LATERAL COOLANT FLOW BETWEEN FUEL ASSEMBLIES IN MIXED CORES
This paper presents the results of an analysis of lateral coolant flow between adjacent fuel assemblies with non-identical spacing grids in a mixed core consisting of TVSA-T mod.1 and TVSA-T mod.2 fuel assemblies. The calculation was carried out using modified subchannel code SUBCAL which allows to...
Main Authors: | Vojtech Caha, Jiří Čížek |
---|---|
Format: | Article |
Language: | English |
Published: |
CTU Central Library
2018-05-01
|
Series: | Acta Polytechnica CTU Proceedings |
Subjects: | |
Online Access: | https://ojs.cvut.cz/ojs/index.php/APP/article/view/4836 |
Similar Items
-
MIXED CORE SUBCHANNEL MODEL FOR SUBCAL AND COUPLING WITH ANDREA
by: Vojtěch Caha, et al.
Published: (2018-12-01) -
Application of CUPID for subchannel-scale thermal–hydraulic analysis of pressurized water reactor core under single-phase conditions
by: Seok Jong Yoon, et al.
Published: (2018-02-01) -
CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development
by: Sebastian Davies, et al.
Published: (2021-02-01) -
Solution Techniques for Single-Phase Subchannel Equations
by: Hansel, Joshua Edmund
Published: (2013) -
Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor
by: Seok-Kyu Chang, et al.
Published: (2016-04-01)