CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core

Salama, Amgad; El-Morshedy, Salah El-Din

doi:10.1016/j.anucene.2011.09.005

Cited by 43 publications

(14 citation statements)

References 22 publications

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“…However, the result of the redistribution is different from that acquired by Salama and El-Morshedy (2012), which suggests that flow in channel-3 almost remains unchanged in different blockage ratio scenarios. The difference results from the different blockage modeling methods.…”

Section: Mass Flow Rate Transientscontrasting

confidence: 66%

“…According to Salama and El-Morshedy (2012), the average inlet velocity of the upper plenum is set to 2.3 m/s. In order to define an accurate flow boundary for the inlet, fully developed velocity and turbulence profiles are added to the inlet, and these quantities are fixed during transient calculations.…”

Section: Resultsmentioning

confidence: 99%

“…However, it is not wise to investigate the accident in such a big scale, even in the scale of one full fuel assembly. According to the work of Lu et al (2009) and Salama and El-Morshedy (2012), parameters in the blocked channel and its adjacent channel are affected mostly, while those in the third channel are slightly influenced. Since the geometry of the channels and plates is symmetric, only a quarter of the domain is considered to reduce the mesh size.…”

Section: Assumptions and Simplificationsmentioning

confidence: 98%

“…Finally, the blockage plane arrives at the inlet of the blocked channel and stops there. During this process, the heat generation rate of the fuel is set to a chopped cosine function with the effective length set to 0.6 m, and the extrapolated length is 0.76 m (Salama and El-Morshedy, 2012). Due to the potential big rise in temperature, the density, specific heat, thermal conductivity and viscosity of the coolant are all considered to change with temperature at the form of quartic polynomials.…”

Section: Assumptions and Simplificationsmentioning

confidence: 99%

See 3 more Smart Citations

CFD study on inlet flow blockage accidents in rectangular fuel assembly

Fan

Peng

Guo

2015

Nuclear Engineering and Design

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Section: Mass Flow Rate Transientscontrasting

confidence: 66%

Section: Resultsmentioning

confidence: 99%

Section: Assumptions and Simplificationsmentioning

confidence: 98%

Section: Assumptions and Simplificationsmentioning

confidence: 99%

See 2 more Smart Citations

CFD study on inlet flow blockage accidents in rectangular fuel assembly

Fan

Peng

Guo

2015

Nuclear Engineering and Design

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“…In reality, blockage of flow channel may, most probably, be a result of change in channel geometry. For example, fuel plates could buckle inward along the length or the width of the plates as a consequence of excessive thermal stresses, manufacturing imperfections, misalignments, unbalanced forces due to hydrodynamic instabilities, or any other reason (Kim and Davis [20], Pierro et al [19], Adorni et al [5], Lu et al [6], Salama and El-Morshedy [21,22], Salama [23], etc.). In particular, the manufacturing processes of fuel plates, as depicted in Figure 1, indicates that buckling of fuel plates is an inevitable consequence of the rolling processes.…”

Section: Motivationmentioning

confidence: 97%

Three-Dimensional, Numerical Investigation of Flow and Heat Transfer in Rectangular Channels Subject to Partial Blockage

Salama

El-Amin

Sun

2014

Heat Transfer Engineering

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Numerical simulation of flow and heat transfer in two adjacent channels is conducted with one of the channels partially blocked. This system simulates typical channels of a material testing reactor. The blockage is assumed due to the buckling of one of the channel plates inward along its width. The blockage ratio considered in this work is defined as the ratio between the cross-sectional area of the blocked and the unblocked channel. In this work, we consider a blockage ratio of approximately 40%. However, the blockage is different along the width of the channel, ranging from 0% at the end of the channel to 90% in the middle. The channel walls are sandwiching volumetric heat sources that vary spatially as chopped cosine functions. Interesting patterns are highlighted and investigated. The reduction in the flow area of one channel results in the flow redistributing among the two channels according to the changes in their hydraulic conductivities. The results of the numerical simulations show that the maximum wall temperature in the blocked channel is well below the boiling temperature at the operating pressure. INTRODUCTIONThere is no doubt that materials used in the design and operations of nuclear reactors are subjected to a harsh environment that is very unusual. In addition to structural stresses resulting from the interaction of the different components of reactor systems and the thermal stresses associated with the generation of heat within the core, which may be common in several engineering applications, there are also induced stresses that are unique to nuclear reactor cores and may not be found in any other application. For example, the exposure of these material to continuous bombardment with neutrons and fission products (irradiation) results in new phenomena such as swelling of fuel elements and the wear of containment materials. It is therefore important that experimental studies on irradiation effects in fuel and reactor structural materials be conducted to accurately predict their Color versions of one or more of the figures in the article can be found online at www.tandfonline.com/uhte. mechanical behavior and the possible changes in their nuclear chemistry. Unfortunately, it is not possible to mimic such an environment in a single isolated experiment. In other words, the only way to study such effects is within nuclear reactors themselves, which motivated the design of special types of nuclear reactors, called material testing reactors (MTR). These are designed to address in considerable detail the development and the qualification of materials and fuels under irradiation with sizes and environment conditions relevant for nuclear power plants in order to optimize safe operations of existing and future power reactors. MTR typically operate at low temperatures (coolant below 100 • C), the operating conditions are severe in a sense. That is, while power reactor fuel operates at power density of about 5 kW/cm 3 , a research reactor fuel may be at 17 kW/cm 3 in the fuel region. Furthermore, in MTR, bu...

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Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core

Shi

Zhang

et al. 2018

NUCL SCI TECH

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CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core

Cited by 43 publications

References 22 publications

CFD study on inlet flow blockage accidents in rectangular fuel assembly

CFD study on inlet flow blockage accidents in rectangular fuel assembly

Three-Dimensional, Numerical Investigation of Flow and Heat Transfer in Rectangular Channels Subject to Partial Blockage

Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core

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