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

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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Bibliographic Details
Main Authors: NAM-IL TAK, MIN-HWAN KIM, HONG-SIK LIM, JAE MAN NOH, TIMOTHY J. DRZEWIECKI, VOLKAN SEKER, THOMAS J. DOWNAR, JOSEPH KELLY
Format: Article
Language:English
Published: Elsevier 2013-11-01
Series:Nuclear Engineering and Technology
Subjects:
HTGR
Bypass Flow
Prismatic Core
GAMMA+
AGREE
Validation
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573315301765

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http://www.sciencedirect.com/science/article/pii/S1738573315301765

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