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An Experimental Reversed Heat Flux Investigation of the Helium-Cooled Modular Divertor with Multiple Jets

Journal Article · · Fusion Science and Technology
 [1];  [2];  [2];  [2]
  1. Georgia Inst. of Technology, Atlanta, GA (United States). G. W. Woodruff School of Mechanical Engineering; G. W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology
  2. Georgia Inst. of Technology, Atlanta, GA (United States). G. W. Woodruff School of Mechanical Engineering
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The Georgia Institute of Technology group has performed studies to characterize the thermal hydraulics of a single “finger” module of the helium-cooled modular divertor with multiple jets (HEMJ) proposed for long-pulse magnetic fusion reactors in a helium (He) loop designed with maximum mass flow rate of 10 g/s. However, testing divertor modules at prototypical heat fluxes and temperatures remains an engineering challenge. A new larger helium loop with a maximum mass flow rate of 100 g/s, suitable for evaluating helium-cooled divertors with larger surface areas such as a nine-finger HEMJ module, is currently being constructed. This work presents an experimental validation of a numerical model exploring the applicability of the “reversed heat flux approach,” which cools (versus heats) the plasma-facing surface of the divertor module to evaluate the helium-side heat transfer coefficient (HTC). The approach is to be used for performance evaluation of single and multiple modules of HEMJ in existing and future large helium loops. A cooling facility for producing a jet of water with a maximum mass flow rate of 1.4 kg/s at a maximum pressure of 0.4 MPa and temperature of 295 K (Re = 2.2 × 105) is described. Numerical and experimental results are presented for the heat flux and average helium impingement surface temperature over a range of water flow rates (0.5 to 1.4 kg/s) for heat fluxes as high as 5 MW/m2. The numerical model suggests that the HTC of the water impingement surface is comparable to or greater than that of the helium impingement surface. For given helium and water temperatures, the heat flux values are generally limited by conduction across the outer shell. These initial studies provide guidance on extending this approach to estimating the thermal-hydraulic performance of larger divertor module designs while reducing the challenges associated with studying such designs in the normal heating configuration at their extremely high prototypical temperatures and incident heat fluxes.

Research Organization:
Georgia Inst. of Technology, Atlanta, GA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24); National Science Foundation (NSF)
Grant/Contract Number:
FG02-01ER54656
OSTI ID:
1593401
Journal Information:
Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 8 Vol. 75; ISSN 1536-1055
Publisher:
American Nuclear SocietyCopyright Statement
Country of Publication:
United States
Language:
English

References (5)

An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD journal November 2005
Experimental study of DEMO helium cooled divertor target mock-ups to estimate their thermal and pumping efficiencies journal October 2005
Thermal Hydraulics of Helium-Cooled Finger-Type Divertors at Higher Incident Heat Fluxes journal May 2019
Correlating Equations for Impingement Cooling of Small Heat Sources With Single Circular Liquid Jets journal February 1993
An Experimental Study of the Helium-Cooled Modular Divertor with Multiple Jets at Nearly Prototypical Conditions journal October 2015

Figures / Tables (9)

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
helium-cooled divertor
impinging jet
reversed heat flux
thermal-hydraulics