Results 21 to 30 of about 3,005 (266)
Nuclear Engineering and Technology, 2020 In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed.
H. Sadeghi +3 more
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Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor
Nuclear Materials and Energy, 2021 The effects of inboard materials on the size of a tokamak fusion reactor were studied based on reactor system parameters determined through a coupled analysis of tokamak systems and neutron transport. With an inboard blanket, the shielding capability was
B.G. Hong, W. Cho
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Nuclear Design of Heliotron Fusion Reactor Blankets
Journal of Nuclear Science and Technology, 1981 A study is made of the nuclear characteristics of blanket designs intended for a heliotron fusion reactor that employs an 1=2 helical heliotron field and no toroidal coils. The blankets in front of the superconducting magnet (shielding blankets) are utilized for neutron shielding, and the other blanket regions (breeding blankets) for tritium breeding ...
NAKASHIMA, Hideki +2 more
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LiquidsSpecifically engineered heavy liquid metals are proposed as candidate coolants and tritium breeders for advanced nuclear applications. Understanding the wetting behaviours of these liquids on relevant substrate configurations is crucial to tackle the ...
Abhishek Saraswat +3 more
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Applicability Analysis of Energy Storage Techniques for CFETR Fusion Power Plant
南方能源建设, 2022 [Introduction] The power output of China Fusion Engineering Test Reactor (CFETR) is periodic, which can not directly meet the stable and continuous input requirements of conventional power generation equipment. CFETR fusion power plant needs to integrate
Zhanpeng LIANG +3 more
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Fusion Blanket Inherent Safety Assessment [PDF]
Fusion Technology, 1986 Fusion has significant potential safety advantages. There is a strong incentive for designing fusion plants to ensure that inherent safety will be achieved. Accordingly, both the Tokamak Power Systems Studies and MINIMARS have identified inherent safety as a design goal.
Sze, D.K., Jung, J., Cheng, E.T.
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Energies, 2016 The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high ...
Laila El-Guebaly +3 more
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The investigation of the neutronic responses of components in the K-DEMO
Nuclear Fusion, 2023 The neutronic response of consisting materials of the Korean fusion DEMOnstration reactor (K-DEMO) in its fusion neutron environment is a crucial consideration factor from the conceptual design stage of the K-DEMO.
Byung Chul Kim
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Blanket materials for dt fusion reactors [PDF]
Journal of Nuclear Materials, 1981 Abstract This paper presents an overview of the critical materials issues that must be considered in the development of a tritium breeding blanket for a tokamak fusion reactor that operates on the D-T-Li fuel cycle. The primary requirements of the blanket system are identified and the important criteria that must be considered in the development of ...
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Pediatric Blood &Cancer, EarlyView.ABSTRACT Pediatric radiation therapy presents unique challenges compared to adult treatments, including those of immobilization, potential need for sedation, and the critical importance of accurate, reproducible positioning. Additionally, heightened attention to imaging doses is necessary to minimize long‐term toxicity in survivors.
Parham Alaei +17 more
wiley +1 more source