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
- 2019.1
- 수록면
- 1,272 - 1,278 (7page)
이용수
초록· 키워드
오류제보하기
A lumped kinetic modeling platform is developed to investigate the coupled nuclear/thermo-fluid featuresof the closed natural circulation loop in a low power lead cooled fast reactor. This coolant materialserves a reliable choice with noticeable thermo-physical safety characteristics in terms of natural convection. Boussienesq approximation is resorted to appropriately reduce the governing partial differentialequations (PDEs) for the fluid flow into a set of ordinary differential equations (ODEs). As a maincontributing step, the coolant circulation speed is accordingly correlated to the loop operational powerand temperature levels. Further temporal analysis and control synthesis activities may thus be carriedout within a more consistent state space framework. Nyquist stability criterion is thereafter employed tocarry out a sensitivity analysis for the system stability at various power and heat sink temperature levelsand results confirm a widely stable natural circulation loop
목차
등록된 정보가 없습니다.
참고문헌 (18)
참고문헌 신청
D. T. Ingersoll / 2009 / Deliberately small reactors and the second nuclear era / Prog. Nucl. Energy 51:589~603
H. van Dam / 1992 / Physics of nuclear reactor safety / Rep. Prog. Phys 11:2025~2077
Y. Zvirin / 1981 / A review of natural circulation loops in pressurized water reactors and other systems / Nucl. Eng. Des 67:203~225
J. Vujic / 2012 / Small modular reactors: simpler, safer, faster? / Energy 43:288~295
L. Cinotti / 2011 / Lead cooled system design and challenges in the frame of Generation IV international forum / J. Nucl. Mater 415:245~253
H. van Dam / 1992 / Physics of nuclear reactor safety / Rep. Prog. Phys 11:2025~2077
Y. Zvirin / 1981 / A review of natural circulation loops in pressurized water reactors and other systems / Nucl. Eng. Des 67:203~225
J. Vujic / 2012 / Small modular reactors: simpler, safer, faster? / Energy 43:288~295
L. Cinotti / 2011 / Lead cooled system design and challenges in the frame of Generation IV international forum / J. Nucl. Mater 415:245~253
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
연구용 원자로에서 자연대류 냉각 시 원자로구조물 유동의 전산유체역학 분석
대한기계학회 춘추학술대회
2019 .11
-
Sensitivity analysis of numerical schemes in natural cooling flows for low power research reactors
Advances in energy research
2017 .01
-
전산유체역학을 이용한 연구용 원자로에서의 자연대류 연구
대한기계학회 춘추학술대회
2018 .12
-
Experimental investigation of two-phase natural circulation loop as passive containment cooling system
Nuclear Engineering and Technology
2021 .12
-
Numerical simulation of a toroidal single-phase natural circulation loop with a k-k-ω transitional turbulence model
Nuclear Engineering and Technology
2024 .01
-
Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate
Nuclear Engineering and Technology
2022 .01
-
Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor
Nuclear Engineering and Technology
2020 .12
-
단순화된 피동 원자로건물 냉각계통 내 자연순환에 관한 수치적 연구
한국안전학회지
2018 .01
-
Investigation of two-phase natural circulation with the SMART-ITL facility for an integral type reactor
Nuclear Engineering and Technology
2022 .03
-
Effects of decay heat and cooling condition on the reactor pool natural circulation under RVACS operation in a water 2-D slab model
Nuclear Engineering and Technology
2023 .05
-
EVALUATION OF PLANT OPERATIONAL STATES WITH THE CONSIDERATION OF LOOP STRUCTURES UNDER ACCIDENT CONDITIONS
Nuclear Engineering and Technology
2015 .01
-
Numerical Analysis of the Temperature Distribution of the EM Pump for the Sodium Thermo-hydraulic Test Loop of the GenIV PGSFR
Nuclear Engineering and Technology
2021 .05
-
Assessment of MARS-KS prediction capability for natural circulation flow in passive heat removal system
Nuclear Engineering and Technology
2024 .08
-
Study on load tracking characteristics of closed Brayton conversion liquid metal cooled space nuclear power system
Nuclear Engineering and Technology
2024 .05
-
강제 공냉식에 의한 LED 전구 수명연장에 관한 연구
동력시스템공학회지
2018 .08
-
Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition
Nuclear Engineering and Technology
2019 .01
-
Development and validation of the lead-bismuth cooled reactor system code based on a fully implicit homogeneous flow model
Nuclear Engineering and Technology
2024 .04
-
Discharge header design inside a reactor pool for flow stability in a research reactor
Nuclear Engineering and Technology
2020 .10
-
마이크로채널 반응기를 이용한 강화된 저온 피셔-트롭쉬 합성반응의 전산유체역학적 해석
한국가스학회지
2017 .08
-
대형원전 냉각재 순환계통 모의 유동실험의 압력섭동과 진동응답 신호주기성 분석
한국유체기계학회 학술대회 논문집
2019 .07
이 논문의 저자 정보
최근 본 자료
댓글(0)
0