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High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
Hangbok Choi, John Bolin
Nuclear Technology | Volume 206 | Number 7 | July 2020 | Pages 1010-1018
Regular Technical Paper | doi.org/10.1080/00295450.2019.1699008
Articles are hosted by Taylor and Francis Online.
Fuel performance analysis was conducted for silicon carbide (SiC) composite clad uranium carbide (UC) fuel of a 500-MW(thermal) gas-cooled fast reactor, specifically the energy multiplier module (EM2) under normal operation. The analysis consists of two parts: Part I includes a description of design bases and criteria, fuel element design specifications, and material properties and models, while Part II (this paper) includes the fuel modeling approach, computer code, and the fuel design evaluation. In Part II, the FRAPCON-4.0 code was updated to include material properties and models of UC fuel, SiC composite cladding, and helium coolant, and named FRAPCON-4.0GA. The analysis was performed using the hot rod power envelope and burnup history. The results show that the present design of the EM2 fuel element has ample margin to melting owing to the high thermal conductivity of the UC fuel and annular pellet configuration. The operating temperature of the fuel element also minimizes the radiation-induced deformation of the SiC composite cladding. The simulation results show that the hoop stress of the cladding is below its tensile stress limit, i.e., one-third of ultimate tensile stress, while the cladding hoop strain limit is reached at 22.5 year, which is less than its design life of 32 years. However, sensitivity calculations of the swelling rate and design parameters indicate that it is feasible to reduce the cladding hoop strain by accommodating the fuel swelling into the open pore. Considering uncertainties associated with the material properties and models, it is highly recommended to experimentally verify the UC swelling and SiC composite creep, which are critical properties in analyzing the long-life fuel behavior.
