The fusion-driven hybrid system and its material selection

Wu, Yican; Qian, Jin; Yu, Jin‐Hai

doi:10.1016/s0022-3115(02)01272-2

Cited by 120 publications

(50 citation statements)

References 20 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Fusion energy [1][2][3][4][5][6] is a potential choice of human energy for its sustainable energy source, low risk of severe accidents, short-lived radioactive waste. Blanket is a key component for energy transformation and extraction in fusion reactor, and the liquid metal breeder blanket concept has been studied extensively in the world due to their high heat removal, adequate tritium breeding ratio, relative simple design, potential attractiveness of economy and safety [7][8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Experimental Studies of MHD Pressure Drop of PbLi Flow in Rectangular Pipes Under Uniform Magnetic Field

Meng

Zhu

et al. 2015

J Fusion Energ

View full text Add to dashboard Cite

Liquid metal flow of blanket in fusion reactor would bear pressure drop caused by magnetic field. To investigate the magnetohydrodynamic (MHD) pressure drop characteristics, experiments of PbLi flow in an electrically conducting rectangular pipe subjected to a transverse magnetic field were performed on loop DRAGON-IV. A measurement approach for differential pressure in high temperature liquid PbLi was adopted, and detailed data on pressure drop in PbLi MHD flow under various magnetic fields were measured. Electric potential method in the experimental pipe was adopted to measure the flow rate. The obtained experiment results for the MHD pressure drop were in good agreement with theory calculation. Through theoretical analysis, it has been found that the temperature of experimental pipe has a remarkable impact on MHD pressure drop. The change of temperature from 430 to 650°C can lead to a decrease of MHD pressure drop by 10 %. Further experimental studies on the temperature effect on MHD pressure drop are needed.

show abstract

Section: Introductionmentioning

confidence: 99%

Experimental Studies of MHD Pressure Drop of PbLi Flow in Rectangular Pipes Under Uniform Magnetic Field

Meng

Zhu

et al. 2015

J Fusion Energ

View full text Add to dashboard Cite

show abstract

“…As fusion reactor is one of the most promising solution methods of the sustainable development for nuclear energy utilization, many research and development works for fusion reactor are in progress [1][2][3][4][5], of which the International Thermonuclear Experimental Reactor (ITER) Project is the world-wide biggest fusion reactor research project. The neutron energy of ITER is 14 MeV and the neutron generated by a deuterium tritium (D-T) fusion neutron generator is just the same.…”

Section: Introductionmentioning

confidence: 99%

Heat Transfer Experiment and Simulation of the Verification Facility for High Power Rotating Tritium Target System

Wang

et al. 2015

J Fusion Energ

View full text Add to dashboard Cite

High intensity D-T fusion neutron generator (HINEG) is important for research and development work of fusion reactors, of which the rotating target system is one of the key components. The design of the cooling technology principle verification facility both for tritium target systems of the 3 9 10 13 and 10 14 n/s HINEG was proposed. The facility employed the jet array cooling method. The first stage heat transfer experiment was carried out and the heat transfer processes was simulated by CFD method, which aimed at the investigations of the new cooling enhancement technology. The experimental results, which had a good agreement with the numerical simulation results, show that the maximum temperature of the target surface was about 89.4°C under 60 kW heating condition and the average equivalent convection heat transfer coefficient of the jet array cooling was about 57,000 W/(m 2 K). All the results show that the verification facility could achieve the cooling requirement for 3 9 10 13 n/s neutron yield (60 kW) design objective and the jet array cooling enhancement technology was effective.

show abstract

“…Proposed roadmap and testing strategy of fusion energy has been being planned based on the assessment and design analysis of the developed series fusion reactors and hybrid system concepts in China [1][2][3][4][5][6][7][8][9][10] as well as a summary of related design and R&D activities in the world. In that development strategy, based on wide survey and analysis of development of the international fusion reactors and related research by FDS Team, a China Fusion DEMO Reactor (C-DEMO) concept has been proposed [11].…”

Section: Introductionmentioning

confidence: 99%

Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor

et al. 2014

View full text Add to dashboard Cite

Full superconducting tokamak and water-cooling Cu magnets tokamak are two options proposed for China Fusion Engineering Test Reactor (CFETR). Based on the concept design, the total construction cost was assessed with System Analysis Program for Parameters Optimization and Economic Assessment of Fusion Reactor, and the economy of the two options was compared with considering the cost of electricity consumption in D-T burning operation stage. The total of both costs and D-T burning operation time for different material neutron radiation damage of the two options were also analyzed. The results showed that the two options would have different economic advantages in construction and operation, and that the Cu magnets tokamak option could save both time and cost if the required material neutron radiation damage of CFETR is \75 dpa.

show abstract

The fusion-driven hybrid system and its material selection

Cited by 120 publications

References 20 publications

Experimental Studies of MHD Pressure Drop of PbLi Flow in Rectangular Pipes Under Uniform Magnetic Field

Experimental Studies of MHD Pressure Drop of PbLi Flow in Rectangular Pipes Under Uniform Magnetic Field

Heat Transfer Experiment and Simulation of the Verification Facility for High Power Rotating Tritium Target System

Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor

Contact Info

Product

Resources

About