Open Access
MCNP-A General Monte Carlo N-Particle Transport Code
Judith F. Briesmeister
- 01 Jan 1993
TL;DR: In this article, the authors present a practical guide for the use of general-purpose Monte Carlo code MCNP, including several examples and a discussion of the particular techniques and the Monte Carlo method itself.
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Abstract: This manual is a practical guide for the use of our general-purpose Monte Carlo code MCNP. The first chapter is a primer for the novice user. The second chapter describes the mathematics, data, physics, and Monte Carlo simulation found in MCNP. This discussion is not meant to be exhaustive---details of the particular techniques and of the Monte Carlo method itself will have to be found elsewhere. The third chapter shows the user how to prepare input for the code. The fourth chapter contains several examples, and the fifth chapter explains the output. The appendices show how to use MCNP on various computer systems and also give details about some of the code internals.
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Citations
BEDVH-A method for evaluating biologically effective dose volume histograms: application to eye plaque brachytherapy implants.
Nolan L. Gagne,Kara L. Leonard,Kathryn E. Huber,John E. Mignano,Jay S. Duker,Nora V. Laver,Mark J. Rivard +6 more
TL;DR: BEDVH permits evaluation of the relative biological effectiveness for brachytherapy implants as well as assessing the influence of implant duration T, radionuclide choice, and radiobiological parameters on the biologically effective dose (BED) throughout the entire volume of regions of interest for episcleral brachyTherapy.
28
Adaptive anisotropic diffusion filtering of Monte Carlo dose distributions.
TL;DR: It is shown that the adaptive anisotropic diffusion method can reduce statistical noise significantly (two to five times, corresponding to the reduction of simulation time by a factor of up to 20), while preserving important gradients of the dose distribution well.
28
Calculated dosimetric parameters of the IoGold 125I source model 3631-A.
TL;DR: Basic dosimetric parameters as recommended by the AAPM Task Group No. 43 (TG-43) have been determined for recently available IoGold 125I brachytherapy seeds and results compared with soon to be published experimental parameters also for 125I IoGold seeds as well with parameters for model 6702 and 6711 125I seeds.
Detection of fast neutrons in a plastic scintillator using digital pulse processing to reject gammas
Paul L. Reeder,A.J. Peurrung,R.R. Hansen,David C. Stromswold,Walter K. Hensley,Charles W. Hubbard +5 more
TL;DR: In this paper, the authors report on neutron-gamma discrimination in a plastic scintillator based on the time delay inherent in second and third chance neutron scattering, and demonstrate that a neutron signal should be significantly broader than a pulse from a gamma event.
28
Neutron capture and transmission measurements and resonance parameter analysis of niobium
N. J. Drindak,J. A. Burke,G. Leinweber,J. A. Helm,J. G. Hoole,Robert C. Block,Yaron Danon,R.E. Slovacek,B. E. Moretti,C. J. Werner,M. E. Overberg,S. A. Kolda,M. J. Trbovich,D. P. Barry +13 more
TL;DR: In this paper, the authors used the multi-level R-matrix Bayesian code SAMMY version M2 to determine the capture resonance integral for all stable isotopes of samarium.
References
MCNP capabilities for nuclear well logging calculations
TL;DR: The Los Alamos Radiation Transport Code System (LARTCS) as discussed by the authors consists of state-of-the-art Monte Carlo and discrete ordinates transport codes and data libraries.
42
ACTL: evaluated neutron activation cross section library-evaluation techniques and reaction index. [Tables, 10/sup -10/ to 20 MeV]
Gardner,R.J. Howerton +1 more
- 17 Oct 1978
TL;DR: A library of evaluated neutron-induced activation cross sections (ACTL) was compiled and general descriptions of the evaluation methods and an index to the evaluated cross sections are presented.
Average neutronic properties of prompt fission products
D.G. Foster,E.D. Arthur +1 more
- 01 Feb 1982
TL;DR: In this paper, the average neutronic properties of the ensemble of fission products producted by fast-neutron fission of /sup 235/U and /sup 239/Pu, where the properties are determined before the first beta decay of any of the fragments, are described.
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