Results 21 to 30 of about 138,513 (347)

Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket

Nuclear Engineering and Technology, 2023
Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure.
Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang   +11 more
doaj   +1 more source

U.S. Solid Breeder Blanket Design for ITER [PDF]

Fusion Technology, 1991
The US blanket design activity has focused on the developments and the analyses of a solid breeder blanket concept for ITER. The main function of this blanket is to produce the necessary tritium required for the ITER operation and the test program. Safety, power reactor relevance, low tritium inventory, and design flexibility are the main reasons for ...
Y. Gohar, H. Attaya, M. Billone, C. Lin, C. Johnson, S. Majumdar, D. Smith, A. Raffray, A. Badawi, Z. Gorbis, A. Ying, M. Abdou, P. Goranson, B. Nelson, D. Williamson, C. Baker, I. Sviatoslavsky, J. Blanchard, E. Mogahed, M. Sawan, G. Kulcinski   +20 more
openaire   +1 more source

Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term Indian DEMO fusion reactor

International Journal of Energy Research, 2020
Helium cooled dual breeder (HCDB) blanket concept is designed for Indian DEMO fusion reactor and it is made of two tritium breeder materials PbLi and Li2TiO3. It has helium as a coolant and the India specific RAFMS as a structural material. High‐pressure
H. Swami, D. Sharma, A. Mistry, C. Danani, P. Chaudhuri, R. Srinivasan   +5 more
semanticscholar   +1 more source

Molecular Dynamics Simulations of Lead and Lithium in Liquid Phase [PDF]

, 2011
Pb17Li is today a reference breeder material in diverse fusion R&D programs worldwide. Extracting dynamic and structural properties of liquid LiPb mixtures via molecular dynamics simulations, represent a crucial step for multiscale modeling efforts ...
Cuesta Lopez, Santiago, Fraile García, Alberto, Perlado Martín, José Manuel   +2 more
core   +3 more sources

ITER solid breeder blanket materials database [PDF]

, 1993
The databases for solid breeder ceramics (Li{sub 2},O, Li{sub 4}SiO{sub 4}, Li{sub 2}ZrO{sub 3} and LiAlO{sub 2}) and beryllium multiplier material are critically reviewed and evaluated. Emphasis is placed on physical, thermal, mechanical, chemical stability/compatibility, tritium, and radiation stability properties which are needed to assess the ...
Billone, M. C., Dienst, W., Flament, T., Lorenzetto, P., Noda, K., Roux, N.   +5 more
openaire   +2 more sources

A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium‐cooled ceramic breeder blanket

International Journal of Energy Research, 2020
China Fusion Engineering Test Reactor (CFETR) is a brand new Tokamak reactor which is currently being designed to fill the intervals between ITER and future DEMO fusion reactor.
Shijie Cui, Dalin Zhang, Yueheng Lang, Xinyu Jiang, W. Tian, G. Su, Q. Cao, Xinghua Wu, F. Zhao, Jian-gang Li   +9 more
semanticscholar   +1 more source

Annihilation kinetics of irradiation defects in promising tritium breeding pebbles

Nuclear Materials and Energy, 2021
Lithium-based tritium breeding materials will be adopted to produce tritium in the D-T fusion reactor. Li2TiO3 and Li4SiO4 pebbles have been proposed as candidates in water-cooled ceramic breeder blanket (WCCB) and helium-cooled ceramic breeder blanket ...
Baolong. Ji, Shouxi. Gu, Qiang. Qi, X.-C. Li, Yingchun. Zhang, Haishan. Zhou, Guang-Nan Luo   +6 more
doaj   +1 more source

Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II

International Journal of Energy Research, 2020
China Fusion Engineering Test Reactor (CFETR) has two operation phases: Phase I with Pf = 200 MW is to demonstrate the steady‐state operation; Phase II with Pf = 1 GW is to validate the DEMO technology. Helium Cooled Ceramic Breeder (HCCB) blanket is one
Shijie Cui, Dalin Zhang, Yueheng Lang, Xinyu Jiang, W. Tian, G. Su, Q. Cao, Xinghua Wu, F. Zhao, Jian-gang Li   +9 more
semanticscholar   +1 more source

Thermal Hydraulic Analysis on the Water Lead Lithium Cooled Blanket for CFETR

Energies, 2021
A new type of Water Lead Lithium Cooled (WLLC) blanket that adopts the modular design scheme, water cooling the structure components, liquid PbLi as breeder and coolant, and SiC as the thermal insulator between PbLi and structures is under development as
Kecheng Jiang, Yi Yu, Xuebin Ma, Qiuran Wu, Lei Chen, Songlin Liu, Kai Huang   +6 more
doaj   +1 more source

IFMIF suitability for evaluation of fusion functional materials [PDF]

, 2011
The International FusionMaterials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusionmaterials at relevant fusion irradiation conditions.
A. García, A. Ibarra, Arnold, Casal, D. Rapisarda, Daum, Decreton, F. Mota, F. Sordo, Fischer, Grant, Hodgson, J. Jordanova, M. Perlado, Malang, Malang, Malerba, Moeslang, Mota, N. Casal, R. Vila, Simakov, Simakov, V. Queral, Vladimirov, Wachtman   +25 more
core   +2 more sources