Application of Krylov Acceleration Technique in Method of Characteristics–Based Neutron Transport Code-Reference-Cited by-同舟云学术

Application of Krylov Acceleration Technique in Method of Characteristics–Based Neutron Transport Code

Published:2018-08-24 Issue:2 Volume:192 Page:153-188
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Mazumdar Tanay¹²,Gupta Anurag³²

Affiliation:

1. Bhabha Atomic Research Centre, Reactor Physics and Nuclear Engineering Section, Research Reactor Services Division, Reactor Group, Mumbai-400085, India

2. Homi Bhabha National Institute, Anushaktinagar, Mumbai-400094, India

3. Bhabha Atomic Research Centre, Reactor Physics Design Division, Reactor Design and Development Group, Mumbai-400085, India

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2018.1499340

Reference50 articles.

1. Verification of 3D Heterogeneous Core Transport Calculation Utilizing Non-linear Iteration Technique

2. J. R. ASKEW, “A Characteristics Formulation of the Neutron Transport Equation in Complicated Geometries,” AEEW-M, p. 1108, United Kingdom Atomic Energy Authority (1972).

3. CRX: A code for rectangular and hexagonal lattices based on the method of characteristics

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