Directional diffusion coefficients and leakage-corrected discontinuity factors: Implementation in Serpent and tests-Reference-Cited by-同舟云学术

Directional diffusion coefficients and leakage-corrected discontinuity factors: Implementation in Serpent and tests

Published:2016-01 Issue: Volume:87 Page:101-112
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Dorval E.

Funder

YTERA

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference32 articles.

1. Blanchet, D., Buiron, L., Stauff, N., Kim, T.K., Taiwo, T., 2011. AEN – WPRS sodium fast reactor core definitions. Tech. Rep. version 1.2 – September 19th. CEA and Argonne National Laboratory.

2. Bretscher, M.M., February 1977. Computing control rod worths in thermal research reactors. Tech. Rep. ANL/RERTR/TM-29. Argonne National Laboratory.

3. Cross Sections Evaluation Working Group, 2010. ENDF-6 Formats Manual, Tech. Rep. BNL-90365-2009 Rev. 1. Brookhaven National Laboratory.

4. DeLorey, T., 1993. A transient, quadratic nodal method for triangular-Z geometry (Ph.D. thesis). Massachusetts Institute of Technology.

5. Dorval, E., 2014. TRIZ: multi-group neutron diffusion in triangular-Z geometry. Version 1.0. Tech. Rep. FF-2014-01. Aalto University School of Science.

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