A5061184910- Nuclear Physics and Applications
- Radiation Therapy and Dosimetry
- Nuclear reactor physics and engineering
- Radiation Dose and Imaging
- Radiation Detection and Scintillator Technologies
- Advanced Radiotherapy Techniques
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Radioactivity and Radon Measurements
- Radioactive contamination and transfer
- Fusion materials and technologies
- Atomic and Subatomic Physics Research
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- ZnO doping and properties
- Advanced X-ray and CT Imaging
- Ga2O3 and related materials
- Radiation Shielding Materials Analysis
- Advances in Oncology and Radiotherapy
- Laser-Plasma Interactions and Diagnostics
- Medical Imaging Techniques and Applications
- Health, Environment, Cognitive Aging
- Luminescence Properties of Advanced Materials
- Radioactive element chemistry and processing
- Advanced Semiconductor Detectors and Materials
Georgia Institute of Technology
2015-2024
Oak Ridge National Laboratory
2015-2024
State Street (United States)
2016-2022
United States Military Academy
2020
United States Nuclear Regulatory Commission
2015
University of Florida
2010-2012
North Carolina State University
2010
University of Tennessee at Knoxville
2010
University of South Carolina
2010
Southeast University
2010
PREFACE MAIN POINTS EXECUTIVE SUMMARY 1. INTRODUCTION 2. Quantities used in radiation protection for external exposure 3. Determination of organ absorbed doses OF the ICRP/ICRU REFERENCE phantomS 4. Conversion coefficients 5. Relationships between dose conversion For operational and quantities References Annex A - Effective B Organ photons C neutrons D Skeletal fluence-to-dose response functions Photons E Neutrons F eye lens G Special considerations assessing local skin equivalent H superior...
Abstract Composites made with boron might be absorbers of low energy neutrons, and could used for structural materials spacecraft. Polyethylene/boron nitride composites were fabricated using conventional polymer processing techniques, evaluated mechanical radiation shielding properties. The powder surfaces also functionalized to improve interfacial adhesion. Addition neat an injection molding grade HDPE increased the tensile modulus from 588 735 MPa 15 vol % filler. bonding a trifunctional...
Effective doses were calculated from the delivery of , and conventional intensity‐modulated radiation therapy (IMRT) prostate treatment plans. ICRP‐60 tissue weighting factors used for calculations. Photon measured in phantom all beam energies. Neutron spectra ICRP‐74 quality conversion to calculate ambient dose equivalents. The equivalents corrected each using neutron depth data literature. then as a measure component ICRP protection quantity, organ equivalent dose. IMRT resulted an...
Neutrons are a by‐product of high‐energy x‐ray radiation therapy (threshold for reactions in high‐ material ). Neutron production varies depending on photon beam energy as well the manufacturer accelerator. from modern linear accelerators (linacs) has not been extensively compared, particularly terms differences strategies that various manufacturers have used to implement multileaf collimators (MLCs) into their linac designs. However, such information is necessary determine neutron dose...
Secondary neutron doses from the delivery of conventional and intensity modulated radiation therapy (IMRT) treatment plans were compared. IMRT was delivered using dynamic multileaf collimation (MLC). Additional measurements made with static MLC a primary collimated field size sizes , . Neutron spectra measured effective calculated. The resulted in higher fluence dose equivalent. These increases approximately ratio monitor units. compared to Monte Carlo calculations. actual component...
The study of One Million U.S. Radiation Workers and Veterans, the Person Study (MPS), examines health consequences, both cancer non-cancer, exposure to ionizing radiation received gradually over time. Recently MPS has focused on mortality patterns from neurological behavioral conditions, e.g., Parkinson's disease, Alzheimer's dementia, motor neuron disease such as amyotrophic lateral sclerosis. A fuller picture radiation-related late effects comes studying occurrence (incidence) conditions...
Multifunctional composites made with boron are absorbers of low energy nuetrons, and could be used for structural shielding materials. Polyethylene/boron carbide were fabricated using conventional polymer processing techniques, evaluated mechanical radiation properties. Addition neat (powder nanoparticles) to an injection molding grade HPDE showed superior properties compared HDPE. Radiation measurements a 2 wt% composite improved over those the polyethylene.
A computer study of the dose distribution for gadolinium neutron capture therapy is carried out to determine its feasibility. Gadolinium a potential (NCT) agent that produces gamma radiation, conversion electrons, and Auger electrons. The from neutrons, neutron-induced gammas, reaction products in were modeled using Los Alamos National Laboratory Monte Carlo photon code. results these calculations are has promise as an NCT agent. Using two parallel opposed epithermal beams tumor at 8.0-cm...
Journal Article Measurements of secondary neutron dose from 15 MV and 18 IMRT Get access Rebecca M. Howell, Howell *Corresponding author: Rebecca@radonc.emory.org Search for other works by this author on: Oxford Academic PubMed Google Scholar Michele S. Ferenci, Ferenci Nolan E. Hertel, Hertel Gary D. Fullerton, Fullerton Timothy Fox, Fox Lawrence W. Davis Radiation Protection Dosimetry, Volume 115, Issue 1-4, 20 December 2005, Pages 508–512, https://doi.org/10.1093/rpd/nci041 Published: 2005
Report Committee 26 of the ICRU proposes a set operational quantities for radiation protection external radiation, directly based on effective dose and an extended range particles energies. It is accompanied by estimating deterministic effects to eye lens local skin. The are designed overcome conceptual technical shortcomings those presently in use. This paper describes proposed quantities, highlights improvements with respect present, legal monitoring quantities.
The personal dose equivalent, H(p)(d), is the quantity recommended by International Commission on Radiation Units and Measurements (ICRU) to be used as an approximation of protection effective when performing dosemeter calibrations. equivalent can defined for any location depth within body. Typically, interest trunk, where dosemeters are usually worn, in this instance a suitable 30 × 15 cm(3) slab-type phantom. For condition, denoted H(p,slab)(d) depths, d, taken 0.007 cm non-penetrating 1...
ICRP Publication 116 on 'Conversion coefficients for radiological protection quantities external radiation exposures', provides fluence-to-dose conversion organ-absorbed doses and effective dose various types of exposures (ICRP 2010 116). The publication supersedes the 74 1996 74, ICRU 1998 Report 57), including new particle expanding energy ranges considered. were calculated using ICRP/ICRU computational phantoms 2009 110) representing reference adult male female 2002 89), together with a...
As part of a broader effort to calculate effective dose rate coefficients for external exposure photons and electrons emitted by radionuclides distributed in air, soil or water, age-specific stylized phantoms have been employed determine relating organs tissues the body. In this article, computed using International Commission on Radiological Protection reference adult male voxel phantom are compared with values Oak Ridge National Laboratory an air submersion geometry. Monte Carlo...
The Oak Ridge National Laboratory Center for Radiation Protection Knowledge (CRPK) has undertaken a number of calculations in support revision to the United States Environmental Agency (US EPA) Federal Guidance Report on external exposure radionuclides air, water and soil (FGR 12). Age-specific mathematical phantom were performed conditions submersion radioactive air immersion water. Dose rate coefficients calculated discrete photon electron energies folded with emissions from 1252 using...
The normalized $^{238}$U(n,f)/$^{235}$U(n,f) cross section ratio has been measured using the NIFFTE fission Time Projection Chamber from reaction threshold to $30$~MeV. fissionTPC is a two-volume MICROMEGAS time projection chamber that allows for full three-dimensional reconstruction of fission-fragment ionization profiles neutron-induced fission. measurement was performed at Los Alamos Neutron Science Center, where neutron energy determined time-of-flight. reported here first made with...
One of the largest sources data on radiation exposure in humans is study atomic bomb survivors at Hiroshima and Nagasaki, Japan performed by Radiation Effects Research Foundation (RERF). As part their retrospective dosimetry efforts for survivors, RERF published two core systems: Dosimetry System 1986 (DS86) 2002 (DS02). Due to computing limitations time, only three stylized phantoms (an infant, child adult) were used DS86 DS02 represent entire Japanese population. In this study, we sought...
Purpose: Estimated dose rates that may result from exposure to patients who had been administered iodine‐131 ( 131 I) as part of medical therapy were calculated. These effective rate estimates compared with simplified assumptions under United States Nuclear Regulatory Commission Guide 8.39, which does not consider body tissue attenuation nor time‐dependent redistribution and excretion the I. Methods: Dose estimated for members public potentially exposed external irradiation recently treated...
Using the Monte Carlo code MCNP4A, a response matrix for multisphere spectrometer using TLD-600 as thermal neutron detector, has been calculated bare detector and 2, 3, 5, 8, 10 12 inch diameter moderating spheres. The TLD was modelled ribbon type TLD. Response calculations were carried out at 20 energies from to MeV. A 49 25 different sphere diameters obtained by interpolation of responses. responses compared with Mares Schraube's 6 LiI(Eu) scintillator-based system. present have same shape...
Abstract In this work neutron‐sensitive scintillators based on GaN have been produced by MOCVD. The consist of GaNepilayers grown 2 inch double side polished sapphire wafers, with neutron conversion layers top. Two materials were investigated: enriched LiF and Gd. Undoped silicon‐doped epilayers examined for their scintillation properties. All the showed response when exposed to a thermalized AmBesource, however peak which is more easily discriminated from gamma photomultiplier tube....
In June 2006, the Radiation Studies Branch of Centers for Disease Control and Prevention held a workshop to explore rapid methods facilitating radiological triage large numbers potentially contaminated individuals following detonation dispersal device. Two options were discussed. The first was use traditional gamma cameras in nuclear medicine departments operated as makeshift whole-body counters. Guidance on this approach is currently available from CDC. This would be feasible if manageable...