A5079687803- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Radiation Dose and Imaging
- Radiation Therapy and Dosimetry
- Advanced Radiotherapy Techniques
- Fusion materials and technologies
- Radiation Detection and Scintillator Technologies
- Engineering Applied Research
- Nuclear Engineering Thermal-Hydraulics
- Radioactivity and Radon Measurements
- Radiation Shielding Materials Analysis
- Atmospheric and Environmental Gas Dynamics
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Copper Interconnects and Reliability
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2014-2024
CEA Paris-Saclay
2014-2024
Université Paris-Saclay
2018-2024
CEA Paris-Saclay - Etablissement de Saclay
2015-2016
Direction des énergies
2011-2014
Abstract TRIPOLI-4® is a general-purpose Monte Carlo radiation transport code developed at CEA Paris-Saclay center. It uses continuous-energy nuclear data to simulate neutron, photon, electron and positron in fields like protection shielding, fission reactor physics, criticality safety, instrumentation. The verification validation assessments of input output (I/O) are one the fundamental processes assume accuracy credibility numerical studies for its engineering applications. T4G an...
A new prototype display tool T4G for TRIPOLI-4 Monte Carlo transport code is being developed and validated.This paper explains the basics of demonstrates its objectives -easy to use, interactive with user, fast display, great help build debug geometry material input data, useful check variance reduction parameters mesh tally output.It improves final quality by better error checking reduces files maintenance cost industrial engineering projects.For team, also a speed up considerably...
This paper presents a diagnosis tool for the users of TRIPOLI-4 Monte Carlo transport code.The aim is to facilitate adjustment variance reduction scheme when dealing with coupled neutron-photon simulations.Up now, neutron and photon importance functions have been generated independently by biasing both particles was necessary, leading further adjustments user after running first simulation.The idea here combine in fast step map on one hand, production data used simulation other so as provide...
In order to ensure adequate radiation protection of critical groups such as staff, caregivers and the general public coming into proximity nuclear medicine (NM) patients, it is necessary consider impact emitted by patients during their stay at hospital or after leaving hospital. Current risk assessments are based on ambient dose rate measurements in a single position specified distance from patient carried out several time points administration radiopharmaceutical estimate whole-body...
TRIPOLI-4® is a general-purpose Monte Carlo radiation transport code developed at CEA Paris-Saclay center. It uses continuousenergy nuclear data to simulate neutron for diverse engineering fields. Neutron multiplication calculations of subcritical systems are important application areas including criticality safety, reactor ex-core monitoring, and non-proliferation materials. Subcritical experiments were performed by the LANL teams improve simulation capabilities MCNP validate 3He based...
This paper summarizes the results of an intercomparison on use ICRP Reference Computational Phantoms with radiation transport codes, which was organized by EURADOS working group 6. Three exercises are described: exposure to anterior-posterior (AP) photon point source, AP neutron and two typical medical X-ray examinations. The three received 17, 8 solutions, respectively. Participants originated from fifteen different countries, used a wide range Monte Carlo codes. Due difficulties in...
TRIPOLI-4® is a general-purpose Monte Carlo radiation transport code developed by the Service d'Études des Réacteurs et de Mathématiques Appliquées at CEA-Saclay. It uses continuous-energy nuclear data to simulate neutron, photon, electron, and positron in fields like shielding, reactor physics, criticality safety. To study protection dosimetry human tissues organs, male female adult computational phantoms from Medical Internal Radiation Dose–Oak Ridge National Laboratory family...
Nuclear decommissioning takes place in several stages due to the radioactivity reactor structure materials. A good estimation of neutron activation products distributed materials impacts obviously on planning and low-level radioactive waste management. Continuous energy Monte-Carlo radiation transport code TRIPOLI-4 has been applied protection shielding analyses. To enhance application nuclear activities, both experimental computational benchmarks are being performed. calculate facilities,...
EURADOS Working Group 6 has organized an intercomparison exercise on the use of ICRP Reference Computational Phantoms with radiation transport codes. This paper summarizes results a specific task from modelling internal sources. The quantities to be calculated were absorbed fractions and for monoenergetic photon electron sources as well S-values two radionuclides in four source organs. Twelve participants eleven countries participated this using Monte Carlo codes FLUKA, Geant4, MCNP code...
TRIPOLI-4 Monte Carlo transport code, developed by CEA, has been widely used in fission reactor physics, and it can be fusion device neutronics. In order to verify the calculation features of a simple dogleg duct model was built simulate 14-MeV neutron based on SINBAD benchmark, called streaming experiment. The reaction rates bent back surface iron experimental assembly for <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">93</sup> Nb(n,2n)...
The gamma-ray dose calculation is essential for the radiation shielding of pressurized water reactor (PWR) spent fuels. Homogenization modeling fuel pin lattices typical PWR pins regularly applied on protection in an air medium. However, depending size homogenized lattice and location detectors, under-estimation or over-estimation due to homogenization can be obtained with respect detailed heterogeneous model. In previous published results from MCNP-4A 4C calculations pins, very different...
Neutron and photon fluxes generated from the operation of fission reactors fuel cycle facilities are normally well attenuated with shielding ceiling walls.However, skyshine dose rates were observed at 1.5 -2 km away JCO criticality accident site Tokai-mura.In this study reactor neutron calculations Baikal-1 experiments have been performed TRIPOLI-4 Monte Carlo transport code.Baikal-1 carried out 300 kW RA research reactor.The 85 cm thick concrete plug in upper direction was removed during...
TRIPOLI-4® is a 3D continuous-energy Monte-Carlo particle transport code developed by CEA (SERMA) and devoted to shielding, reactor physics, criticality-safety nuclear instrumentation. In this paper, we present the recent developments in for shielding radiation protection applications. Some of these additional features are already available version 10 released December 2015. Other development.
Abstract The ICRP 110 adult male and female voxel phantoms are the official computational models representing (International Commission on Radiological Protection) Reference Male Female. In 2018, Working Group 6 (WG6) of European Radiation Dosimetry (EURADOS) organized a study usage reference phantoms. Organ dose calculation tasks with radiation transport codes were proposed in occupational, environmental, medical dosimetry. TRIPOLI-4 Monte Carlo code has been widely used shielding,...
To support the development of Sodium-cooled Fast Reactors (SFRs) Generation IV nuclear energy systems and to study use TRIPOLI-4® Monte Carlo code JEFF-3.1.1 data library on core neutronics large fast neutron reactors, in this work two recent Organisation for Economic Co-operation Development/Nuclear Energy Agency (OECD/NEA) computational benchmarks 3600-MW(thermal) SFRs were analyzed with continuous-energy TRIPOLI-4 code. Both a mixed oxide [(U,Pu)O2] carbide [(U,Pu)C] investigated. Under...