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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
Benjamin Wellons, Rishya Sankar Kumaran, Sanghun Lee, Shikha Prasad
Nuclear Technology | Volume 209 | Number 1 | January 2023 | Pages 69-81
Technical Paper | doi.org/10.1080/00295450.2022.2108686
Articles are hosted by Taylor and Francis Online.
An open-source code RadSigPro 1.0 has been developed and used for fast processing of nanosecond-long pulses from scintillation detectors. This processing includes pulse height distribution (PHD), pulse shape discrimination (PSD), and time of flight (TOF). The code has been implemented onto the programmable logic design of a field programmable gate array (FPGA) design for on-the-fly processing of neutron and gamma-ray pulses. A weighted average of the percent difference of the results for RadSigPro 1.0 implemented on a CPU and a FPGA logic design is calculated. This shows a 0% difference for the PHD data sets, a 0.458% and 0.344% difference for the designated gamma detector and neutron detector PSD data sets, respectively, and a 0% difference for the TOF data set. When the FPGA logic design is applied and simulated, it computed the total and tail pulse areas within 5 ns of the arrival of the final data point used for accumulation and also captured the pulse height value within 2 ns of the arrival of the pulse’s maximum data point.
