Modified APEX reactor as a fusion breeder (original) (raw)
Three-dimensional neutronic calculations for a fusion breeder APEX reactor using some libraries
Yurdunaz Çelik
Annals of Nuclear Energy, 2011
View PDFchevron_right
On the proliferation issues of a fusion fission fuel factory using a molten salt
Paolo Peerani
2010
View PDFchevron_right
Investigation of tritium breeding ratio using different coolant material in a fusion–fission hybrid reactor
Haci Mehmet Sahin
International Journal of Hydrogen Energy, 2016
View PDFchevron_right
Determination of the Required Tritium Breeding Ratio for the Next Fusion Experimental Reactor
Yoichi Watanabe
Fusion Technology, 1989
View PDFchevron_right
Optimized transition from the reactors of second and third generations to the Thorium Molten Salt Reactor
E. Merle-lucotte
View PDFchevron_right
Neutronic performance of proliferation hardened thorium fusion breeders
Necmettin Şahin
Fusion Engineering and Design, 2001
View PDFchevron_right
Neutronic analysis of a thorium fusion breeder with enhanced protection against nuclear weapon proliferation
Sümer Şahin
Annals of Nuclear Energy, 1999
View PDFchevron_right
Fusion-fission hybrid reactor facility: neutronic research
Andrey Arzhannikov
Nuclear Energy and Technology, 2022
View PDFchevron_right
Overview of the Physical Properties of Molten Salt Reactor Using Flibe
Daniel de Souza Gomes
Journal of Engineering Research (ISSN 2764-1317), 2023
View PDFchevron_right
Investigation of neutronic potential of a moderated (D–T) fusion driven hybrid reactor fueled with thorium to breed fissile fuel for LWRs
mustafa bayrak
Energy Conversion and Management, 2000
View PDFchevron_right
Influence of the processing and salt composition on the thorium molten salt reactor
E. Merle-lucotte
View PDFchevron_right
Neutronic study on a magnetic fusion reactor using protective liquid wall of thorium molten salts
senay yalcin
Energy Conversion and Management, 2008
View PDFchevron_right
LWR spent fuel transmutation in a high power density fusion reactor
Sümer Şahin
Annals of Nuclear Energy, 2004
View PDFchevron_right
Fusion Reactor Design IV (Report on the 4th IAEA Technical Committee Meeting and Workshop, Yalta, USSR, 26 May – 6 June 1986)
Gerald Kulcinski
Nuclear Fusion, 1986
View PDFchevron_right
Neutronic analysis of PROMETHEUS reactor fueled with various compounds of thorium and uranium
senay yalcin
Annals of Nuclear Energy, 2002
View PDFchevron_right
Fusion Blankets and Fluoride-Salt-Cooled High-Temperature Reactors with Flibe Salt Coolant: Common Challenges, Tritium Control, and Opportunities for Synergistic Development Strategies Between Fission, Fusion, and Solar Salt Technologies
Guiqiu Zheng
Nuclear Technology
View PDFchevron_right
Neutronics analysis of HYLIFE-II blanket for fissile fuel breeding in an inertial fusion energy reactor
Haci Mehmet Sahin
Ann Nucl Energ, 2003
View PDFchevron_right
Transmutation and Breeding Performance Analysis of Molten Chloride Salt Fast Reactor Using a Fuel Management Code with Nodal Expansion Method
Xiandi Zuo
Energies
View PDFchevron_right
Development of a Hybrid Fusion Fission Reactor for Cleaner Energy Production
Eugne Loh
Universiti Teknologi PETRONAS, 2024
View PDFchevron_right
Molten salt reactors and possible scenarios for future nuclear power deployment
F. Perdu, E. Merle-lucotte
Physor, Chicago, …, 2004
View PDFchevron_right
Preliminary proliferation study of the molten salt fast reactor
E. Merle-lucotte
EPJ Nuclear Sciences & Technologies
View PDFchevron_right
Analysis of the Tritium Requirements for a Power Reactor
Eric Proust
Nuclear Technology - Fusion, 1983
View PDFchevron_right
Optimized transition from the reactors of second and third generation to the Thorium Molten Salt Reactor
E. Merle-lucotte
2007
View PDFchevron_right
Neutronic Analysis for Feasibility of Fusion-Driven Subcritical System with Constant Fusion Power by Online Feeding of Molten Salt Fuel
SeongHee Hong
Fusion Science and Technology, 2019
View PDFchevron_right
Utilization of high-density fuel and beryllium elements for the neutron flux enhancement in typical MTR type research reactors
ahmed aslam
Progress in Nuclear Energy, 2007
View PDFchevron_right
Design and analysis of Molten Salt Reactor fueled by TRU from LWR
Massimiliano Fratoni, Augusto Gandini
View PDFchevron_right
Compendium of Papers by the Fusion Reactor Studies Group
Farrokh Najmabadi
View PDFchevron_right
Mass transfer operational units applied to the liquid breeding material of fusion reactor for tritium recovery
Roberto Baratti
The International Journal of Applied Radiation and Isotopes, 1985
View PDFchevron_right
Neutronic analysis of a high power density hybrid reactor using innovative coolants
senay yalcin
Sadhana, 2005
View PDFchevron_right
Neutronic analysis of denaturing plutonium in a thorium fusion breeder and power flattening
Mustafa BAYRAK
Energy Conversion and Management, 2005
View PDFchevron_right
Mass Transfer Operational Units Applied to the Liquid Breeding Material of Fusion Reactors for Tritium Recovery
Roberto Baratti
Fusion Technology, 1985
View PDFchevron_right
Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D–T) driven hybrid reactor system
Osman Ipek
Annals of Nuclear Energy, 2001
View PDFchevron_right
Reactor physic and reprocessing scheme for innovative molten salt reactor system
E. Merle-lucotte
Journal of Fluorine Chemistry, 2009
View PDFchevron_right
Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems
Ken Czerwinski
2005
View PDFchevron_right
Selection Criteria for Fusion Reactor Structures
Sümer Şahin
Journal of Thermal Engineering
View PDFchevron_right