Generalized Equivalence Theory Used with Spatially Linear Sources in the Method of Characteristics for Neutron Transport-Reference-Cited by-同舟云学术

Generalized Equivalence Theory Used with Spatially Linear Sources in the Method of Characteristics for Neutron Transport

Published:2020-05-28 Issue:11 Volume:194 Page:1044-1055
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Giudicelli Guillaume¹,Smith Kord¹,Forget Benoit¹

Affiliation:

1. Massachusetts Institute of Technology, Nuclear Science and Engineering Department, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139

Funder

Nuclear Energy University Program

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2020.1765606

Reference32 articles.

1. Handbook of Nuclear Engineering

2. T. DOWNAR et al. “PARCS V3.0 U.S. NRC Core Neutronics Simulator Theory Manual,” UM-NERS-09-001 (2009).

3. STUDSVIK, “SIMULATE-3 Advanced Three-Dimensional Two-Group Reactor Analysis Code,” SSP-09/447 University Release (2009).

4. W. BOYD, “Reactor Agnostic Multi-Group Cross Section Generation for Fine-Mesh Deterministic Neutron Transport Simulations,” PhD Thesis, Massachusetts Institute of Technology (2017).

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