Results 91 to 100 of about 525,516 (210)

Development of tritium breeding blankets for DT-burning fusion reactors [PDF]

, 1980
This study examines the status of understanding of blanket tritium recovery and the performance of potentially viable tritium breeding materials under conditions anticipated in a DT-fueled fusion reactor environment.
Clemmer, R. G.
core  

Water-cooled lead and ceramic breeder (WLCB) breeding blanket (BB) for the EU DEMO: Neutronic campaigns for T breeding optimization

Nuclear Materials and Energy
A novel Breeding Blanket (BB) concept, the Water-cooled Lead and Ceramic Breeder (WLCB) BB, has been developed under the EUROfusion Programme to address key challenges identified during the Pre-Conceptwual Design (PCD) phase for the driver BB concepts ...
Iole Palermo, Francisco A. Hernandez, Salvatore D’Amico, Jin Hun Park, Pavel Pereslavtsev, Guangming Zhou, Iñaki Zumalde   +6 more
doaj   +1 more source

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

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

The effect of Li2TiO3 pebbles on the mechanical properties of ARAA under breeding blanket conditions

Nuclear Materials and Energy
The breeding blanket serves as a critical element for achieving a self-sustaining tritium cycle and generating sufficient energy in fusion reactors.
Yunsong Jung, Youngah Park, Duck Young Ku, Yi-Hyun Park, Hyoseong Gwon   +4 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

Accelerator driven production of tritium: target and blanket design

, 1996
Due to the character of the original source materials and the nature of batch digitization, quality control issues may be present in this document. Please report any quality issues you encounter to digital@library.tamu.edu, referencing the URI of the ...
Ragusa, Jean Concetto
core   +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

The Breeding Blanket Interface (BBI) and the Tritium Systems Test Assembly (TSTA) [PDF]

, 1989
The Tritium System Test Assembly (TSTA) project at Los Alamos National Laboratory is charged with developing and demonstrating the fusion fuel processing requirement for the magnetic fusion energy program.
Sze, D. K., Finn, P. A., Anderson, J. L., Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)), Clemmer, R. G., Bartlit, J. R., Yoshida, H., Sherman, R., Enoeda, M., Okuno, K., Naruse, Y., Los Alamos National Lab., NM (USA)   +11 more
core  

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