| 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: This email address is being protected from spambots. You need JavaScript enabled to view it.
Abstract
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

