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Fusion Engineering and Design 4950 (2000) 719725 Heat deposition, damage, and tritium breeding
 

Summary: Fusion Engineering and Design 49­50 (2000) 719­725
Heat deposition, damage, and tritium breeding
characteristics in thick liquid wall blanket concepts
M.Z. Youssef *, M.A. Abdou
School of Engineering and Applied Science, Uni6ersity of California, Los Angeles, CA, USA
Abstract
The advanced power extraction (APEX) study aims at exploring new and innovative blanket concepts that can
efficiently extract power from fusion devices with high neutron wall load. Among the concepts under investigation is
the free liquid FW/liquid blanket concept in which a fast flowing liquid FW ( 2­3 cm) is followed by thick flowing
blanket (B) of 40­50 cm thickness with minimal amount of structure. The liquid FW/B are contained inside the
vacuum vessel (VV) with a shielding zone (S) located either behind the VV and outside the vacuum boundary (case
A) or placed after the FW/B and inside the VV (case B). In this paper we investigate the nuclear characteristics of
this concept in terms of: (1) attenuation capability of the liquid FW/B/S and protection of the VV and magnet against
radiation damage; (2) profiles of tritium production rate and tritium breeding ratio (TBR) for several liquid
candidates; and (3) profiles of heat deposition rate and power multiplication. The candidate liquid breeders considered
are Li, Flibe, Li­Sn, and Li­Pb. Parameters varied are (1) FW/B thickness, L, (2) Li-6 enrichment and (3) thickness
of the shield. © 2000 Elsevier Science B.V. All rights reserved.
Keywords: Liquid wall; Blanket concepts; Heat deposition; Tritium breeding characteristics
www.elsevier.com/locate/fusengdes
1. Introduction

  

Source: Abdou, Mohamed - Fusion Science and Technology Center, University of California at Los Angeles

 

Collections: Plasma Physics and Fusion