A5102854012- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Radiation Detection and Scintillator Technologies
- Graphite, nuclear technology, radiation studies
- Radioactive contamination and transfer
- Radioactive element chemistry and processing
- Radioactivity and Radon Measurements
- Nuclear Issues and Defense
- Risk and Safety Analysis
- Classical Philosophy and Thought
- Infrastructure Resilience and Vulnerability Analysis
- Nuclear physics research studies
- Particle Detector Development and Performance
- Isotope Analysis in Ecology
- Radioactive Decay and Measurement Techniques
- Radiation Effects in Electronics
- Fusion materials and technologies
- Theology and Philosophy of Evil
- Heat transfer and supercritical fluids
- Nuclear Engineering Thermal-Hydraulics
- Graphene research and applications
- Ion-surface interactions and analysis
- Military Strategy and Technology
The University of Texas at Austin
2001-2025
Los Alamos National Laboratory
1999-2022
Sandia National Laboratories California
2020-2022
Walker (United States)
2019
Compact Membrane Systems (United States)
2019
National Strategic Research Institute
2016
University of Nebraska–Lincoln
2016
Texas A&M University
2005-2015
Mitchell Institute
2005-2015
University of California, Berkeley
1999
SOURCES is a computer code that determines neutron production rates and spectra from (α,n) reactions, spontaneous fission delayed emission owing to the decay of radionuclides in homogeneous media, interface problems three-region problems. The also capable calculating due reactions induced by monoenergetic beam alpha particles incident on slab target material. are calculated using an assumed isotropic angular distribution centre-of-mass system with library 107 nuclide alpha-particle spectra,...
A methodology, based on the multiattribute utility analysis, for assessment of diverse fuel cycles proliferation resistance was developed. This methodology is intended to allow effectiveness safeguards implementation at facilities within a large-scale cycle and ability choose technologies in part their deter nuclear materials. Fuel under consideration include reactors, reprocessing facilities, storage enrichment plants, fabrication uranium conversion mining milling operations. The method...
The preliminary results from a series of nuclear fluorescence imaging experiments using variety radioactive sources and shielding are given. These were done as part proof concept to determine if could be used safeguards measurements tool or for warhead verification arms control treaties such the New Strategic Arms Reduction Treaty Fissile Material Cut-Off Treaty. An off-the-shelf Princeton Instruments charged coupled device camera system was image emission photons de-excitation nitrogen...
A new nondestructive assay technique called self-interrogation neutron resonance densitometry (SINRD) is currently being developed at Los Alamos National Laboratory to improve existing nuclear safeguards and material accountability measurements for light water reactor fuel assemblies. The viability of using SINRD the detection possible diversion scenarios pressurized 17 × spent low-enriched uranium (LEU) mixed oxide (MOX) assemblies was investigated via Monte Carlo N-Particle eXtended...
We report the preparation of surfactant-assisted carbon nanotube dispersions using gum arabic, Triton X-100, and graphene oxide as dispersing agents for removing rare earth elements in an aqueous solution. The analytical tools, including (a) scanning electron microscopy (b) neutron activation analysis, were utilized qualitative quantitative examinations, respectively. Neutron analysis was employed to quantitatively determine percent extraction nuclides onto structure, while images produced...
A new nondestructive assay technique called self-interrogation neutron resonance densitometry (SINRD) is currently being developed at Los Alamos National Laboratory to improve existing nuclear safeguards and material accountability measurements for light water reactor fuel assemblies. The viability of using SINRD quantify the fissile content (235U 239Pu) in pressurized 17 × spent low-enriched uranium mixed-oxide assemblies was investigated via Monte Carlo N-particle extended transport code...
Atomic-level defects dictate the mechanical properties of carbon fibers and strong correlations have been established between crystallite sizes properties. We recently demonstrated similar with hydrogen content, but reliably quantifying content is not possible using only inelastic neutron scattering experiments. Here, we present prompt-gamma activation analysis (PGAA) experiments collected on 20 commercially available to quantify find fiber modulus content. then evaluate role defect type...
The Los Alamos National Laboratory (LANL) has developed a system for determining 237Np, 241Am, and 243Am concentrations in spent fuel from measurements of the 240Pu/239Pu isotopic ratio using calculations performed with HELIOS lattice-physics code. Benchmark several pressurized water reactors (PWRs) were compared to measured values literature fuels burnups ranging 0 50 000 MWd/tonne U. A direct correlation can be found between higher-actinide each type. Comparisons calculated suggests that...
AbstractWork performed in part for an American Nuclear Society Standards Committee Subgroup (ANS 19.9) to assess the status of delayed neutron data is summarized. Recent measurements emission conducted at Texas A&M University are also described. During last 10 yr, there have been advances nuclear libraries (e.g., improved fission product yields) that make it possible quantitatively predict from basic data. The six-group available literature both macroscopic level experiments and microscopic...
The use of light-weight, high-strength composite materials in motors, generators, and energy storage devices has become common as a means to maximize density. To ensure reliability, non-destructive destructive evaluation techniques have been employed measure the mechanical properties fabricated components. In carbon fiber-reinforced, polymer matrix composites, strength is primarily derived from fiber volume fraction. Due lack nondestructive method, for determination are currently...