VALIDATION OF NUMERICAL METHODS TO CALCULATE BYPASS FLOW IN A PRISMATIC GAS-COOLED REACTOR CORE

For thermo-fluid and safety analyses of a High Temperature Gas-cooled Reactor (HTGR), intensive efforts are in progress in the developments of the GAMMA+ code of Korea Atomic Energy Research Institute (KAERI) and the AGREE code of the University of Michigan (U of M). One of the important requirement...

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Main Authors: NAM-IL TAK, MIN-HWAN KIM, HONG-SIK LIM, JAE MAN NOH, TIMOTHY J. DRZEWIECKI, VOLKAN SEKER, THOMAS J. DOWNAR, JOSEPH KELLY
Formato: Artigo
Idioma:Inglês
Publicado em: Elsevier 2013-11-01
Colecção:Nuclear Engineering and Technology
Assuntos:
HTGR
Bypass Flow
Prismatic Core
GAMMA+
AGREE
Validation
Acesso em linha:http://www.sciencedirect.com/science/article/pii/S1738573315301765
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