Issue |
2014
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
|
|
---|---|---|
Article Number | 01104 | |
Number of page(s) | 6 | |
Section | 1. Computational Nuclear Applications: a. Nuclear Reactor Analysis | |
DOI | https://doi.org/10.1051/snamc/201401104 | |
Published online | 06 June 2014 |
Iterative Transport-Diffusion Methodology For LWR Core Analysis
1 The Pennsylvania State University, University Park, PA, USA
2 Westinghouse Electric Company LLC, Cranberry Township, PA, USA
* Corresponding Author, E-mail: kni1@psu.edu
This paper presents an update on the development of an advanced methodology for core calculations that uses local heterogeneous solutions for on-the-fly nodal cross-section generation. The Iterative Transport-Diffusion Method is an embedded transport approach that is expected to provide results with near 3D transport accuracy for a fraction of the time required by a full 3D transport method. In this methodology, the infinite environment used for homogenized nodal cross-section generation is replaced with a simulated 3D environment of the diffusion calculation. This update focuses on burnup methodology, axial leakage and 3D modeling.
Key words: NGM / ITDM / Embedded Transport / Partial Currents
© Owned by the authors, published by EDP Sciences, 2014