Explicit decay heat calculation in the nodal diffusion code DYN3D-Reference-Cited by-同舟云学术

Explicit decay heat calculation in the nodal diffusion code DYN3D

Published:2018-11 Issue: Volume:121 Page:374-381
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Bilodid Y.^ORCID,Fridman E.^ORCID,Kotlyar D.^ORCID,Shwageraus E.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference28 articles.

1. ANSI/ANS-5.1-, 2005. Decay Heat Power in Light Water Reactors.

2. Austregesilo, H., Bals, C., Hora, A., Lerchl, G., Romstedt, P., 2006. ATHLET, Mod 2.1 Cycle A, Models and Methods, GRS – P – 1/Vol. 4, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Germany.

3. Becker, A., Anton, G., Børresen, S., 2009. SNF: Spent fuel analyses based on casmo/simulate in-core fuel management, in: American Nuclear Society – 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV.

4. The HEXNEM3 nodal flux expansion method for the hexagonal geometry in the code DYN3D;Bilodid;Ann. Nucl. Energy,2018

5. Hybrid microscopic depletion model in nodal code DYN3D;Bilodid;Ann. Nucl. Energy,2016

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