Transient coupled calculations of the Molten Salt Fast Reactor using the transient fission matrix approach
A Laureau, D Heuer, E Merle-Lucotte… - … Engineering and Design, 2017 - Elsevier
In this paper we present transient studies of the Molten Salt Fast Reactor (MSFR). This
generation IV reactor is characterized by a liquid fuel circulating in the core cavity, requiring …
generation IV reactor is characterized by a liquid fuel circulating in the core cavity, requiring …
A review of the current nuclear data performance assessments in advanced nuclear reactor systems
AA Ryzhkov, GV Tikhomirov, MY Ternovykh - Annals of Nuclear Energy, 2024 - Elsevier
There is a rise in sensitivity and uncertainty analyses with respect to nuclear data, which are
a basis for a neutron transport simulation. The analyses are primarily concerned with the …
a basis for a neutron transport simulation. The analyses are primarily concerned with the …
The rapid fission matrix approach to reactor core criticality calculations
Abstract The Real-time Analysis for Particle transport and In-situ Detection (RAPID) code
uses a unique, extremely fast, fission matrix–based methodology to compute the eigenvalue …
uses a unique, extremely fast, fission matrix–based methodology to compute the eigenvalue …
Validation of coupled fission matrix–TRACE methods for thermal-hydraulic and control feedback on the Penn State Breazeale Reactor
A Rau, WJ Walters - Progress in Nuclear Energy, 2020 - Elsevier
A new method for calculating power shape and critical control rod position is described and
validated in view of increasing the fidelity of the Penn State Breazeale Reactor's (PSBR) fuel …
validated in view of increasing the fidelity of the Penn State Breazeale Reactor's (PSBR) fuel …
Transient Fission Matrix: Kinetic calculation and kinetic parameters βeff and Λeff calculation
A Laureau, M Aufiero, PR Rubiolo… - Annals of Nuclear …, 2015 - Elsevier
In this paper, we present a time dependent version of the fission matrix method called
Transient Fission Matrix (TFM) that we developed to perform accurate spatial kinetic …
Transient Fission Matrix (TFM) that we developed to perform accurate spatial kinetic …
SP3-coupled global variance reduction method based on RMC code
A global variance reduction (GVR) method based on the SPN method is proposed. First, the
global multi-group cross-sections are obtained by Monte Carlo (MC) global homogenization …
global multi-group cross-sections are obtained by Monte Carlo (MC) global homogenization …
A block Arnoldi method for the SPN equations
The simplified spherical harmonics equations are a useful approximation to the stationary
neutron transport equation. The eigenvalue problem associated with them is a challenging …
neutron transport equation. The eigenvalue problem associated with them is a challenging …
A local fission matrix correction method for heterogeneous whole core transport with RAPID
The recently developed RAPID code uses a unique pre-calculated fission matrix method in
order to solve the whole-core eigenvalue problem very quickly and accurately. However, in …
order to solve the whole-core eigenvalue problem very quickly and accurately. However, in …
Overview of the TRIPOLI-4 Monte Carlo code, version 12
FX Hugot, A **aphanh, C Jouanne… - EPJ Nuclear Sciences …, 2024 - epjn.epj.org
In this paper we present an overview of the recent advances of the general-purpose Monte
Carlo code TRIPOLI-4®, developed at CEA. The features described in this work, which refer …
Carlo code TRIPOLI-4®, developed at CEA. The features described in this work, which refer …
NEUTRONIC ANALYSIS ON MOLTEN SALT REACTOR FUJI-12 USING 235U AS FISSILE MATERIAL IN LiF-BeF2-UF4 FUEL.
Neutronic analysis on the Molten Salt Reactor FUJI-12 using the fissile material< sup> 235
U in LiFBeF< sub> 2-UF< sub> 4 has been carried out. The problem faced in the use of …
U in LiFBeF< sub> 2-UF< sub> 4 has been carried out. The problem faced in the use of …