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Biomedical subjects

D J Simpkin

Publications and source records attributed to D J Simpkin.

At least 19 recordsLinked to original sources

Radiation protection standards: their evolution from science to philosophy.

The concept of applying constraints on individual sources to a small fraction of the public dose limit has been deemed inappropriate when shielding the medical X-ray sources. This represents a broad-based consensus of medical physics and radiological societies in the United States, and the report series on the shielding design for medical X-ray sources (including dental, X-ray imaging and therapeutic X ray) from the National Council on Radiation Protection and Measurements (NCRP) utilises 1 mSv y(-1) as a source control limit. In the present study, the rationale for such a conclusion is discussed, and a somewhat critical look at the current model of radiation protection of the public is made.

Environmental Exposure↗

Primary shielding barriers for diagnostic x-ray facilities: a new model.

Traditional methods of diagnostic x-ray shielding design assume that the raw primary beam impinges directly on the structural barrier with attenuation by the patient and by the hardware in the x-ray beam (cassette, cassette holder, x-ray table) being ignored. Moreover, primary barrier calculations are done assuming a single, conservatively high value of the operating potential, rather than the lower kVp values more representative of clinical usage. This results in extreme conservatism, which is no longer defensible in light of the lowered dose limit to a member of the general public of 1 mSv y-1, which is equal in magnitude to natural background radiation (excluding radon). A shielding model is developed that accounts for attenuation of the primary beam prior to impinging on the structural barrier and which uses a workload which is distributed over a range of clinically realistic operating potentials. The resulting model is as simple to use as that, assuming a single value of the kVp. Sample calculations are performed and the results compared to those from more traditional shielding calculation methods.

Building Codes↗

Secondary shielding barriers for diagnostic x-ray facilities: scatter and leakage revisited.

Methods are presented for determining the thickness requirements for barriers against scatter and leakage radiation generated in a diagnostic x-ray facility. Equations are developed that express the shielded doses due to scatter and leakage with explicit dependence on the operating potential used in clinical settings. The 1972 scatter experiment of Trout and Kelley is revisited, with suggested values for the scatter fraction that are somewhat different from those used in Report Number 49 of the NCRP. The dose from leakage radiation due to operation at clinical kVp settings is seen to be orders of magnitude below that predicted by the model in NCRP49. The unshielded secondary radiation dose in air at unit distance and workload is presented as a function of operating potential and for clinical workload distributions. The net transmission of secondary radiations through common shielding materials is presented. Compared to that for the primary beam at the same potential, the transmission of secondary radiation is more penetrating due to the inclusion of leakage radiation that has been hardened by the tube housing. Sample shielding calculations illustrate the utility of this scheme.

Health Facility Environment↗

Scatter radiation intensities about mammography units.

The intensity of scattered x rays about two clinically installed mammographic units was measured at 25, 30, and 35 kVp over a range of scattering angles. The scatter-to-primary ratio for backscattering is measured to be 4 to 7 times greater than that for 90 degrees scattering. The scatter fraction is the ratio of scatter dose at 1 m to primary dose at 1 m per primary x-ray field area. Averaged over various phantom and field sizes, the scatter fraction for mammography ranges from 0.01 x 10(-6) cm-2 to 0.2 x 10(-6) cm-2 at 0 degrees, approximately 0.25 x 10(-6) cm-2 at 90 degrees, to 1.7 x 10(-6) cm-2 at 163 degrees, with not more than 30% difference between the scatter intensity generated at 25 and 35 kVp. The differences in the scatter fraction measured off two mammography units from two manufacturers are less than 10% for scattering angles greater than 45 degrees. However, the intensity of forward scatter depends strongly on the construction of the image receptor assembly and x-ray tube collimator, with a sharp rise in the scatter fraction at approximately 25 degrees for the 18 x 24 cm2 image receptor apparently due to scatter off the collimator. The dose (normalized at 1 m per 100 patients) in directions toward adjacent walls, ceiling, and floor is conservatively calculated, providing a quick method for estimating the unshielded dose to an occupied area.

Female↗

Evaluation of NCRP Report No. 49 assumptions on workloads and use factors in diagnostic radiology facilities.

A survey of modern medical institutions has been performed to measure the workload and primary beam use factors used in diagnostic x-ray installations in comparison to those suggested in Report 49 of the NCRP. Seven types of radiology installations were investigated, namely general radiographic rooms, general fluoroscopic and radiographic rooms (fluoroscopic and radiographic tubes surveyed separately), chest radiographic rooms, mammographic suites, and cardiac and peripheral angiographic suites. The radiologic technique (kVp and mAs) for each exposure performed on a total of 2396 patients was recorded either manually or by a commercially-available invasive electronic sensing system. Additionally, the direction of the primary beam during the exposure was recorded. The kVp distribution of the workload data was determined and normalized per patient for each of the seven types of installations. The total average workload per patient surveyed in each type of installation is 2.5, 13, 1.5, 0.22, 6.7, 160, and 64 mA min per patient for the above installation types. For general radiographic rooms the primary beam was directed at the floor for 69% of the total workload, with the remaining 21.5%, 6.5% and 1.6% of the workload directed toward three walls. When multiplied by the average number of patients examined weekly in each type of installation, the mean weekly workloads observed are 270, 230, 35, 44, 320, 3100, and 1400 mA min for the above-listed types of installations. Additionally, a significant fraction of the observed workloads occur at potentials much less than the kVp values typically assumed for radiation shielding.

Biophysical Phenomena↗

Transmission data for shielding diagnostic x-ray facilities.

Recently published exposure transmission curves for broad diagnostic x-ray beams in lead, concrete, gypsum wallboard, steel, plate glass, and wood have been used to calculate the transmission in 5 kVp increments over the 25 to 35 kVp range for molybdenum-anode tubes and 50 to 150 kVp for tungsten-anode tubes. The data are fit to a three parameter model for ease in calculating the x-ray transmission with computers or calculators.

Biophysical Phenomena↗

Shielding requirements for constant-potential diagnostic x-ray beams determined by a Monte Carlo calculation.

A Monte Carlo calculation has been performed to determine the transmission of broad constant-potential x-ray beams through Pb, concrete, gypsum wallboard, steel and plate glass. The EGS4 code system was used with a simple broad-beam geometric model to generate exposure transmission curves for published 70, 100, 120 and 140-kVcp x-ray spectra. These curves are compared to measured three-phase generated x-ray transmission data in the literature and found to be reasonable. For calculation ease the data are fit to an equation previously shown to describe such curves quite well. These calculated transmission data are then used to create three-phase shielding tables for Pb and concrete, as well as other materials not available in Report No. 49 of the NCRP.

Calcium Sulfate↗

A general solution to the shielding of medical x and gamma rays by the NCRP Report No. 49 methods.

A general method for extending the principles and techniques of NCRP Report No. 49 of the National Council on Radiation Protection and Measurements has been developed. Equations are derived that determine the photon exposure through a radiation barrier taking into account the primary, scatter and leakage radiation from multiple radiation sources of various beam qualities. Applications of this include a general solution for medical radiation structural shielding and an analysis of commonly used diagnostic radiology shielding tables.

Gamma Rays↗

Shielding requirements for mammography.

Shielding requirements for mammography installations have been investigated. To apply the methodologies of NCRP Report No. 49, the scatter-to-incident ratio of a typical mammography beam was measured, and the broad beam transmission was calculated for several representative beam spectra. These calculations were found to compare favorably with published low kVp tungsten-targeted x-ray transmission through a variety of shielding materials. Radiation shielding tables were developed from the calculated transmissions through Pb, concrete, gypsum, steel, plate glass, and water, using a technique which eliminates the "add one HVL" rule. It is concluded that Mo-targeted x-ray beams operated at 35 kVp require half the shielding of W-targeted beams operated at 50 kVp, and that adequate, cost-effective shielding calculations will consider alternatives to Pb.

Calcium Sulfate↗

Radiation shielding of multiple x-ray sources in diagnostic radiology.

A unified approach to the problem of barrier thickness calculations for diagnostic x-ray rooms containing multiple x-ray tubes emitting primary, scatter, and leakage radiation is presented. Given the reasonable constraint that all x-ray tubes in a room operate at the same maximum potential (kVp), the required barrier thickness is determined completely and accurately from a single transcendental equation relating the Kux and BLx values calculated for each radiation source separately. A useful approximation to this is discussed and examples given.

Radiation Protection↗

The effect of counting system deadtime on thyroid uptake measurements.

Equations are derived and the results of numerical calculations shown that illustrate the effect of counting system deadtime on measured thyroid uptake of radioiodine. It is predicted that the observed uptake is higher than the true uptake due to system deadtime. This is shown for both paralyzing and nonparalyzing deadtime. The effect of increasing the administered activity is shown to increase the measured uptake, in a manner predicted by the paralyzable and nonparalyzable deadtime models.

Humans↗

EGS4 Monte Carlo determination of the beta dose kernel in water.

The EGS4 Monte Carlo code has been used to simulate the emission and energy deposition in H2O about point sources of monoenergetic electrons and radionuclides of potential use in radioimmunotherapy. The radiations studied were 0.05, 0.1, 0.5, 1.0, 2.0, and 3.0 MeV monoenergetic electrons and 32P, 67Cu, 90Y, 105Rh, 131I, 153Sm, 186Re, and 188Re beta particles and conversion and Auger electrons. Ten batches of 10,000 electrons (or 10,000 radionuclide decays) each were started isotropically at a point in an infinite homogeneous H2O phantom. The parameter-reduced electron-step transport algorithm (PRESTA) version of the EGS4 Monte Carlo code was used to follow these and their progeny, scoring the energy deposited in thin spherical shells. The scaled dose kernels are calculated and compared to kernels available in the literature. These previously published kernels either completely ignore secondary electrons or are based on a Monte Carlo code which improperly sampled the Landau energy straggling distribution.

Beta Particles↗

The spatial and energy dependence of bremsstrahlung production about beta point sources in H2O.

A Monte Carlo simulation was performed to characterize the spatial and energy distribution of bremsstrahlung radiation from beta point sources important to radioimmunotherapy (RIT). Using the EGS4 Monte Carlo code, the isotropic emission and transport of monoenergetic 0.1-, 0.5-, 1.0-, 2.0-, and 3.0-MeV electrons and 32P and 90Y beta particles was simulated in an infinite, homogeneous H2O phantom. The probability of bremsstrahlung production for each Monte Carlo-simulated electron step was accumulated in energy intervals not exceeding 5 keV and stored as a function of radial position. To validate this scheme, the EGS4 code was tested in the continuous slowing down approximation (csda) mode, with resulting radiation yields seen to agree with values in ICRU Report No. 37 (ICRU, Bethesda, MD, 1984) to better than 1.6%. The radiation yield calculated with the simulation of secondary particles is seen to be 3%-5% greater than the csda yield. The photon energy distributions are characterized by a typically broad bremsstrahlung spectrum with the probability of photon generation decreasing with radial distance. In the energy range 0.05-0.511 MeV, the probability for bremsstrahlung production from 90Y (2.76 x 10(-2) decay-1) is twice that from 32P (1.35 x 10(-2) decay-1). When passed through 10 cm of H2O and put upon a standard NaI scintillation camera, count rates of 2.3 x 10(-6) and 1.2 x 10(-6) counts s-1 Bq-1 are estimated from point sources of 90Y and 32P. These results predict the inherent spatial resolution limitation and provide the initial data required for modeling and analyzing the scatter, attenuation, and image formation processes in quantitative imaging of bremsstrahlung for RIT dosimetry.

Humans↗