Jeremy Sweezy

ORCID: 0000-0003-4847-470X
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About
Contact & Profiles
Research Areas
  • Nuclear Physics and Applications
  • Nuclear reactor physics and engineering
  • Graphite, nuclear technology, radiation studies
  • Radiation Detection and Scintillator Technologies
  • Radiation Therapy and Dosimetry
  • Nuclear and radioactivity studies
  • Nuclear Materials and Properties
  • Particle Detector Development and Performance
  • Probabilistic and Robust Engineering Design
  • Atomic and Subatomic Physics Research
  • Electron and X-Ray Spectroscopy Techniques
  • Boron Compounds in Chemistry
  • Medical Imaging Techniques and Applications
  • Risk and Safety Analysis
  • Solar Radiation and Photovoltaics
  • Nuclear Engineering Thermal-Hydraulics
  • Scientific Measurement and Uncertainty Evaluation
  • Advanced X-ray and CT Imaging
  • Earthquake Detection and Analysis
  • Statistical and numerical algorithms
  • Scientific Research and Discoveries
  • Advanced Multi-Objective Optimization Algorithms
  • Embedded Systems Design Techniques
  • Simulation Techniques and Applications
  • Cold Fusion and Nuclear Reactions

Los Alamos National Laboratory
2014-2024

Jeremy Benn Associates (United Kingdom)
2004

Georgia Institute of Technology
2002

Atlanta Technical College
2002

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...

10.13182/nt11-135 article EN Nuclear Technology 2012-12-01

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...

10.1051/epjn/2025003 article EN cc-by EPJ Nuclear Sciences & Technologies 2025-01-01

10.1016/s0168-9002(01)01466-8 article EN Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment 2002-01-01

In order to reduce the user's time and computer needed solve deep penetration problems, an automated variance reduction capability has been developed for MCNP Monte Carlo transport code. This new MCNP5 employs PARTISN multigroup discrete ordinates code generate mesh-based weight windows. The technique of using deterministic methods importance maps widely used increase efficiency calculations. application this method in uses existing window feature translate geometry into suitable PARTISN....

10.1093/rpd/nci257 article EN Radiation Protection Dosimetry 2005-12-20

Journal Article Performance of Multisphere Spectrometry Systems Get access J.E. Sweezy, Sweezy Search for other works by this author on: Oxford Academic PubMed Google Scholar N.E. Hertel, Hertel K.G. Veinot, Veinot R.A. Karam Radiation Protection Dosimetry, Volume 78, Issue 4, 1 August 1998, Pages 263–272, https://doi.org/10.1093/oxfordjournals.rpd.a032359 Published: 01 1998

10.1093/oxfordjournals.rpd.a032359 article EN Radiation Protection Dosimetry 1998-08-02

The developmental version of MCNP5 has recently been extended to provide for continuous-energy transport high-energy protons. This enhancement involves the incorporation several significant new physics models into code. Multiple Coulomb scattering is treated with an advanced model that takes account projectile and nuclear target form factors. In next version, this will a coupled sampling both angular deflection collisional energy loss, including straggling. proton elastic also new, based on...

10.1093/rpd/nci109 article EN Radiation Protection Dosimetry 2005-12-20

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...

10.1051/snamc/201406011 article EN 2014-01-01

10.1016/j.jcp.2018.06.032 article EN publisher-specific-oa Journal of Computational Physics 2018-08-16

A general particle population control method has been derived from splitting and Russian Roulette for dynamic Monte Carlo transport. well-known method, known as the comb, shown to be a special case of this method. This incorporated in Los Alamos National Laboratory’s Application Toolkit (MCATK) examples it’s use are both super-critical sub-critical systems.

10.1051/snamc/201403202 article EN 2014-01-01

A variety of methods employing radiation transport and point-kernel codes have been used to model two skyshine problems. The first problem is a 1 MeV point source photons on the surface earth inside 2 m tall radius silo having black walls. downfield from was estimated with without 30-cm-thick concrete lid silo. second benchmark estimate 12 cylindrical canisters emplaced in low-level radioactive waste trench. are filled ion-exchange resin representative radionuclide loading, largely 60Co,...

10.1093/rpd/nci274 article EN Radiation Protection Dosimetry 2005-12-20

Photoneutron spectral measurements in the vicinity of a high energy medical accelerator have been performed. A LiI (Eu) scintillator and paired thermoluminescent dosimeters were used conjunction with moderating multispheres to measure neutron spectra. The photoneutron fluence rate, lethargy, average energy, quality factors calculated using recursive unfolding algorithm. dose rates equivalent received by patient operators due these neutrons estimated from unfolded Doses predicted...

10.1097/00004032-199809000-00007 article EN Health Physics 1998-09-01

The Monte Carlo Application Toolkit (MCATK) provides solution options for problems with time varying properties in mesh geometries and simple solid bodies. paper describes the toolkit’s mechanism handling focusing on managing particle population. included results show robustness of this approach systems degrees criticality without user intervention.

10.1051/snamc/201403203 article EN 2014-01-01

The combination of fast neutron therapy and boron capture is currently being studied as a possible treatment for some radio-resistant brain tumours. In an attempt to design boron-enhanced beam the Fermilab Fast Neutron Therapy Facility, use moderating material surrounding patient's head has been investigated. Graphite, polyethylene, water heavy were materials, using MCNP. tungsten, iron, lead bismuth materials small filter collimator near was Calculations showed that made tungsten with...

10.1093/rpd/nci256 article EN Radiation Protection Dosimetry 2005-12-20
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