Results 41 to 50 of about 8,745 (215)
Numerical Solution of Governing Thermal-Hydraulic Equations in the Core of PBMR Using the Porous Media Model [PDF]
Numerical solution of governing thermal-hydraulic equations in the core of a pebble bed modular reactor (PBMR) is investigated using the porous media approach.
Mohammad Hossein Estaki +3 more
doaj
Study on efficiency calibrating method of well-type γ ray spectrometer for soil samples
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
Study of Self-Absorption in Gamma-Ray Spectroscopy of Environmental Samples [PDF]
HPGe detector has been simulated by using MCNP code, and the detector response has been determined. Monte Carlo simulations have been performed for different elemental composition and density as environmental Marinelli samples (z =10-90, ρ = 0.8-2 g/cm3).
Mahboobeh Lotfi +2 more
doaj
Calculation of Dose Distribution in Neutron Brachytherapy Using 252-Cf Source Through the Monte Carlo Simulation and Comparison with Experimental Data [PDF]
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
Abstract Background TG‐43 formalism dose calculation for brachytherapy with the homogeneous water‐based assumption is widely used, which can lead to dose inaccuracy in treatment planning. Purpose Extremity malignancies are also treated with high‐dose‐rate (HDR) 192Ir interstitial brachytherapy, a treatment site that has not been specifically ...
Peixiong Li +10 more
wiley +1 more source
CALCULATION OF NEUTRON FLUX DISTRIBUTION AT PIERCING BEAM PORTS OF PLATE TYPE RESEARCH REACTOR BANDUNG [PDF]
Based on a strategic plan of TRIGA 2000 Bandung’s future operation, BATAN has already decided to implement an option to convert the fuel elements core of TRIGA 2000 from using the cylindrical type of elements produced by General Atomic to MTR plate type ...
Bahrum, E. S. (Epung) +7 more
core +1 more source
Evaluation of RAPID for a UNF cask benchmark problem
This paper examines the accuracy and performance of the RAPID (Real-time Analysis for Particle transport and In-situ Detection) code system for the simulation of a used nuclear fuel (UNF) cask.
Mascolino Valerio +2 more
doaj +1 more source
Dose modeling of superficial brachytherapy applicator geometries using multiple radioisotopes
Abstract Background Superficial brachytherapy enables localized dose delivery for superficial cutaneous lesions, but conventional applicators may be limited in treating extended, irregular, or curved surfaces. Geometric constraints, gaps or overlaps between adjacent applicators, and placement‐related uncertainties can reduce dose uniformity ...
Jin Jegal +5 more
wiley +1 more source
MCNP variance reduction overview [PDF]
The MCNP code is rich in variance reduction features. Standard variance reduction methods found in most Monte Carlo codes are available as well as a number of methods unique to MCNP. We discuss the variance reduction features presently in MCNP as well as
Booth, T. E., Hendricks, J. S.
core

