Thermal methods for on-line power monitoring of the IPR-R1 TRIGA Reactor

Experimental Investigation of Thermal Hydraulics in the IPR-R1 TRIGA Nuclear Reactor

“…The data obtained during the experiments provide an excellent picture of the IPR-R1 reactor's thermal performance. The experiments confirm the efficiency of natural circulation in removing the heat produced in the reactor core by nuclear fission (Mesquita & Rezende, 2010).…”

Thermal-hydraulic and neutronic experimental research in the TRIGA reactor of Brazil

“…The temperature coefficient of reactivity is defined as the change in reactivity due to a variation in the average temperature of each component of the core. Using the values of the temperatures found in the fuel and in the core, it was presented an experimental curve of the total temperature reactivity coefficient versus the core average temperature (Mesquita and Souza, 2010).…”

Improving the Performance of the Power Monitoring Channel

“…The sensitive tips of the thermocouples are located one at the center of the fuel section and the other two 25.4 mm above, and 25.4 mm below the center. Figure 18 shows the diagram and design of the instrumented fuel element (Zacarias Mesquita and Cesar Rezende, 2010). The instrumented fuel element which is placed in proper thimble (B6 position) is obvious in Figure 19, a core upper view.…”

“…19. Core upper view with the instrumented fuel element (Zacarias Mesquita and Cesar Rezende, 2010) During the experiments it was observed that the temperature difference between fuel element and the pool water below the reactor core (primary loop inlet temperature) do not change for the same power value. Figure 20 compares the reactor power measuring results using the linear neutron channel and the temperature difference channel method (Zacarias Mesquita and Cesar Rezende, 2007).…”

“…Zacarias Mesquita, A.;Cesar Rezende, H. (2007 This book presents a comprehensive review of studies in nuclear reactors technology from authors across the globe. Topics discussed in this compilation include: thermal hydraulic investigation of TRIGA type research reactor, materials testing reactor and high temperature gas-cooled reactor; the use of radiogenic lead recovered from ores as a coolant for fast reactors; decay heat in reactors and spent-fuel pools; present status of two-phase flow studies in reactor components; thermal aspects of conventional and alternative fuels in supercritical water?cooled reactor; two-phase flow coolant behavior in boiling water reactors under earthquake condition; simulation of nuclear reactors core; fuel life control in light-water reactors; methods for monitoring and controlling power in nuclear reactors; structural materials modeling for the next generation of nuclear reactors; application of the results of finite group theory in reactor physics; and the usability of vermiculite as a shield for nuclear reactor.…”