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정책동향보고서

제목 글로벌) 트랜스우라늄 관리를 위한 국제 협력 활용: 비교 연구
국가 [글로벌]  출처 NEA
산업구분 [원자력발전]  등록일 2026.06.22
본 보고서는 원자력기구(NEA) 전문가 그룹이 다양한 원자로 기술과 국제 협력을 통해 트랜스우라늄(TRU) 관리 전략을 비교·분석한 보고서이다.
원문 제목 및 목차
제목 :
Harnessing International Co-operation for the Management of Transuranics: A Comparative Study
원문목차 :
List of abbreviations and acronyms .................................................................................................. 13 

Executive summary .............................................................................................................................. 15 

1. Introduction ....................................................................................................................................... 17 

2. Phase 1: Evaluation of different scenarios for TRU management ............................................ 19 
 2.1. Core concepts used in Phase 1 and the overall description of scenarios ........................... 19 
 2.2. Phase 1 Scenario evaluation ..................................................................................................... 20 
 2.3. Summary and conclusions of Phase 1 ..................................................................................... 50 

3. Phase 2: Analysis of the “most promising” scenarios ............................................................... 55 
 3.1. Introduction ................................................................................................................................ 55 
 3.2. Common reference framework ................................................................................................ 56 
 3.3. Presentation of the specificities of the eight chosen scenarios ........................................... 58 
 3.4. Results .......................................................................................................................................... 65 
 3.5. Summary and conclusions of Phase 2 ..................................................................................... 87 
 References .......................................................................................................................................... 88 

4. Conclusions ....................................................................................................................................... 89 
 
Appendix A. Reactor types considered in the study ...................................................................... 91 
 A.1. PWR UOX .................................................................................................................................... 91 
 A.2. PWR MOX UE IMR ...................................................................................................................... 92 
 A.3. Sodium fast reactors ................................................................................................................. 93 
 A.4. GFR2400 ....................................................................................................................................... 96 
 A.5. SFR burner concept.................................................................................................................... 98 
 A.6. ADS .............................................................................................................................................. 99 
 References ........................................................................................................................................ 100 

Appendix B. Description of the common framework used in Phase 1 ..................................... 101 
 B.1. Reactors ..................................................................................................................................... 102 
 B.2. Plants ......................................................................................................................................... 103 
 B.3. Data compilation for the study .............................................................................................. 103 
 B.4. Expected outputs ...................................................................................................................... 104 
 
Appendix C. Simulated scenarios in Phase 2 ................................................................................ 107 
 C.1. Operational parameters .......................................................................................................... 107 
 C.2. Flows of nuclear material ....................................................................................................... 109 
 
Appendix D. Detailed results in Phase 2 ........................................................................................ 113 
 D.1. All results .................................................................................................................................. 113 
 D.2. Results within groups ............................................................................................................. 122 
 D.3. Effect of Country B ................................................................................................................... 147
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