2021
DOI: 10.15392/bjrs.v8i3b.610
|View full text |Cite
|
Sign up to set email alerts
|

Numerical Simulation Study on the Air/Water Counter- current Flow Limitation in Nuclear Reactors

Abstract: After a loss-of-coolant accident (LOCA) in a Pressurized Water Reactor (PWR), the temperature of the fuel elements cladding increases dramatically due to the heat produced by the fission products decay, which is not adequately removed by the vapor contained in the core. In order to avoid this sharp rise in temperature and consequent melting of the core, the Emergency Core Cooling System is activated. This system initially injects borated water from accumulator tanks of the reactor through the inlet pipe (cold … Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1

Citation Types

0
1
0

Year Published

2023
2023
2023
2023

Publication Types

Select...
1

Relationship

0
1

Authors

Journals

citations
Cited by 1 publication
(1 citation statement)
references
References 6 publications
0
1
0
Order By: Relevance
“…Issa [9,11] also performed Etf simulations in ANSYS-FLUENT, performing comparisons with experimental data. Other authors used VOF models in ANSYS-FLUENT to describe the CCFL [24,25]. Benz [26] used VOF in OpenFOAM with some modifications in the turbulence models.…”
Section: Introductionmentioning
confidence: 99%
“…Issa [9,11] also performed Etf simulations in ANSYS-FLUENT, performing comparisons with experimental data. Other authors used VOF models in ANSYS-FLUENT to describe the CCFL [24,25]. Benz [26] used VOF in OpenFOAM with some modifications in the turbulence models.…”
Section: Introductionmentioning
confidence: 99%