Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR [PDF]
Performing three-dimensional pin-by-pin full core calculations based on an improved solution of the multi-group diffusion equation is an affordable option nowadays to compute accurate local safety parameters for light water reactors.
Aragonés +16 more
core +2 more sources
Direct sediment transfer from land to deep-sea: Insights into shallow multibeam bathymetry at La Réunion Island [PDF]
International audienceSubmarine canyon heads are key areas for understanding the triggering factors of gravity currents responsible for the transfer of detrital sediment to the deep basins.
Ammann, Jérôme +9 more
core +4 more sources
Development of Cross-Section Library for DYN3D Code
At present, SSTC NRS uses the HELIOS code for generation of few-group cross-section libraries for WWER core calculations. There is an urgent issue of selecting the appropriate approach to implement the cross-section library into the DYN3D code. The paper overviews the application of approaches used by SSTC NRS, such as a multidimensional table and ...
V. Khalimonchuk +3 more
openaire +3 more sources
Hot Zero and Full Power Validation of PHISICS RELAP-5 Coupling [PDF]
PHISICS is a reactor analysis toolkit developed over the last 3 years at the Idaho National Laboratory. It has been coupled with the reactor safety analysis code RELAP5-3D.
A., Epiney +4 more
core
Coupled calculations COBAYA4/CTF for different MSLB scenarios in the frame of NURESAFE project [PDF]
The new version of COBAYA diffusion code, COBAYA4, has been integrated into SALOME platform in order to enable the coupling with other thermal-hydraulics codes of the platform.
Cuervo Gómez, Diana +3 more
core
Annual report 2006 // Institute of Safety Research [PDF]
[no abstract ...
Rindelhardt, Udo, Weiss, Frank-Peter
core +2 more sources
Asymptotic Derivation and Numerical Investigation of Time-Dependent Simplified Pn Equations
The steady-state simplified Pn (SPn) approximations to the linear Boltzmann equation have been proven to be asymptotically higher-order corrections to the diffusion equation in certain physical systems.
Frank, M. +3 more
core +1 more source
The european project NURISP for nuclear reactor simulation [PDF]
The NURISP project aims at developing the European NURESIM reference simulation platform [1] for nuclear reactor. A first version of NURESIM was delivered in 2008.
Ahnert Iglesias, Carolina +5 more
core
Advanced Reactor Physics Methods for Transient Analysis of Boiling Water Reactors [PDF]
The safety assessment of nuclear power plants requires the consideration of the several physical phenomena taking place in the reactor core. Since the last decade, the simulations are performed using the so-called Best-Estimate (BE) thermal-hydraulic ...
Gonzalez Vargas, Jose Angel
core +2 more sources
Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project [PDF]
Within the subproject 3 of the NURISP project three neutron kinetic codes have been implemented into the NURESIM platform. For all three codes (CRONOS2, COBAYA3 and DYN3D) the coupling with the thermal hydraulic code FLICA4 was accomplished using the ...
Ahnert Iglesias, Carolina +4 more
core

