel, and giving shape of structural concept in in-vessel refueling machine, steam generator, sodium pump have been conducted have been conducted.

- Safely evaluation of conceptual design: A preliminary safety evaluation for candidate design concepts was performed and the need of advanced decay heat removal has been suggested. Through the safely evaluation of design basis events and ATWSs for demonstration reactor concept, the improved safety performance and inherent safety characteristics were confirmed. The PSA study quantified the CDF of 5.4e⁷y.

○ Developrnent and Validation of Advanced Technologies
• Development of Technologies for Improved Economics
- Evaluation of applicability of super critical CO2 Brayton cycle to SFR: For the application of supercritical CO2 Braylon Cycle to SFR, major design issues are development of control logics for various power levels and fabrication of major components. Through the R&D, optimal control logics were developed to maintain high system efficiency for various power levels and optimal design concept of heat exchanger was developed with 1!5th pressure loss.

- Development of under- sodium inspection system for reactor in-vessel structures: Novel under-sodium waveguide sensor has been developed and the prototype under-sodium inspection system using waveguide sensor has been designed and manufactured for the application of under-sodium viewing of in-vessel structures submerged in an opaque liquid sodium of SFR. The performance lest of the under-sodium waveguide sensor and inspection system has been carried out and evaluated with the sodium test facility. The basic technology of under-sodium viewing using the waveguide sensor was established for the potential use in SFR. The safety and economy can be improved by the application of the under-sodium waveguide sensor and inspection system to the refueling process and in-service inspection of a sodium-cooled fast reactor

• Fundamental Facility Construction for the Safety Evaluation
- Construction of Component Performance Test Sodium Loop and the Separate Performance Test of Major Components: For the first step of the sodium thermal-hydraulic test program at KAERI, the detailed design of STELLA-1 facility for demonstrating thermal-hydraulic performance of the major components has been completed. The manufacturing and inslallation process of heat exchangers, mechanical sodium pump, pressure vessels and related pipe lines were successfully completed in 2011, and the performance tests will be started in next fiscal year.

- Development of Sodium Measurement Methodology: Sodium measurement instruments were designed and manufactured. The performance tests of these instruments were successfully performed. Measurement uncertainties of the protype were as follows; flow rale transducer within ±1.9%FS, local velocity transducer within ±2.5%FS, level transducer within ±3.7%FS, and response time of pressure transducer was 0.7 sec.

• Development of Basic Technologies for Melallic Fuel
- Technology development for fuel slugs fabrication: Fabrication technology of fuel slugs based upon a gravity casting was developed and fuel slugs, diameter of 5 mm and length of 300 mm, were fabricated. Casting soundness, thermal, mechanical and microstructural characteristics of the fuel slugs were examined and their soundness was maintained. Metallic fuel rods of 1 m length were fabricated and examined the design requirements were satisfied. Fuel rodlets were fabricated and irradiated in HANARO reactor.

- Development of basic technology for cladding lube fabrication: Advanced alloy materials for cladding tube showing better mechanical performance than the conventional HT9 c1adding were developed and applied for the patent. Cladding tube fabrication processes such as cold work and heat treatment were developed to improve the mechanical properties of cladding tube. HT9 cladding tube was manufactured and evaluated Lo investigate the effects of cladding tube fabrication processes.

- Performance evaluation of metal fuel: To evaluate fuel performances at both high temperature and high burnup, interaction tests between metal fuel and cladding were performed and barrier technology such as Cr electroplating on the inner surface of cladding was developed and it showed the capability of preventing fuel cladding interaction. Fuel irradiation capsule Lo simulate SFR fuel irradiation conditions was designed and fuels were irradiated in HANRO reactor. Fuel rod performance analysis code(a version ) was developed.

○ Validation of Basic Technologies
• Development and Preliminary Validation of Computational Tools
- Development of cross section adjustment technology : A cross section adjustment code named as A TCROSS was developed for enhancing the prediction accuracy of design and safety parameters through the reduction of uncertainty arising from cross section uncertainty. The status of covariance data was investigated and a set of 150-group covariance data has been produced. Publicly available physics data was selected through the assessment of similarity with a reference core and an adjusted cross section library is being generated.

-Development of methodology for assessing reactor core thermal- hydraulic uncertainties: Thc uncertainty assessment with HCFs was carried out by comparative studies of statistical analysis methods. The MATRA - LMR code with HCFs was established to estimate the core T/H uncertainties. The core T/H designs during U/TRU fuel alteration was performed using the SLTHEN code. The T/H characteristics of the candidate demonstration reactor were also investigated to prepare the experimental conditions for the licensing procedures.

-Reactor physics experiment: The reactor physics experiment on a low TRU conversion ratio core is carried out for securing the physics experiment database required for the licensing of a prototype SFR. The experiment was performed in the BFS-2 facility through a collaboration with IPPE Russia. The first criticality was attained in August 10, 2010 and all other measurements were completed in October 2011. An as-built Monte- Carlo model corresponding to each measurement configuration was developed in this study.

- Development of high temperature design and evaluation for 60 years design life: To establish the high temperature structural design and evaluation technologies for system and components, the SIE ASME-NH computer program, which implements the evaluation procedures of ASME-NH code rules, has been developed and verified. Developed technologies have been used for ASME-NH code committee to revise the creep-fatigue code rules of Gr.91 steel which requires very conservative criteria.

- Safety analysis code development and validation: Development of MARS-LMR thermal-hydraulic model and reactivity feedback model has been completed. Through the evaluation of EBR-II and Phenix test data, the applicability of the code has been proven. The draft topical report on flow blockage analysis code MATRA-LMR/FB has also been prepared by integrating all the previous studies, which will be utilized in future licensing analysis.

• Development of Sodium Technologies
- Development of Impurity Measurement and Control Technology: Analysis of the up-to-date technology for the improved impurity purification apparatus was performed. Cold traps with different shapes of mesh packing which is a major factor for the performance of the cold traps, were developed. An experimental facility including these cold traps was designed and in stalled, and the performance lest of cold traps has been carried out. With this Lest results, an evaluation of thc improved cold trap has been performed. In addition, a large cold trap was designed and the performance test and an evaluation was carried out in a same loop.

- Development of SWR Protection Technology: Experimental study on the multi-larget wastage and consequential surface degradation effect was carried out for the reference SG tube bundle model. The test conditions are totally based on the prototype SFR SG with an intermediate steam leak rate. The event propagation model, which can predict preliminarily the process of stepwise leak propagation from micro leak to large leak, was developed.

- Development of Sodium Treatment Process Technology: New improved concept of sodium treatment process technology was developed by reviewing the current slate-of-the-art. With water mockup testl, a sodium atomizing feed nozzle was developed to maintain a uniform reaction. Design requirements such as optimum flowing conditions were obtained for the design and manufacture of test facility. A test facility for the sodium treatment process technology was installed and the feasibility Lest for the nozzle and this new process is being performed with sodium.
(출처: Summary 18p)

목차 Contents

• 표지 ... 1
• 제출문 ... 6
• 보고서 요약서 ... 7
• 요약문 ... 8
• Summary ... 16
• Contents ... 24
• 목차 ... 26
• 표목차 ... 28
• 그림목차 ... 29
• 제1장 연구개발 과제의 개요 ... 34
• 제1절 연구개발의 필요성 ... 34
• 제2절 연구개발 목표 및 내용 ... 36
• 1. 최종목표 ... 36
• 2. 단계목표 및 내용 ... 36
• 제2장 국내·외 기술개발 현황 ... 44
• 제1절 국외 기술개발 현황 ... 44
• 제2절 국내 기술개발 현황 ... 46
• 제3절 국내·외 기술개발 현황에서 차지하는 위치 ... 48
• 제3장 연구개발 수행내용 및 결과 ... 54
• A. 1단계(’07-’09) 연구개발 수행내용 및 결과 ... 54
• 제1절 제4세대 소듐냉각 고속로 고유개념 설정 ... 54
• 1. 고유개념 설정 ... 54
• 제2절 선진기술 개발 ... 62
• 1. 경제성 향상 선진기술 개발 ... 62
• 2. 안전성 입증 기반실험 ... 67
• 3. 금속 연료심/선피복재 제조 원천기술 확보 ... 68
• 제3절 국내 기반기술 개발 ... 71
• 1. 전산 코드 고유화 ... 71
• 2. 설계기준사고 해석 방법론 개발 ... 75
• 3. 기술 및 품질 관리 ... 77
• 4. 소듐기술 개발 ... 79
• B. 2단계('10~'11) 연구개발 수행내용 및 결과 ... 83
• 제1절 제4세대 소듐냉각 고속로 고유개념 개발 ... 83
• 1. 고유개념 실증로 개념설계 ... 83
• 제2절 선진기술 개발 및 검증 ... 106
• 1. 경제성 향상 선진기술 개발 ... 106
• 2. 안전성 입증 실험기반 구축 ... 109
• 3. 금속연료 기본 기술 개발 ... 117
• 제3절 기반기술 검증 ... 123
• 1. 고유전산코드 개발 및 예비검증 ... 123
• 2. 소듐기술 개발 ... 128
• 제4장 목표달성도 및 관련분야에의 기여도 ... 132
• 제5장 연구개발 결과의 활용계획 ... 148
• 재6장 연구개발 과정에서 수집한 해외과학정보 ... 150
• 제7장 연구시설·장비현황 ... 166
• 제8장 참고문헌 ... 168
• 기술개발 종합 ... 174
• 제출문 ... 176
• 보고서 요약서 ... 177
• 요약문 ... 178
• SUMMARY ... 182
• CONTENTS ... 186
• 목차 ... 188
• 표목차 ... 190
• 그림목차 ... 191
• 제 1 장 연구개발과제의 개요 ... 194
• 제 1 절 연구개발의 목적 및 필요성 ... 194
• 1. 연구 개발의 목적 ... 194
• 2. 연구개발의 필요성 ... 194
• 제 2 절 연구개발의 범위 ... 195
• 1. 1단계 (‘ 07 년-’09년 ) ... 195
• 2 .2단계 (‘ 10 년 ’ 11년) ... 196
• 제 2 장 국내외 기술개발 현황 ... 197
• 1. 국외 기술 개발 현황 ... 197
• 2. 국내 기술개발 현황 ... 198
• 제 3 장 연구개발수행 내용 및 결과 ... 200
• A .1단계(’07 ~ ’09 ) 연구개발수행 내용 및 결과 ... 200
• 제 1 절 제 4 세대 소듐냉각 고속로 고유 개념 설정 ... 200
• 1. 고유개념 설정 ... 200
• 2. 지속성,경제성,안전성,핵확산 저항성 평가 ... 208
• 3. 시나리오 연구 ... 210
• 4. 기술 및 품질 관리 ... 217
• B. 2 단계(’ 10~ ’ 11) 연구개발수행 내용 및 결과 ... 222
• 1. 실증로 설계종합 ... 222
• 2. 공정 및 프로젝트 관리 ... 248
• 3. 품질 관리 및 보증 ... 260
• 4. 경제성 평가 ... 264
• 제 4 장 목표달성도 및 관련분야에의 기여도 ... 288
• 제 1 절 단계 목표 및 달성도 ... 288
• 1. 1 단계 (‘07년 - ’09 년) ... 288
• 2. 2 단계 (‘ 10년 - ’ 11 년) ... 290
• 제 2 절 관련분야에의 기여도 ... 292
• 제 5 장 연구개발결과의 활용계획 ... 293
• 제 1 절 연구 개발결과의 활용계획 ... 293
• 제 2 절 추가연구의 필요성 ... 293
• 제 6 장 연구 개발과정에서 수집한 해외과학기술정보 ... 294
• 제 7 장 연구시설·장비 현황 ... 296
• 제 8 장 참고문헌 ... 297
• 노심 핵심기반기술 개발 ... 302
• 제출문 ... 304
• 보고서 요약서 ... 305
• 요약문 ... 306
• SUMMARY ... 314
• CONTENTS ... 323
• 목차 ... 326
• 표목차 ... 329
• 그림목차 ... 331
• 제 1 장 연구개발과제의 개요 ... 336
• 제 1 절 연구 개발의 필요성 ... 336
• 제 2 절 연구 개발 목표 및 내용 ... 338
• 1. 최종목표 ... 338
• 2. 1 단계 목표 및 내용 ... 338
• 3. 2 단계 목표 및 내용 ... 341
• 제 2 장 국내 외 기술개발 현황 ... 344
• 제 1 절 국외 기술개발 현황 ... 344
• 제 2 절 국내 기술 개발 현황 ... 346
• 제 3 절 국내 · 외 기술개발 현황에서 차지하는 위치 ... 347
• 제 3 장 연구개발수행 내용 및 결과 ... 350
• 제 1 절 고유개념 설정 ... 350
• 1. 제 4세대 소듐냉각 고속로 고유 노심개념 설정 ... 350
• 2. TRU 연소로 고유 노심 예비개념설정 ... 358
• 제 2 절 기반기술 개발 ... 364
• 1. 유효단면적 생산체제 검증 ... 364
• 2. 노섬설계 전산코드 고유화 ... 369
• 제 3 절 제 4세대 소듀 냉각 고속로 고유개념 개발 ... 373
• 1. 실증로 노심 개념설계 ... 373
• 제 4 절 기반기술 검증 ... 407
• 1. 단면적 라이브러리 보정기술개발 ... 407
• 2. 노섬 열유체 불확실도 평가 방법론 개발 ... 424
• 3. 노물리 실험 ... 442
• 제 4 장 목표 달성도 및 관련분야에의 기여도 ... 465
• 제 5 장 연구개발결과의 활용계획 ... 475
• 제 6 장 연구개발과정에서 수집한 해외 과학기술정보 ... 478
• 제 7 장 연구시설 · 장비 현황 ... 479
• 제 8 장 참고문헌 ... 480
• 핵연료 핵심기반기술 개발 ... 484
• 제출문 ... 485
• 보고서 요약서 ... 486
• 요약문 ... 487
• SUMMARY ... 494
• CONTENTS ... 502
• 목차 ... 505
• List of Table ... 508
• List of Figures ... 509
• 제 1 장 연구개발과제의 개요 ... 513
• 제 2 장 국내외기술개발 현황 ... 518
• 제 3 장 연구개발 내용 및 결과 ... 523
• 제 1 절 금속연료 제조 및 미세 조직 최적화 ... 523
• 1. 개요 ... 523
• 2 용해주조로 설계 ... 523
• 3. 금속 연료 제조 기술자료 수집 및 분석 ... 524
• 4. 용해주조 기초기술 개발 ... 525
• 5 금속연료심 제조기기 설계 및 제작 ... 525
• 6. 금속 연료심 재료물성 예비 시험 ... 526
• 7. 용해주조 기초기술 확보 ... 526
• 8. 조사시험용 축소시편 제작 ... 527
• 9 금속연료심 재료물성 시험 및 평가 ... 528
• 10. 용해주조로 제작 ... 529
• 11. 요약 ... 530
• 제 2 절 신피복재 성능평가 ... 531
• 1. 개요 ... 531
• 2. 피복관열 및 기계물성 자료 수집 및 분석 ... 531
• 3. 피복재 합금 1 차 후보군 도출 및 시험 제조 ... 531
• 4. 피복재와 소듐 양립성 시험장치 설계/제작 ... 532
• 5. 후보 피복재 고온 크리프, 인장/충격 특성 시험 및 평가 ... 532
• 6. 피복재 합금 2차 후보군 도출 및 시험 제조 ... 533
• 7. 신피복재 고온 크리프 특성 시험 및 평가 ... 533
• 8 신피복재 합금 재료 규격 선정 ... 534
• 9. 신피복재와 소듐의 양립성 시험 ... 535
• 10 피복재 고온 크리프 시험 장치 설치 ... 536
• 11. 요약 ... 536
• 제 3 절 MA 함유 금속연료 성능평가 ... 537
• 1 개요 ... 537
• 2. 금속 핵연 료심/피복재 상호반응 예비평가 ... 537
• 3. 집합체 휨 및 연료봉 다발 굽힘 변형 평가 ... 538
• 4. MA 함유 금속연료 열전도도 모델개발 ... 538
• 5. 연료봉 다발 굽힘 및 접촉 변형 모델 평가 ... 539
• 6. MA함유 원소재 분배 모델 개발 ... 539
• 7. 고속로 조건 하나로 조사시험 캡슐 설계 ... 540
• 8. 금속핵 연료심/피복재 상호반응 노외 시험장치 설계 ... 540
• 9. MA 함유 금속핵연료 핵분열기체방출 모델 개발 ... 541
• 10. MA 함유 핵연료 예비성능 평가 ... 541
• 11. 금속연료 하나로 조사시험 캡슐 제작 ... 541
• 12. 금속핵 연료심 /피복재 상호 반응 시험장치 제작 ... 542
• 13. 요약 ... 542
• 제 4 절 실증로 금속연료 개념설계 ... 543
• 1. 개요 ... 543
• 2 금속연료 열기계적 인자 평가 ... 543
• 3 금속 연료 설계인자 생산 ... 544
• 4. 요약 ... 548
• 제 5 절 금속연료심 제조 기본기술 확보 ... 549
• 1. 개요 ... 549
• 2. 금속 연료심 제조 및 미세구조 분석 ... 549
• 3. 금속 연료심 재료물성 시험 및 평가 ... 551
• 4 금속연료심 표면 검사기술 개발 ... 553
• 5. 금속 연료심 제조공정 개발 ... 553
• 6 금속연료심 내부결함 겸사 기술 개발 ... 555
• 7. 금속연료봉 예비 제조 ... 557
• 8. 요약 ... 559
• 제 6 절 피복관 제조 기본기술 개발 ... 560
• 1. 개요 ... 560
• 2. 피복관 예비시 제품 제조 ... 560
• 3. 피복재 성능 시험 ... 561
• 4. 피복관 시험장치 제작 ... 564
• 5. 피복관 예비시제품 성능평가 ... 564
• 6 피복재 성능 시험 및 평가 ... 566
• 7. 피복관 제조 공정변수 평가 ... 567
• 8. 요약 ... 569
• 제 7 절 금속연료 성능평가 ... 570
• 1. 개요 ... 570
• 2 금속연료심 /피복재 상호반응 시험 ... 570
• 3. 금속연료 하나로 조사시험 ... 571
• 4.‘ 금속연료심 /피복관 상호반응 시험 및 평가 ... 574
• 5. MA 함유 금속 연료 성능분석 코드 (a 버전) ... 575
• 6 금속 연료 하나로 조사시험 및 조사후시험 ... 575
• 7. 요약 ... 576
• 제 4 장 목표달성도 및 관련분야에 기여도 ... 577
• 제 5 장 연구개발 결과의 활용계획 ... 584
• 제 6 장 연구개발과정에서 수집한 해외과학기술정보 ... 586
• 제 7 장 연구시설· 장비 현황 ... 589
• 제 8 장 참고문헌 ... 590
• 끝페이지 ... 596