Parametric neutronic analysis of HCLL blanket for DEMO fusion reactor utilizing vacuum vessel ITER FDR design-Reference-Cited by-同舟云学术

Parametric neutronic analysis of HCLL blanket for DEMO fusion reactor utilizing vacuum vessel ITER FDR design

Published:2006-09 Issue:19 Volume:81 Page:2213-2220
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Jordanova J.,Fischer U.,Pereslavtsev P.,Poitevin Y.,Li Puma A.,Nikolova-Todorova N.

Publisher

Elsevier BV

Subject

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

Reference4 articles.

1. MCNP™ A General Monte Carlo N-Particle Transport Code, Version 4C,2000

2. Y. Chen, U. Fischer, P. Pereslavtsev, F. Wasastjerna, The EU Power Plant Conceptual Study—Neutronic Design Analyses for Near Term and Advanced Reactor Models, Report, Institute fur Reaktorsicherheit, FZKA 6763, April 2003.

3. A.B. Paschenko, H. Wienke, FENDL/E-2.0 Evaluated Nuclear Data Library of Neutron-nucleus Interaction Cross Sections and Photon Production Cross Sections and Photon-atom Interaction Cross Sections for Fusion Applications, IAEA-NDS-175, Rev. 3 (1998).

4. ITER General Design Requirement Document (GDRD), S10 GDRD 2 95-02-10 F1.0, June 1995.

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