지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2015.4
- 수록면
- 253 - 259 (7page)
이용수
초록· 키워드
오류제보하기
The fast neutron reactor BOR-60 is one of the key experimental facilities worldwide to perform large-scale tests of fuel, absorbing, and structural materials for advanced reactors. The BOR-60 reactor was put into operation in December 1969, and by the end of 2014 it had been operating on power for ∼265,000 hours. BOR-60 still demonstrates potential capabilities to extend the lifetime of sodium-cooled fast reactors. The BOR-60 lifetime should have expired at the end of 2014. Over the past few years, a great scope of work has been performed to justify the possibility of extending its lifetime. The work included inspection of the equipment conditions, calculations and experimental research on operating parameters and the conditions of nonremovable components, investigation of the structural material samples after their long-term operation under irradiation, etc. Based on the results of the work performed, the residual lifetime was evaluated and the reactor operator made a decision to extend the lifetime period of the BOR-60 reactor. After considering both a set of documents about the reactor conditions and the positive decision of independent experts, the Regulatory Authority of the Russian Federation extended the BOR-60 operating license up to 2020.
목차
등록된 정보가 없습니다.
참고문헌 (8)
참고문헌 신청
A. L. Izhutov / 2010 / Prolongation of the BOR-60 Reactor Operation / RRFM-2010 conference
International Atomic Energy Agency / 1995 / Management of Research Reactor Ageing
E. A. Gomin / 1994 / Marin Description of Application and Instruction for the User of the MCU-RFFI Calculation Program of the Neutron-physical Characteristics of Nuclear Reactors by the Monte Carlo Method
A.V. Varivtsev / 2014 / Improved method for calculating the radiation heat generation in the BOR-60reactor / Phys. At. Nucl 77(14):1664~1670
J. E. Flinn / 1976 / Neutron Swelling Observation on Austenitic Stainless Steels Irradiated in EBR-II / Proceedings of the Workshop on Correlation of Neutron and Charged Particle Damage
International Atomic Energy Agency / 1995 / Management of Research Reactor Ageing
E. A. Gomin / 1994 / Marin Description of Application and Instruction for the User of the MCU-RFFI Calculation Program of the Neutron-physical Characteristics of Nuclear Reactors by the Monte Carlo Method
A.V. Varivtsev / 2014 / Improved method for calculating the radiation heat generation in the BOR-60reactor / Phys. At. Nucl 77(14):1664~1670
J. E. Flinn / 1976 / Neutron Swelling Observation on Austenitic Stainless Steels Irradiated in EBR-II / Proceedings of the Workshop on Correlation of Neutron and Charged Particle Damage
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
행동경영과학(BOR)에 관한 연구동향
대한산업공학회 춘계공동학술대회 논문집
2018 .04
-
대용량 액체수소 저장탱크의 BOR 성능에 관한 연구
한국가스학회 학술대회논문집
2024 .05
-
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
-
Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications
방사성폐기물학회지
2018 .01
-
열저항 네트워크 모델을 이용한 LNG 화물창 Scale Effect 분석
대한조선학회 논문집
2023 .08
-
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
Nuclear Engineering and Technology
2024 .06
-
Vessel failure sensitivities of an advanced reactor for SBLOCA
Nuclear Engineering and Technology
2020 .01
-
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
-
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
-
On the cyclic change in the dynamics of the IBR-2M pulsed reactor
Nuclear Engineering and Technology
2023 .05
-
A simple method for estimating the major nuclide fractional ?ssion rates within light water and advanced gas cooled reactors
Nuclear Engineering and Technology
2020 .09
-
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
-
Comparative study on response of thiocyanate shock load on continuous and fed batch anaerobic-anoxic-aerobic sequential moving bed reactors
Environmental Engineering Research
2015 .03
-
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
-
Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
Nuclear Engineering and Technology
2020 .01
-
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
-
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
-
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
-
Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
Nuclear Engineering and Technology
2021 .06
-
Optimization of a Tilted-Slide Reactor Operation for the Fast Pyrolysis of Biomass
AFORE
2021 .10
이 논문의 저자 정보
최근 본 자료
댓글(0)
0