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Tritium breeding control within liquid metal blankets
Fusion Engineering and Design, 2013Abstract A key requirement for DEMO is the on-site breeding of tritium. In order to do this, a robust control system must be employed to ensure enough tritium is being bred to sustain the fusion reactor, whilst not breeding an amount which would exceed the plant's tritium inventory license.
L. Morgan, J. Pasley
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Tritium inventory and permeation in the ITER breeding blanket
Fusion Engineering and Design, 2000Abstract A model has allowed us to perform the analysis of the tritium inventory and permeation in the international thermonuclear experimental reactor (ITER) breeding blanket under the hypothesis of steady state conditions. Li 2 ZrO 3 (reference) and Li 2 TiO 3 (alternative) have been studied as breeding materials.
V. Violante +5 more
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Enhancing tritium breeding characteristics of a fusion reactor blanket
Annals of Nuclear Energy, 1998Abstract In this paper we have reported our results of a detailed time dependent study of neutron spectra, tritium production rate, tritium breeding ratio, slowing down time and average energy following a pulse of 14 MeV neutrons in Li+C assemblies of different sizes. We have solved the time dependent diffusion equation with energy dependent buckling
Sanjay Gupta, Suresh Garg, Feroz Ahmed
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Neutronics Optimization of Tritium Breeding Blanket for the FDS
Plasma Science and Technology, 2002Neutronics optimization calculations have been performed for the tritium breeding blankets with solid ceramic breeder Li2O and liquid eutectic breeder Li17Pb83, respectively, based on a 2-D geometrical configuration using the Monte Carlo neutron-photon transport code MCNP/4B.
Zheng Shan-liang +2 more
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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 +3 more
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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 +3 more
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Blanket Simulation and Tritium Breeding Ratio Calculation for ITER Reactor
Journal of Fusion Energy, 2015In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium–tritium fusion power reactor using Monte Carlo MCNPX is done. To this end Li4SiO4 was considered as the blanket module. In order to improve the distribution of power density in the blanket module, an arrangement of the neutron multiplier Be in the breeding ...
N. Zandi +4 more
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Design of a tritium breeding blanket for volumetric neutron source
Fusion Engineering and Design, 1998Abstract A water-cooled and austenitic stainless-steel-structured breeding blanket system is designed for a volumetric neutron source (VNS), based on a steady-state tokamak device. The designed VNS with super-conducting coils has a 4.5 m main radius and a total of 300 MW in fusion power.
Y. Asaoka +7 more
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Tritium breeding performance of a self-cooled water based blanket
Fusion Engineering and Design, 1987Abstract A major issue in the design of fusion reactor blankets is the trade-off between tritium breeding and other blanket design requirements. While net breeding is required, the blanket design should also ensure adequate heat removal, efficient power production and sufficient shielding.
M.J. Embrechts +4 more
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Tritium release from breeding blanket materials in high magnetic field
Fusion Engineering and Design, 2007Abstract Under the operating conditions of a fusion reactor, the blanket materials: ceramic and Be pebbles will be at a high temperature (up to 1123 K), under action of intense radiation (up to 10 19 n m −2 s −1 ) and magnetic field (MF) up to 7–10 T. In order to introduce action of radiation and MF in post-irradiation investigations of the tritium
A. Vītiņš +4 more
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An on-line method for tritium breeding studies in Li-blankets
Nuclear Instruments and Methods in Physics Research, 1982Abstract An on-line method for tritium breeding measurements in lithium blankets is described. The apparatus comprizes two tiny ionization chambers (≈ 1.3 cm 3 each) separated by a common electrode holding 6 LiF radiating materials. Tritium producing events due to neutron interaction with the radiating material result in triton and alpha particles ...
O.P. Joneja, R. Hecker, A. Mohsin
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