Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel-Reference-Cited by-同舟云学术

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Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel

Published:2023-11 Issue: Volume:192 Page:109974
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Guo Xiaoyu^ORCID,Guo Yuchuan^ORCID,Guo Simao,Wang Guanbo,Li Zeguang,Li Rundong,Wang Zi,Wang Kan

Funder

Ministry of Science and Technology of the People's Republic of China

National Key Research and Development Program of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference38 articles.

1. Conceptualization of the micro research reactor cooled by heat pipes (MRR-HP), part-I: Neutronics analyses;Allaf;J. Nucl. Sci. Technol.,2023

2. Burnup calculations for the HOMER-15 and SAFE-300 reactors;Amiri,2002

3. Evinci micro reactor;Arafat;Nucl. Plant J.,2019

4. Review of the Oak Ridge National Laboratory (ORNL) Neutronic Calculations Regarding the Conversion of the High Flux Isotope Reactor (HFIR) to the Use of Low Enriched Uranium (LEU) Fuel;Bergeron,2013

5. Thermophysical properties of materials for nuclear engineering: A tutorial and collection of data;Bobkov,2008

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. Analysis of zirconium hydride moderator effect on the micro lead-based reactor;Annals of Nuclear Energy;2025-01

2. Review of reactor conceptual design and thermal hydraulic characteristics for heat pipe in nuclear systems;Frontiers in Energy Research;2023-12-04

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