Evaluation of a three-dimensional discrete ordinates radiation transport tool for the support of ITER design-Reference-Cited by-同舟云学术

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Evaluation of a three-dimensional discrete ordinates radiation transport tool for the support of ITER design

Published:2007-10 Issue:15-24 Volume:82 Page:2008-2014
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Pampin R.,Loughlin M.J.

Publisher

Elsevier BV

Subject

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

Reference4 articles.

1. ATTILA Version 5: User Manual;McGhee,2006

2. Briesmeister JF, MCNP—a general Monte Carlo N-particle transport code version 4C, LA-13709-M, Los Alamos National Laboratory report.

3. Transmagic Inc., Westminster CO, USA.

4. Loughlin MJ, EFDA report EFDA/05-1278, August 2006.

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1. Advancements in computational methods for neutron shielding;Micro and Nanostructured Composite Materials for Neutron Shielding Applications;2020

2. Angular adaptive discrete ordinates method for deuterium–tritium neutron streaming experiments simulating narrow gaps;Fusion Engineering and Design;2019-01

3. A space–angle DGFEM approach for the Boltzmann radiation transport equation with local angular refinement;Journal of Computational Physics;2015-09

4. Attila Validation with Fusion Benchmark Experiments at JAEA/FNS;Nuclear Technology;2009-12

5. Radiation transport analyses for IFMIF design by the Attila software using a Monte-Carlo source model;Fusion Engineering and Design;2009-01

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