A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor

Author:

Kabach Ouadie1ORCID,Chetaine Abdelouahed1,Benchrif Abdelfettah2,Amsil Hamid12,El Banni Fadi3

Affiliation:

1. Nuclear Reactor and Nuclear Security Group Energy Centre, Department of Physics FSR, Mohammed V University Rabat Morocco

2. Direction of Studies and Scientific Researches National Centre of Nuclear Energy Sciences and Techniques (CNESTEN) Rabat Morocco

3. LASMES, SSMT Felix Houphouet‐Boigny University Abidjan Ivory Coast

Publisher

Wiley

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

Cited by 7 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. Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly;Nuclear Engineering and Design;2023-12

2. Revolutionizing LWR SMR reactors: exploring the potential of (Th-233U-235U)O2 fuel through a parametric study;Energy Sources, Part A: Recovery, Utilization, and Environmental Effects;2023-08-03

3. Study on kinetic parameters of pebble bed reactor with TRISO duplex fuel;Nuclear Technology and Radiation Protection;2023

4. Study on neutronic characteristics of NuScale reactor core with thorium coating;CHEMISTRY BEYOND BORDERS: INTERNATIONAL CONFERENCE ON PHYSICAL CHEMISTRY: The 1st Annual Meeting of the Physical Chemistry Division of the Indonesian Chemical Society;2023

5. Neutronic and burnup characteristics of potential dual‐cooled annular ( Th‐ 233 U‐ 235 U ) O 2 fuel for the advanced pressurized water reactors: An assembly‐level analysis;International Journal of Energy Research;2022-08-29

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