VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods
Published 2022 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods
Authors
Keywords
-
Journal
ANNALS OF NUCLEAR ENERGY
Volume 178, Issue -, Pages 109335
Publisher
Elsevier BV
Online
2022-07-21
DOI
10.1016/j.anucene.2022.109335
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- Development and preliminary application of deterministic code NECP-FISH for neutronics analysis of fusion-reactor blanket
- (2022) Jianxin Miao et al. ANNALS OF NUCLEAR ENERGY
- Variational nodal methods for neutron transport: 40 years in review
- (2022) Tengfei Zhang et al. Nuclear Engineering and Technology
- Application of stiffness confinement method within variational nodal method for solving time-dependent neutron transport equation
- (2022) Wei Xiao et al. COMPUTER PHYSICS COMMUNICATIONS
- Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application
- (2021) Yaqi Wang et al. NUCLEAR TECHNOLOGY
- Variational nodal method for three-dimensional multigroup neutron diffusion equation based on arbitrary triangular prism
- (2021) Kun Zhuang et al. ANNALS OF NUCLEAR ENERGY
- Development of high-fidelity neutron transport code STREAM
- (2021) Sooyoung Choi et al. COMPUTER PHYSICS COMMUNICATIONS
- Analysis and comparison of the 2D/1D and quasi-3D methods with the direct transport code SHARK
- (2021) Chen Zhao et al. Nuclear Engineering and Technology
- High-fidelity multi-physics coupling study on advanced heat pipe reactor
- (2021) Wei Xiao et al. COMPUTER PHYSICS COMMUNICATIONS
- Perturbation Theory-Based Whole-Core Eigenvalue Sensitivity and Uncertainty (SU) Analysis via a 2D/1D Transport Code
- (2020) Ji Ma et al. Science and Technology of Nuclear Installations
- Quadratic axial expansion function with sub-plane acceleration scheme for the high-fidelity transport code PROTEUS-MOC
- (2020) Guangchun Zhang et al. ANNALS OF NUCLEAR ENERGY
- Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors
- (2019) Tengfei Zhang et al. ANNALS OF NUCLEAR ENERGY
- A hybrid acceleration method to pin-by-pin calculations using the heterogeneous variational nodal method
- (2019) Tengfei Zhang et al. ANNALS OF NUCLEAR ENERGY
- Comparison of the performance of heterogeneous variational nodal method and 2D/1D-MOC on pin-resolved neutron transport calculations of PWR
- (2019) Yongping Wang et al. ANNALS OF NUCLEAR ENERGY
- A new high-fidelity neutronics code NECP-X
- (2018) Jun Chen et al. ANNALS OF NUCLEAR ENERGY
- Acceleration of 3D pin-by-pin calculations based on the heterogeneous variational nodal method
- (2018) Tengfei Zhang et al. ANNALS OF NUCLEAR ENERGY
- Acceleration of within group iteration for pin-by-pin calculations
- (2018) Tengfei Zhang et al. ANNALS OF NUCLEAR ENERGY
- Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core
- (2018) Wen Yang et al. NUCLEAR ENGINEERING AND DESIGN
- An improved variational nodal method for the solution of the three-dimensional steady-state multi-group neutron transport equation
- (2018) Tengfei Zhang et al. NUCLEAR ENGINEERING AND DESIGN
- Transient analysis of C5G7-TD benchmark with MPACT
- (2018) Qicang Shen et al. ANNALS OF NUCLEAR ENERGY
- OECD/NEA benchmark for time-dependent neutron transport calculations without spatial homogenization
- (2017) Jason (Jia) Hou et al. NUCLEAR ENGINEERING AND DESIGN
- A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors
- (2017) Tengfei Zhang et al. NUCLEAR SCIENCE AND ENGINEERING
- A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport for Pressurized Water Reactors
- (2017) Tengfei Zhang et al. NUCLEAR SCIENCE AND ENGINEERING
- The OpenMC Monte Carlo particle transport code
- (2012) Paul K. Romano et al. ANNALS OF NUCLEAR ENERGY
- FAST REACTOR PHYSICS AND COMPUTATIONAL METHODS
- (2012) W.S. Yang Nuclear Engineering and Technology
- Gram-Schmidt orthogonalization: 100 years and more
- (2012) Steven J. Leon et al. NUMERICAL LINEAR ALGEBRA WITH APPLICATIONS
- The 3-D time-dependent transport code TORT-TD and its coupling with the 3D thermal-hydraulic code ATTICA3D for HTGR applications
- (2011) A. Seubert et al. NUCLEAR ENGINEERING AND DESIGN
- Gmsh: A 3-D finite element mesh generator with built-in pre- and post-processing facilities
- (2009) Christophe Geuzaine et al. INTERNATIONAL JOURNAL FOR NUMERICAL METHODS IN ENGINEERING
Find the ideal target journal for your manuscript
Explore over 38,000 international journals covering a vast array of academic fields.
SearchAdd 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 Now