Results 101 to 110 of about 2,139 (206)

Neutron production evaluation from a ADS target utilizing the MCNPX 2.6.0 code

open access: yes, 2010
Accelerators Driven Systems (ADS) are an innovative type of nuclear system, which is useful for long-lived fission product transmutation and fuel regeneration.
Graiciany P. Barros   +9 more
core   +1 more source

Comparisons of the Calculations Using Different Codes Implemented in MCNPX Monte Carlo Transport Code for Accelerator Driven System Target

open access: yes, 2012
The MCNPX code offers options based on physics packages; the Bertini, ISABEL, INCL4 intra-nuclear models, and Dresner, ABLA evaporation-fission models and CEM2k cascade-exciton model.
Yurdunaz Çelik   +7 more
core   +1 more source

Towards a better understanding of detection properties of different types of plastic scintillator crystals using physical detector and MCNPX code

open access: yes, 2022
The purpose of this comprehensive research is to observe the impact of scintillator crystal type on entire detection process. For this aim, MCNPX (version 2.6.0) is used for designing of a physical plastic scintillation detector available in our ...
Lidya Amon Susam   +6 more
core   +1 more source

Recent developments in MCNPX{trademark}

open access: yes, 1998
The MCNPX Monte Carlo particle transport code is rapidly developing into a significant computational tool for high-energy transport applications.
Adams, K.J.   +2 more
core  

Cellular dosimetry of strontium-90 using the Monte Carlo code MCNPX, detection and X-ray microanalysis

open access: yes, 2014
The aim of this study is to provide data that increase knowledge about the possible health effects of exposure to 90Sr contaminant in drinking water.
D. Franck   +13 more
core   +1 more source

Low energy fusion for a safe and compact neutron source

open access: yes, 2013
Neutrons are primarily produced at large international facilities using either spallation reactions or nuclear fission. There is a demand for small scale neutron production for use at hospitals and borders for a variety of applications.
Seviour, Rebecca, Albright, S.
core  

A comparatıve study on shielding properties of some composite materials by MCNPX code [PDF]

open access: yes, 2019
347-350The radiation mass attenuation coefficients of composite material samples as shielding materials have been calculated at 356, 511, 662, 1173, 1274 and 1332 keV photon energies by using general purpose Monte Carlo code MCNPX (version 2.6.0).
Altunsoy, Elif Ebru   +4 more
core  

An Intercomparison Exercise Between EGSnrc and MCNPX for Validation of New egs kerma User Code

open access: yes, 2023
Background: The “Case 1” exercise described in the TG report 195 of the American Association of Physicists inMedicine was used. This exercise aims to verify the material attenuation of a filter of aluminum and the half andquarter-value layer calculations.
Ferreira, C.V.G.   +4 more
core  

HIZLANDIRICI GÜDÜMLÜ SİSTEMLERDE BAZI UZUN ÖMÜRLÜ NÜKLEER ATIKLARIN DÖNÜŞÜMÜNÜN İNCELENMESİ

open access: yesSüleyman Demirel Üniversitesi Fen-Edebiyat Fakültesi Fen Dergisi, 2009
Özet: Bu çalışmada Hızlandırıcı Güdümlü Sistem (ADS) kullanılarak uzun yarı ömürlü 99Tc, 129I, 237Np, 238U ve 239Pu nükleer atıkların kararlı veya kısa yarı ömürlü izotoplara dönüşümleri incelenmiştir. Bunun için sırasıyla 1, 2 ve 3 GeV enerjili ve 10 mA
Mehmet Emin KORKMAZ
doaj  

Benchmarking photoneutron production of Mcnpx simulations with experimental results

open access: yes, 2002
Accelerator driven subcritical systems (ADS) are one of the most viable methods for the transmutation and effective utilization of nuclear fuel. An important aspect of coupling the accelerator to a nuclear reactor is the generation of a high-energy ...
Sadineni, Suresh Babu
core   +1 more source

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