HTGR高温气冷堆

Principle
Inherent safety characteristics：
Fuel temperature does not exceed 1600 ° C limit under any accident conditions Fission products are always contained in the fuel particles No accidental melting and radioactive mass release of the core
Principle
Helium
Chemical inertness Easy to purify Good thermal conductivity
Principle
The helium coolant is pumped from the bottom of the reactor into the core. Helium will be heated through the gap of sphere fuel, and the output temperature can reach 950 degrees. Then high temperature helium goes into the steam generator and makes water transfer into steam. Finally high temperature steam drives turbine to generate electricity.
The third generation of nuclear power plants：Advanced light water reactor
Introduction
The fourth generation of nuclear energy system:
Very-High-Temperature Gas-Cooled Reactor System（超高温反应堆系统） Gas-Cooled Fast Reactor System(气体冷却快堆 系统) Lead-cooled Fast Reactor System（铅冷却快堆系 统） Molten Salt Reactor System（熔盐反应堆系统） Sodium-Cooled Fast Reactor System（钠冷却快 堆系统） Supercritical-Water-Cooled Reactor System（超 临界冷却反应堆系统） A promising one
Conclusion
HTGR:
High temperature and high efficiency High conversion ratio High security Small environmental pollution，and can be built in densely populated areas Broad application prospect
Tough(不易破损) High temperature resistance 60mm fuel spheres
Principle
Graphite cladding Graphite matrix Coated particle
Coated particles are too small to be used directly, so they will be dispersed in the graphite mix to be pressed into the fuel entity. Then, the fuel entity is placed in a spherical fuel element consisting of graphite cladding
HTGR
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CONTENTS
1. Introduction 2.Development 3.Principle 4. Conclusions
Introduction
The second generation of nuclear power plants: Standardization, mass construction
Ceramic pellet fuel Helium
Higher temperature Higher efficiency Safer
Principle
0.5mm fuel kernel Uranium dioxide 0.92mm coated particle
Sphere ceramic pellet fuel
No Industrial uranium enrichment technology
Natural uranium
High cost Low efficiency18.8%
Development
Second generation gas cooled reactor
Advanced gas cooled reactor(AGR):
Conclusion
Plant overview
China has independently developed the world's first high-temperature gas-cooled reactor nuclear power plant with the fourth generation of nuclear power technology in Rongcheng Shandong
Principle
Sphere fuel:
The 60mm sphere fuel is continuously loaded into the core from the top, and the spent fuel ball Hale Waihona Puke Baiduill be measured. If the sphere fuel is not up to the predetermined fuel consumption depth, it will be sent back to the reactor again. Generally the sphere fuel will be used more than 10 times.
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Development
High temperature gas cooled reactor:
Fuel: High temperature ceramic pellet fuel Coolant: Helium-950℃ Moderator: Graphite breakthrough Cladding material: Ceramics
50s-60s
70s-80s 90s
The forth generation of nuclear power plants： safety、less waste 、 prevention of nuclear proliferation
1999
The first generation of nuclear power plants: feasibility
China and japan lead the world
Development
First generation gas cooled reactor(50s70s)
Magnox type gas cooled reactor
Fuel: Natural uranium Coolant: CO2-400℃ Moderator: Graphite Cladding material: Magnox
Fuel: 2% UO2 Coolant: CO2-670℃ Moderator: Graphite Cladding material: Stainless steel Low enriched uranium Stainless steel
Small volume-low cost High efficiency-40%