Heat Transfer in Helium Coolant Channel of Dual-Functional Lithium Lead Test Blanket Module to ITER Fusion Reactor

Dual-functional Lithium Lead Test Blanket Module (DFLL-TBM) was proposed by China for testing in the International Thermonuclear Experimental Reactor (ITER).When an in-TBM helium coolant tube breaks, high pressure helium will discharge into the Pb-Li breeding zones. The pressure shock in the TBM will threaten the structural integrity and safety of ITER. Simulation and analysis on helium coolant tube break accident of DFLL-TBM was performed, and two cases with different break sizes were considered. Computational results indicate that intense pressure waves spread quickly from the break to the surrounding structures and the variation of pressure in the TBM breeding box is drastic especially when the pressure wave propagation encounters large resistance such as at the bending corner of the flow channel, the inlet and outlet of Pb-Li, etc. The maximum pressure in the TBM breeding box which is even higher than the operating pressure of helium also occurs in these zones. Although the pressure shock lasts for a very short time, its effect on the structural integrity of DFLL-TBM needs to be paid attention to.

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Development of Single Pebble Benchmark Ex. I-2A for IAEA UAM CRP With MOOSE

Volume 6B: Thermal-Hydraulics and Safety Analyses ◽

10.1115/icone26-82155 ◽

2018 ◽

Author(s):

Jinlin Niu ◽

Lidong Wang ◽

Jiong Guo ◽

Fu Li

Keyword(s):

Heat Transfer ◽

Convective Heat Transfer Coefficient ◽

Object Oriented ◽

Thermal Parameters ◽

Maximum Temperature ◽

Coolant Temperature ◽

Simulation Environment ◽

Helium Coolant ◽

Solid Temperature ◽

Shell Region

Ex. I-2a is Uncertainty Analysis in Modelling (UAM) of stand-alone thermal-hydraulics in steady state. It belongs to IAEA Coordinated Research Project (CRP). In this paper, the work is divided into two steps. Firstly, a single pebble model is developed based on Multiphysics Object Oriented Simulation Environment (MOOSE). The model includes two regions: homogeneous fuel region and shell region. One physical field is concerned: solid temperature field. The field is solved in a Jacobian-free Newton–Krylov (JFNK) way in the MOOSE framework. Secondly, perturbation of thermal parameters is done. In this paper, helium coolant temperature, convective heat transfer coefficient, power density and solid conductivity are the main thermal parameters which are concerned. Different kinds of perturbation of thermal parameters are conducted. Thus, variation of temperature profile across the pebble, Doppler temperature, moderator temperature and maximum temperature could be got.

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Development and Validation of Numerical Simulation Program for MHD Flow and Heat Transfer in Liquid Metal Blanket of Fusion Reactor

Nuclear Science and Technology ◽

10.12677/nst.2019.73012 ◽

2019 ◽

Vol 07 (03) ◽

pp. 83-90

Author(s):

佳佳韩

Keyword(s):

Heat Transfer ◽

Numerical Simulation ◽

Liquid Metal ◽

Fusion Reactor ◽

Mhd Flow ◽

Simulation Program ◽

Flow And Heat Transfer ◽

Development And Validation

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Magnetohydrodynamic Correction in Film Boiling Heat Transfer on Liquid Metal in Presence of an Ideal Magnetic Field With Particular Reference to Fusion Reactor Project

Journal of Heat Transfer ◽

10.1115/1.3220145 ◽

2009 ◽

Vol 131 (12) ◽

Cited By ~ 4

Author(s):

F. J. Arias

Keyword(s):

Magnetic Field ◽

Heat Transfer ◽

Liquid Metal ◽

High Magnetic Field ◽

Boiling Heat Transfer ◽

Fusion Reactor ◽

Horizontal Surface ◽

Film Boiling ◽

Experimental Measurements

The author proposed a magnetohydrodynamic correction from a horizontal surface in liquid-metal in the presence of an ideal magnetic field. The theoretical correction agrees qualitatively with the available experimental measurements made on mercury in a high magnetic field where transition/film boiling is expected.

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