Transient characteristics of typical design basis accidents in integrated small reactor NHR200-II using RELAP5 model
Published 2023 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
Transient characteristics of typical design basis accidents in integrated small reactor NHR200-II using RELAP5 model
Authors
Keywords
-
Journal
ANNALS OF NUCLEAR ENERGY
Volume 192, Issue -, Pages 110014
Publisher
Elsevier BV
Online
2023-07-12
DOI
10.1016/j.anucene.2023.110014
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- SPH simulation of natural convection in a modeled reactor core using a new combinatorial kernel
- (2022) Nan Gui et al. ANNALS OF NUCLEAR ENERGY
- Loss of flow accident analysis in Atucha II nuclear power plant using RELAP5 model
- (2022) Santiago F. Corzo et al. NUCLEAR ENGINEERING AND DESIGN
- Prediction method for thermal-hydraulic parameters of nuclear reactor system based on deep learning algorithm
- (2021) Qi Lu et al. APPLIED THERMAL ENGINEERING
- BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D
- (2021) Fabio Alcaro et al. PROGRESS IN NUCLEAR ENERGY
- Study on LOFA and LOHS Accidents with Passive Safety System for Integrated Marine Reactor
- (2021) Dong Li et al. NUCLEAR SCIENCE AND ENGINEERING
- Techno-Economic Assessment of Fuel Cycle Facility of System Integrated Modular Advanced Reactor (SMART)
- (2021) Salah Ud-Din Khan et al. Sustainability
- Severe Accident Phenomena: A Comparison Among the NuScale SMR, Other Advanced LWR Designs, and Operating LWRs
- (2020) Scott J. Weber et al. NUCLEAR TECHNOLOGY
- Coupled 3D thermal–hydraulic and neutron kinetic Relap5 model for transient analysis of a 1200-MWe nuclear PWR plant
- (2020) Marco Palmero European Physical Journal Plus
- Recent progress of CFD applications in PWR thermal hydraulics study and future directions
- (2020) Mingjun Wang et al. ANNALS OF NUCLEAR ENERGY
- Third generation of vortex identification methods: Omega and Liutex/Rortex based systems
- (2019) Chaoqun Liu et al. Journal of Hydrodynamics
- A numerical investigation of SBLOCA scenario in nuclear heating reactor
- (2019) Meng Lu et al. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
- Re-assessment of station blackout accident in VVER-1000 NPP with additional measures following Fukushima accident using Relap/Mod3.2
- (2019) M. Jabbari et al. ANNALS OF NUCLEAR ENERGY
- Development of stability maps for flashing-induced instability in a passive containment cooling system for iPOWER
- (2019) Sang Gyu Lim et al. Nuclear Engineering and Technology
- Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition
- (2019) Weitong Li et al. Science and Technology of Nuclear Installations
- Review of Electromagnetic Vibration in Electrical Machines
- (2018) Xueping Xu et al. Energies
- ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions
- (2018) Takeshi Takeda Nuclear Engineering and Technology
- Severe accident management measures for a generic German PWR. Part II: Small-break loss-of-coolant accident
- (2018) M. Jobst et al. ANNALS OF NUCLEAR ENERGY
- Analysis of a loss-of-flow accident resulting from the primary pump shaft break transient of the NUR research reactor
- (2018) Mohammed Azzoune et al. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
- Development, validation and application of multi-point kinetics model in RELAP5 for analysis of asymmetric nuclear transients
- (2016) Santosh K. Pradhan et al. NUCLEAR ENGINEERING AND DESIGN
- The B&W mPower™ Scalable, Practical Nuclear Reactor Design
- (2016) Jeff A. Halfinger et al. NUCLEAR TECHNOLOGY
- Analytical validation of operator actions in case of primary to secondary leakage for VVER-1000/V320
- (2015) M. Andreeva et al. NUCLEAR ENGINEERING AND DESIGN
- Stability of self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: The stability performance of the CAREM-25 reactor
- (2013) C.P. Marcel et al. NUCLEAR ENGINEERING AND DESIGN
- Thermo-hydraulic experimental validation of an integrated modular small reactor operating in full power natural circulation
- (2013) XingTuan Yang et al. Science China-Technological Sciences
- The SCDAP/RELAP5 3.2 model of AP1000 on SBLOCA
- (2012) Heng Xie et al. PROGRESS IN NUCLEAR ENERGY
Find Funding. Review Successful Grants.
Explore over 25,000 new funding opportunities and over 6,000,000 successful grants.
ExploreBecome a Peeref-certified reviewer
The Peeref Institute provides free reviewer training that teaches the core competencies of the academic peer review process.
Get Started