Results 101 to 110 of about 525,516 (210)

Structural assessment of the gripper interlock of the DEMO breeding blanket transporter. [PDF]

Heliyon, 2023
Mozzillo R, Bachmann C, Fanelli P, Janeschitz G, Steinbacher T.   +4 more
europepmc   +1 more source

Development of water-cooled cylindrical blanket in JA DEMO

Nuclear Fusion
The concept of the tritium breeding blanket for Japan’s DEMOnstration fusion reactor (JA DEMO) has been developed with pressure tightness against in-box loss-of-coolant accidents based on a water-cooled solid breeder concept.
Someya Youji, Tanigawa Hiroyasu, Sakamoto Yoshiteru, the Joint Special Design Team for Fusion DEMO   +3 more
doaj   +1 more source

Tritium Processing System for the ITER Li/V Blanket Test Module [PDF]

, 1997
The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate blanket concepts under a real fusion environment. To assure fuel self-sufficiency the tritium breeding, recovery and processing have to be demonstrated ...
Dagher, M. A., Sze, D. K., Abdou, M. A., Waganer, L. M., Hua, T. Q.   +4 more
core  

Technologies and modelling issues for tritium processing in the European Test Blanket Systems and perspectives for DEMO

, 2014
One of the main objectives of the experimental campaign on the Test Blanket Systems (TBS) in ITER is the demonstration of the efficient processing of the tritium generated in the Test Blanket Module (TBM).
Aiello, A.
core   +1 more source

Experimental and Numerical Analysis of a Pd-Ag Membrane Unit for Hydrogen Isotope Recovery in a Solid Blanket. [PDF]

Membranes (Basel), 2023
Narcisi V, Tamborrini L, Farina L, Cortese G, Romanelli F, Santucci A.   +5 more
europepmc   +1 more source

ITER breeding blanket design [PDF]

, 1995
A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase.
Mohri, K., Raffray, R., Ioki, K., Cardella, A., Zolti, E., Lousteau, D., Gohar, Y.   +6 more
core  

Neutronics experiment of tritium breeding in supercritical CO2 cooled lithium-lead blanket mock-up by D–T neutron irradiation

Nuclear Fusion
The tritium breeding capacity of fusion blankets is a critical factor in achieving tritium self-sufficiency in fusion reactors. Current designs for tritium production in blankets are based on neutronics simulations, whose accuracy requires experimental ...
Qiankun Shao, Qingjun Zhu, Zuocong Liu, Tianyi Liu, Jie Bao, Songlin Liu   +5 more
doaj   +1 more source

Feasibility Study to Byproduce Medical Radioisotopes in a Fusion Reactor. [PDF]

Molecules, 2023
Li J, Zheng S.
europepmc   +1 more source

Implications of T loss in first wall armor and structural materials on T-self-sufficiency in future burning fusion devices

Nuclear Fusion
Future fusion reactors will have to breed enough tritium (T) to sustain continuous operation and to produce excess T to power up other fusion reactors. Therefore, T is a scarce resource that must not be lost inside the fusion power plants systems.
K. Schmid, T. Schwarz-Selinger, R. Arredondo, A. Theodorou, T. Pomella Lobo   +4 more
doaj   +1 more source

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review. [PDF]

Materials (Basel), 2022
Alba R, Iglesias R, Cerdeira MÁ.
europepmc   +1 more source