scholarly journals Visual interfaces for the digital simulation system of the IPR-R1 Triga nuclear research reactor

2020 ◽  
Vol 6 (21) ◽  
pp. 80-90
Author(s):  
Amir Z. Mesquita ◽  
Adriano de A. M. Felippe ◽  
Aldo M. F. Lage ◽  
Patrícia A. M. Ribeiro
Keyword(s):  
Research Reactor ◽  
Technology Development ◽  
Digital Simulation ◽  
Nuclear Research ◽  
Simulation System ◽  
Human Machine Interaction ◽  
System Variables ◽  
Simplified Modeling ◽  
Physical Phenomena ◽  
Visual Interfaces

Nuclear Technology Development Center (CDTN) offers the Training Course for Research Reactor Operator (Ctorp). This course is offered since 1974 and about 250 nuclear professionals were certificated by CDTN. Thus, a digital simulation system for the IPR-R1 Triga research reactor was developed to be a tool for teaching, training and recycling professionals. The simulator was developed using the LabVIEW® (Laboratory Virtual Instruments Engineering Workbench), with support calculation software, where mathematical models and graphical interface configurations form a friendly platform, which allows the trainee to be identified with the physical systems of the research reactor. A simplified modeling of the main physical phenomena related to the operation of the reactor and the reactivity control systems, reactor cooling and reactor protection was used. The digital simulator allows an HMI (Human-Machine Interaction) by manipulating system variables and monitoring trends in quantities during the operation of the reactor, showing an interactive tool for teaching, training and recycling for professionals in the IPR-R1 Triga nuclear research, allowing simulations of the start, power and stop operations. This paper presents the design and results of the user visual interfaces developed for the reactor operation simulator. This is the equivalent part of structured text programming and, therefore, the most significant part of the developed simulator.

scholarly journals ANALYSIS OF AN EXTREME LOSS OF COOLANT IN THE IPR-R1 TRIGA REACTOR USING A RELAP5 MODEL

2013 ◽  
Vol 12 (2) ◽  
pp. 46
Author(s):  
P. A. L. Reis ◽  
A. L. Costa ◽  
C. Pereira ◽  
M. A. F. Veloso ◽  
H. V. Soares ◽  
...  
Keyword(s):  
Research Reactor ◽  
Technology Development ◽  
Nuclear Research ◽  
Hydraulic Analysis ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Transient Case ◽  
Fuel Elements ◽  
Thermal Hydraulic Analysis ◽  
Pool Type

The RELAP5/MOD3.3 code has been applied for thermal hydraulic analysis of power reactors as well as nuclear research reactors with good predictions. The development and the assessment of a RELAP5 model for the IPR-R1 TRIGA have been validated for steady state and transient situations. The reactor is located at the Nuclear Technology Development Centre (CDTN), Brazil. It is a 250 kW, light water moderated and cooled, graphite-reflected, open pool type research reactor. In this work, an extreme transient case of loss of coolant accident (LOCA) has been simulated. For this type of analysis, the automatic scram of the reactor was not considered because the main aim was to verify the evolution of the fuel elements heating in the absence of coolant. The temperature evolutions are presented as well as an analysis about the temperature safety limits.

scholarly journals MCNP model of L-54M nuclear research reactor: validation by preliminary graphite radiological characterization

2019 ◽  
Vol 322 (3) ◽  
pp. 1341-1350
Author(s):  
Eros Mossini ◽  
Luca Codispoti ◽  
Giorgio Parma ◽  
Filippo Maria Rossi ◽  
Elena Macerata ◽  
...  
Keyword(s):  
Research Reactor ◽  
Nuclear Research ◽  
Nuclear Research Reactor ◽  
Radiological Characterization

scholarly journals Evaluation of technological radiation sources in the pumping station of the primary circulation loop and on the top of the pool type research reactor

2018 ◽  
Vol 33 (1) ◽  
pp. 31-46
Author(s):  
Stoyan Kadalev
Keyword(s):  
Heat Carrier ◽  
Decay Time ◽  
Research Reactor ◽  
Irradiation Time ◽  
Nuclear Research ◽  
Circulation Loop ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
Radiation Sources ◽  
Pool Type

The present paper considers the approach to an assessment of technological radiation sources in the primary water-water reactor circulation loop. In principle, such an evaluation is a multidisciplinary task that covers not only the irradiation of the nuclei, the formation of new isotopes and their decay when they are unstable, but also calculations in the field of hydraulics in order to perform an assessment of the irradiation time and the decay time. A general and a more detailed review of the radiation sources formation in the nuclear facilities and the pool type research reactors with demineralized water as a heat carrier are prepared. The initial isotopic composition of the heat carrier has been adopted according to the Vienna Standard Mean Ocean Water recommended by the International Atomic Energy Agency. The general mathematical model of the processes of nuclei irradiation, the formation of new isotopes and their decay, the assessment of the irradiation time and the decay time is described in details, enabling the repetition of this evaluation to a particular facility. The presented approach is applied in the reconstruction design of the nuclear research reactor IRT-2000, Sofia, Bulgaria.

State of the Art of Nuclear Reactor Instrument Automation

1974 ◽  
Vol 96 (4) ◽  
pp. 394-398
Author(s):  
M. Taeschner ◽  
R. Gariod
Keyword(s):  
High Performance ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
State Of The Art ◽  
Nuclear Research ◽  
Automation System ◽  
Nuclear Research Reactor ◽  
High Investment

Due to its complexity, nuclear reactor instrument automation is a challenge to engineers. High investment and running costs of a nuclear research reactor imply the use of advanced equipment and concepts for instrument automation when striving for high performance, reliability, and operational convenience under budgetary pressure. The article describes a successfully operating instrument automation system stressing the important underlying concepts trying to avoid too much details on specific hardware which is dependent on the time when one must order things.

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