Validations of the radiation transport module NEUTRO: A deterministic solver for the neutron transport equation-Reference-Cited by-同舟云学术

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Validations of the radiation transport module NEUTRO: A deterministic solver for the neutron transport equation

Published:2021-08 Issue: Volume:169 Page:112497
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Soba Alejandro^ORCID,Cazado Mauricio E.^ORCID,Houzeaux Guillaume^ORCID,Gutierrez-Milla Albert,Mantsinen Mervi J.,Saez Xavier^ORCID

Funder

European Regional Development Fund

Publisher

Elsevier BV

Subject

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

Reference39 articles.

1. Alya: towards exascale for engineering simulation codes;Vazquez;arXiv,2014

2. Transport Theory;Duderstadt,1978

3. Augé: Development of a Deterministic Neutron Transport Code Based on the Alya System;Riera,2016

4. MCNP-A General Monte Carlo Code for Neutron and Photon Transport;Briesmeister,1986

5. Fusion Electricity – A Roadmap to the Realisation of Fusion Energy;Romanelli,2012

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Spatiotemporal Dynamics and Driving Forces of Ecological Environment Quality in Coastal Cities: A Remote Sensing and Land Use Perspective in Changle District, Fuzhou;Land;2024-08-29

2. Validating NEUTRO, a deterministic finite element neutron transport solver for fusion applications, with literature tests, experimental benchmarks and other neutronic codes;Plasma Physics and Controlled Fusion;2022-08-30

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