Results 51 to 60 of about 317 (164)
Evaluating Embedded Monte Carlo vs. Total Monte Carlo for Nuclear Data Uncertainty Quantification [PDF]
The purpose of this paper is to compare a new method called Embedded Monte Carlo (EMC) to the well-known Total Monte Carlo (TMC) method for nuclear data uncertainty propagation.
Biot Grégoire +3 more
doaj +1 more source
Development of an Event Tracking Feature in OpenMC for Neutron Noise Analysis [PDF]
We present the development and implementation of a neutron event-tracking capability in OpenMC, an open-source, community-driven Monte Carlo radiation transport code.
Saliba Michel +5 more
doaj +1 more source
A calculation technique computing the adjoint flux of perturbed system is developed for the exact perturbation theory in Monte Carlo transport. By using a correlated sampling and iterated fission probability methods together, the adjoint flux of ...
Jo Yunki, Lee Deokjung
doaj +1 more source
JEZEBEL and GODIVA. Informal report [PDF]
Various code options and input data are tested in the calculation of the fast reactor benchmarks, JEZEBEL and GODIVA. Their effects on the eigenvalue and /sup 238/U to /sup 235/U central fission rate ratio are documented. Although the results can be used to improve past or future calculations, it appears that no reasonable choice of data or options can
openaire +2 more sources
This study formulated equations in operator form using the first-order Adjoint-Weighted Perturbation (AWP) method. These equations are designed to calculate the relative change of reactor parameters—such as the multiplication factor (k), general reaction
Sung Hoon Choi
doaj +1 more source
A Re-Analysis of Historical Los Alamos Critical Assembly Reaction Rate Measurements
Starting in the 1950s and continuing into the early 1970s, a number of foil irradiations and fission chamber measurements were made in a variety of Fast critical assemblies at Los Alamos National Laboratory. These include (i) Godiva, a bare HEU spherical
Kahler A.C., MacInnes M., Chadwick M.B.
doaj +1 more source
Evaluation of nuclear data using the Half Monte Carlo technique [PDF]
The Total Monte Carlo (TMC) technique has proven to be a powerful tool to propagate uncertainties in nuclear data to the uncertainty in macroscopic quantities, such as neutron fluxes at detector positions and the criticality of reactor cores.
Andersson-Sundén Erik +6 more
doaj +1 more source
Initial validation of ALFRED: A Monte Carlo code built on Geant4 for TREAT energy deposition
Predicting the energy deposited in the specimen during an experiment in the Transient Reactor Test (TREAT) Facility is a complex problem due to the nature of the transients occurring in the reactor.
Paul A. Ferney, Nicolas P. Martin
doaj +1 more source
Effect of reflected neutrons for fast pulsed reactor characteristics with metallic nuclear fuel
BackgroundFast neutron pulsed reactors are sensitive to wall scattering neutrons, and their waveforms are changed by reflected neutrons. In addition, their operation may be adversely affected when there are too many reflected neutrons.PurposeThis study ...
GUO Shuwei +8 more
doaj +1 more source
Reconstrução com prótese imediata pós maxilectomia
OBJETIVO: Avaliar a eficiência da reconstrução com Prótese Imediata para Grandes Perdas da Maxila (PIGPM) em pacientes submetidos a maxilectomia, considerando-se o tempo de: internação hospitalar, retirada da sonda naso enteral, deglutição, fonação e ...
Renato Alberto Aldo Miracca +2 more
doaj +1 more source

