HTR-10
HTR-10 is a nuclear reactor designed and constructed by the Institute of Nuclear and New Energy Technology (INET) at Tsinghua University in China. The HTR-10 is a High-temperature gas-cooled reactor (HTGR), a type of thermal-neutron reactor that utilizes uranium fuel and helium as a coolant.
Design and Construction[edit | edit source]
The HTR-10 is a pebble-bed reactor, a design that uses small, spherical fuel elements called pebbles. These pebbles, approximately the size of tennis balls, contain thousands of tiny uranium fuel particles. The design of the HTR-10 allows for a high power density with a relatively low core volume, contributing to its overall safety and efficiency.
The construction of the HTR-10 began in 1995 and was completed in 2000. The reactor achieved its first criticality in December 2000 and was connected to the grid in January 2003.
Operation and Performance[edit | edit source]
The HTR-10 has a thermal power output of 10 MW and an electrical output of 3 MW. The reactor operates at a temperature of 700 degrees Celsius, which is significantly higher than most other reactor designs. This high operating temperature allows for a higher thermal efficiency and the potential for hydrogen production.
The HTR-10 has demonstrated excellent safety performance throughout its operation. The reactor is designed to be inherently safe, meaning that it can withstand a variety of accident scenarios without the need for human intervention or mechanical safety systems.
Future Developments[edit | edit source]
The success of the HTR-10 has led to plans for the construction of larger, commercial-scale HTGRs in China. The HTR-PM project, a 210 MW pebble-bed reactor, is currently under construction and is expected to be operational by 2020.
See Also[edit | edit source]
References[edit | edit source]
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