CFD simulation of the IAEA 10MW generic MTR reactor under loss of flow transient

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

doi:10.1016/j.anucene.2010.09.025

Cited by 28 publications

(3 citation statements)

References 18 publications

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“…T c (y; z) = q (z) κ c y + T cs (z) (17) where y is the distance along the y-direction (as shown in Figure 3b), T cs is the clad surface temperature, T w is the coolant temperature, is the heat flux, h is the heat transfer coefficient, T c is the clad temperature at any depth, and κ c is the thermal conductivity of the clad material. • Fuel zone temperatures:…”

Section: Discretization and Validationmentioning

confidence: 99%

“…Interesting phenomena were observed, including the probable existence of secondary flows, swirl, and so on that were not possible to observe using one-dimensional simulations (Toth and Aszodi [12], Chang and Tavoularis [13,14], Tzanos [15], and many others). On the other hand, El-Morshedy and Salama [16], Salama and El-Morshedy [17], and Salama [18] investigated numerically the three-dimensional, thermalhydraulic performance of the IAEA generic MTR under a hot channel condition considering both normal operating conditions and fast loss of flow accident (FLOFA) using the CFD code FLUENT. They highlighted interesting patterns and phenomena that motivated the application of CFD into several other steady-state and transient scenarios in this system.…”

Section: Introductionmentioning

confidence: 99%

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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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Section: Discretization and Validationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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

Salama

El-Amin

Sun

2014

Heat Transfer Engineering

Self Cite

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show abstract

“…Though a lot of researches are about RIA (El-Messiry, 2000;Bousbia-salah and Hamidouche, 2005;Varvayanni et al, 2005;Hamidouche and Bousbia-salah, 2010), many investigations on LOFA have been done based on the benchmark problem (Hainouna et al, 2010;El-Morshedy, 2011;Chatzidakisa et al, 2013), most of which use one-dimensional codes. Salama and El-Morshedy (2011) and Salama (2012) showed the importance and advantages of using three-dimensional There are two ways to simulate the flow blockage accident. System analysis codes (Adorni et al, 2005;Lu et al, 2009) assume that all the calculated quantities can only change along the flow direction, and use lots of empirical formulas to solve problems.…”

Section: Introductionmentioning

confidence: 99%