TY - GEN
T1 - Three dimensional numerical simulation of thermal-hydraulic behaviors of CSNS decoupled poisoned hydrogen moderator with non-uniform heat source
AU - Tong, Jian Fei
AU - Wang, Jiao Long
AU - Zhang, Hao Chun
AU - Ji, Yu
AU - Tan, He Ping
N1 - Publisher Copyright:
Copyright © 2016 by ASME.
PY - 2016
Y1 - 2016
N2 - The Chinese Spallation Neutron Source (CSNS) is the national major scientific equipment, which will be completed around 2018. The moderator is the core of the CSNS parts, and CSNS uses three types of moderator to meet the requirements of different neutron wavelength and pulse shapes, and the structure and flow field of Decoupled Poisoned Hydrogen Moderator (DPHM) is the most complicated. Currently, Computational Fluid Dynamics (CFD) is the primary tool for thermal design of DPHM to ensure the reliability of calculation result and precision of the engineering requirements. In the current work, three-dimensional simulation of fluid-solid conjugate heat transfer and flow for container pipe, poisoned plate and moderator material were carried out, by compiling corresponding UDF program for ANSYS FLUENT to describe the non-uniform heat source distribution accurately. Thermal-Hydraulic behaviors such as pressure disturbance, pressure rise and temperature distribution cooling capacity are investigated.
AB - The Chinese Spallation Neutron Source (CSNS) is the national major scientific equipment, which will be completed around 2018. The moderator is the core of the CSNS parts, and CSNS uses three types of moderator to meet the requirements of different neutron wavelength and pulse shapes, and the structure and flow field of Decoupled Poisoned Hydrogen Moderator (DPHM) is the most complicated. Currently, Computational Fluid Dynamics (CFD) is the primary tool for thermal design of DPHM to ensure the reliability of calculation result and precision of the engineering requirements. In the current work, three-dimensional simulation of fluid-solid conjugate heat transfer and flow for container pipe, poisoned plate and moderator material were carried out, by compiling corresponding UDF program for ANSYS FLUENT to describe the non-uniform heat source distribution accurately. Thermal-Hydraulic behaviors such as pressure disturbance, pressure rise and temperature distribution cooling capacity are investigated.
KW - 3-D numerical simulation
KW - Chinese spallation neutron source
KW - Nonuniform heat source
UR - https://www.scopus.com/pages/publications/84995576468
U2 - 10.1115/ICONE24-60639
DO - 10.1115/ICONE24-60639
M3 - 会议稿件
AN - SCOPUS:84995576468
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Thermal-Hydraulics
PB - American Society of Mechanical Engineers (ASME)
T2 - 2016 24th International Conference on Nuclear Engineering, ICONE 2016
Y2 - 26 June 2016 through 30 June 2016
ER -