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

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

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

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

• Nuclear power in China
• Nuclear reactor technology
• High-temperature gas-cooled reactor

References

<references />

Error creating thumbnail:

   This article is a nuclear physics or atomic physics–related stub. You can help WikiMD by expanding it!

• Tsinghua 04790004
  Tsinghua 04790004