Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods
Published 2020 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods
Authors
Keywords
Heat pipe cooled reactor, Neutronic and thermal–mechanical coupling, Monte Carlo method, Finite element method
Journal
ANNALS OF NUCLEAR ENERGY
Volume 151, Issue -, Pages 107923
Publisher
Elsevier BV
Online
2020-11-02
DOI
10.1016/j.anucene.2020.107923
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- Neutronics and thermal-hydraulics coupling analysis in accelerator-driven subcritical system
- (2020) Yugao Ma et al. PROGRESS IN NUCLEAR ENERGY
- Heat pipe failure accident analysis in megawatt heat pipe cooled reactor
- (2020) Yugao Ma et al. ANNALS OF NUCLEAR ENERGY
- Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
- (2019) Chenglong Wang et al. Nuclear Engineering and Technology
- The JFNK method for the PWR's transient simulation considering neutronics, thermal hydraulics and mechanics
- (2019) Qingming He et al. Nuclear Engineering and Technology
- RMC/CTF multiphysics solutions to VERA core physics benchmark problem 9
- (2019) Yugao Ma et al. ANNALS OF NUCLEAR ENERGY
- Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis
- (2019) Jincheng Wang et al. ANNALS OF NUCLEAR ENERGY
- The technology of micro heat pipe cooled reactor: A review
- (2019) B.H. Yan et al. ANNALS OF NUCLEAR ENERGY
- On-the-fly treatment of temperature dependent cross sections in the unresolved resonance region in RMC code
- (2018) Shichang Liu et al. ANNALS OF NUCLEAR ENERGY
- Conceptual design and analysis of a multipurpose micro nuclear reactor power source
- (2018) Hao Sun et al. ANNALS OF NUCLEAR ENERGY
- Numerical Methods in Coupled Monte Carlo and Thermal-Hydraulic Calculations
- (2017) Daniel F. Gill et al. NUCLEAR SCIENCE AND ENGINEERING
- Analysis of BEAVRS two-cycle benchmark using RMC based on full core detailed model
- (2017) Kan Wang et al. PROGRESS IN NUCLEAR ENERGY
- MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6
- (2017) Brian N. Aviles et al. PROGRESS IN NUCLEAR ENERGY
- Development of on-the-fly temperature-dependent cross-sections treatment in RMC code
- (2016) Shichang Liu et al. ANNALS OF NUCLEAR ENERGY
- Modeling and simulation challenges pursued by the Consortium for Advanced Simulation of Light Water Reactors (CASL)
- (2016) Paul J. Turinsky et al. JOURNAL OF COMPUTATIONAL PHYSICS
- Advanced multiphysics coupling for LWR fuel performance analysis
- (2015) J.D. Hales et al. ANNALS OF NUCLEAR ENERGY
- RMC – A Monte Carlo code for reactor core analysis
- (2015) Kan Wang et al. ANNALS OF NUCLEAR ENERGY
- Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project
- (2015) Bruno Chanaron et al. ANNALS OF NUCLEAR ENERGY
- Physics-based multiscale coupling for full core nuclear reactor simulation
- (2015) Derek R. Gaston et al. ANNALS OF NUCLEAR ENERGY
- Monte Carlo domain decomposition for robust nuclear reactor analysis
- (2014) Nicholas Horelik et al. PARALLEL COMPUTING
- Full scope thermal-neutronic analysis of LOFA in a WWER-1000 reactor core by coupling PARCS v2.7 and COBRA-EN
- (2014) Omid Noori-Kalkhoran et al. PROGRESS IN NUCLEAR ENERGY
- Coupled neutronics thermal-hydraulics analysis using Monte Carlo and sub-channel codes
- (2012) Miriam Vazquez et al. NUCLEAR ENGINEERING AND DESIGN
- MOOSE: A parallel computational framework for coupled systems of nonlinear equations
- (2009) Derek Gaston et al. NUCLEAR ENGINEERING AND DESIGN
Add your recorded webinar
Do you already have a recorded webinar? Grow your audience and get more views by easily listing your recording on Peeref.
Upload NowAsk a Question. Answer a Question.
Quickly pose questions to the entire community. Debate answers and get clarity on the most important issues facing researchers.
Get Started