Thermal power calibrations of the IPR-R1 TRIGA reactor by the calorimetric and the heat balance methods

Mesquita, Amir Zacarías; Rezende, Hugo Cesar; Souza, Rose Mary Gomes do Prado

doi:10.1016/j.pnucene.2011.08.003

Cited by 15 publications

(2 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This method has uncertainties of about 4%. For continuous monitoring of the thermal reactor power level, the instrumentation for temperature and flow signal measurement was incorporate in the data acquisition system (Mesquita et al, 2011). The methodologies and graphical interfaces implemented in this project provide greater reliability and transparency in its operations.…”

Section: Discussionmentioning

confidence: 99%

Power Measurement Methodologies for Pool Nuclear Research Reactors

Mesquita

Palma

Rezende

et al. 2021

Lat. Americ. J. of Develop.

Self Cite

View full text Add to dashboard Cite

Redundancy and diversity are two important criteria for power measurement in nuclear reactors. Other criteria such as accuracy, reliability and response speed are also of major concern. Power monitoring of nuclear reactors is normally done by means of neutronic instruments, i.e. by the measurement of neutron flux. The greater the number of channels for power measuring the greater is the reliability and safety of reactor operations. The aim of this research is to develop new methodologies for on-line monitoring of nuclear reactor power using other reliable processes. One method uses the temperature difference between an instrumented fuel element and the pool water below the reactor core. Another method consists of the steady-state energy balance of the primary and secondary reactor cooling loops. A further method is the calorimetric procedure whereby a constant reactor power is monitored as a function of the temperature-rise rate and the system heat capacity. Another methodology, which does not employ thermal methods, is based on measurement of Cherenkov radiation produced within and around the core. The first three procedures, fuel temperature, energy balance and calorimetric, were implemented in the IPR-R1 Triga nuclear research reactor at Belo Horizonte (Brazil) and are the focus of the work described here. Knowledge of the reactor thermal power is very important for precise neutron flux and fuel element burnup calculations. The burnup is linearly dependent on the reactor thermal power and its accuracy is important in the determination of the mass of burned 235U, fission products, fuel element activity, decay heat power generation and radiotoxicity. The thermal balance method developed in this project is now the standard methodology used for IPR-R1 Triga reactor power calibration and the fuel temperature measuring is the most reliable way of on-line monitoring of the reactor power. This research project primarily aims at increasing the reliability and safety of nuclear reactors using alternative methods for power monitoring.

show abstract

Section: Discussionmentioning

confidence: 99%

Power Measurement Methodologies for Pool Nuclear Research Reactors

Mesquita

Palma

Rezende

et al. 2021

Lat. Americ. J. of Develop.

Self Cite

View full text Add to dashboard Cite

show abstract

“…The reactor thermal power and the measuring devices were calibrated according to the methodology described by Mesquita et al (2011) [3]. This method consists in the steady-state energy balance of the primary cooling loop of the reactor.…”

Section: Methodsmentioning

confidence: 99%

Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 kW

Mesquita

2021

Braz. J. Rad. Sci.

Self Cite

View full text Add to dashboard Cite

In order to study the safety aspects connected with the permanent increase of the maximum steady state power of the IPR-R1 Triga Reactor of the Nuclear Technology Development Center (CDTN), experimental measurements were done with the reactor operating at power levels of 265 kW and 105 kW, with the pool forced cooling system turned off. A number of parameters were measured in real-time such as fuel and water temperatures, radiation levels, reactivity, and influence of cooling system. Information on all aspects of reactor operation was displayed on the Data Acquisition System (DAS) shown the IPR-R1 online performance. The DAS was developed to monitor and record all operational parameters. Information displayed on the monitor was recorded on hard disk in a historical database. This paper summarizes the behavior of some operational parameters, and in particular, the evolution of the temperature in the fuel element centerline positioned in the core hottest location. The natural circulation test was performed to confirm the cooling capability of the natural convection in the IPR-R1 reactor. It was confirmed that the IPR-R1 has capability of long-term core cooling by natural circulation operating at 265 kW. The measured maximum fuel temperature of about 300 oC was lower than the operating limit of 550 oC. It has been proven that without cooling in the primary the gamma dose rate above reactor pool at high power levels was rather high.

show abstract