Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries

Author:

Hou J.,Choi H.,Ivanov K.N.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference21 articles.

1. AEA, 1997. WIMSD: A Neutronics Code for Standard Lattice Physics Analysis. ANSWERS Software Service, AEA Technology.

2. Bandini, B., 1990. A three-dimensional transient neutronics routine for the TRAC-PF1 reactor thermal hydraulic computer code. Ph.D. Thesis, Pennsylvania State University.

3. Cathalau, S., Lefebvre, J.C., West, J.P., 1996. Proposal for a second stage of the benchmark on power distributions within assemblies, NEA/NSC/DOC (96)2, Nuclear Energy Agency.

4. Colameco, D., 2012. Next generation Iterative Transport-Diffusion Methodology (ITDM) for LWR Core Analysis, Ph.D. Thesis, Pennsylvania State University.

5. Derstine, K.L., 1984. DIF3D: A code to solve one-, two-, and three-dimensional finite-difference diffusion theory problems, ANL-82-64, Argonne National Laboratory.

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