First neutronics analysis for ITER bio-shield equatorial port plug

Author:

Dang Tongqiang,Ying Dongchuan,Yang Qi,Loughlin Michael,Davis Andrew

Publisher

Elsevier BV

Subject

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

Reference15 articles.

1. ITER nuclear analysis strategy and requirements;Loughlin;Fusion Science and Technology,2009

2. CAD-based interface programs for fusion neutron transport simulation;Wu;Fusion Engineering and Design,2009

3. Rigorous MCNP based shutdown dose rate calculations: computational scheme, verification calculations and application to ITER;Chen;Fusion Engineering and Design,2002

4. X-5 Monte Carlo Team, MCNP—A General Monte Carlo N-Particle Transport Code, Version 5, 24 April 2003.

5. FISPACT-2007: User Manual;Forrest,2007

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4. Neutronic design optimization of ITER TBM port#2 bio-shield plug;Fusion Engineering and Design;2018-12

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