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
- 2020.11
- 수록면
- 2,442 - 2,451 (10page)
- DOI
- https://doi.org/10.1016/j.net.2020.04.021
이용수
초록· 키워드
오류제보하기
The safety level of Sodium Fast Reactors is directly related with the sodium void reactivity. A low-voideffect design has been proposed within the Horizon2020 ESFR-SMART project thanks to the introductionof a sodium plenum above the active core. In order to assess the impact of this core conception ontransient analysis, a map with the spatial distribution of sodium void worth can be computed and fedinto a point-kinetics-based transient code. Due to the spatial correlations between neighboring zones,the global effect of voiding two different axial or radial regions is not necessarily the sum of both individual contributions. Neglecting those correlations in the void worth map and consequently in thetransient analysis may lead to an unrealistic prediction of the transient sequences. In this work, a methodbased on sensitivity analysis and similarity assessment is proposed for predicting those correlations. Themethod proved to be able to establish correlations between axial slices of a sub-assembly and waschecked against realistic sodium void propagation patterns
목차
등록된 정보가 없습니다.
참고문헌 (19)
참고문헌 신청
K. Mikityuk / 2017 / ESFRSMART:new Horizon-2020 project on SFR safety / Int. Conf. On Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
A. Lazaro / 2014 / Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II : optimised core and representative transient analysis / Nucl. Eng. Des 277:265~276
F. Varaine / 2012 / Pre-conceptual design study of ASTRID core / International Congress on Advances in Nuclear Power Plants
J. Guidez / 2018 / New safety measures proposed for European sodium fast reactor in horizon-2020 ESFR-SMART project / Generation-IV International Forum Symposium, France, Paris
J. Krepel / 2015 / Mapping of sodium void worth and Doppler effect for sodium-cooled fast reactor / International Congress on Advances in Nuclear Power Plants, Nice, France
A. Lazaro / 2014 / Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II : optimised core and representative transient analysis / Nucl. Eng. Des 277:265~276
F. Varaine / 2012 / Pre-conceptual design study of ASTRID core / International Congress on Advances in Nuclear Power Plants
J. Guidez / 2018 / New safety measures proposed for European sodium fast reactor in horizon-2020 ESFR-SMART project / Generation-IV International Forum Symposium, France, Paris
J. Krepel / 2015 / Mapping of sodium void worth and Doppler effect for sodium-cooled fast reactor / International Congress on Advances in Nuclear Power Plants, Nice, France
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
An ultra-long-life small safe fast reactor core concept having heterogeneous driver-blanket fuel assemblies
Nuclear Engineering and Technology
2021 .11
-
Physics Study of Canada Deuterium Uranium Lattice with Coolant Void Reactivity Analysis
Nuclear Engineering and Technology
2017 .01
-
멀티 스케일 기법을 이용한 결함의 거동 변화 예측
한국소성가공학회 학술대회 논문집
2016 .04
-
Research on void drift between rod bundle subchannels
Nuclear Engineering and Technology
2024 .08
-
SAFETY ASPECTS OF INTERMEDIATE HEAT TRANSPORT AND DECAY HEAT REMOVAL SYSTEMS OF SODIUM-COOLED FAST REACTORS
Nuclear Engineering and Technology
2015 .04
-
Dynamic data validation and reconciliation for improving the detection of sodium leakage in a sodium-cooled fast reactor
Nuclear Engineering and Technology
2023 .04
-
Review on sodium corrosion evolution of nuclear-grade 316 stainless steel for sodium-cooled fast reactor applications
Nuclear Engineering and Technology
2021 .11
-
소듐냉각고속로 잔열제거계통의 나선형 소듐-공기 열교환기 해석을 위한 1차원 시스템 코드 모델링 및 해석
대한기계학회 춘추학술대회
2024 .11
-
EP-Cu 증착 공정에서의 전류 조건에 따른 Void 생성 관계 연구
한국정밀공학회 학술발표대회 논문집
2016 .05
-
High-temperature integrity evaluation of finned-tube sodium-to-air heat exchanger in a sodium test facility
대한기계학회 춘추학술대회
2016 .04
-
Experimental study of sodium fire and its characteristics under the coupling action of columnar liquid sodium flow and concrete
Nuclear Engineering and Technology
2021 .09
-
Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit
Nuclear Engineering and Technology
2016 .01
-
Experimental study on capture of carbon dioxide and production of sodium bicarbonate from sodium hydroxide
Environmental Engineering Research
2016 .09
-
Two-Way Flexural Behavior of Donut-Type Voided Slabs
International Journal of Concrete Structures and Materials
2018 .03
-
Study on dynamic interaction between crack and inclusion or void by using XFEM
Structural engineering and mechanics : An international journal
2017 .01
-
소듐금속화재에 대한 아르곤 가스 소화약제의 적용성 분석
한국위험물학회지
2020 .06
-
베타 컴플렉스를 이용한 평면에서 원들의 빈 공간 분석법
한국CDE학회 논문집
2019 .09
-
Programmatic Void: A Design Methodology : Case Study Analysis of SANAA’s 《New Mercedes-Benz Museum》 and 《Rolex Learning Center》
대한건축학회 학술발표대회 논문집
2022 .10
-
RECYCLING OPTION SEARCH FOR A 600-MWE SODIUM-COOLED TRANSMUTATION FAST REACTOR
Nuclear Engineering and Technology
2015 .01
-
액체소듐 및 소듐-탄산소듐혼합물의 전기전도도 특성
한국신·재생에너지학회 학술대회 초록집
2015 .11
이 논문의 저자 정보
최근 본 자료
댓글(0)
0