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Nuclear Science and Engineering Volume 186, 2017 - Issue 3
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Technical Papers

A Neutron Transport Characteristics Method for 3D Axially Extruded Geometries Coupled with a Fine Group Self-Shielding Environment

S. SantandreaUniversité Paris-Saclay, DEN-Service d’études des réacteurs et de mathématiques appliquées (SERMA), CEA, F-91191Gif-sur-Yvette, FranceCorrespondence[email protected]
ORCID Iconhttp://orcid.org/0000-0001-9387-007X
ORCID Icon,
D. SciannandroneUniversité Paris-Saclay, DEN-Service d’études des réacteurs et de mathématiques appliquées (SERMA), CEA, F-91191Gif-sur-Yvette, France
,
R. SanchezUniversité Paris-Saclay, DEN-Service d’études des réacteurs et de mathématiques appliquées (SERMA), CEA, F-91191Gif-sur-Yvette, France
,
L. MaoUniversité Paris-Saclay, DEN-Service d’études des réacteurs et de mathématiques appliquées (SERMA), CEA, F-91191Gif-sur-Yvette, France
&
L. GrazianoUniversité Paris-Saclay, DEN-Service d’études des réacteurs et de mathématiques appliquées (SERMA), CEA, F-91191Gif-sur-Yvette, France
Pages 239-276 | Received 08 Sep 2016, Accepted 25 Nov 2016, Published online: 10 May 2017

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Sooyoung Choi, Andrew Fitzgerald, Nicholas Herring & Brendan Kochunas. (2024) Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations. Nuclear Science and Engineering 198:4, pages 914-944.
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Derek R. Gaston, Benoit Forget, Kord S. Smith, Logan H. Harbour, Gavin K. Ridley & Guillaume G. Giudicelli. (2021) Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh. Nuclear Technology 207:7, pages 931-953.
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Michael Jarrett, Brendan Kochunas, Edward Larsen & Thomas Downar. (2019) Polar Parity for Efficient Evaluation of Anisotropic Transverse Leakage in the 2D/1D Transport Method. Nuclear Science and Engineering 193:12, pages 1291-1309.
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Guangchun Zhang, Albert Hsieh, Won Sik Yang & Yeon Sang Jung. (2019) Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC. Nuclear Science and Engineering 193:8, pages 828-853.
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Arthur Le Bars, Andrea Gammicchia & Simone Santandrea. Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code. Nuclear Science and Engineering 0:0, pages 1-16.
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Articles from other publishers (9)

An Wang, Junying Wang, Zhezhao Ding, Xiaoxu Geng, Haodong Shan, Yun Hu & Dandan Chen. (2024) A cyclic-track decomposition method for 3D MOC neutron transport simulation. Nuclear Engineering and Design 422, pages 113148.
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A. Brighenti, S. Santandrea, I. Zmijarevic & Z. Stankovski. (2022) Development and validation of a time-dependent deterministic model for neutron noise on CROCUS experimental measurements. Annals of Nuclear Energy 165, pages 108753.
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A. Gammicchia, S. Santandrea & S. Dulla. (2022) Cross sections polynomial axial expansion within the APOLLO3® 3D characteristics method. Annals of Nuclear Energy 165, pages 108673.
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Emiliano Masiello, Roland Lenain & Wesley Ford. (2020) 3D heterogeneous Cartesian cells for transport-based core simulations. Annals of Nuclear Energy 142, pages 107364.
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Li Mao, Igor Zmijarevic & Richard Sanchez. (2020) A subgroup method based on the equivalent Dancoff-factor cell technique in APOLLO3® for thermal reactor calculations. Annals of Nuclear Energy 139, pages 107212.
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A. Gammicchia, S. Santandrea, I. Zmijarevic, R. Sanchez, Z. Stankovski, S. Dulla & P. Mosca. (2020) A MOC-based neutron kinetics model for noise analysis. Annals of Nuclear Energy 137, pages 107070.
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Li Mao, Igor Zmijarevic & Kornilios Routsonis. (2019) Application of the SPH method to account for the angular dependence of multigroup resonant cross sections in thermal reactor calculations. Annals of Nuclear Energy 124, pages 98-118.
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Rodolfo M. Ferrer & Joel D. RhodesIIIIII. (2018) The linear source approximation and particle conservation in the Method of Characteristics for isotropic and anisotropic sources. Annals of Nuclear Energy 115, pages 209-219.
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Simone Santandrea, Laurent Graziano & Daniele Sciannandrone. (2018) Accelerated polynomial axial expansions for full 3D neutron transport MOC in the APOLLO3® code system as applied to the ASTRID fast breeder reactor. Annals of Nuclear Energy 113, pages 194-236.
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