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A Fission-Fusion Hybrid Reactor in Steady-State L-Mode Tokamak Configuration with Natural Uranium [PDF]

Forget, B., Parker, R., Reed, M.
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Lithium Titanate Foam for Tritium Breeding Application

Journal of Nuclear Materials, 2023
N. Khan, A. Sinha, V. Sudarsan
semanticscholar   +2 more sources

Development of tritium dynamic transport analysis tool for tritium breeding blanket system using Modelica

Fusion Engineering and Design, 2020
Abstract Demonstration of the engineering feasibility of tritium breeding, including tritium generation, tritium extraction, tritium control and tritium safety is one of the main objectives of ITER Testing Blanket Module (TBM) Program. As one of TBM concepts, the tritium transport assessment of the China Helium Cooled Ceramic Breeder TBM and its ...
Ruyan Li, Xiaoyu Wang, Long Zhang, Jun Wang   +3 more
semanticscholar   +2 more sources

Tritium Breeding Ratio Evaluation of Solid Breeder Concepts for the FESS-FNSF

Fusion science and technology, 2023
This paper presents a parametric study of the Fusion Energy System Studies-Fusion Nuclear Science Facility’s (FNSF’s) tritium breeding performance for several solid breeder concepts, neutron multiplying materials, and blanket materials, assuming volume ...
Felipe S. Novais, Nicholas R. Brown, G. Maldonado   +2 more
semanticscholar   +1 more source

Neutronic analysis of Indian helium-cooled solid breeder tritium breeding module for testing in ITER

Plasma Science and Technology, 2022
India has proposed the helium-cooled solid breeder blanket concept as a tritium breeding module to be tested in ITER. The module has lithium titanate for tritium breeding and beryllium for neutron multiplication. Beryllium also enhances tritium breeding.
H. Swami, Deepak Kumar Sharma, C. Danani, P. Chaudhuri, R. Srinivasan, Rajesh Kumar   +5 more
semanticscholar   +1 more source

Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions

Nuclear Fusion, 2021
The accurate assessment of tritium breeding parameters within fusion blankets is crucial for future magnet-confined fusion machines to realize fuel self-sufficiency.
Qingjun Zhu, Wuhui Chen, J. Bao, Hua Du, Songlin Liu, Kai Huang   +5 more
semanticscholar   +1 more source

Neutronic Comparison of Tritium-Breeding Performance of Candidate Tritium-Breeding Materials

Plasma Science and Technology, 2003
Tritium self-sustainment, which will meet the fuel requirement of fusion reactor, is one of the key issues of fusion power development. The tritium breeding performances of various tritium-breeding materials are compared based on a series of neutronics calculations using three-dimensional Monte Carlo neutron-photon transport code MCNP/4C with the IAEA ...
Zheng Shanliang, Wu Yican
openaire   +1 more source

Deuterium-tritium fusion reactors without external tritium breeding

Physics Letters A, 1998
Abstract An inherent property of deuterium fusion burn-up equations is presented, due to which deuterium-tritium reactions can be exploited without needing tritium breeding in external blankets. A small amount of tritium is added to the deuterium plasma in order to trigger ignition at less than 10 keV, and the same amount of tritium is found in the ...
S Eliezer, Z Henis, J.M Martínez-Val, M Piera   +3 more
openaire   +1 more source

Tritium Breeding in Hybrid Reactors

Fusion Technology, 1986
The difficulty of achieving tritium self-sufficiency in a deuterium-tritium (D-T) hybrid has been reported in relation to different hybrid designs and concepts using lithium as the breeding material. Lithium-6 enrichment has been suggested to overcome this problem, provided the contribution of /sup 7/Li to tritium production is usually negligible, as ...
Mireia Piera, José M. Martinez-Val
openaire   +1 more source