Results 101 to 110 of about 16,330 (259)

MCNP® Code Version 6.3.0 Theory & User Manual

, 2022
J. Kulesza, T. Adams, J. Armstrong, Simon Bolding, Forrest Brown, J. Bull, T. Burke, A. Clark, R. Forster, Jesse F. Giron, Tristan Grieve, C. Josey, R. Martz, G. Mckinney, E. Pearson, M. Rising, C. Solomon, S. Swaminarayan, T. Trahan, S. Wilson, A. Zukaitis   +20 more
semanticscholar   +1 more source

Phenomenological Analysis on 1,000°C Material Irradiation Testing in HANARO using the Instrumented-Capsule(15M-03K) [PDF]

EPJ Web of Conferences
With 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, Park Junesic, Choo Ki Nam, Yang Seong Woo   +3 more
doaj   +1 more source

Spectral measurements in critical assemblies: MCNP specifications and calculated results [PDF]

, 1999
Recently, a suite of 86 criticality benchmarks for the Monte Carlo N-Particle (MCNP) transport code was developed, and the results of testing the ENDF/B-V and ENDF/B-VI data (through Release 2) were published.
Frankle, Stephanie C., Briesmeister, Judith F.   +1 more
core   +1 more source

MCNP® Code Version 6.3.0 Release Notes

, 2023
M. Rising, J. Armstrong, Simon Bolding, Forrest Brown, J. Bull, T. Burke, A. Clark, David Dixon, R. Forster, Jesse F. Giron, Tristan Grieve, Henry Hughes, C. Josey, J. Kulesza, R. Martz, A. McCartney, G. Mckinney, S. Mosher, E. Pearson, C. Solomon, S. Swaminarayan, J. Sweezy, S. Wilson, A. Zukaitis   +23 more
semanticscholar   +1 more source

Simulation study of alpha-neutron reactions from AmBe directional source using MCNP 6.1.1 with TENDL 2012, 2014, and 2017 libraries.

Applied Radiation and Isotopes, 2019
Angular dependence of 9Be(α, n)12C was simulated in Monte-Carlo N-Particle transport 6.1.1 (MCNP) with TALYS Evaluated Nuclear Data Library (TENDL) 2012, 2014, and 2017 data to determine secondary neutron direction and energy for neutron imaging.
Kyle M. Paaren, Hyoung K. Lee
semanticscholar   +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., Licea, A., Schwarz, R., Hiller, M.   +3 more
core  

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.
core   +1 more source

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.
core   +1 more source

MCNP-X Monte Carlo Code Application for Mass Attenuation Coefficients of Concrete at Different Energies by Modeling 3 × 3 Inch NaI(Tl) Detector and Comparison with XCOM and Monte Carlo Data

, 2016
Gamma-ray measurements in various research fields require efficient detectors. One of these research fields is mass attenuation coefficients of different materials.
H. O. Tekin
semanticscholar   +1 more source

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.
core