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Description of Thin Liquid Wall Protection w/Porous Walls

This document describes thin, wetted, and porous wall concepts for liquid wall-cooled fusion reactors, including design bases, heat transport systems, and thermal hydraulics calculations. It discusses two blanket concepts involving helium-cooled solid breeding blankets and liquid breeding blankets with porous walls. The text covers baseline power core geometry, heat transport system definitions, and heating and thermal hydraulics data based on ARIES and Prometheus designs.

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Description of Thin Liquid Wall Protection w/Porous Walls

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  1. Description of Thin Liquid Wall Protection w/Porous Walls L. Waganer The Boeing Company 22 April 2002 ARIES Meeting at UW, Madison Page 1

  2. Description of the Thin,Wetted, Porous Wall Concepts • A design basis for two blanket concepts is given to enable comparative analyses • One is a stand-alone first wall and supply channel with a helium-cooled, solid breeding blanket • Lead is the coolant • The other design is a liquid breeding blanket with a porous first wall and supply channel • Lithium-lead is the coolant Page 2

  3. Thin Liquid Wall-Cooled Concepts Page 3

  4. Baseline Power Core Geometry • First wall surface is a right circular cylinder of radius Rfw and height Rfw with hemispherical ends • Wall surface area = 4π Rfw2 + 2π Rfwx H = 6π Rfw2 Page 4

  5. Definition of Heat Transport Systems • Bulk shield closely fits around Vacuum Vessel (~2.25-2.4 x Rfw =11-12 m) • Lead (or lithium-lead) intermediate heat exchangers are as close as possible outside shield • Minimum piping run is ~30 m in and 30 m out including pumps • IHX are roughly 1.4 m diameter and 14 m long for liquid metal section (1.0 m dia x 10 m for LiPb for reduced power level) Page 5

  6. Heating and Thermal Hydraulics • This data is based upon Prometheus Data for laser case • Promtheus wall geometry • Lead coolant • 780 MW surface heat • 1267 MW total Balanced flow rate is the same as Prometheus design Page 6

  7. Heating and Thermal Hydraulics • Consider this data as preliminary for rough sizing • Used ARIES wall configuration • LiPb coolant • 570 MW surface heat, ref Perkins • 734 MW total (58% of Prometheus) • 350° delta T vs 150° • Less pumping power Balanced flow rate could be smaller than 10 mm (if nuclear heating is correct) Page 7

  8. Calculations on Flow Rates and Volumes • The mass and mass flow rate is much lower with ARIES LiPb coolant system • - Less power transported at a higher delta T • Residence time inside reactor is similar, but time outside is slightly longer Page 8

  9. Next Actions? • If these data are useful, I can update my analyses with the appropriate heat fluxes, configurations, and material parameters Page 9

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