An easy way to perform a radiation damage calculation in a complicated geometry-Reference-Cited by-同舟云学术

An easy way to perform a radiation damage calculation in a complicated geometry

Published:2008-12 Issue:10-12 Volume:83 Page:1828-1831
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Hogenbirk A.

Publisher

Elsevier BV

Subject

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

Reference9 articles.

1. MCNP, A General Monte Carlo N-Particle Transport Code, Version 4C, in: J.F. Briesmeister (Ed.), Report LA-13709-M, Los Alamos National Laboratory, April 2000.

2. J.S. Hendricks, MCNP4C3, 3/22/01, Report X-5:RN(U)-JSH-01-17, Los Alamos National Laboratory, April 13, 2001.

3. D. Leichtle, U. Fischer, Realistic modelling of displacement damage in solid breeder materials by means of BCA-computer simulations, in: Proceedings of 20th Symposium On Fusion Technology, Marseille, France, September 7–11, 1998.

4. R.E. MacFarlane, D.W. Muir, The NJOY Nuclear Data Processing System, Version 91, Report LA-12740-M, Los Alamos National Laboratory, October 1994.

5. ENDF-201, ENDF/B-VI Summary Documentation, in: P.F. Rose (Ed.), Report BNL-NCS 17541, 4th ed., 1996.

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