Searched for: contributor%3A%22van+der+Hagen%2C+T.H.J.J.+%28promotor%29%22
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Zweistra, C.A. (author)
This research investigates a phenomenon that is referred to as “the empathy gap” (Konrath, et.al, 2011). The empathy gap is the situation in which there is diminished ability in Perspective Taking (PT) and Emotional Concern (EC), caused by technology. The central objective of this investigation has been to understand what the empathy gap is, how...
doctoral thesis 2019
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Valori, V. (author)
Fluids above the critical point are widely used in industry. Chemical, pharmaceutical, food industry and energy production are some examples. In the energy production sector they are mainly used as cooling fluids, because they allow to increase the thermal efficiency of the power plants. However, the fundamentals of their heat transfer behavior...
doctoral thesis 2018
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Peeters, J.W.R. (author)
doctoral thesis 2016
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Wols, F.J. (author)
Nuclear power plants are expected to play an important role in the worldwide electricity production in the coming decades, since they provide an economically attractive, reliable and low-carbon source of electricity with plenty of resources available for at least the coming hundreds of years. However, the design of nuclear reactors can be...
doctoral thesis 2015
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Perkó, Z. (author)
This thesis presents novel adjoint and spectral methods for the sensitivity and uncertainty (S&U) analysis of multi-physics problems encountered in the field of reactor physics. The first part focuses on the steady state of reactors and extends the adjoint sensitivity analysis methods well established for pure neutron transport problems to...
doctoral thesis 2015
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Auwerda, G.J. (author)
To more accurately predict the temperature distribution inside the reactor core of pebble bed type high temperature reactors, in this thesis we investigated the stochastic properties of randomly stacked beds and the effects of the non-homogeneity of these beds on the neutronics and thermal-hydraulics in the core of pebble bed reactors. To...
doctoral thesis 2014
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Christie, S.A. (author)
This thesis describes the application of adjoint techniques to fuel cycle analysis, in order to provide a more accurate description of the effects of nuclides on reactor behaviour. Transmutation and decay processes change the composition of the fuel. Allowing for these changes makes it possible to create different fuel compositions that yield...
doctoral thesis 2014
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Gilli, L. (author)
This thesis presents the development and the implementation of an uncertainty propagation algorithm based on the concept of spectral expansion. The first part of the thesis is dedicated to the study of uncertainty propagation methodologies and to the analysis of spectral techniques. The concepts introduced within this preliminary analysis are...
doctoral thesis 2013
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Sjenitzer, B.L. (author)
In this thesis a new method for the analysis of power transients in a nuclear reactor is developed, which is more accurate than the present state-of-the-art methods. Transient analysis is important tool when designing nuclear reactors, since they predict the behaviour of a reactor during changing conditions, such as a control-rod movement,...
doctoral thesis 2013
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Nagy, K. (author)
doctoral thesis 2012
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Marmier, A. (author)
The work presented in this thesis covers three fundamental aspects of High Temperature Reactor (HTR) performance, namely fuel testing under irradiation for maximized safety and sustainability, fuel architecture for improved economy and sustainability, and a novel Balance of Plant concept to enable future high-tech process heat applications with...
doctoral thesis 2012
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Mahmood, A. (author)
The vertical rod/tube bundle geometry has a wide variety of industrial applications. Typical examples are the core of light water nuclear reactors (LWR) and vertical tube steam generators. In the core of a LWR, primarily coolant flows upward but their also exist a flow in lateral direction, called crossflow, in the gaps in between the sub...
doctoral thesis 2011
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Christoforou, S. (author)
The ability of the Monte Carlo method to solve particle transport problems by simulating the particle behaviour makes it a very useful technique in nuclear reactor physics. However, the statistical nature of Monte Carlo implies that there will always be a variance associated with the estimate obtained, making the reduction of this variance,...
doctoral thesis 2010
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Boer, B. (author)
The core design of a pebble-bed type Very High Temperature Reactor (VHTR) is optimized, aiming for an increase of the coolant outlet temperature to 1000 C, while retaining its inherent safety features. The VHTR has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that...
doctoral thesis 2009
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Marcel, C.P. (author)
The stability of natural circulation boiling water reactors is investigated with a strong emphasis on experiments. Two different facilities are used for such a task: the GENESIS facility (to which a void reactivity feedback system is artificially added) and the CIRCUS facility. In addition, numerical codes are also used in the investigation.
doctoral thesis 2007
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Agung, A. (author)
In this thesis a conceptual design of an innovative high temperature reactor based on the fluidization principle (FLUBER) is proposed. The reactor should satisfy the following requirements: (a) modular and low power, (b)) large shutdown margin, (c) able to produce power when the bed of particles expands and stop as soon as the coolant flow is...
doctoral thesis 2007
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van Rooijen, W.F.G. (author)
This research concerns the fuel cycle and safety aspects of a Gas Cooled Fast Reactor, one of the so-called "Generation IV" nuclear reactor designs. The Generation IV Gas Cooled Fast Reactor uses helium as coolant at high temperature. The goal of the GCFR is to obtain a "closed nuclear fuel cycle", where only natural uranium is used as raw...
doctoral thesis 2006
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Flaska, M. (author)
A proper knowledge of neutron cross sections is very important for the operation safety of various nuclear facilities. Reducing uncertainties in the neutron cross sections can lead to an enhanced safety of present and future nuclear power systems. Accurate neutron cross sections also play a relevant role in many other disciplines such as...
doctoral thesis 2006
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Furuya, M. (author)
Currently, 434 nuclear power plants are in operation worldwide. 21% of them are known as Boiling Water Reactors (BWRs). These BWRs have pumps that cool their reactor cores (the forced circulation BWRs). In the design of new BWRs, ways to cool the core by a natural circulation flow, without pumps, also called natural circulation BWRs, are being...
doctoral thesis 2006
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Légrády, D. (author)
doctoral thesis 2005
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