Results 131 to 140 of about 2,294 (180)

Associations Between Prenatal Phthalate Exposure and Atopic Symptoms in Childhood: Effect Modification by Child Sex. [PDF]

Toxics
Bhatt KD, Mistry S, Lamadrid-Figueroa H, Tamayo-Ortiz M, Mercado-Garcia A, Lane JM, Téllez-Rojo MM, Wright RO, Wright RJ, Estrada-Gutierrez G, Carroll KN, Alcala CS, Rosa MJ.   +12 more
europepmc   +1 more source

A comparative Monte Carlo simulation study on shielding features of the CaF₂-CaO-B₂O₃-P₂O₅-SrO-Ta₂O₅ glass system against X-ray by GEANT4 and MCNPX codes. [PDF]

Sci Rep
Isazadeh F, Abdi Saray A.
europepmc   +1 more source

Unveiling the radiation shielding efficacy of diorite, granodiorite, tonalite, and granite: experimental and simulation study. [PDF]

Sci Rep
Elsafi M, El-Nahal MA, Alawy MK, Nabil IM.   +3 more
europepmc   +1 more source

A comparison and evaluation of statistical methods for mediation analysis with mixtures of environmental exposures. [PDF]

BMC Med Res Methodol
McGrath S, Wang Y, Lin YT, Meeker JD, Park SK, Warren JL, Mukherjee B.   +6 more
europepmc   +1 more source

Development of PMMA based polymer composite incorporating WO₃ for gamma radiation shielding using synthesis and Monte Carlo simulation. [PDF]

Sci Rep
Mokhtari Dorostkar M, Abdi Saray A.
europepmc   +1 more source

High-Temperature MCNP Cross Sections

, 1987
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MCNP Output Data Analysis with ROOT (MODAR)

Computer Physics Communications, 2010
MCNP Output Data Analysis with ROOT (MODAR) is a tool based on CERN's ROOT software. MODAR has been designed to handle time–energy data issued by MCNP simulations of neutron inspection devices using the associated particle technique. MODAR exploits ROOT's Graphical User Interface and functionalities to visualize and process MCNP simulation results in a
Cedric Carasco
exaly   +2 more sources

The comparison of MCNP perturbation technique with MCNP difference method in critical calculation

Nuclear Engineering and Design, 2010
Abstract For a nuclear fission system, we calculated Δkeff, which arise from system material composition changes, by two different approaches, the MCNP perturbation technique and the MCNP difference method. For every material composition change, we made four different runs, each run with different cycles or each cycle generating different neutrons ...
Bin Liu, Xuefeng Lv, Wei Zhao, Kai Wang, Jing Tu, Xiaoping Ouyang   +5 more
openaire   +1 more source

MCNP Monte Carlo: a precis of MCNP

SPIE Proceedings, 1997
MCNPTM Monte Carlo: a precis of MCNPKenneth J. AdamsTransport Methods Group, XTM MS B226Los Alamos National Laboratory, Los Alamos, NM, 87545ABSTRACTMCNPTM* is a general purpose tiiree-dimensional time-dependent neutron, photon, and electron transport code.
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Nuclear data for MCNP

2006
The sources of neutron and photon transport data are described as well as the processing of the evaluated data sets into continuous-energy and multigroup cross-section sets. The procedures for checking and validating the processed data are discussed. The question of why so many data sets are available is addressed by indicating the differences between ...
Little, R. C., Seamon, R. E.
openaire   +1 more source