Results 101 to 110 of about 3,747 (225)

Neutron-induced dpa, transmutations, gas production, and helium embrittlement of fusion materials

, 2013
In a fusion reactor materials will be subjected to significant fluxes of high-energy neutrons. As well as causing radiation damage, the neutrons also initiate nuclear reactions leading to changes in the chemical composition of materials (transmutation ...
Dudarev, S. L., Gilbert, M. R., Nguyen-Manh, D., Packer, L. W., Sublet, J. -Ch., Zheng, S.   +5 more
core   +1 more source

Tritium breeding capability of heliotron-H fusion reactor blankets. [PDF]

Journal of Nuclear Science and Technology, 1982
Hideki NAKASHIMA, Masao OHTA, Atsuo IIYOSHI   +2 more
openaire   +1 more source

Experimental Investigation on Pressure Drops of Purge Gas Helium in Packed Pebble Beds for Nuclear Fusion Blanket

Energies
The flow characteristics of purge gas helium in the pebble bed of the tritium breeding blanket are important in analyzing the tritium purging process and optimizing the design of the solid breeder blanket.
Hao Cheng, Baoping Gong, Bing Zhou, Juemin Yan, Long Wang, Long Zhang, Yongjin Feng, Xiaoyu Wang   +7 more
doaj   +1 more source

Impact of trapping on tritium self-sufficiency and tritium inventories in fusion power plant fuel cycles

Nuclear Fusion
The dynamic analysis of fusion power plant (FPP) fuel cycles highlights the challenge of achieving tritium self-sufficiency in future FPPs. While state-of-the-art fuel cycle models offer valuable insights into the necessary design parameters for ...
Samuele Meschini, Rémi Delaporte-Mathurin, George R. Tynan, Sara E. Ferry   +3 more
doaj   +1 more source

High-Temperature Intrinsic Defect Chemistry of Li₈PbO₆ Ceramic Breeding Material. [PDF]

J Phys Chem C Nanomater Interfaces, 2023
Davies AW, Neilson WD, Bedford RT, Murphy ST.   +3 more
europepmc   +1 more source

Calculation of Temperature Fields in a Lithium Ceramic Pebble Bed during Reactor Irradiation in a Vacuum. [PDF]

Materials (Basel), 2023
Chikhray Y, Kulsartov T, Zaurbekova Z, Kenzhina I, Samarkhanov K.   +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

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

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

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