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Thermodynamics of Nuclear Energy Conversion Systems—Nonflow and Steady Flow
Published in Neil E. Todreas, Mujid S. Kazimi, Nuclear Systems Volume I, 2021
Neil E. Todreas, Mujid S. Kazimi
A gas-cooled reactor is designed to heat helium gas to a maximum temperature of 540°C. The helium flows through a gas turbine, generating work to run the compressors and an electric generator and then through a regenerative heat exchanger and two stages of compression with precooling to 40°C before entering each compressor. Each compressor and the turbine have an isentropic efficiency of 85% and the exchanger drop factor β is equal to 1.05. Each compression stage has a pressure ratio, rp, of 1.27. The heat exchanger effectiveness, ξ, is 0.90.
Modern Power Systems
Published in Stephen W. Fardo, Dale R. Patrick, Electrical Power Systems Technology, 2020
Stephen W. Fardo, Dale R. Patrick
High-temperature Gas-cooled Reactor (HTGR)—The high-temperature gas-cooled reactor, shown in Figure 4-20 uses pressurized helium gas to transfer heat from the reactor to a steam-production system. The advantage of helium gas over water is that the helium can operate at much higher temperatures.
Nuclear Reactor Fluid Mechanics
Published in Robert E. Masterson, Nuclear Reactor Thermal Hydraulics, 2019
Most gases follow this law at low and intermediate pressures. Finally, the kinetic theory of gases predicts that the viscosity of most gases is directly proportional to the square root of the absolute temperature. Because of this, the viscosity of the coolant in a gas-cooled reactor (GCR), whether it is hydrogen, helium, or carbon dioxide, is subject to the following relationship:
Effect of Cladding Surface Roughness on Thermal-Hydraulic Response of Nuclear Fuel Rod of Advanced Gas-Cooled Reactor
Published in Nuclear Science and Engineering, 2022
Sadek Hossain Nishat, Md. Hossain Sahadath, Farhana Islam Farha
Cooling is a challenging issue in nuclear reactors. Sufficient cooling must be required to properly remove nuclear reactor core heat to produce electric power as well as to prevent fuel cladding damage and core meltdown.9 Many nuclear reactors use liquid water as reactor coolant to sufficiently and safely remove the reactor core heat. But, some nuclear power reactors, for example, MAGNOX, Advanced Gas-Cooled Reactor (AGR), HTGR, etc., use gaseous fluid as the reactor coolant.10 In the U.K.-designed AGRs, carbon dioxide (CO2) is used as the reactor coolant. Because CO2 is a gaseous fluid, its thermal property especially the convective heat transfer coefficient is lower than for liquid fluids. So, a main issue is to enhance the surface heat transfer coefficient of AGR fuel cladding. For this purpose, ribs are placed on the AGR fuel cladding11 to augment or enhance the heat transfer coefficient and to enhance the thermal efficiency of the whole nuclear power plant system.
Summary of Tritium Source Term Study in 10 MW High Temperature Gas-Cooled Test Reactor
Published in Fusion Science and Technology, 2020
X. Liu, W. Peng, F. Xie, J. Cao, Y. Dong, X. Duan, Y. Wen, B. Shan, K. Sun, G. Zheng
The history of the research and development of HTGRs has been summarized in the literature.9 Typically, there are two types of HTGRs: prismatic and pebble-bed reactors. The Peach Bottom reactor, Fort St. Vrain reactor, and 350 MW(thermal) modular high temperature gas-cooled reactor (MHTGR) in the United States and the high-temperature engineering test reactor (HTTR) in Japan are prismatic reactors.10 The Arbeitsgemeinschaft Versuchsreaktor (AVR), thorium high-temperature reactor (THTR), and 200 MW(thermal) HTR-module in Germany, pebble-bed modular reactor (PBMR) in South Africa, and 10 MW high temperature gas-cooled test reactor (HTR-10) in China are pebble-bed reactors.11,12 The first pebble-bed gas-cooled test reactor in China, HTR-10, uses helium, graphite, and graphite spheres containing embedded tristructural-isotropic (TRISO)–coated particles as primary coolant, reflector, and fuel elements, respectively.