Results 41 to 50 of about 1,341 (152)

Validation of UNIST Monte Carlo code MCS for criticality safety calculations with burnup credit through MOX criticality benchmark problems

open access: yesNuclear Engineering and Technology, 2021
This paper presents the validation of the MCS code for critical safety analysis with burnup credit for the spent fuel casks. The validation process in this work considers five critical benchmark problem sets, which consist of total 80 critical ...
Duy Long Ta, Ser Gi Hong, Deokjung Lee
doaj   +1 more source

A novel method for calculating number buildup factor in gamma-ray transmission measurements using narrow beam geometry [PDF]

open access: yesNuclear Technology and Radiation Protection
In this article, we present a novel method to calculate the number buildup factor for arbitrary materials in gamma-ray transmission measurements using a narrow beam geometry.
Chuong Huynh Dinh   +4 more
doaj   +1 more source

Features of MCNP6

open access: yes, 2014
MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, but it is much more than the sum of these two computer codes. MCNP6 is the result of six years of effort by the MCNP5 and MCNPX code development teams.
J. Elson   +22 more
core   +1 more source

Kinetic parameters of the Dalat nuclear research reactor with LEU fuel using MCNP6 and JENDL-5 library [PDF]

open access: yesNuclear Technology and Radiation Protection
Kinetic parameters of a nuclear reactor are essential in reactor dynamic and safety related characteristics. Kinetic parameters of the Dalat nuclear research reactor were evaluated using the MCNP6.3 code and a new nuclear data library (JENDL-5).
Dau Duc-Tu   +7 more
doaj   +1 more source

Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS

open access: yesNuclear Engineering and Technology, 2021
The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor operated by the Research Center Rez in the Czech Republic has been conducted with the MCS Monte Carlo code developed at the Computational Reactor Physics ...
Fathurrahman Setiawan   +2 more
doaj   +1 more source

Source-detector effective solid angle calculation using MCNP6 code

open access: yesBrazilian Journal of Radiation Sciences, 2021
Nuclear techniques based on the attenuation of gamma radiation are used in the industry to calculate flow rate, determine fluid density, predict inorganic scale in oil pipelines, evaluate industrial mixers, among other applications. In order to use these
Roos Sophia de Freitas Dam   +3 more
doaj   +1 more source

Network‐wide assessment of soil water content calibration and sensitivity to biomass proxies using cosmic‐ray neutron sensing in the Roaring Fork Basin, Colorado

open access: yesVadose Zone Journal, Volume 25, Issue 3, May/June 2026.
Abstract Soil water content (SWC) is a key state variable of the climate system but is often uncertain in water balance monitoring, especially in alpine environments. SWC measurements can be challenging in alpine environments due to the topography and rocky soils.
Sophia M. Becker   +4 more
wiley   +1 more source

Constraining the Hydration of Clay Minerals and Abundances of Amorphous Phases in Gale Crater, Mars

open access: yesJournal of Geophysical Research: Planets, Volume 131, Issue 5, May 2026.
Abstract Both water and organic matter are required for the development and persistence of life. Phyllosilicates (clay minerals) have high surface areas that easily sorb water and organic matter. The Curiosity rover has investigated several hundred meters of stratigraphy in Gale crater, including where clays were detected from orbit.
Sean Czarnecki   +3 more
wiley   +1 more source

Validation of the MCNP6 code for SFR shielding design analysis

open access: yes, 2019
In this paper, the uncertainty of the Monte Carlo code MCNP6 for the sodium-cooled fast reactor (SFR) shielding design is studied. Shielding analysis, which ensures the radiation safety of the core design, is challenging for the Monte Carlo modeling ...
Jeong, Sanggeol   +8 more
core   +1 more source

Studi Model Benchmark Mcnp6 Dalam Perhitungan Reaktivitas Batang Kendali Htr-10 [PDF]

open access: yes, 2016
STUDI MODEL BENCHMARK MCNP6 DALAM PERHITUNGAN REAKTIVITAS BATANG KENDALI HTR-10. Dalam operasi reaktor nuklir, sistem batang kendali memainkan peranan yang sangat penting karena didesain untuk mengendalikan reaktivitas teras dan memadamkan reaktor. Nilai
Jupiter S.Pane, Zuhair, Suwoto, Putranto Ilham Yazid   +2 more
core   +1 more source

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