RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS-Reference-Cited by-同舟云学术

RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS

Published:2014-10 Issue:5 Volume:46 Page:655-666
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

YOON HAN YOUNG,LEE JAE RYONG,KIM HYUNGRAE,PARK IK KYU,SONG CHUL-HWA,CHO HYOUNG KYU,JEONG JAE JUN

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. “Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1,”;Jeong;Annals of Nuclear Energy,1999

2. “A semi-implicit method for two-phase fluid dynamics,”;Lilies;Journal of Computational Physics,1978

3. M. Robert, M. Farvacque, M. Parent, and B. Faydide, “CATHARE 2 V2.5: A Fully Validated CATHARE, Version for Various Applications,” Proc. 10th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH 10), Seoul, Republic of Korea, October 5-9, 2003.

4. “Validation of the Large Interface Model of NEPTUNE_CFD 1.0.8 for Pressurized Thermal Shock (PTS) applications,”;Coste;Nuclear Engineering and Design,2012

5. “The CUPID Code Development and Assessment Strategy,”;Jeong;Nuclear Engineering and Technology,2010

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