CFD Modeling of Supercritical Water Heat Transfer in a Vertical Bare Tube Upward Flow; ICONE 23. The 23rd International Conference on Nuclear Engineering "Nuclear Power – Reliable Global Energy", May 17-21, 2015, Makuhari Messe, Chiba, Japan

CFD Modeling of Supercritical Water Heat Transfer in a Vertical Bare Tube Upward Flow; ICONE 23. The 23rd International Conference on Nuclear Engineering "Nuclear Power – Reliable Global Energy", May 17-21, 2015, Makuhari Messe, Chiba, Japan

Detalhes bibliográficos
Parent link:ICONE 23. The 23rd International Conference on Nuclear Engineering "Nuclear Power – Reliable Global Energy", May 17-21, 2015, Makuhari Messe, Chiba, Japan.— 2015
Autor Corporativo: Национальный исследовательский Томский политехнический университет (ТПУ) Институт неразрушающего контроля (ИНК) Кафедра экологии и безопасности жизнедеятельности (ЭБЖ)
Outros Autores: Agranat V. Vladimir, Malin M. Michael, Pioro I. Igor, Abdullah R. Rand, Perminov V. A. Valeriy Afanasievich
Resumo:A customized Computational Fluid Dynamics (CFD) model of supercritical water (SCW) heat transfer in a vertical tube upward flow is developed and validated using experimental data obtained under the operating conditions typical for SCW cooled reactors (SCWRs): at a pressure of 24 MPa, an inner tube diameter of 10 mm, an inlet temperature of 320 or 350 °C and a heated tube length of 4 m. The three values of mass flux (500, 1000 and 1500 kg/m2s) and various values of wall heat flux (from 141 to 729 kW/m2) are considered. Physical properties of SCW are calculated by using the REFPROP software from National Institute of Standards and Technology (NIST). The model has been incorporated into the commercial general-purpose CFD software, PHOENICS. Various turbulence models and numerical grid settings are tested. The study has demonstrated a good agreement between the CFD predictions and the experimental data on the inside tube wall temperature and heat transfer coefficient with use of a two-layer low-Reynolds-number k-e turbulence model. Practical recommendations are made regarding potential model applications in 3D analyses of SCWRs.
В фонде НТБ ТПУ отсутствует
Idioma:inglês
Publicado em: 2015
Assuntos:
труды учёных ТПУ
Computational Fluid Dynamics
Supercritical Water
Heat Transfer
Upward Flow
Validation
PHOENICS
Formato: Capítulo de Livro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=602266

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