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1

Fuel flow test through a leaky fuel assembly

Ułanowicz Leszek, Jastrzębski Grzegorz, Tomaszek Łukasz, Szczepaniak Paweł

Journal of KONBiN

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2023

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Vol. 53, iss. 1

109--136

EN

The occurrence of an external leak in the aviation fuel unit leads to a catastrophic aviation event. The aim of the research was to estimate the flow of the fuel stream through the fuel filter chamber with its external unsealing. The research was carried out using experimental methods and computer CFD modelling. Experimental studies were carried out on a specially designed test stand. During the tests, the flow rate of the fuel stream flowing out to the environment was changed. Numerical calculations allowed to obtain the values of the stream and pressure inside the leaky filter chamber. The results of numerical calculations were compared with the results of experimental measurements. The CFD method significantly supplemented the information on the fuel flow inside the considered filter chamber at its external unsealing. The use of software based on the CFD method allows to obtain reliable values characterizing the fuel flow in the aviation fuel unit.

PL

Wystąpienie nieszczelności zewnętrznej w lotniczym zespole paliwowym prowadzi do katastroficznego zdarzenia lotniczego. Celem badań było oszacowanie przepływu strugi paliwa przez komorę filtra paliwowego, przy jego zewnętrznym rozszczelnieniu. Badania wykonano metodami eksperymentalnymi oraz z użyciem komputerowego modelowania CFD. Badania eksperymentalne przeprowadzono na specjalnie zaprojektowanym stanowisku badawczym. W czasie badań zmieniano natężenie przepływu strugi paliwa wypływającej do otoczenia. Obliczenia numeryczne pozwoliły uzyskać wartości strumienia i ciśnienia wewnątrz nieszczelnej komory filtra. Wyniki obliczeń numerycznych zostały porównane z wynikami pomiarów eksperymentalnych. Metoda CFD w znacznym stopniu uzupełniła informacje o przepływie paliwa wewnątrz rozpatrywanej komory filtra przy jego zewnętrznym rozszczelnieniu. Wykorzystanie oprogramowania bazującego na metodzie CFD pozwala uzyskać wiarygodne wartości charakteryzujące przepływ paliwa w lotniczym zespole paliwowym.

2

Thermal-hydraulic calculations for a fuel assembly in a European Pressurized Reactor using the RELAP5 code

Skrzypek M., Laskowski R.

Nukleonika

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2015

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Vol. 60, No. 3, part 2

537--544

EN

The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear reactor. The aim of the paper is to describe the phenomena and calculate thermal-hydraulic characteristic parameters in the fuel assembly for a European Pressurized Reactor (EPR). To perform thermal-hydraulic calculations, the RELAP5 code was used. This code allows to simulate steady and transient states for reactor applications. It is also an appropriate calculation tool in the event of a loss-of-coolant accident in light water reactors. The fuel assembly model with nodalization in the RELAP5 (Reactor Excursion and Leak Analysis Program) code was presented. The calculations of two steady states for the fuel assembly were performed: the nominal steady-state conditions and the coolant flow rate decreased to 60% of the nominal EPR flow rate. The calculation for one transient state for a linearly decreasing flow rate of coolant was simulated until a new level was stabilized and SCRAM occurred. To check the correctness of the obtained results, the authors compared them against the reactor technical documentation available in the bibliography. The obtained results concerning steady states nearly match the design data. The hypothetical transient showed the importance of the need for correct cooling in the reactor during occurrences exceeding normal operation. The performed analysis indicated consequences of the coolant flow rate limitations during the reactor operation.

3

Optimization of fuel assembly with gadolinium for LWRS

Cudrnak P., Necas V.

Journal of Power Technologies

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2011

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Vol. 91, nr 4

186-190

EN

At present, the fuel assemblies of Light Water Reactors require mainly cost-effective production of electricity. The objective of in-core fuel management is to achieve the objective of minimizing fuel cycle cost by using advanced models of core loading strategies. Current development is focused mainly on optimizing the design of gadolinium fuel, thereby to reduce the average enrichment of fuel assemblies and the binding of the excess reactivity at the beginning of the fuel cycle. This paper deals with different ways of optimizing fuel assemblies containing a burnable absorber for PWR and VVER reactors. These calculations were made in SCLAE 6 code, TRION module.