Results 81 to 90 of about 2,139 (206)
Worst‐Case Accident Analysis of Accident Tolerant Fuel in NuScale Using RELAP5/MOD3‐Based Code
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Research in nuclear engineering focusses on improving the safety of light water reactors (LWRs), driven by accidents like Fukushima in 2011. The severity of this accident was a result of active cooling system failures and cladding material oxidation resulting in hydrogen explosions.
Willem Zuidersma +3 more
wiley +1 more source
Results in Physics, 2019 Photon and neutron attenuation properties of La2O3 based Li2O-SiO2-La2O3 glass system have been evaluated through MCNPX (2.6.0) Monte Carlo code at some photon energies of 0.256–1.33 MeV.
O. Kilicoglu +6 more
doaj +1 more source
A Comparison between GATE and MCNPX monte carlo codes in simulation of medical linear accelerator
Journal of Medical Signals & Sensors, 2014 Radiotherapy dose calculations can be evaluated by Monte Carlo (MC) simulations with acceptable accuracy for dose prediction in complicated treatment plans. In this work, Standard, Livermore and Penelope electromagnetic (EM) physics packages of GEANT4 application for tomographic emission (GATE) 6.1 were compared versus Monte Carlo N-Particle eXtended ...
Hamid-Reza, Sadoughi +4 more
openaire +2 more sources
Results in Physics, 2019 In the present work, we studied the radiation shielding parameters such as mass attenuation coefficients, effective atomic number, half value layer, mean free path, macroscopic effective removal cross-sections and neutron transmission function for ...
M. Almatari +5 more
doaj +1 more source
Investigation of radial dose distribution and cumulative dose of radiopharmaceuticals used for pain palliation of bone metastases [PDF]
مجله علوم و فنون هستهای, 2015 A cancer that begins in an organ, such as breast or prostate, and then spreads to the bone, results in metastatic bone. The treatment of the bone metastases is one of the most important challenges of nuclear medicine.
Hassan Ranjbar +3 more
doaj
CEM03.03 and LAQGSM03.03 Event Generators for the MCNP6, MCNPX, and MARS15 Transport Codes
, 2008 A description of the IntraNuclear Cascade (INC), preequilibrium, evaporation, fission, coalescence, and Fermi breakup models used by the latest versions of our CEM03.03 and LAQGSM03.03 event generators is presented, with a focus on our most recent developments of these models.
Mashnik, S. G. +5 more
openaire +2 more sources
, 2011 International audienceThis paper describes the results of the simulation of a radiophotoluminescent (RPL) dosemeter with the Monte Carlo transport code MCNPX.
Clairand, I. +9 more
core +1 more source
Neutronic Investigation of Fissionable Spallation Targets in Accelerator Driven Systems [PDF]
مجله علوم و فنون هستهای, 2017 Spallation process is the most important neutron generation method in industry, medicine, etc. This process in the subcritical reactor core is also another technique.
M Amirkhani, M Hassanzadeh
doaj
EPJ Web of Conferences, 2017 MCUNED code is an MCNPX extension able to handle evaluated nuclear data library for light ion transport simulations. In this work the MCUNED code is improved to describe more accurately the neutron emission during deuteron induced nuclear reaction.
Sauvan Patrick +3 more
doaj +1 more source
Using MCNPX for space applications [PDF]
, 2002 The Los Alamos National Laboratory Monte Carlo N-Particle, eXtended-energy radiation transport code MCNPX is rapidly becoming an international standard for a wide spectrum of high-energy radiation transport applications. One such application includes the
Waters, L. S. (Laurie S.) +3 more
core