In this paper, the Monte Carlo N-Particle extended computer code (MCNP) were used to design a model of European Sodium-cooled Fast Reactor. The multiplication factor, conversion delayed neutrons fraction, doppler constant, control rod worth, sodium void masses for major heavy nuclei, radial and axial power distribution at high burnup are studied. results show that reactor breeds fissile isotope...

Abstract In order to facilitate the power control method design of heat pipe nuclear reactor and avoid high complexity core modelling, paper adopts lumped parameter build thermal state dynamic model reactor. Firstly, equivalence structure transfer process “MegaPower” is carried out describe a single in hexagonal block. The complex simplified into two-zone with only fuel monolith. And equivalent...

The naval industry has integrated the generation of energy through nuclear processes, due to large amount that is produced in these for example, ship NS OTTO HAHN, which used a propulsion plant with generated by reactor pressurized water (PWR), operated under fission process. Also, other examples are military ships and icebreakers. In order know contribution this type plants, work carries out m...

Model-independent reactor isotopic cross sections per fission are determined by global fits of the antineutrino data from High-Enriched Uranium (HEU) rates, Low-Enriched (LEU) and fuel evolution data. Taking account implicit quasi-linear relationship between fractions $^{239}\rm{Pu}$ $^{241}\rm{Pu}$ in LEU data, Inverse-Beta-Decay (IBD) yields their correlations fissionable isotopes $^{235}\rm{...

This problem is known as the Lambda Modes problem. The fundamental eigenvalue (the largest one) is called the effective multiplication, k-effective, of the reactor core. This eigenvalue and its corresponding eigenfunction describe the steady state neutron distribution in the core. On the other hand, to compute the dominant modes of the reactor core is useful to develop modal methods [2] to inte...

This summary deals with a fundamental question in any reactor model validation practice: given a body of available experiments, and an envisaged domain of reactor operating conditions (referred to as reactor application), can one develop a quantitative measure that measures the portion of the prior uncertainties of the reactor application that is covered by the available experiments? Coverage h...

To increase the power density and maximum allowable fuel burnup in light water reactors, new fuel rod designs are investigated. Such fuel is desirable for improving the economic performance light water reactors loaded with transuranic-bearing fuel for transmutation, as well as those using UO2 fuel. A proposal for using silicon carbide duplex as fuel cladding is investigated. The cladding consis...

The new research reactor of the Technische Universität München will provide the German needs of neutrons for the beginning of the next century. High intensities of thermal neutrons are provided by a particular densely packed core of highly enriched uranium and are extracted by 12 beam apertures. The low thermal power of 20 MW allows the positioning of a D2 cold source at a maximum of the therma...

Monte Carlo methods for reactor analysis have been in development with the eventual goal of full-core analysis. To attain results with reasonable uncertainties, large computational resources are needed. Variance reduction methods have been developed in order to reduce the computational resources required to obtain results in a practical amount of time. This work seeks to expand research in the ...

To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the time-dependent neutron diffusion equation inside the reactor core. In particular, we will consider here VVER-type reactors which use the neutron diffusion equation discretized on hexagonal meshes. Several algorithms to integrate the time dependent neutron diffusion equation have been developed, by m...