DEVELOPMENT OF A CORE THERMO-FLUID ANALYSIS CODE FOR PRISMATIC GAS COOLED REACTORS

A new computer code, named CORONA (Core Reliable Optimization and thermo-fluid Network Analysis), was developed for the core thermo-fluid analysis of a prismatic gas cooled reactor. The CORONA code is targeted for whole-core thermo-fluid analysis of a prismatic gas cooled reactor, with fast computat...

Full description

Bibliographic Details
Main Authors: NAM-IL TAK, SUNG NAM LEE, MIN-HWAN KIM, HONG SIK LIM, JAE MAN NOH
Format: Article
Language:English
Published: Elsevier 2014-10-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573315301042