Abo Bibliothek: Guest
Proceedings of CHT-17 ICHMT International Symposium on Advances in Computational Heat Transfer
May 28 - June 1, 2017, Napoli, Italy

DOI: 10.1615/ICHMT.2017.CHT-7


ISBN Print: 9781-56700-4618

ISSN: 2578-5486

ADVANCES IN COMPUTATIONAL HEAT TRANSFER IN A PRISMATIC GAS COOLED NUCLEAR REACTOR CORE

pages 1345-1348
DOI: 10.1615/ICHMT.2017.CHT-7.1410
Get accessGet access

ABSTRAKT

KAERI (Korea Atomic Energy Research Institute) has been studying a VHTR (Very High Temperature Reactor) to utilize a nuclear power plant for diverse purposes. The VHTR is designed to operate under high-temperature and pressure condition for its lifetime (40 years or longer). To use the VHTR safely and efficiently, a reliable code to analyse the thermal-hydraulics in the reactor core is in demand. A commercial CFD tool might give an accurate solution, but it still has a burden in terms of the computational speed and computer memory usage. A system code to solve a fluid one dimension and a solid as three dimensions has been developed to investigate the temperature distribution and flow rate in the reactor core of a VHTR. In the present study, the hot spot temperature and temperature gradient in the columns in the reactor core are investigated with combinations of various unit cells.

Digitales Portal Digitale Bibliothek eBooks Zeitschriften Referenzen und Berichte Forschungssammlungen Preise und Aborichtlinien Begell House Kontakt Language English 中文 Русский Português German French Spain