Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel

Author:

Wang ChenglongORCID,Qin Hao,Tian Wenxi,Qiu Suizheng,Su G.H.

Funder

Natural Science Foundation of China

China Postdoctoral Science Foundation

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference28 articles.

1. Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity;Forsberg;Nucl. Technol.,2003

2. Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat;Forsberg,2012

3. Thermal-hydraulic analyses of transportable fluoride salt-cooled high-temperature reactor with CFD modeling;Wang;Nucl. Technol.,2016

4. Fuel pebble optimization for the thorium-fueled Pebble Bed Fluoride salt-cooled high-temperature reactor (PB-TFHR);Fang;Prog. Nucl. Energy,2018

5. FHR, HTGR, and MSR Pebble-bed reactors with multiple pebble sizes for fuel management and coolant cleanup;Forsberg;Nucl. Technol.,2019

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