Preliminary Neutronics/Thermal-Hydraulics Design and Analyses of the Helium-Cooled Mixed Bed Breeder Blanket for Cfetr Under 1.5 Gw Fusion Power

[1]  Hongchun Wu,et al.  The neutron-photon-coupling analysis of the tritium-breeding blanket in CFETR by NECP-MCX , 2021 .

[2]  Xinghua Wu,et al.  Neutronics and shielding design of CFETR HCCB blanket , 2021, Fusion Engineering and Design.

[3]  Xiaofang Luo,et al.  Effects of bed dimension, friction coefficient and pebble size distribution on the packing structures of the pebble bed for solid tritium breeder blanket , 2021 .

[4]  Jie Li,et al.  NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems , 2021 .

[5]  R. Gaisin,et al.  Industrial-scale manufacturing experience of titanium beryllide block for DEMO blanket application , 2020 .

[6]  F. Arbeiter,et al.  Validation study of turbulence models for thermal-hydraulic simulation of helium cooled DONES high flux test module , 2020 .

[7]  Jae-Hwan Kim,et al.  Compatibility of advanced tritium breeders and neutron multipliers , 2020 .

[8]  Min Li,et al.  Updated design of water-cooled breeder blanket for CFETR , 2019, Fusion Engineering and Design.

[9]  Kenji Tobita,et al.  Development of water-cooled blanket concept with pressure tightness against in-box LOCA for JA DEMO , 2019, Fusion Engineering and Design.

[10]  Y.T. Song,et al.  Progress of the CFETR design , 2019, Nuclear Fusion.

[11]  Gandolfo Alessandro Spagnuolo,et al.  Advancements in the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO: Holistic Design Approach and Lessons Learned , 2019, Fusion Science and Technology.

[12]  Satoshi Kakudate,et al.  Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade , 2019, Fusion Science and Technology.

[13]  I. Ricapito,et al.  An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort , 2019, Fusion Engineering and Design.

[14]  Jie Cheng,et al.  Improving the optimization algorithm of NTCOC for application in the HCSB blanket for CFETR Phase II , 2018, Fusion Engineering and Design.

[15]  Jie Cheng,et al.  Development and application of a neutronics/thermal-hydraulics coupling optimization code for the CFETR helium cooled solid breeder blanket with mixed pebble beds , 2017 .

[16]  Zaixin Li,et al.  Neutronics study on HCCB blanket for CFETR , 2017 .

[17]  Qingwei Yang,et al.  Overview of the present progress and activities on the CFETR , 2017 .

[18]  Jun Ho Yeom,et al.  Design concept of K-DEMO for near-term implementation , 2015 .

[19]  Songlin Liu,et al.  Conceptual design of a water cooled breeder blanket for CFETR , 2014 .

[20]  M. Gadomska,et al.  Overview of EU DEMO design and R&D activities , 2014 .

[21]  N. Asakura,et al.  Simplification of blanket system for SlimCS fusion DEMO reactor , 2011 .

[22]  S. Ide,et al.  Compact DEMO, SlimCS: design progress and issues , 2009 .

[23]  A. Hogenbirk,et al.  An easy way to perform a radiation damage calculation in a complicated geometry , 2008 .

[24]  S. Gordeev,et al.  Analysis of turbulence models for thermohydraulic calculations of helium cooled fusion reactor components , 2006 .

[25]  D. Maisonnier,et al.  The European power plant conceptual study , 2005 .

[26]  C. Johnson,et al.  Ceramic breeder material development , 1998 .

[27]  Mohamed A. Abdou,et al.  Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors , 1986 .