A5061182900- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
- Nuclear physics research studies
- Advanced Numerical Methods in Computational Mathematics
- Superconducting Materials and Applications
- NMR spectroscopy and applications
- Fusion materials and technologies
- Radiation Effects in Electronics
- Numerical methods for differential equations
- Advanced Mathematical Modeling in Engineering
- earthquake and tectonic studies
- Advanced Battery Technologies Research
- Earthquake Detection and Analysis
- Cold Fusion and Nuclear Reactions
- Recycling and Waste Management Techniques
- Statistical and numerical algorithms
- Radioactive Decay and Measurement Techniques
Idaho National Laboratory
2009-2024
Brookhaven National Laboratory
2013
Oak Ridge National Laboratory
2013
Office of Nuclear Physics
2013
Office of Science
2013
North Carolina State University
2003-2006
Pennsylvania State University
2001
Tokyo Gakugei University
1977
In this paper, a new neutron kinetics solver for cylindrical R-Z geometry, CYNOD, is presented the simulation of coupled transient problems pebble bed reactors. The code utilizes Direct Coarse Mesh Finite Difference method, in which set one-dimensional equations each transverse direction solved by means analytic Green’s function method. A method that deals with control rod cusping also presented. heterogeneous fuel kernel model implemented order to accurately take into account Doppler...
In this paper, the development is presented of a splitting method that can efficiently solve coarse-mesh discretized low-order quasi-diffusion (LOQD) equations. The LOQD problem reproduce exactly transport scalar flux and current. To equations efficiently, proposed. splits into two parts: (a) D captures significant part solution in central parts assemblies be reduced to diffusion-type equation (b) Q accounts for complicated behavior near assembly boundaries. Independent discretizations are...
In this paper, we develop a homogenization methodology for the two-dimensional low-order quasi-diffusion equations full-core reactor calculations that is based on family of spatially consistent coarse-mesh discretization methods. The solution generated by these methods preserves number spatial moments fine-mesh transport over each assembly. proposed method reproduces accurately complicated large-scale behavior within assemblies. To demonstrate performance developed methodology, present...