THE DOUNREAY FAST REACTOR VAULT CHARACTERISATION USING THE MONTE CARLO N-PARTICLE CODE AS A TOOL TO SUPPORT DECOMMISSIONING PLANNING [PDF]
EPJ Web of Conferences, 2021 A combined empirical and theoretical characterisation approach was taken in order to investigate the activity distribution and inventory in the Dounreay Fast Reactor (DFR) vault, so as to aid with the decommissioning and waste management strategy of the ...
Baldioli Vittoria +3 more
doaj +1 more source
Monte Carlo Particle Lists: MCPL [PDF]
, 2017 A binary format with lists of particle state information, for interchanging particles between various Monte Carlo simulation applications, is presented.
Cai, Xiao Xiao +5 more
core +2 more sources
Study on efficiency calibrating method of well-type γ ray spectrometer for soil samples
He jishu, 2021 BackgroundPutting samples into the well-type γ ray spectrometer can greatly improve the activity measurement efficiency, therefore it can reduce the measurement time and the mass of samples.PurposeThis study aims to accurately obtain detection ...
LAI Yongfang +4 more
doaj +1 more source
Determination of neutron spectrum parameters at IREN facility using the MCNP simulation and experimental validation [PDF]
Nuclear Technology and Radiation ProtectionThe determination of the characteristics of neutron spectrum at different irradiation positions on the outer wall of moderator chamber of the intense resonance neutron source by simulation method using MCNP code was presented.
Nhat Le Tran Minh +14 more
doaj +1 more source
Urinary Phthalate Metabolites and Biomarkers of Oxidative Stress in a Mexican-American Cohort: Variability in Early and Late Pregnancy. [PDF]
, 2016 People are exposed to phthalates through their wide use as plasticizers and in personal care products. Many phthalates are endocrine disruptors and have been associated with adverse health outcomes.
Bradman, Asa +6 more
core +3 more sources
, 2009 The Reduced Enrichment Research and Test Reactor (RERTR) Program uses the REBUS-PC computer code to provide reactor physics and core design information such as neutron flux distributions in space, energy, and time, and to track isotopic changes in fuel and neutron absorbers with burnup.
Stevens, J. G. +1 more
openaire +2 more sources
Elaborate SMART MCNP Modelling Using ANSYS and Its Applications
EPJ Web of Conferences, 2017 An MCNP 3-dimensional model can be widely used to evaluate various design parameters such as a core design or shielding design. Conventionally, a simplified 3-dimensional MCNP model is applied to calculate these parameters because of the cumbersomeness ...
Song Jaehoon +3 more
doaj +1 more source
Calculation of Dose Distribution in Neutron Brachytherapy Using 252-Cf Source Through the Monte Carlo Simulation and Comparison with Experimental Data [PDF]
مجله علوم و فنون هستهای, 2018 Detailed recognition of dose distribution around the brachytherapy sources in order to create appropriate plans for treatment of cancer is very important.
Gh Izadi Vasafi +2 more
doaj +1 more source
MCNP: Multigroup/adjoint capabilities [PDF]
, 1994 This report discusses various aspects related to the use and validity of the general purpose Monte Carlo code MCNP for multigroup/adjoint calculations. The increased desire to perform comparisons between Monte Carlo and deterministic codes, along with the ever-present desire to increase the efficiency of large MCNP calculations has produced a greater ...
Wagner, J. C. +3 more
openaire +2 more sources
CEA-JSI Experimental Benchmark for validation of the modeling of neutron and gamma-ray detection instrumentation used in the JSI TRIGA reactor [PDF]
EPJ Web of Conferences, 2021 Constant improvements of the computational power and methods as well as demands of accurate and reliable measurements for reactor operation and safety require a continuous upgrade of the instrumentation.
Fausser Clément +18 more
doaj +1 more source