Research for axial power distribution control of a space nuclear reactor based on nonlinear model

2022 ◽  
Vol 168 ◽  
pp. 108917
Author(s):  
Chengxuan Zhao ◽  
Xiao Yang ◽  
Minghan Yang ◽  
Jianye Wang ◽  
Shuai Chen
2021 ◽  
pp. 103564
Author(s):  
Wenjie Zeng ◽  
Qingfeng Jiang ◽  
Yinuo Liu ◽  
Shoujun Yan ◽  
Guangchun Zhang ◽  
...  

Author(s):  
Achmad Solih ◽  
Jamaaluddin Jamaaluddin

Panel system power distribution at Lippo Plaza Mall Sidoarjo consists of several parts, namely from Cubicle 20 KV, 20 KV step-down transformer for 380 V, then the supply to LVMDP (Low Voltage Main Distribution Panel) The new panel to the user. Before delivery to users to note that the power factor is corrected using a capacitor bank. Less good a power factor is turned into inductive load on the capacitor bank so that temperatures high  because of high load resulting capacitor bank erupt. To overcome in this study proposes a safety panel automation power distribution control system using a microcontroller. Control system microcontrollers for safety panel power distribution consists of: Microcontroller (Arduino Nano), Light sensor (LDR), temperature sensor (LM35DZ), LCD 16x2 I2C, Actuators (fan, buzzer, relay switch breaker network three phase), switch ( relay 5 VDC), ADC as Input data. The working principle of this microcontroller LM35DZ if the sensor detects a high temperature fan will flash, if the LDR sensor detects sparks then the buzzer will sound as a warning sign of the dangers and disconnected the electricity network. From the design of a safety tool for power distribution panels due to high temperatures or sparks as well as the expected rate of fire outbreaks can be prevented.


2021 ◽  
Vol 31 (1) ◽  
pp. 60-71
Author(s):  
Leonardo Acosta Martínez ◽  
Carlos Rafael García Hernández ◽  
Jesus Rosales García ◽  
Annie Ortiz Puentes

One of the challenges of future nuclear power is the development of safer and more efficient nuclear reactor designs. The AP1000 reactor based on the PWR concept of generation III + has several advantages, which can be summarized as: a modular construction, which facilitates its manufacture in series reducing the total construction time, simplification of the different systems, reduction of the initial capital investment and improvement of safety through the implementation of passive emergency systems. Being a novel design it is important to study the thermohydraulic behavior of the core applying the most modern tools. To determine the thermohydraulic behavior of a typical AP1000 fuel assembly, a computational model based on CFD was developed. A coupled neutronic-thermohydraulic calculation was performed, allowing to obtain the axial power distribution in the typical fuel assembly. The geometric model built used the certified dimensions for this type of installation that appear in the corresponding manuals. The thermohydraulic study used the CFD-based program ANSYS-CFX, considering an eighth of the fuel assembly. The neutronic calculation was performed with the program MCNPX version 2.6e. The work shows the results that illustrate the behavior of the temperature and the heat transfer in different zones of the fuel assembly. The results obtained agree with the data reported in the literature, which allowed the verification of the consistency of the developed model.


2019 ◽  
Vol 2019 ◽  
pp. 1-8
Author(s):  
Shengzhe Li ◽  
Dongmei Yang ◽  
Tengfei Zhang ◽  
Xiaojing Liu

CIPS is a shift in the axial power towards the bottom half of the core, also known as axial offset anomaly (AOA), which results from the deposited of corrosion products during an operation. The main reason of CIPS is the solute particles especially boron compounds concentrated inside the porous deposit. The impact of CIPS is that the axial power distribution control may be more difficult and the shutdown margin can be decreased simultaneously. Besides, it also requires estimated critical condition (ECC) calculations to account for the effects of AOA. In this article, thermal-hydraulic subchannel code and boron deposit model have been combined to analyze the CIPS risk. The neutronics codes deal with the generation of homogenized neutron cross section as well as the calculation of local power factor. A simple rod assembly is analyzed with this combined method and simulation results are presented. Simulation results provide the boron hideout amount inside crud deposits and power shapes. The obtained results clearly show the power shape suppression in regions where crud deposits exist, which is a clear indication of CIPS phenomenon. And the CIPS effects on CHF have also been investigated. Result shows a margin of DNBR decrease in the crud case.


Author(s):  
Guangwen Bi ◽  
Chuntao Tang ◽  
Bo Yang

Elimination of soluble boron will be a challenge to reactor operation for PWR. This paper is to promote a control strategy of soluble boron-free operation for a small PWR, through selection of burnable poison (BP), BP loading and control rod loading, based on the reactivity balance and manage requirement. The analysis for on-power operation and shutdown condition indicated that this strategy could be suitable for long-term and short-term reactivity and power distribution control for soluble boron-free operation.


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