scholarly journals The MCNP Code: 6.3 and Beyond

2022 ◽  
Author(s):  
Colin Josey ◽  
Joel Kulesza ◽  
Michael Rising
Keyword(s):  
Mcnp Code

A comparison study for mass attenuation coefficients of some amino acids using MCNP code

Kerntechnik ◽  
2017 ◽  
Vol 82 (3) ◽  
pp. 339-343 ◽  
Author(s):  
S. M. Vahabi ◽  
M. Bahreinipour ◽  
M. Shamsaie-Zafarghandi
Keyword(s):  
Amino Acids ◽  
Comparison Study ◽  
Mcnp Code ◽  
Attenuation Coefficients ◽  
Mass Attenuation Coefficients ◽  
Mass Attenuation

Reduction of the gamma-ray component from fission neutron source - optimization for biological irradiations and comparison with MCNP code

1999 ◽  
Vol 44 (5) ◽  
pp. 1207-1218 ◽  
Author(s):  
S Endo ◽  
D L Stevens ◽  
P Bonner ◽  
M A Hill ◽  
H Nikjoo ◽  
...  
Keyword(s):  
Neutron Source ◽  
Gamma Ray ◽  
Fission Neutron ◽  
Mcnp Code

Organ dose conversion coefficients based on a voxel mouse model and MCNP code for external photon irradiation

2011 ◽  
Vol 148 (1) ◽  
pp. 9-19 ◽  
Author(s):  
X. Zhang ◽  
X. Xie ◽  
J. Cheng ◽  
J. Ning ◽  
Y. Yuan ◽  
...  
Keyword(s):  
Mouse Model ◽  
Organ Dose ◽  
Mcnp Code ◽  
Photon Irradiation ◽  
Conversion Coefficients

Comparison of photon attenuation coefficients of various barite concretes and lead by MCNP code, XCOM and experimental data

2013 ◽  
Vol 55 ◽  
pp. 288-291 ◽  
Author(s):  
S.P. Shirmardi ◽  
M. Shamsaei ◽  
M. Naserpour
Keyword(s):  
Experimental Data ◽  
Mcnp Code ◽  
Attenuation Coefficients ◽  
Photon Attenuation

On the Rapid Generation of Complete XRF Spectra for Material Analysis from Fundamental Parameters

2021 ◽  
Vol 105 ◽  
pp. 110-118
Author(s):  
Jie Si Ma ◽  
Fu Sheng Li ◽  
Yan Chun Zhao
Keyword(s):  
Simulated Data ◽  
Target Material ◽  
Mcnp Code ◽  
X Ray ◽  
Fundamental Parameters ◽  
Elemental Compositions ◽  
Statistical Precision ◽  
Proposed Model ◽  
Time Calculation ◽  
Rapid Generation

X-ray Fluorescence (XRF) analysis technology is used widely to detect and measure elemental compositions of target samples. The MCNP code developed by LANL can be utilized to simulate and generate the XRF spectrum of any sample with various elemental compositions. However, one shortcoming of MCNP code is that it takes quite a lot of time (in hours or longer) to generate one XRF spectrum with reasonable statistical precision; the other shortcoming is that MCNP code cannot produce L shell spectrum accurately. In this paper, a new computation model based on the Sherman equation (i.e., Fundamental Parameters, FP) is proposed to overcome the drawbacks of the MCNP code. The most important feature of this model is to achieve a full and accurate generation of spectral information of each element in a target material very rapidly (in seconds or less), including both K and L shell spectral peaks. Furtherly, it is demonstrated that the simulated data by this new mode match the experimental data very well. It proves that the proposed model can be a better alternative of MCNP code in the application of generation the XRF spectra of many materials, in terms of speed and accuracy. The proposed model can perform the simulation of XRF spectra in situ both fast and accurately, which is essential for real-time calculation of chemical composition by use of X-ray spectrometer, especially for those trace elements in target materials.

Isodose distributions and dose uniformity in the Portuguese gamma irradiation facility calculated using the MCNP code

2001 ◽  
Vol 61 (3-6) ◽  
pp. 791-793 ◽  
Author(s):  
C. Oliveira ◽  
J. Salgado
Keyword(s):  
Gamma Irradiation ◽  
Mcnp Code ◽  
Dose Uniformity

scholarly journals Universal dependence of the total number albedo of photons on the mean number of photon scatterings

2011 ◽  
Vol 26 (3) ◽  
pp. 249-253 ◽  
Author(s):  
Vladan Ljubenov ◽  
Rodoljub Simovic
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
Analytic Functions ◽  
Least Squares Method ◽  
Mcnp Code ◽  
Initial Photon ◽  
Aluminum Iron ◽  
Universal Dependence ◽  
The Mean ◽  
Good Agreement

This paper presents the results of research on photon reflection from plane targets based on Monte Carlo simulations performed by the MCNP code. Five materials (water, concrete, aluminum, iron, and copper) are examined in the area of initial photon energies of up to 200 keV. The values of the total number albedo for photons dependent on the initial photon energy or the mean number of photon scatterings are calculated and graphically presented. We have shown that the values of the total number albedo for different target materials, expressed as a function of the mean number of photon scatterings, are in good agreement with each other and can be approximated by simple, universal analytic functions obtained by the least squares method. The accuracy of these analytic appoximations is confirmed by their comparison with the results of PENELOPE and FOTELP Monte Carlo codes.

scholarly journals DESAIN KOLIMATOR TIPE TABUNG UNTUK PENYEDIAAN BERKAS RADIOGRAFI DENGAN SUMBER GENERATOR NETRON

2007 ◽  
Vol 10 (2) ◽  
Author(s):  
Yohannes Sardjono
Keyword(s):  
Monte Carlo ◽  
Mcnp Code ◽  
Beam Filter

DESAIN KOLIMATOR TIPE TABUNG UNTUK PENYEDIAAN BERKAS RADIOGRAFI DENGAN SUMBERGENERATOR NETRON. Telah dilakukan desain kolimator untuk penyediaan berkas radiografi netron dengansumber generator netron. Kolimator ini berguna untuk mendapatkan fluks netron termal yang optimal dengan pengotorradiasi (netron epitermal dan gamma) yang sekecil-kecilnya. Proses desain dilakukan dengan melakukan simulasimenggunakan Monte Carlo N-Particle (MCNP) code untuk menghitung tally berupa fluks netron dan laju dosisekuivalen. Desain kolimator yang dipilih adalah jenis tabung yang tersusun dari material moderator parafin, reflektorgrafit, dan kolimator wall alumunium. Parameter optimasi desain adalah panjang kolimator 4 - 8 cm, dengan interval 1cm, jenis bahan moderator (parafin, grafit, berilium, dan air), jenis beam filter adalah timbal, dan material apertureadalah boron atau kadmium. Kriteria penerimaan adalah fluks netron termal 103 - 106 n.cm-2.s-1, n/γ ratio > 106n.cm-2.mR-1 dan Cd ratio > 2. Untuk keselamatan lingkungan digunakan parafin sebagai biological shielding dan timbalsebagai casing. Dari hasil perhitungan optimasi desain dapat diperoleh bahwa kolimator dengan sumber generatornuetron menghasilkan keluaran fluks netron termal 4.67 + 0.5981 x 103 n.cm-2.s-1, rasio netron-gamma (n/γ) ≥ (1.56 +0,000111).106 n.cm–2 mR-1 dan laju dosis ekuivalen pada jarak 10 cm dari permukaan fasilitas adalah 0,0378 - 0,0521mR/jam.

scholarly journals Neutrons along the labyrinth of high energy medical accelerators: Effect of wall materials

2019 ◽  
Vol 21 ◽  
pp. 169
Author(s):  
M. Fakinou ◽  
I. E. Stamatelatos ◽  
J. Kalef-Ezra
Keyword(s):  
Monte Carlo ◽  
Cost Effective ◽  
High Energy ◽  
Wall Material ◽  
Mcnp Code ◽  
Dose Equivalent ◽  
Concrete Wall ◽  
Ambient Dose Equivalent ◽  
Wall Materials ◽  
Ambient Dose

Neutron streaming along the labyrinth of a generic bunker of an 18MV medical accelerator was evaluated. Monte Carlo simulations using MCNP code were performed to calculate neutron ambient dose equivalent along the labyrinth. The effect of plain, borated and barites concrete wall material, as well as borated concrete and plywood (Celotex), as neutron absorbing wall liners, was examined. The results of the study suggest that plywood can provide a cost effective material to attenuate neutron streaming along the labyrinth.

Sign in / Sign up

Export Citation Format

Share Document