A low aspect ratio tokamak transmutation system

Qiu, Linjing; Wu, Yican; Xiao, Bingjia; Xu, Qianfan; Huang, Qunying; Wu, Bin; Chen, Y.X.; Xu, Wenhai; Liu, X.P.

doi:10.1088/0029-5515/40/3y/325

Cited by 104 publications

(32 citation statements)

References 8 publications

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“…The average computational time of the proposed method was approximately 35 minutes (the size of CT was down-sampled to 128×128×40) with CPU. Next, we will attempt to speed up the proposed method and aim to apply our ARTS-IGRT system [4][5][6][7][8][9][10][11][12][13] to clinical practice. In addition to the processing time, automatic contour propagation could be applied not only to mono-modality images (such as CT-to-CT), but also to multi-modality images (such as CT-to-MR).…”

Section: Discussionmentioning

confidence: 99%

Deformable image registration of CT images for automatic contour propagation in radiation therapy

Cao

et al. 2015

BME

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Abstract. Radiotherapy treatment plan may be replanned due the changes of tumors and organs at risk (OARs) during the treatment. Deformable image registration (DIR) based Computed Tomography (CT) contour propagation in the routine clinical setting is expected to reduce time needed for necessary manual tumors and OARs delineations and increase the efficiency of replanning. In this study, a DIR method was developed for CT contour propagation. Prior structure delineations were incorporated into Demons DIR, which was represented by adding an intensity matching term of the delineated tissues pairs to the energy function of Demons. The performance of our DIR was evaluated with five clinical head-and-neck and five lung cancer cases. The experimental results verified the improved accuracy of the proposed registration method compared with conventional registration and Demons DIR.

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Section: Discussionmentioning

confidence: 99%

Deformable image registration of CT images for automatic contour propagation in radiation therapy

Cao

et al. 2015

BME

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“…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

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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.

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“…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

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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.

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A low aspect ratio tokamak transmutation system

Cited by 104 publications

References 8 publications

Deformable image registration of CT images for automatic contour propagation in radiation therapy

Deformable image registration of CT images for automatic contour propagation in radiation therapy

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

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