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

Bibliografiske detaljer
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
Institution som forfatter: Национальный исследовательский Томский политехнический университет (ТПУ) Институт неразрушающего контроля (ИНК) Кафедра экологии и безопасности жизнедеятельности (ЭБЖ)
Andre forfattere: Agranat V. Vladimir, Malin M. Michael, Pioro I. Igor, Abdullah R. Rand, Perminov V. A. Valeriy Afanasievich
Summary: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
Sprog:engelsk
Udgivet: 2015
Fag:
Format: Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=602266

MARC

LEADER 00000naa0a2200000 4500
001 602266
005 20250909135333.0
035 |a (RuTPU)RU\TPU\tpu\27768 
090 |a 602266 
100 |a 20150904d2015 k||y0rusy50 ba 
101 0 |a eng 
102 |a JP 
200 1 |a CFD Modeling of Supercritical Water Heat Transfer in a Vertical Bare Tube Upward Flow  |f V. Agranat [et al.] 
330 |a 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. 
333 |a В фонде НТБ ТПУ отсутствует 
463 1 |t ICONE 23. The 23rd International Conference on Nuclear Engineering "Nuclear Power – Reliable Global Energy", May 17-21, 2015, Makuhari Messe, Chiba, Japan  |d 2015 
610 1 |a труды учёных ТПУ 
610 1 |a Computational Fluid Dynamics 
610 1 |a Supercritical Water 
610 1 |a Heat Transfer 
610 1 |a Upward Flow 
610 1 |a Validation 
610 1 |a PHOENICS 
701 1 |a Agranat  |b V.  |g Vladimir 
701 1 |a Malin  |b M.  |g Michael 
701 1 |a Pioro  |b I.  |g Igor 
701 1 |a Abdullah  |b R.  |g Rand 
701 1 |a Perminov  |b V. A.  |c a specialist in the field of ecology and life safety  |c associate Professor of Tomsk Polytechnic University, Doctor of physical and mathematical sciences  |f 1958-  |g Valeriy Afanasievich  |3 (RuTPU)RU\TPU\pers\35094 
712 0 2 |a Национальный исследовательский Томский политехнический университет (ТПУ)  |b Институт неразрушающего контроля (ИНК)  |b Кафедра экологии и безопасности жизнедеятельности (ЭБЖ)  |3 (RuTPU)RU\TPU\col\18720 
801 1 |a RU  |b 63413507  |c 20150904 
942 |c BK