scholarly journals Determination of the boron concentration of OPR 1000 reactor critical state using the Cosi OPR1000 system

2016 ◽  
Vol 19 (4) ◽  
pp. 241-248
Author(s):  
Son An Nguyen ◽  
Nguyen Trung Tran ◽  
Tuan Quoc Tran ◽  
Cuong Quang Ly ◽  
Lan Thi Ha Le ◽  
...  

In the operation of a nuclear power plant (NPP), to adjust the capacity of NPP is necessary. When the NPP capacity is changed the nuclear fission is also changed. The methods used in changing the capacity of NPP include: changing the boron concentration, changing the position of the control rod groups, and changing the boron concentrations and the position of the control rod groups together. This report presents some results of the research, measurement boron concentrations when nuclear power plans OPR1000 critically state in the cases of ARO, ARI SB, ARI R1, R5 = 191 cm on the basis of the bisection method in the boron concentrations adjustment. The experiment is performed on core the simulator for OPR 1000 nuclear power plant. The results in the 4 cases were similar with NPP operating data using OPR1000 reactor.

2018 ◽  
Vol 1 (6) ◽  
pp. 177-184
Author(s):  
Son An Nguyen ◽  
Nguyen Trung Tran

In order to operate a nuclear power plant, ensuring safety is the most important factor. The function of safety rods are to shut down the reactor in case of emergency. The purpose of this paper to show the result of research and determine the value of safety rods SA, SB. Determination of the Boron concentration corresponding to each group of safety rods of OPR1000 nuclear reactor ensures the safely in the whole operation process. Experimental simulation is carried out in the system simulating core reactor OP1R1000 (CoSi OPR1000). The expermental result corresponds with the theoretic calculated result of Sa and Sb with 1500 pcm, 4000 pcm. The concentrations of Boron appropriately are 134 ppm and 284 ppm, respectively.


2019 ◽  
Vol 7 (2A) ◽  
Author(s):  
Marcelo Bessa Nisti ◽  
Cátia H.R. Saueia ◽  
Bruna Castilho ◽  
Barbara P. Mazzilli

The study of artificial radionuclides dispersion into the environment is very important to control the nuclear waste discharges, nuclear accidents and nuclear weapons testing. The accidents in Fukushima Daiichi Nuclear Power Plant and Chernobyl Nuclear Power Plant, released several radionuclides in the environment by aerial deposition and liquid discharge, with various level of radioactivity. The 90Sr was one of the elements released into the environment. The 90Sr is produced by nuclear fission with a physical half-life of 28.79 years with decay    energy of 0.546 MeV. The aims of this study are to evaluate the precision and accuracy of three methodologies for the determination of 90Sr in water samples: Cerenkov, LSC direct method and with radiochemical            separation. The performance of the methodologies was evaluated by using two scintillation counters (Quantulus and Hidex). The parameters Minimum Detectable Activity (MDA) and Figure Of Merit (FOM) were determined for each method, the precision and accuracy were checked using 90Sr standard solutions. 


1993 ◽  
Vol 640 (1-2) ◽  
pp. 371-378 ◽  
Author(s):  
Archava Siriraks ◽  
John Stillian ◽  
Dennis Bostic

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