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
- 2021.10
- 수록면
- 3,182 - 3,195 (14page)
- DOI
- https://doi.org/10.1016/j.net.2021.04.015
이용수
초록· 키워드
오류제보하기
The implementation and validation of multi-dimensional (multi-D) features in thermal-hydraulic systemcodes aims to extend the application of these codes towards multi-scale simulations. The main goal is thesimulation of large-scale three-dimensional effects inside large volumes such as piping or vessel. Thisnovel approach becomes especially relevant during the simulation of accidents with strongly asymmetricflow conditions entailing density gradients. Under such conditions, coolant mixing is a key phenomenonon the eventual variation of the coolant temperature and/or boron concentration at the core inlet and onthe extent of a local re-criticality based on the reactivity feedback effects. This approach presents severaladvantages compared to CFD calculations, mainly concerning the model size and computational efforts.
However, the range of applicability and accuracy of the newly implemented physical models at this pointis still limited and needs to be further extended. This paper aims at contributing to the validation of themulti-D features of the system code ATHLET based on the simulation of the Tests 1.1 and 2.1, conducted atthe test facility ROCOM. Overall, the multi-D features of ATHLET predict reasonably well the evolutionfrom both experiments, despite an observed overprediction of coolant mixing at the vessel during bothexperiments
목차
등록된 정보가 없습니다.
참고문헌 (24)
참고문헌 신청
OECD / 1995 / Proceedings of the OECD/NEA/CSNI Specialist Meeting on Boron Dilution Reactivity Transients vol. 96, NEA/CSNI/R / Comitee on the Safety of Nuclear Installations OECD Nuclear Energy Agency :3
S. Kliem / 2004 / Core response of a PWR to a slug of under-borated water / Nucl. Eng. Des 230:121~132
S. Kliem / 2012 / OECD PKL2 Project e Final Report on the ROCOM Tests
S. Kliem / 2016 / OECD PKL3 Project e Final Report on the ROCOM Tests
U. Rohde / The European project FLOMIX-R: description of the slug mixing and buoyancy related experimens at the different test facilities, Final report on WP2. Technical Report FZR-430
S. Kliem / 2004 / Core response of a PWR to a slug of under-borated water / Nucl. Eng. Des 230:121~132
S. Kliem / 2012 / OECD PKL2 Project e Final Report on the ROCOM Tests
S. Kliem / 2016 / OECD PKL3 Project e Final Report on the ROCOM Tests
U. Rohde / The European project FLOMIX-R: description of the slug mixing and buoyancy related experimens at the different test facilities, Final report on WP2. Technical Report FZR-430
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
On the validation of ATHLET 3-D features for the simulation of multidimensional flows in horizontal geometries under single-phase subcooled conditions
Nuclear Engineering and Technology
2022 .09
-
Validation of CFD Calculation Using ROCOM Flow Measurements in Primary Loop of Coolant in PWR Model
Nuclear Engineering and Technology
2016 .01
-
CFD study of the PTS experiment in ROCOM test facility
Nuclear Engineering and Technology
2020 .12
-
Unsteady Single-Phase Natural Circulation Flow Mixing Prediction Using CATHARE Three-Dimensional Capabilities
Nuclear Engineering and Technology
2017 .01
-
원자로 내 붕소 혼합 현상 예측
한국유체기계학회 학술대회 논문집
2021 .07
-
Transient full core analysis of PWR with multi-scale and multi-physics approach
Nuclear Engineering and Technology
2024 .03
-
Comparative study of CFD and 3D thermal-hydraulic system codes in predicting natural convection and thermal stratification phenomena in an experimental facility
Nuclear Engineering and Technology
2023 .04
-
Thermal-hydraulic 0D/3D coupling in OpenFOAM: Validation and application in nuclear installations
Nuclear Engineering and Technology
2023 .05
-
CFD/RELAP5 Coupling Analysis of the ISP No. 43 Boron Dilution Experiment
Nuclear Engineering and Technology
2022 .01
-
Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests
Nuclear Engineering and Technology
2022 .11
-
Hydraulic performance and flow resistance tests of various hydraulic parts for optimal design of a reactor coolant pump for a small modular reactor
Nuclear Engineering and Technology
2023 .03
-
Review of researches on coupled system and CFD codes
Nuclear Engineering and Technology
2021 .09
-
이종 냉각수 활용 3중 열교환기 적용 전동식 냉방시스템 성능 특성 연구
한국자동차공학회 춘계학술대회
2016 .05
-
CFD Simulation of Multiphase Flow by Mud Agitator in Drilling Mud Mixing System
한국해양공학회지
2021 .04
-
SMART 유동혼합헤더집합체 열혼합 특성 해석
한국전산유체공학회지
2015 .03
-
Uncertainty quantifi cation of the power control system of a small PWR with coolant temperature perturbation
Nuclear Engineering and Technology
2022 .06
-
최적화 설계를 통한 혼합가스 성능시험용 고온 고압 용기의 제작
한국기계가공학회지
2019 .11
-
Transient Safety Analysis of M2LFR-1000 Reactor using ATHLET
Nuclear Engineering and Technology
2019 .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
-
Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel
Nuclear Engineering and Technology
2021 .01
이 논문의 저자 정보
최근 본 자료
댓글(0)
0