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ISSN Печать: 1940-2503
ISSN Онлайн: 1940-2554
IF:
1.5
5-Year IF:
1
Immediacy Index:
0.3
Eigenfactor:
0.00017
JCI:
0.28
SJR:
0.279
SNIP:
0.544
CiteScore™::
2.5
H-Index:
22
Indexed in
EVALUATION OF THE NEUTRONIC FEEDBACK EFFECTS IN LOSS OF COOLANT ACCIDENT SIMULATION OF THE IPR-R1 TRIGA REACTOR
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Краткое описание
The safety analysis of research reactors includes simulations of selected cases classified by the International Atomic Energy Agency (IAEA), since the simulations are performed using validated nodalizations and internationally recognized, accepted, and validated best estimate codes. The thermal hydraulic analysis is considered as an essential aspect in the study of safety of nuclear reactors, since it can predict proper working conditions, steady state and transient, thereby ensuring the safe operation of a nuclear reactor. A RELAP5 model verified for the IPR-R1 TRIGA research reactor was used here to perform transient studies. A loss of coolant accident (LOCA) event was simulated. The obtained results demonstrate that, to more realistically simulate this type of transient, it is necessary to consider also the neutronic feedback effects in the thermal hydraulic calculations.
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