Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR

Author:

Cui Shijie,Zhang Dalin,Lian Qiang,Cheng Jie,Tian Wenxi,Su G.H.,Qiu Suizheng

Funder

evaluation and research on the thermal-hydraulic design and safety analysis of Chinese fusion engineering test reactor

Publisher

Elsevier BV

Subject

Energy Engineering and Power Technology,Condensed Matter Physics,Fuel Technology,Renewable Energy, Sustainability and the Environment

Reference32 articles.

1. Y.X.; Wan, CFETR Team. Design and strategy for the Chinese fusion engineering test reactor (CFETR), in: SOFE 2013, San Francisco, USA, 10–14 June, 2013.

2. Wan Y.X, Li J, Liu Y, Wang X.L, CFETR Team. Overview of the present progresses and activities on the Chinese fusion engineering test reactor, in: 26th IAEA fusion energy conference, Kyoto, Japan, 17–22 October, 2016.

3. Overview of the present progress and activities on the CFETR;Wan;Nucl Fusion,2017

4. Feedback controller input design for ignition of deuterium–tritium in NSTX tokamak;Naghidokht;Int J Hydrogen Energy,2016

5. Conceptual design and analysis of the helium cooled solid breeder blanket for CFETR;Chen;Fusion Eng Des,2015

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