Reduced Variance using ADVANTG in Monte Carlo Calculations of Dose Coefficients to Stylized Phantoms [PDF]
The estimation of dose coefficients of external radiation sources to the organs in phantoms becomes increasingly difficult for lower photon source energies. This study focus on the estimation of photon emitters around the phantom. The computer time needed to calculate a result within a certain precision can be lowered by several orders of magnitude ...
Hiller Mauritius +3 more
openaire +3 more sources
ADVANTG An Automated Variance Reduction Parameter Generator [PDF]
The primary objective of ADVANTG is to reduce both the user effort and the computational time required to obtain accurate and precise tally estimates across a broad range of challenging transport applications. ADVANTG has been applied to simulations of real-world radiation shielding, detection, and neutron activation problems.
Mosher, Scott W. +7 more
openaire +4 more sources
PWR Facility Dose Modeling Using MCNP5 and the CADIS/ADVANTG Variance-Reduction Methodology [PDF]
The feasibility of modeling a pressurized-water-reactor (PWR) facility and calculating dose rates at all locations within the containment and adjoining structures using MCNP5 with mesh tallies is presented. Calculations of dose rates resulting from neutron and photon sources from the reactor (operating and shut down for various periods) and the spent ...
Blakeman, Edward D +4 more
core +5 more sources
Shielding analyses supporting the Lithium loop design and safety assessments in IFMIF-DONES [PDF]
The assessment of radiation fields in the lithium loop pipes and dump tank during the operation were performed for International Fusion Materials Irradiation Facility – DEMO-Oriented NEutron Source (IFMIF-DONES) in order to obtain the radiation dose-rate
Marugán, Juan Carlos +3 more
core +5 more sources
ANALYSIS OF DOSE RATES AROUND THE SLOVENIAN SILO-TYPE LILW REPOSITORY USING ADVANTG [PDF]
The ADVANTG code was used to analyze dose rates from the proposed Slovenian silo-type low and intermediate level waste (LILW) repository. Detailed calculations of dose rates are challenging as gamma-sources are located in thick concrete containers and the effect of backscattering in the air has to be considered.
Kotnik Domen +3 more
openaire +2 more sources
Analysis of DD, TT and DT Neutron Streaming Experiments with the ADVANTG Code [PDF]
The paper presents an analysis of DD, TT and DT neutron streaming benchmark experiments with the recently released hybrid transport code ADVANTG (AutomateD VAriaNce reducTion Generator). ADVANTG combines the deterministic neutron transport solver Denovo with the Monte Carlo transport code MCNP via the principle of variance reduction.
Kos, Bor +8 more
openaire +2 more sources
Nuclear design of a shielded cabinet for electronics: The ITER radial neutron camera case study [PDF]
The Radial Neutron Camera (RNC) is a diagnostic system located in ITER Equatorial Port #1 providing several spatial and time-resolved parameters for the fusion power estimation, plasma control and physics studies. The RNC measures the uncollided 14 MeV
Maffucci, A.
core +4 more sources
Graphical Visualisation of the MCNP Mesh Tally File [PDF]
This paper presents an updated version of the MTV3D (Mesh Tally Visualization in 3D) program with Windows graphical user interface for visualization of the MCNP-based mesh tally files. Several improvements over the previous program version are addressing
Markota, Domagoj +2 more
core +2 more sources
Characterization of Fast Neutron Transmission Through an Iron Shield [PDF]
In this paper we give an analysis of the neutron transmission through an iron sphere using Monte Carlo and transport theory methods based on ENDF/B-VII.1 general purpose library. The motivation for this investigation comes from a well-known deficiency in
Matijević, Mario +2 more
core +2 more sources
Overview of the JET results in support to ITER [PDF]
The 2014–2016 JET results are reviewed in the light of their significance for optimising the ITER research plan for the active and non-active operation. More than 60 h of plasma operation with ITER first wall materials successfully took place since its
Abduallev, S. +7 more
core +3 more sources

