Estimation and control of beryllium-7 behavior in liquid lithium loop of IFMIF-Reference-Cited by-同舟云学术

Estimation and control of beryllium-7 behavior in liquid lithium loop of IFMIF

Published:2007-10 Issue:15-24 Volume:82 Page:2490-2496
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Ida Mizuho,Nakamura Hiroo,Sugimoto Masayoshi

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference9 articles.

1. IFMIF International Team, IFMIF Comprehensive Design Report, IEA on-line publication, http://www.iea.org/Textbase/techno/technologies/fusion/IFMIF-CDR_partA.pdf and partB.

2. Fusion Material Irradiation Test facility—a facility for fusion materials qualification;Trego;Nucl. Technol. Fusion,1983

3. Accessibility evaluation of the IFMIF liquid lithium loop considering activated erosion/corrosion materials deposition;Nakamura;Fusion Eng. Des.,2005

4. Evaluation of tritium permeation from lithium loop of IFMIF target system;Matsuhiro;Fusion Sci. Technol.,2005

5. Analytical estimation of accessibility to the activated lithium loop in IFMIF;Ida;J. Nucl. Mater.,2007

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