- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Radiation Detection and Scintillator Technologies
- Laser-Plasma Interactions and Diagnostics
- Nuclear and radioactivity studies
- Manufacturing Process and Optimization
- Gas Dynamics and Kinetic Theory
- Matrix Theory and Algorithms
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Material Properties and Applications
- Computational Geometry and Mesh Generation
- Innovations in Concrete and Construction Materials
- Granular flow and fluidized beds
- Chaos-based Image/Signal Encryption
- Radiation Therapy and Dosimetry
- Heat Transfer and Optimization
- Cholinesterase and Neurodegenerative Diseases
- Particle accelerators and beam dynamics
- Advanced Data Storage Technologies
- Graphite, nuclear technology, radiation studies
- Distributed and Parallel Computing Systems
- Network Packet Processing and Optimization
- Computational Drug Discovery Methods
- Atomic and Subatomic Physics Research
Los Alamos National Laboratory
2024-2025
University of New Mexico
2018-2022
Dalhousie University
2010
After several years of effort involved in merging the Los Alamos National Laboratory MCNP5 and MCNPX codes, 2013 first production release version 6 Monte Carlo N-Particle ® , or MCNP code MCNP6.1 was distributed publicly. Since then, three significant releases have been issued: MCNP6.1.1beta 2014, MCNP6.2 2018, MCNP6.3 2023. While each always contains new features, enhancements, bug fixes, has had a different primary focus, ranging from improved calculational efficiency to powerful utilities...
Since high-throughput screening of compound libraries (virtual or real) against druggable targets is increasingly being used to discover therapies for brain disorders, it crucial ascertain if such methods adequately explore 'neurotherapeutic space (i.e. the total number molecules that are could be neuroactive)'. We present an approach providing estimate size neurotherapeutic space.Molecular modelling and statistical calculations were determine molecules, which exist exist, with necessary...
The apparent ion temperature and neutron-reaction history are important characteristics of a fusion plasma. Extracting these quantities from measured neutron-time-of-flight signal requires accurate knowledge the instrument response function (IRF). This work describes novel method for obtaining IRF directly single DT neutron interactions by utilizing n-alpha coincidence. t(d,α)n nuclear reaction was produced at Sandia National Laboratories’ Ion Beam Laboratory using 300 keV Cockcroft-Walton...
This presentation details some of the new features MCNP6.3. With an included look at Deimos Project. Key points include unstructured mesh and HDF5, fission matrix for criticality calculations, tally features. Future work a Q&A are provided end.
A numerical code library was developed for the radiation transport MCNP6.3 to calculate generalized response sensitivity coefficients fixed source neutron problems with applications inertial confinement fusion (ICF) experiments. The new dependency is used generate a novel time convolution that represents time-of-flight (nToF) signal. traditional suite of macroscopic cross-section sensitivities and constrained probability distribution are available both standard tallies in this library....
This paper describes how to directly sample Monte Carlo flight paths simulate particle transport in media with continuously varying cross sections without using iterative methods. Specifically, this approach supports linear finite-element codes tetrahedral meshes. Two analytical test problems are used verify the method.
A forward analytic model is required to rapidly simulate the neutron time-of-flight (nToF) signals that result from magnetized liner inertial fusion (MagLIF) experiments at Sandia’s Z Pulsed Power Facility. Various experimental parameters, such as burn-weighted fuel-ion temperature and areal density, determine shape of nToF signal are important for characterizing any given MagLIF experiment. Extracting these parameters measured requires an appropriate includes primary deuterium-deuterium...