Whole-core transport solution via deterministic S N transport/p-CMFD overlapping local/global calculation in hexagonal geometry problem

Author:

Yoo Han Jong,Imron Muhammad,Cho Nam Zin

Funder

National Research Foundation of Korea

MSIP

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 articles.

1. Alcouffe, R.E., Baker, R.S., Brinkley, F.W., Marr, D.R., O’Dell, R.D., Walters, W.F., 1995, DANTSYS 3.0—a diffusion-accelerated, neutral-particle transport code system, LA-12969-M. Los Alamos National Laboratory, RSICC Code Package CCC-0547/08.

2. Templates for the Solution of Linear Systems: Building Blocks for Iterative Methods;Barret,1994

3. Overlapping local/global iteration framework for whole-core transport solution;Cho;Nucl. Sci. Eng.,2013

4. On some outstanding problems in nuclear reactor analysis;Cho;Nucl. Eng. Technol.,2012

5. Overlap local/global iteration framework for monte carlo/diffusion nodal calculations;Cho;Trans. Am. Nucl. Soc.,2010

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