Results 91 to 100 of about 8,745 (215)
Dosimetry Study of a VARIAN 600 C/D Linear Accelerator Head Model using MCNP5 Monte Carlo Code
Brazilian Journal of Radiation Sciences, 2019 In radiotherapy treatment planning, tools that improve the accuracy and quality of the radiation treatment for cancer are important for the decreased death of healthy tissue and the probability to produce cancer cells.
Claubia Pereira +5 more
doaj +1 more source
MCNP model of the ITER Tokamak Complex
Fusion Engineering and Design, 2018 Abstract The Tokamak Complex will accommodate the ITER tokamak and some of the plant systems needed for the machine operation. In order to obtain radiation maps in the Tokamak Complex, a new MCNP model was released on September 2016. This model, based on a conservative representation of the latest baseline design, represents a version controlled ...
López-Revelles, A.J. +6 more
openaire +2 more sources
, 1991 Over 50 neutron benchmark calculations have recently been completed as part of an ongoing program to validate the MCNP Monte Carlo radiation transport code.
Whalen, Daniel J. +3 more
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Phenomenological Analysis on 1,000°C Material Irradiation Testing in HANARO using the Instrumented-Capsule(15M-03K) [PDF]
EPJ Web of ConferencesWith the increasing demand for materials development for next-generation nuclear systems such as Molten Salt Reactors, Sodium-cooled Fast Reactors, and Very High-Temperature Reactors, high-temperature irradiation testing has become essential.
Kim Jong Woo +3 more
doaj +1 more source
Variance reduction applications using visual MCNP.
, 2015 Visual MCNP has visual tools that can help solve complex variance reduction problems. This paper will show several applications where Visual MCNP has been used to solve real world problems with a substantial reduction in the running time required to ...
Kum, O. +3 more
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Development of a Neutronic Model of the WWER-1000 Reactor Facility Core
Eurasian Journal of Physics and Functional MaterialsA neutronic model of the WWER-1000 reactor has been developed. The reactor block of the B-320 series, which is the most common among NPPs with the WWER type reactors, was selected for the modeling. The modeling was performed using the MCNP6 software.
Darkhan M. Seken +6 more
doaj +1 more source
MCNP{trademark} Software Quality Assurance plan
, 1996 MCNP is a computer code that models the interaction of radiation with matter. MCNP is developed and maintained by the Transport Methods Group (XTM) of the Los Alamos National Laboratory (LANL).
Abhold, H.M., Hendricks, J.S.
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Verification of the MCNP{trademark} perturbation technique
, 1996 Over the last few decades, users of the Monte Carlo radiation transport code MCNP have expressed the need for a perturbation capability. The perturbation technique chosen for inclusion as a standard feature in future releases of MCNP is described here ...
Iverson, J. L., McKinney, G. W.
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Design Simulation and Radiation Optimization of 90Sr Isotope Generator Radioactive Source
Journal of Isotopes90Sr has strong bremsstrahlung radiation, before manufacturing the radioisotope heat source, it is necessary to first simulate the composition of the 90SrTiO3 ceramic pellet, design the structure of the fuel cladding, and evaluate the bremsstrahlung ...
YANG Liqun, JIA Nannan, ZHOU Jian, LI Yefan, TANG Jun
doaj
MCNP visual editor computer code manual
, 1995 This document contains the manual for using the Monte Carlo N-Particle (MCNP) Visual ...
Schwarz, R. A., Carter, L. L.
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