Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR-Reference-Cited by-同舟云学术

Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR

Published:2017-01 Issue: Volume:114 Page:141-156
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Cui Shijie,Zhang Dalin,Cheng Jie,Tian Wenxi,Su G.H.

Funder

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

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference22 articles.

1. CFETR, design and strategy for the Chinese fusion engineering test reactor (CFETR);Wan,2013

2. Conceptual design and analysis of the helium cooled solid breederblanket for CFETR;Chen;Fusion Eng. Des.,2015

3. Conceptual design of a water cooled breeder blanket for CFETR;Liu;Fusion Eng. Des.,2014

4. Structural design and preliminary analysis of liquid lead–lithiumblanket for China fusion engineering test reactor;Ni;Fusion Eng. Des.,2015

5. Preliminary neutronics design and analysis of helium cooled solidbreeder blanket for CFETR;Lv;Fusion Eng. Des.,2015

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2. Thermal-hydraulic analysis of the CFETR TF coils when subject to nuclear heat load;Fusion Engineering and Design;2021-12

3. Effects of fixed wall and pebble size ratio on packing properties and contact force distribution in binary-sized pebble mixed beds at the maximum packing efficiency state;Powder Technology;2021-09

4. Neurtonics/Thermal-hydraulic analyses of the CFETR HCCB blanket for multiple operation modes under the poloidal nonuniform neutron wall loading condition;Fusion Engineering and Design;2021-07

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