dc.contributor |
Dulla, Sandra |
dc.contributor |
Ravetto, Piero |
dc.contributor.author |
Garcia Domínguez, Carlos |
dc.date |
2012 |
dc.identifier.uri |
http://hdl.handle.net/2099.1/19945 |
dc.language.iso |
eng |
dc.publisher |
Universitat Politècnica de Catalunya |
dc.rights |
info:eu-repo/semantics/openAccess |
dc.subject |
Àrees temàtiques de la UPC::Energies::Energia nuclear |
dc.subject |
Àrees temàtiques de la UPC::Física::Física molecular |
dc.subject |
Nuclear reactors -- Cooling |
dc.subject |
Neutron transport theory |
dc.subject |
Neutrons -- Measurement |
dc.subject |
Monte Carlo method |
dc.subject |
Reactors nuclears -- Refrigeració |
dc.subject |
Neutrons -- Transport, Teoria de |
dc.subject |
Neutrons -- Mesurament |
dc.subject |
Montecarlo, Mètode de |
dc.title |
Generation of nuclear data for lead-cooled fast reactors using the Monte Carlo method |
dc.type |
info:eu-repo/semantics/bachelorThesis |
dc.description.abstract |
The LEADER project goal is to improve and develop a scaled demonstrator of the LFR
technology, ALFRED. The work in this thesis is focused in the ALFRED project framework
and its mission is to obtain few-group cross section data for LFRs. Cross sections
The neutron transport problem is crucial in nuclear engineering and nuclear reactor physics.
Neutron transport theory and the diffusion theory applied to neutron reactions are briefly
described, including their principles and hypothesis. The two different computational
approaches to solve the neutron transport problem are summarized.
The software used to obtain the data is based on a modification of the Monte Carlo method.
Thus, some basic probability theory concepts are introduced. This section follows with the
discussion of the Monte Carlo method and its principles, and how it can be applied to solve
the neutron transport problem.
Afterwards, the Serpent code is explained, as well as its features and characteristics. The
process of creating a 2-dimension model of ALFRED fuel assembly and the elaboration of
Serpent input files are detailed. Cross section data for five neutron energy groups and at
different material temperatures is obtained by running several simulations using Serpent.
The last section includes a brief description of LFR technology and some specific ALFRED
features. Some advantages and disadvantages of LFRs are included, along with some
proposals to solve the disadvantages. The last part of this section illustrates the proposed
ALFRED core scheme, using the data publicly available to date. |
dc.description.abstract |
Outgoing |