SEARCH · Search PubMed

Results for “Beta Particles”

Search indexed PubMed citations on genomics, clinical trials, systematic reviews and public health. Explore titles, authors and supplied subject terms, then open the PubMed record.

SourceResearch connectionFrom yearThrough year

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 271 records · Page 15Linked to original sources

PubMed2007

Beta radiation shielding with lead and plastic: effect on bremsstrahlung radiation when switching the shielding order.

Lead and plastic are commonly used to shield beta radiation. Radiation protection literature is ubiquitous in advising the placement of plastic first to absorb all the beta particles before any lead shielding is used. This advice is based on the well established theory that radiative losses (bremsstrahlung production) are more prevalent in higher atomic number (Z) materials than in low Z materials. Using 32P beta radiation, we measured bremsstrahlung photons transmitted through lead and plastic (Lucite) shielding in different test configurations to determine the relative efficacy of lead alone, plastic alone, and the positional order of lead and plastic. With the source (32P) and detector held at a constant separation distance, we inserted lead and/or plastic absorbers and measured the reduction in bremsstrahlung radiation level measured by the detector. With these test conditions, analysis of measured bremsstrahlung radiation in various thicknesses and configurations of lead and plastic shielding shows the following: placing plastic first vs. lead first reduces the transmitted radiation level only marginally (10% to 40%); 2 mm of additional lead is sufficient to correct the "mistake" of placing the lead first; and for equal thicknesses or weights of lead and plastic, lead is a more efficient radiation shield than plastic.

Beta Particles↗

PubMed2004

Genotoxic and cytotoxic effects of 60Co gamma-rays and 90Sr/90Y beta-rays on Chinese hamster ovary cells (CHO-K1).

Among various types of ionizing radiation, the beta emitter radionuclides are involved in many sectors of human activity, such as nuclear medicine, nuclear industries and biomedicine, with a consequently increased risk of accidental, occupational or therapeutic exposure. Despite their recognized importance, there is little information about the effect of beta particles at the cellular level when compared to other types of ionizing radiation. Thus, the objective of the present study was to evaluate the genotoxic and cytotoxic effects of (90)Sr/(90)Y-a pure, highly energetic beta source-on Chinese hamster ovary (CHO) cells and to compare them with data obtained with (60)Co. CHO cells irradiated with different doses of (60)Co (0.34 Gy min(-1)) and (90)Sr/(90)Y (0.23 Gy min(-1)) were processed for analysis of clonogenic death, induction of micronuclei (MN) and interphase death. The survival curves obtained for both types of radiation were fitted by the exponential quadratic model and were found to be similar. Also, the cytogenetic results showed similar frequencies of radio-induced MN between gamma and beta radiations and the MN distribution pattern among cells did not follow the expected Poisson probability pattern. The relative variance values were significantly higher in cells irradiated with (90)Sr/(90)Y than with (60)Co in all exposure doses. The irradiated cells showed more necrotic cells 72 h and 96 h after exposure to beta than to gamma radiation. In general, the (90)Sr/(90)Y beta-radiation was more damaging than (60)Co gamma-rays. The data obtained also demonstrated the need to use several parameters for a better estimate of cellular sensitivity to the action of genotoxic agents, which would be important in terms of radiobiology, oncology and therapeutics.

Animals↗

PubMed1991

The curability of tumours of differing size by targeted radiotherapy using 131I or 90Y.

A mathematical model has been used to investigate the relationship of curability to tumour size and cell number for spherical tumours treated with targeted 131I or 90Y, assuming uniform uptake of radionuclide throughout the tumour. The analysis shows that, for any given cumulated activity per unit mass of tumour, cure probability is greatest for tumours whose diameter is close to an optimum value which depends on the path length of the emitted beta-particle. Smaller tumours are less curable because of inefficient absorption of radiation energy, and larger tumours are less curable because of greater clonogenic cell number. The lesser curability of very small tumours is a feature of targeted radiotherapy using long-range beta-emitters which does not occur with external beam irradiation. The predicted inefficiency of sterilisation of microscopic tumours poses a problem for targeted radiotherapy which is analogous to "geographic miss" in conventional radiotherapy. The implication is that small micro-metastases could escape sterilisation by radionuclides administered at activity levels sufficient to eradicate larger tumours. It is suggested that single agent targeted radiotherapy should not be used for treatment of disseminated malignancy when multiple tumours of differing size, including micrometastases, may be present. The analysis implies that an advantage might result from the use of a panel of several radionuclides (including short-range emitters) or from combining targeted radiotherapy using long-range beta-emitters with external beam irradiation or some other modality to which microscopic tumours are preferentially vulnerable.

Beta Particles↗

PubMed2004

Absorbed dose distribution in glioma tumors in rat brain after therapeutic intratumoral injection of 201Tl-chloride.

Studies on animals with gliomas inoculated in the brain and treated with intratumoral injections of 201Tl-chloride have previously shown very promising results, with a survival several weeks longer than controls. Total regression was found in some animals, and necrosis was found in all the 201Tl-treated brain tumors. This study was undertaken to estimate the absorbed dose and dose distribution to the tumor based on the localization and clearance properties obtained from images with two high-resolution imaging techniques; pinhole single photon emission computed tomography (SPECT) and beta-camera. The images from the beta-camera were used to calculate the absorbed dose rate, using an in-house-developed, voxel-based Monte Carlo program, based on the EGS4 package. To evaluate the effects of different beta-particle energies on the absorbed dose rate distribution, simulations of medium- and high-energy electrons were conducted. Dose-volume histograms from these simulations show that the energy absorption is very locally distributed for 201Tl and medium energy, whereas high-energy beta emitters show a broader dose-volume distribution. The calculated total absorbed dose of 2-8 Gy in the tumor seems to be relativity low when considering the therapeutic effect that was seen. Further investigations, to determine the cause of the high therapeutic efficacy, are needed.

Animals↗

PubMed2001

Beta versus gamma dosimetry close to Ir-192 brachytherapy sources.

The relative importance of the dose rate component owing to the beta spectrum emitted by 192Ir brachytherapy sources at the short radial distances of interest in intravascular and endobronchial applications is investigated. Separate dosimetric calculations, using Monte Carlo simulations, were performed for the gamma and beta dose rate components of an 192Ir ideal point source as well as real 192Ir source designs used in clinical practice including wire and seed sources and both Nucletron and Varian, old and new, high dose rate (HDR) source designs. A significant dose rate enhancement due to the beta spectrum emitted by 192Ir, greater than 50% for radial distances r<2 mm, was observed for an ideal point source. For real source designs, however, the magnitude of this enhancement was found to depend strongly on the sources' geometric as well as compositional details of the active core and encapsulation. A detectable effect was found for the majority of the investigated sources at radial distances less than 1 mm, but overall findings suggest that the contribution of beta particles is not significant in 192Ir clinical intravascular applications that are currently carried out. However, since treatment of vessels with smaller diameters, in the future, may lead to the development of 192Ir sources and catheters of reduced diameters, the potential effect of the beta spectrum in terms of dose enhancement to tissues in close proximity to 192Ir sources should not be ignored.

Beta Particles↗

PubMed1990

Simulation of angular and energy distributions of the PTB beta secondary standard.

Calculations and measurements have been performed to assess radiation doses delivered by the PTB Secondary Standard that employs 147Pm, 204Tl, and 90Sr:90Y sources in prescribed geometries, and features "beam-flattening" filters to assure uniformity of delivered doses within a 5-cm radius of the axis from source to detector plane. Three-dimensional, coupled, electron-photon Monte Carlo calculations, accounting for transmission through the source encapsulation and backscattering from the source mounting, led to energy spectra and angular distributions of electrons penetrating the source encapsulation that were used in the representation of pseudo sources of electrons for subsequent transport through the atmosphere, filters, and detectors. Calculations were supplemented by measurements made using bare LiF TLD chips on a thick polymethyl methacrylate phantom. Measurements using the 204Tl and 90Sr:90Y sources revealed that, even in the absence of the beam-flattening filters, delivered dose rates were very uniform radially. Dosimeter response functions (TLD:skin dose ratios) were calculated and confirmed experimentally for all three beta-particle sources and for bare LiF TLDs ranging in mass thickness from 10 to 235 mg cm-2.

Beta Particles↗

PubMed2001

Calculation of beta-ray dose distributions from ophthalmic applicators and comparison with measurements in a model eye.

Dose distributions throughout the eye, from three types of beta-ray ophthalmic applicators, were calculated using the EGS4, ACCEPT 3.0, and other Monte Carlo codes. The applicators were those for which doses were measured in a recent international intercomparison [Med. Phys. 28, 1373 (2001)], planar applicators of 106Ru-106Rh and 90Sr-90Y and a concave 106Ru-106Rh applicator. The main purpose was to compare the results of the various codes with average experimental values. For the planar applicators, calculated and measured doses on the source axis agreed within the experimental errors (<10%) to a depth of 7 mm for 106Ru-106Rh and 5 mm for 90Sr-90Y. At greater distances the measured values are larger than those calculated. For the concave 106Ru-106Rh applicator, there was poor agreement among available calculations and only those calculated by ACCEPT 3.0 agreed with measured values. In the past, attempts have been made to derive such dose distributions simply, by integrating the appropriate point-source dose function over the source. Here, we investigated the accuracy of this procedure for encapsulated sources, by comparing such results with values calculated by Monte Carlo. An attempt was made to allow for the effects of the silver source window but no corrections were made for scattering from the source backing. In these circumstances, at 6 mm depth, the difference in the results of the two calculations was 14%-18% for a planar 106Ru-l06Rh applicator and up to 30% for the concave applicator. It becomes worse at greater depths. These errors are probably caused mainly by differences between the spectrum of beta particles transmitted by the silver window and those transmitted by a thickness of water having the same attenuation properties.

Beta Particles↗

PubMed1998

National radioactivity standards for beta-emitting radionuclides used in intravascular brachytherapy.

The uses of beta-particle emitting radionuclides in therapeutic medicine are rapidly expanding. To ensure the accurate assays of these nuclides prior to administration, radioactivity standards are needed. The National Institute of Standards and Technology (NIST), the national metrological standards laboratory for the United States, uses high-efficiency liquid scintillation counting to standardize solutions of such beta emitters, including 32P, 90Sr/90Y, and 188Re. Additional measurements are made on radionuclidic impurities, half lives, and other decay-scheme parameters (such as branching decay ratios or gamma-ray abundances) using HPGe detectors and reentrant ionization chambers. Following such measurements at NIST, standards are disseminated in three ways: Standard Reference Materials (SRMs), calibrations for source manufacturers, and calibration factors for commercial instruments. Uncertainties in the activity calibrations for these nuclides are of the order of +/-0.5% (at approximately 1-standard deviation confidence intervals).

Academies and Institutes↗

PubMed1985

Lyoluminescence response of irradiated saccharides to radiation quality effects.

Lyoluminescence sensitivity of five different saccharide powders to electron irradiation has been determined using luminol solution as a solvent. Effect of electron energy variation in the range of 5-20 MeV on the lyoluminescence yield has been measured. The light conversion efficiencies of different saccharides irradiated with x-rays, beta-particles, gamma-rays, fast electrons, 170-MeV/c pi(-)-mesons and 8-MeV neutrons have been calculated. Factors affecting light conversion efficiency, sensitivity and accuracy of measurements are discussed.

Beta Particles↗

PubMed1977

Ultrastructure of the different fibre types in axial muscles of the sharks Etmopterus spinax and Galeus melastomus.

Red, intermediate and white axial muscle fibres of the sharks Etmopterus spinax and Galeus melastomus were studied by electron microscopy and morphometry. The mitochondrial content is more than thirty percent in red, less than one percent in white, and up to fifteen percent in intermediate fibres. About one third of the mitochondria in red fibres are accumulated close to the sarcolemma. Red fibres contain much glycogen, present as rosettes (alpha particles). Intermediate fibres contain less glycogen (as beta particles). White fibres have scarcely any visible energy reserves. Red fibres contain slightly less (4-5%) of the sarcotubular system than the other fibre types (6-8%). In all fibre types, the terminal cisternae of the SR are regularly divided by clefts. Triads or dyads are generally positioned at the Z discs, but in Galeus white fibres two dyads may be present, one on each side of the Z disc. The morphology is discussed in relation to current views on the functions of different muscle fibre types.

Animals↗

PubMed1979

Sources of Atomic and Nuclear Data for Biomedical Purposes.

Users of nuclear and atomic data for biomedical purposes often have difficulty in identifying the most up-to-date and appropriate sources of such data. The biomedical Subcommittee of the UK Nuclear Data Committee have prepared a list of recommended data sources available at the beginning of 1978 on radioactive decay schemes; neutron cross-sections and data for neutron activation analysis; excitation functions for the production of radionuclides by charged particles; W-values for neutron and electron dosimetry; X- and gamma-ray cross-sections; stopping powers and ranges for charged particles; and dose deposition by electrons and beta particles.

Alpha Particles↗

PubMed1999

Environmental radon daughters reveal pathognomonic changes in the brain proteins and lipids in patients with Alzheimer's disease and Parkinson's disease, and cigarette smokers.

This paper presents an investigation of the retention of environmental radon daughters, 210Po (alpha particle emitting radio-nuclide) and 210Bi (beta particle emitting radio-nuclide), in lipid and protein fractions of the cortical grey and subcortical white matter from the frontal and temporal brain lobes of patients who had suffered from Alzheimer's disease or Parkinson's disease, of cigarette smokers, and of control subjects. 210Po and 210Bi radioactivity increased tenfold in the cortical grey and subcortical white protein fraction in patients with Alzheimer's disease and smokers, and tenfold in the cortical grey and subcortical white lipid fraction in patients with Parkinson's disease. Free radicals generated by radon daughters may add to the severity of the radio-chemical injury to the brain astrocytes. The pathognomonic distribution of radon daughters to lipids in patients with Parkinson's disease and to proteins in patients with Alzheimer's disease was attributed to high chlorine affinity of radon daughters. The changes in the membrane protein pores, channels, and gates in patients with Alzheimer's disease and in the lipid bilayer in patients with Parkinson's disease are at the core of what the authors think are two systemic brain diseases.

Aged↗

PubMed1998

A mouse bone marrow dosimetry model.

UNLABELLED: Bone marrow is the primary dose-limiting organ in radioimmunotherapy. Athymic nude mouse models are used to guide radioimmunotherapy in humans. In the mouse, the dimensions of the marrow are comparable to the mean range of the beta particles for a wide variety of beta-emitting radionuclides, so local beta energy deposition cannot be assumed. METHODS: We have developed a computer simulation model in which slab, spherical and cylindrical geometries of the bone marrow of the mouse were incorporated. The energy deposition within the marrow was estimated using beta dose point kernels for several beta-emitting radionuclides. RESULTS: The calculated percentages of energy deposited in the mouse marrow using the full geometry were 46%, 24% and 10% for 131I-, 186Re- and 90Y-radiolabeled antibodies, respectively. Assuming a concentration of activity in the marrow of 0.36 times the blood activity concentration, the percentages of energy deposition in the marrow from marrow and whole-body sources were 61%, 40% and 29% for 131I, 186Re and 90Y, respectively. CONCLUSION: This work shows that, even for the lower mean beta energy-emitting radionuclide, such as 131I, accurate computation of the mouse bone marrow dose involves including both the energy loss from beta decays within the marrow and dose contributions from tissue surrounding the marrow.

Animals↗

PubMedDate not supplied

Radiation safety requirements for cardiovascular brachytherapy.

Cardiovascular brachytherapy, the use of high intensity radiation to inhibit the growth of neointimal tissue after coronary revascularization by either balloon angioplasty or other methods is being tested in a number of clinical trials to assess the efficacy of the treatment. This new use of radiation to aleviate the suffering of individuals with coronary artery disease has excited many interventionalists and has caused others to view the new technique with skepticism. There are a number of operational and safety concerns to face in incorporating this treatment modality into the cardiac catheterization laboratory. Delivering the radiation dose to the patient with a minimum of radiation exposure to both patient and operating personnel requires close attention to the physical characteristics of the radiation source as well as the administrative and regulatory requirements imposed on the facility by federal and state regulators. The insertion of the source into the proper artery and location is the task of the cardiologist in collaboration with the radiation oncologist. The determination of the appropriate radiation dose is the responsibility of the medical physicist. The safe handling of the radioisotope source is the responsibility of the radiation safety specialist. State and federal regulations dictate minimum requirements of safety in the handling of radioactive sources used in cardiovascular brachytherapy. These requirements involve close monitoring of the patient and operating personnel to insure that radiation exposures are minimized. They involve the restricted access of nonessential personnel to the cath lab during the treatment. The entrances to the cath lab must be monitored to prevent unauthorized entry. Operating personnel must be closely monitored to maintain radiation exposures as low as reasonably achievable (ALARA). The patient must be monitored to insure that the source is implanted for the prescribed time and the patient's exposure is also ALARA consistent with the medical benefit expected. Public corridors must be monitored to prevent public exposures to the radiation emanating from the patient. The radiation exposure field around the patient during a typical gamma treatment presents what the regulators define as a high radiation area. This means that the exposure levels are in excess of 100 milli-rem (mrem) per hour at 30 cm from the patient. In fact, the exposure levels around the patient for a typical treatment are in the roentgens per hour range. The use of beta particle emitting radionuclides (Sr90/Y90 and P32) presents a much lower safety problem. But the use of radioactive materials in the cath lab still presents new safety concerns such as training, monitoring, record keeping, and public relations among the cath lab technologists.

Beta Particles↗

PubMed1994

Absorbed dose in the skin from beta emitters in medical and laboratory containers.

The International Commission on Radiation Protection have recently recommended an annual dose limit for the skin of radiation workers of 500 mSv at a depth of 20-100 microns averaged over any 1 cm2 regardless of the area exposed. It has previously been shown by the authors that beta dose rates on the outer surfaces of typical laboratory containers (vials, test tubes) or on medical syringes can exceed 100 mSv h-1 for radionuclide concentrations of the order of 1 MBq g-1, depending on container diameter, wall thickness and material and the beta particle energy spectrum. Since the fingers are frequently in contact with such containers it is of some importance to extend these dose calculations to depths below the skin surface, taking into consideration the anatomy of skin on the fingers. Using an extension of a Monte Carlo method previously described, dose rates have been calculated for the clinically useful radionuclides 90Y, 32P, 198Au, 153Sm and 131I. For polypropylene syringes the beta dose rates at a depth of 270 microns (a typical basal cell depth in the fingers) range from 77 to 135 mGy h-1 per MBq g-1 for 90Y (maximum energy 2.27 MeV) and approximately zero to 0.62 mGy h-1 per MBq g-1 for 131I (maximum energy 0.61 MeV). These results emphasize the importance of adequate finger protection when using high energy beta emitters and especially for clinicians who typically inject specific activities of the order of 100 MBq g-1 of 32P; in such cases annual permissible dose rates are exceeded in a matter of minutes. It is recommended that a minimum of 5 mm perspex finger protection be used for 90Y and 32P.

Beta Particles↗

PubMed1996

Radiolytic protein surface mapping.

We report that high energy beta particles may function as a means for mapping the surface of a protein. Comparable to Fe-EDTA in the presence of ascorbate and peroxide, 90Y-EDTA alone can break polypeptide backbone bonds on the surface of E. coli RNA polymerase. The two methods give very similar fragmentation patterns, although some unique fragments are produced by each. Radiolytic footprinting may prove useful for mapping proteins inside living cells, since beta-radiolysis produces reactive species up to approximately 1 cm away from the emitting 90Y.

Beta Particles↗

PubMed2002

The radial depth-dose distribution of a 188W/188Re beta line source measured with novel, ultra-thin TLDs in a PMMA phantom: comparison with Monte Carlo simulations.

The radial depth-dose distribution of a prototype 188W/188Re beta particle line source of known activity has been measured in a PMMA phantom, using a novel, ultra-thin type of LiF:Mg,Cu,P thermoluminescent detector (TLD). The measured radial dose function of this intravascular brachytherapy source agrees well with MCNP4C Monte Carlo simulations, which indicate that 188Re accounts for > or = 99% of the dose between 1 mm and 5 mm radial distance from the source axis. The TLDs were calibrated using a 90Sr/90Y beta secondary standard. Several correction factors are calculated using analytical and Monte Carlo methods. An analysis of the measurement uncertainty is made. Since it is partly determined by components of uncertainty arising from random effects, repeated measurements yield a lower uncertainty. The expanded uncertainty in the absolute dose at 2 mm radial distance equals 11%, 10%, 9% and 8% for 1, 2, 3 and 5 measurements, respectively. After a correction for source non-uniformity, the measured dose rate per unit source activity at 2 mm radial distance equals (1.53 +/- 0.16) Gy min(-1) GBq(-1) (2sigma), in agreement with the value of (1.45 +/- 0.01) Gy min(-1) GBq(-1) (2sigma) predicted by the MCNP4C simulations.

Beta Particles↗

PubMed1992

Absorbed doses to skin from radionuclide sources on the body surface.

Beta-particle and electron doses are reported for radionuclides on the skin surface. Upper and lower bounds on doses are based on Monte Carlo calculations that include or exclude electron scattering in air, respectively. Upper bounds agree well with results of point-kernel calculations performed by others.

Absorption↗