Results 21 to 30 of about 525,516 (210)

Introduction on tritium transport analysis model for HCCP breeding blanket system

Fusion Engineering and Design
Hyung Gon Jin, Yonghee Lee
exaly   +2 more sources

Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X

Nuclear Materials and Energy, 2022
Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo, K. Schmid, I. Ricapito, A. Lukenskas, G.A. Spagnuolo   +4 more
doaj   +1 more source

Modeling and analysis of the tritium fuel cycle for ARC- and STEP-class D-T fusion power plants

Nuclear Fusion, 2023
The limited tritium resources available for the first fusion power plants (FPPs) make fuel self-sufficiency and tritium inventory minimization leading issues in FPP design. This work builds on the model proposed by Abdou et al (2020 Nucl.
Samuele Meschini, Sara E. Ferry, Rémi Delaporte-Mathurin, Dennis G. Whyte   +3 more
doaj   +1 more source

Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code

IEEE Access, 2023
This work presents the results of the implementation in the GEneral Tokamak THErmal-hydraulic Model of available models for the generation and transport of any dispersed material in flowing PbLi eutectic mixture.
Fabrizio Lisanti, Pietro Arena, Roberto Bonifetto, Antonio Froio, Francisco Alberto Hernandez Gonzalez, Gandolfo Alessandro Spagnuolo, Roberto Zanino   +6 more
doaj   +1 more source

Advancements in Designing the DEMO Driver Blanket System at the EU DEMO Pre-Conceptual Design Phase: Overview, Challenges and Opportunities

Journal of Nuclear Engineering, 2023
The EU conducted the pre-conceptual design (PCD) phase of the demonstration reactor (DEMO) during 2014–2020 under the framework of the EUROfusion consortium.
Francisco A. Hernández, Pietro Arena, Lorenzo V. Boccaccini, Ion Cristescu, Alessandro Del Nevo, Pierre Sardain, Gandolfo A. Spagnuolo, Marco Utili, Alessandro Venturini, Guangming Zhou   +9 more
doaj   +1 more source

Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment

Nuclear Materials and Energy, 2021
Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient breeding and extraction systems, as well as minimizing tritium losses to the surrounding systems, such as plasma-facing components, vacuum vessel, cooling ...
R. Arredondo, K. Schmid, F. Subba, G.A. Spagnuolo   +3 more
doaj   +1 more source

Deuterium ion irradiation for tritium breeding material and evaluation for tritium inventories in test blanket module and blanket of a demonstration reactor [PDF]

Journal of Nuclear Materials, 2011
The tritium produced in a tritium breeder of blanket has to be recovered under the temperature distribution to reduce the tritium inventory. Lithium titanate pebbles were irradiated by deuterium ions with different temperatures and ion fluences. The deuterium retained in the pebbles desorbed in forms of HD, D2, HDO and D2O.
Hino, T., Shibata, H., Yamauchi, Y., Nobuta, Y., Suzuki, S., Akiba, M.   +5 more
openaire   +3 more sources

Impact of Blanket Configuration on the Design of a Fusion-Driven Transmutation Reactor

International Journal of Renewable Energy Development, 2018
A configuration of a fusion-driven transmutation reactor with a low aspect ratio tokamak-type neutron source was determined in a self-consistent manner by using coupled analysis of tokamak systems and neutron transport.
Bong Guen Hong
doaj   +1 more source

An intelligent optimization method for the HCSB blanket based on an improved multi-objective NSGA-III algorithm and an adaptive BP neural network

Nuclear Engineering and Technology, 2023
To improve the performance of blanket: maximizing the tritium breeding rate (TBR) for tritium self-sufficiency, and minimizing the Dose of backplate for radiation protection, most previous studies are based on manual corrections to adjust the blanket ...
Wen Zhou, Guomin Sun, Shuichiro Miwa, Zihui Yang, Zhuang Li, Di Zhang, Jianye Wang   +6 more
doaj   +1 more source

TRITIUM TRANSFER AND CONCENTRATION IN THE OCEAN [PDF]

, 2004
Environmental transport models have been developed for evaluation of radiation doses from tritium released into the atmosphere. Recently, models contain not only inhalation and skin absorption as routes of tritium transfer from the atmosphere to humans ...
Hidayanto, Eko
core   +1 more source