A NEW NUMERICAL NUCLEAR REACTOR NEUTRONICS CODE SHARK

A New Numerical Nuclear Reactor Neutronics Code SHARK

In order to establish the next-generation reactor physics calculation method based on knife set the numerical nuclear reactor technology and realize high-fidelity modeling and calculation, a new numerical nuclear reactor neutronics code SHARK is developed.The code is based on the direct transport method with construct solid geometry (CSG) method, a

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Assessing the Effect of Variable Ambient Temperature on the Self-ignition of a Reaction-diffusion System Employing a Reduced Order Modelling Methodology

The system Water Bottle Cap under study in this work is a self-igniting pile of solid material.To predict and understand the effect of steep changes of the state variables on such systems, a reaction-diffusion model is employed.These systems can exhibit complex oscillatory behaviour, and changes in ambient conditions over time may strongly impact t

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