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A closer look at the initial NLIC selections—Part 2
In January, the Department of Energy announced its new Nuclear Lifecycle Innovation Campus (NLIC) program, inviting states via a request for information to express their interest in hosting a facility supporting work from the front to the back end of the nuclear fuel cycle.
By April, 26 states had expressed interest in hosting such a facility. At the end of July, the DOE signed memorandums of understanding with five states—Idaho, Louisiana, Oklahoma, Tennessee, and Utah—to more closely explore the possibilities of state-federal partnerships. These MOUs are not firm commitments from either the federal or state governments. Time will tell which—if any—of the five states develop projects through the program. In the meantime, today, we are taking a close look at what Utah, Idaho, Tennessee can offer in terms of a preexisting nuclear sector that could support new fuel cycle developments.
Derjew Ayele Ejigu, Xiaojing Liu
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1239-1254
Technical Paper | doi.org/10.1080/00295639.2022.2138688
Articles are hosted by Taylor and Francis Online.
A pressurized water reactor (PWR) is a system of several integrated components such as the core, steam generator, hot leg, cold leg, and plenums. The subsystems consist of critical parameters and malfunctions that cause potential accidents. Therefore, a PWR requires a control system for safe and stable operation over its lifetime. In this study, the state-space model of the PWR core is established and validated with published work. Then, a beetle antenna search (BAS) algorithm–optimized radial basis function (RBF) neural network proportional-integral-derivative (PID) control (BAS-RBF-PID) strategy is proposed to regulate the core power. The BAS-RBF-PID control approach computes the control input to optimize the PWR core output power to track the reference command. The integral absolute error and integral time absolute error criterion functions are used to measure the control performance. The sensitivity of the control input on the PWR output is examined through the Jacobian, and the stability is analyzed by using the Lyapunov approach and Nichols chart. The simulation results verified that the PWR core output power chased the reference command smoothly as compared with the BAS-PID and PID strategies with good performance. This confirms that the control signal optimizes the core power effectively. This study gives the benefit to apply the BAS-RBF-PID algorithm in other nuclear engineering fields for control purposes.