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Haut PDF MINARET, A DETERMINISTIC NEUTRON TRANSPORT SOLVER FOR NUCLEAR CORE CALCULATIONS

MINARET, A DETERMINISTIC NEUTRON TRANSPORT SOLVER FOR NUCLEAR CORE CALCULATIONS

MINARET, A DETERMINISTIC NEUTRON TRANSPORT SOLVER FOR NUCLEAR CORE CALCULATIONS

... here MINARET a deterministic transport solver for nuclear core calculations to solve the steady state Boltzmann ...and a DGFEM to solve spatially the ...

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MINARET or the quest towards the use of time-dependent neutron transport solvers for nuclear core calculations on a regular basis

MINARET or the quest towards the use of time-dependent neutron transport solvers for nuclear core calculations on a regular basis

... TIME-DEPENDENT NEUTRON TRANSPORT SOLVERS FOR NUCLEAR CORE CALCULATIONS ON A REGULAR BASIS ...time-dependent neutron transport equation that is involved in ...

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Development of a Hybrid Deterministic-Stochastic Method for Full Core Neutronics

Development of a Hybrid Deterministic-Stochastic Method for Full Core Neutronics

... by a stochastic simulation to produce neutron flux tallies in few regions or coarse mesh tallies in addition to neutron cross ...in a deterministic lattice calculation to obtain the ...

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Development and validation of uncertainty neutron transport calculations at an industrial scale

Development and validation of uncertainty neutron transport calculations at an industrial scale

... on nuclear parameters such as reactivity is a major issue for conception of nuclear ...on nuclear and technological ...propagate nuclear data uncertainties is Total Monte Carlo [ ...

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Development and validation of sensitivity and uncertainty calculations using the 3D neutron transport code CRONOS2 at an industrial scale

Development and validation of sensitivity and uncertainty calculations using the 3D neutron transport code CRONOS2 at an industrial scale

... at core scale using CRONOS2. It uses stored cross sections computed for each assembly by APOLLO2 and it solves flux calculation in diffusion theory with 4 energy groups thanks to MINOS ...developed ...

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A First Finite Element Solver Shared By Neutron Diffusion, Heat Transfer And Mechanics

A First Finite Element Solver Shared By Neutron Diffusion, Heat Transfer And Mechanics

... - Nuclear reactor core simulations involve several physics, especially in accidental ...transients. Neutron transport is needed to compute the power ...the core. A lot of works ...

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Condensation and homogenization of cross sections for the deterministic transport codes with Monte Carlo method : Application to the GEN IV fast neutron reactors

Condensation and homogenization of cross sections for the deterministic transport codes with Monte Carlo method : Application to the GEN IV fast neutron reactors

... as a challenging topic for neutronic ...the nuclear experimental facility, MASURCA, there was a core configuration named ...is a typical fuel-reflector core ...ZONA2B ...

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A Deterministic against Monte-Carlo Depletion Calculation Benchmark for JHR Core Configurations

A Deterministic against Monte-Carlo Depletion Calculation Benchmark for JHR Core Configurations

... limitations. Deterministic 3D calculations are performed on a hexagonal spatial meshing with the CRONOS2 diffusion code using 6 energy groups ...[2]. Transport-diffusion equivalence factors ...

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Validation of an Isotope Evolution Model for Apollo3 Calculations in SFR Core

Validation of an Isotope Evolution Model for Apollo3 Calculations in SFR Core

... The core step performs full core calculations with a coarser energetic mesh and spatial dis- ...note, core calculations are the result of a synergistic effort of more than ...

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A 2D/1D algorithm for effective cross sections generation in fast reactor neutronic transport calculations

A 2D/1D algorithm for effective cross sections generation in fast reactor neutronic transport calculations

... Boltzmann transport equation over a nuclear reactor core presup- poses the definition of homogenized and energy collapsed cross ...heterogeneous core designs, anisotropy in the neutrons ...

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A First Finite Element Solver Shared by Neutron Diffusion,Heat Transfer and Mechanics

A First Finite Element Solver Shared by Neutron Diffusion,Heat Transfer and Mechanics

... INTRODUCTION Nuclear reactor cores can be deformed by thermal expan- sion, irradiation effects or during particular accidental tran- ...impact neutron trans- port in all reactor types. Fast neutron ...

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A Dynamic Homogenization Method for Nuclear Reactor Core Calculations

A Dynamic Homogenization Method for Nuclear Reactor Core Calculations

... on a very different philosophy, because it does not require any off-line ...calculation. A lattice solver is used as an “on-the-fly” cross- section generator for the core solver, ...

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A domain decomposition method in APOLLO3$^R$ solver, MINARET

A domain decomposition method in APOLLO3$^R$ solver, MINARET

... the core solver ..."traditional" deterministic calculation scheme in two steps is built on ”severe” approximations, thought to offer a satisfying compromise between precision and ...

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Adjoint-based deviational Monte Carlo methods for phonon transport calculations

Adjoint-based deviational Monte Carlo methods for phonon transport calculations

... phonon transport problems of scientific and practical interest involve relatively small driving forces (temperature differences) and thus may be treated by the linearized Boltzmann ...K for a ...

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Classic nuclear localization signals and a novel nuclear localization motif are required for nuclear transport of porcine parvovirus capsid proteins

Classic nuclear localization signals and a novel nuclear localization motif are required for nuclear transport of porcine parvovirus capsid proteins

... ABSTRACT Nuclear targeting of capsid proteins (VPs) is important for genome delivery and precedes assembly in the replication cycle of porcine parvovirus ...potential nuclear localization signals ...

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Azimuthal anisotropies as stringent test for nuclear transport models

Azimuthal anisotropies as stringent test for nuclear transport models

... model calculations for different parametrisations of the nuclear ...is a n-body theory which calculates the time evolution of intermediate energy heavy ion reactions on an event by event ...

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Parareal in time 3D numerical solver for the LWR Benchmark neutron diffusion transient model

Parareal in time 3D numerical solver for the LWR Benchmark neutron diffusion transient model

... from a first decomposition of Ω into several horizontal layers of prisms each of them being subsequently cut into three tetrahedrons as explained in Figure ...

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TRIPOLI-4 and FREYA for Stochastic Analog Neutron Transport. Application to Neutron Multiplicity Counting.

TRIPOLI-4 and FREYA for Stochastic Analog Neutron Transport. Application to Neutron Multiplicity Counting.

... ® for NMC TRIPOLI-4 ® solves the linear Boltzmann equation for neutrons, photons, electrons and positrons with the Monte Carlo method, in any 3-D ...as a reference code for industrial purposes ...

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A parallel solver for incompressible fuid flows

A parallel solver for incompressible fuid flows

... Even for these simple meshes, 3-D parallel solvers are needed since complex flow simulations and targeted applications commonly require grid resolution corre- sponding to 10 7 − 10 9 unknowns to properly capture ...

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Comparison of Monte Carlo methods for adjoint neutron transport

Comparison of Monte Carlo methods for adjoint neutron transport

... particle transport becomes inefficient when the detector is ‘small’ 1 in the phase space: in the limit case of a point-like detector, almost no particles can contribute to the simulation, the probability ...

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