A5023116614- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Graphite, nuclear technology, radiation studies
- Radiation Detection and Scintillator Technologies
- Medical Imaging Techniques and Applications
- Advanced Thermodynamics and Statistical Mechanics
- Thermoelastic and Magnetoelastic Phenomena
- Nuclear physics research studies
- Radiation Therapy and Dosimetry
- Molten salt chemistry and electrochemical processes
- Thermoregulation and physiological responses
- Particle Detector Development and Performance
- Particle Accelerators and Free-Electron Lasers
- Gas Dynamics and Kinetic Theory
- Particle accelerators and beam dynamics
- Numerical Methods and Algorithms
- Field-Flow Fractionation Techniques
- VLSI and Analog Circuit Testing
- Simulation Techniques and Applications
- Granular flow and fluidized beds
- Risk and Safety Analysis
- Protein purification and stability
- Particle Dynamics in Fluid Flows
Los Alamos National Laboratory
2010-2023
The University of Texas Southwestern Medical Center
1998-2003
Analysis Group (United States)
1990-1999
Texas A&M University
1984
MCNP6 is simply and accurately described as the merger of MCNP5 MCNPX capabilities, but it much more than sum those two computer codes. result five years effort by code development teams. These groups people, residing in Los Alamos National Laboratory's (LANL) X Computational Physics Division, Monte Carlo Codes Group (XCP-3), Decision Applications Radiation Transport Team (D-5), respectively, have combined their efforts to produce next evolution MCNP. While maintenance bug fixes will...
MCNPX (Monte Carlo N‐Particle eXtended) is a general‐purpose Monte radiation transport code with three‐dimensional geometry and continuous‐energy of 34 particles light ions. It contains flexible source tally options, interactive graphics, support for both sequential multi‐processing computer platforms. based on MCNP4c has been upgraded to most MCNP5 capabilities. MCNP highly stable tracking neutrons, photons electrons, using evaluated nuclear data libraries low‐energy interaction...
Exact solutions are obtained to the classical time-dependent linear bioheat equation in one-dimensional multiregion cartesian and spherical geometries with temperature-invariant physiological parameters. These enable study of transient temperature behaviour an arbitrary number coupled physiologically distinct regions.
Exact solutions to the classical time-dependent linear bioheat equation, in one-dimensional multi-region Cartesian, cylindrical and spherical geometries with temperature-invariant physiological parameters, are derived computationally evaluated. Earlier work is extended accommodate transient heat sources boundary conditions using method of Green's functions. These enable study temperature behaviour an arbitrary number coupled physiologically distinct regions, when regional heating rates...
An exact solution is obtained to the classical time-dependent linear bioheat equation in one-dimensional multi-region cylindrical geometry with temperature-invariant physiological parameters. This complements previously reported solutions for Cartesian and spherical geometries, enabling study of transient temperature behaviour an arbitrary number coupled physiologically distinct regions three basic geometries.
For pt.I see ibid., vol.35, no.7, p.847-67 (1990). Analytic solutions to the time-dependent multiregion bioheat equation are evaluated numerically for cartesian and spherical models. Principle alternate branch contributions examined. The calculations include a parametric investigation analyses of temperature behaviour in idealised upper thigh tumour
The interaction of radiation with matter can cause activation or fission reactions producing unstable residuals that decay the emission delayed-neutron and/or delayed-gamma radiation. This delayed be exploited for a variety purposes, including homeland security, health physics, instrumentation and equipment design, nuclear forensics. Here we report on capability has been developed to provide automated simulations using MCNP6. We present new high-fidelity simulation results models based...
MCNP6 is simply and accurately described as the merger of MCNP5 MCNPX capabilities, but it much more than sum these two computer codes. result six years effort by code development teams. These groups people, residing in Los Alamos National Laboratory’s X Computational Physics Division, Monte Carlo Codes Group (XCP-3) Nuclear Engineering Nonproliferation Radiation Transport Modeling Team (NEN-5) respectively, have combined their efforts to produce next evolution MCNP. While maintenance major...
Monitoring issues related to activation and fission processes occur in many health physics, instrumentation equipment design, nuclear forensics, homeland security applications. Gamma radiation that is emitted during these as a result of the radioactive decay reaction by-products [delayed gammas (DGs)] provides unique signatures are useful for interrogation information acquisition. Thus, it compelling interest have simulation tool can be used conduct studies provide insights into processes....
An electronic collimation technique is developed which utilizes the chi-square goodness-of-fit measure to filter scattered gammas incident upon a medical imaging detector. In this data mining technique, Compton kinematic expressions are used as fitting templates for measured energy-deposition involving multiple-interaction scatter sequences. Fit optimization conducted using Davidon variable metric minimization algorithm simultaneously determine best-fit gamma angles and their associated...