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in subjects: "Thermonuclear Reactor Walls 700204* -- Fusion Power Plant Technology-- Cooling Systems"

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Heat transfer models for fusion blanket first walls

In the development of magnetically confined fusion reactors, the ability to cool the first wall, i.e., the first material surface interfacing the plasma, appears to be a critical factor involved in establishing the wall load limit. In order to understand the thermal behavior of the first wall time-dependent, one-dimensional heat conduction models are reviewed with differing modes of heat extraction and cooling.

Date: January 1, 1977

Creator: Fillo, J. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermo-fluid mechanics of liquid or gas-cooled tubular first walls

An analysis for hydrodynamically and thermally, fully developed heat transfer in a circular tube coupled with heat conduction in the tube wall is presented. Anisotropy of turbulent energy transport has been taken into account employing theoretical results for eddy diffusivity in the various directions. The energy equations for the fluid and solid body are solved simultaneously and are subject to continuity in heat flux and temperature at the interface. Solutions of the equations are found by se… more

Date: January 1, 1979

Creator: Fillo, J.A. & Powell, J.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

First-wall fusion-blanket heat transfer

To accommodate the high heat flux and neutron and gamma heat generation in the first wall of a fusion reactor, an array of tubes or tube-bank forms a first wall shield of the blanket. A series solution to the two-dimensional (in r,theta coordinates), time-dependent heat conduction equation has been found in terms of Fourier-Bessel (modified Bessel) functions. Steady-state solutions are found as limiting solutions. The heat sources are pulsed on and off to simulate the plasma burn and cool down … more

Date: January 1, 1980

Creator: Fillo, J.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermal-hydraulic limitations on water-cooled limiters

An assessment of the cooling requirements for fusion reactor components, such as the first wall and limiter/divertor, was carried out using pressurized water as the coolant. In order to establish the coolant operating conditions, a survey of the literature on departure from nucleate boiling, critical heat flux, asymmetrical heating and heat transfer augmentation techniques was carried out. The experimental data and the empirical correlations indicate that thermal protection for the fusion react… more

Date: August 1, 1984

Creator: Cha, Y.S. & Misra, B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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MHD (magnetohydrodynamic) flow tailoring in first wall coolant channels of self-cooled blankets

MHD flow tailoring, the use of salient features of MHD flows in strong magnetic fields to create desirable velocity profiles in single ducts, presents the possibility of significant reduction in blanket complexity and cost, and enhancement of thermal hydraulic performance. A particular form of flow tailoring, involving ducts with alternating expansions and contractions lends itself to the design of first wall coolant ducts. The potential benefits of this configuration and its immediate applicab… more

Date: February 1, 1988

Creator: Picologlou, B. F.; Reed, C. R.; Hua, T. Q.; Barleon, L.; Kreuzinger, H. & Walker, J. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Requirements for a helium-cooled blanket heat removal system development facility for fusion reactor research

Existing and potential design problems associated with the helium-cooled blanket assemblies of experimental, demonstration and hybrid reactor designs considered in the Magnetic Fusion Energy (MFE) Program were assessed. It was observed that a balanced program of design, analysis and experimentation would be required to develop, verify and qualify these designs and those of related hardware and equipment. To respond to the potential experimental requirements of the first-generation reactors (the… more

Date: August 1, 1977

Creator: Sutey, A. M.; Zaloudek, F., R. & Bomelburg, H. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Limits of helium cooling in fusion reactor first walls and blankets

This study explores the practical limits of helium cooling in a simple geometry unconstrained by a particular conceptual design. Specifically, the configuration was chosen to be an externally heated straight tube considering both uniform heating and heating of half the external parimeter. Both thermal hydraulic and structural limits to the heat flux have been investigated. Curves are presented to show the heat flux and tube length which simultaneously attain both a well temperature and pressure… more

Date: January 1, 1978

Creator: Stewart, C. W.; Bampton, M .C. C.; Aase, D. T. & Sutey, A. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Comparison of three MHD flow control methods for self-cooled liquid metal blankets

The heat deposition in a blanket is concentrated near the first wall. Uniform liquid-metal velocity in a self-cooled blanket is unattractive, because it leads to low mixed-mean temperature rise through the blanket and reduced power conversion efficiency. The objective of MHD flow control is to use the electromagnetic forces to produce a non-uniform velocity distribution which gives a uniform temperature distribution over the thickness of the blanket. Three methods of MHD flow control are presen… more

Date: January 1, 1986

Creator: Walker, J.S. & Picologlou, B.F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Magneto-fluid-dynamic issues for fusion first wall and blanket systems

Magnetohydrodynamic considerations are shown to be of paramount importance in self-cooled liquid-metal blankets for fusion reactors. Coupling of the stress and MHD pressure drop through the conduit wall thickness is such that, self-cooled liquid-metal blankets without electrical insulators may not be feasible, unless acceptable designs that address satisfactorily MHD-related constraints can be developed. Such an acceptable design, based on current understanding and available analyses and/or exp… more

Date: January 1, 1984

Creator: Picologlou, B.; Reed, C. B.; Nygren, R. & Roberts, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department