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Internal doses by ingestion for Japanese males were estimated from a literature survey. Intakes were derived from estimated food intakes and from whole-body counting. Total annual effective doses from natural and man-made sources were estimated to be 0.4 mSv and 0.002 mSv, respectively.
The Final Focus Test Beam (FFTB) is a new beam line at the Stanford Linear Accelerator Center designed to test new beam optics concepts, hardware, and techniques necessary to achieve and measure the small spot sizes required for future generations of high-energy e+e- linear colliders. The FFTB takes a 47 GeVc-1, 1 kW electron beam at the end of the Stanford Linear Accelerator Center linear accelerator and transports it to the FFTB beam dump. A radiation protection system was designed and installed for the FFTB with the primary goal that the integrated dose equivalent outside the shielding resulting from beam loss would not exceed 10 mSv y-1. This system is comprised of shielding, a beam containment system and a personnel protection system. This paper presents various aspects of radiation safety at Stanford Linear Accelerator Center that were considered in the design of the FFTB radiation protection system. Beam tests were conducted in which the performance of various beam containment devices and the shielding effectiveness were evaluated. Preliminary results from these tests are presented.
Because some designers of aerosol transport systems use the assumption that aerosol penetration through a system is maximized if the flow Reynolds number is 2,800, we have conducted tests to determine if such an assumption is appropriate. Although we do not believe that optimal performance of an aerosol sample transport system can be presented solely in terms of the Reynolds number, we have presented our results in terms of that parameter to compare our work with the results of an earlier study. Two types of experiments were performed. First, the penetration of liquid aerosol particles through horizontal tubes was experimentally investigated for a range of design and operational conditions. For a particle size of 10 microm aerodynamic diameter, the maximum penetration through a 6.7 mm diameter tube was associated with a Reynolds number of approximately 2,000; the maximum penetration through a tube of 15.9 mm occurred at a Reynolds number of about 3,000; and the maximum penetration through a 26.7 mm diameter tube occurred at about 4,000. It was also experimentally demonstrated that for a fixed flow rate through a horizontal tube, there is an optimum tube diameter for which the aerosol penetration is a maximum. An early study dealing with aerosol particle penetration through a 16.8 mm inside diameter loop of tubing (two vertical tubes, two horizontal tubes and three 90 degrees bends) suggested there was a fixed Reynolds number for optimal aerosol penetration independent of particle size. Those experiments were repeated here and the agreement with those tests is excellent; namely, the maximum penetration through a loop of 15.9 mm diameter tube occurs at a Reynolds number of approximately 2,800, independent of particle size. However, when the tube diameter of the transport system layout was changed to 26.7 mm, the Reynolds number associated with maximum penetration varied for different particle sizes, occurring at Reynolds numbers of approximately 5,600 for 8 microm AD particles, 3,800 for 10 microm particles and 3,000 for 15 microm particles.
Under the auspices of the Howard Hughes Medical Institute, a set of consensus guidelines for Radiation Protection Practices has been developed for biomedical research using radioactive materials. The purposes of the guidelines are (1) to promote good radiation protection practices consistent with the needs of biomedical research, the ALARA principle, and regulatory requirements; (2) to establish common goals and consistent practices within radiation safety programs; and (3) to build a meaningful partnership between radiation safety professionals and the biomedical research community. These practices are intended to enhance radiation protection and the efficiency of the research staff. The consensus guidelines will lessen the variability in radiation safety practices that is evident among many academic research institutions and will encourage better acceptance and regulatory compliance by users of radioactive materials in biomedical research.
Biomedical science researchers often express frustration that health physics practices vary widely between individual institutions. A survey examining both internal and external dose assessment practices was devised and mailed to fifty institutions supporting biomedical science research. The results indicate that health physics dose assessment practices and policies are highly variable. Factors which may contribute to the degree of variation are discussed.
This title of this article sounds paradoxical to most people because the general public is not fully aware of the many benefits radiation has brought to people's healthcare. Radiation has provided the most effective means of noninvasive diagnosis of many diseases, thus reducing the need for exploratory surgery, at significantly reduced risks. Furthermore, radiotherapy has been effective in treating many diseases without surgical removal of the diseased part. The breast is one excellent example of the benefits of radiation in both diagnosis and treatment with preservation. Yet the public still regards radiation as mysterious and dangerous, while trained experts regard it as beneficial with manageable risks. This article suggests ways of presenting this material to the public in a manner that is interesting and informative.
Institutional radiation safety programs routinely use wipe test sampling and liquid scintillation counting analysis to indicate the presence of removable radioactive contamination. Significant volumes of liquid waste can be generated by such surveillance activities, and the subsequent disposal of these materials can sometimes be difficult and costly. In settings where large numbers of negative results are regularly obtained, the limited grouping of samples for analysis based on expected value statistical techniques is possible. To demonstrate the plausibility of the approach, single wipe samples exposed to varying amounts of contamination were analyzed concurrently with nine non-contaminated samples. Although the sample grouping inevitably leads to increased quenching with liquid scintillation counting systems, the effect did not impact the ability to detect removable contamination in amounts well below recommended action levels. Opportunities to further improve this cost effective semi-quantitative screening procedure are described, including improvements in sample collection procedures, enhancing sample-counting media contact through mixing and extending elution periods, increasing sample counting times, and adjusting institutional action levels.
Metal tritides including titanium tritide (Ti 3Hx) and erbium tritide (Er 3Hx) have been used as components of neutron generators. The current understanding of metal tritides and their radiation dosimetry for internal exposure is very limited, and the ICRP Publication 30 does not provide for tritium dosimetry in metal tritide form. However, a few papers in the literature suggest that the solubility of metal tritides could be low. The current radiation protection guidelines for metal tritide particles are based on the assumption that their biological behavior is similar to tritiated water, which could be easily absorbed into body fluid. Therefore, these particles could have relatively short biological half-lives (10 d). If the solubility is low, the biological half-life of metal tritide particles and the dosimetry of an inhalation exposure to these particles could be quite different from tritiated water. This paper describes experiments on the dissolution rate of titanium tritide particles in a simulated lung fluid. Titanium tritide particles with mean sizes of 103 microm (coarse) and 0.95 microm (fine) were used. The results showed that the coarse particles dissolved much more slowly than the fine particles. The long-term dissolution half times were 361 and 33 d for the coarse and fine particles, respectively. Dissolution data of the fine particles were consistent with the diffusion theory. The dissolution half times were longer than the 10-d biological half time for tritiated water in the body. This finding has significant implications for the current health protection guidelines, including annual limits of intakes and derived air concentrations.
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There is increasing concern as to whether our limited radiation protection resources are being directed to those radiation sources that produce the greatest return as measured by the cost/risk avoided. Major contributors to this problem include public perception and the lack of an accepted methodology for assigning priorities. Described in this report is a new methodology for assigning these priorities on the basis of cost per risk avoided. This methodology provides several different approaches for comparing the cost effectiveness and priority of these sources, as well as insight into the efficacy of regulatory programs. To demonstrate its application, various radiation sources, selected on the basis of providing insight into problem areas, are evaluated and compared. These resulting assessments show that the current funding and prioritization for the control of radiation sources are, in general, exactly opposite to the risk based efficacy for their control. It is hopeful that the insights resulting from these assessments will assist decision-makers in correcting this situation.
The treatment of cancers by placement of radioactive materials within or adjacent to a tumor is clinically known as brachytherapy. Although the intracavitary treatment of gynecologic cancers using 137Cs has been in widespread use for nearly a century, interstitial techniques using 192Ir have developed within the last decade. Both procedures are performed as temporary implants and typically require a hospital stay of approximately 48 h. Significant differences in source strengths, loading conditions, and patient care requirements are visible between the intracavitary and interstitial techniques. Facilities that are experienced in the use of intracavitary techniques may lack clinical experience in the use of newer interstitial procedures. An examination of radiation exposure to the radiation oncology staff administering the treatment, exposure rate at frequently occupied points in the patient room, and exposure to the nursing staff will be of value to those institutions considering integration of interstitial brachytherapy techniques into their department.
This paper provides a risk-based approach for establishing threshold accountability values for radioactive sealed sources based on current scientific information and realistic assumptions. Although this paper focuses specifically on accountability thresholds, the methodology provided can be easily modified to determine risk-based exemption and licensing thresholds.
Thoriated electrodes are used in TIG welding. TIG welders, along with persons who grind thoriated electrodes and persons located near relevant welding and grinding sites, might be at risk of thorium intake. The isotopes of radiological relevance are 232Th, 230Th, and 228Th. The studies described in the literature do not provide a consistent picture of the actual hazards, and changes in European and German radiological protection laws have now made it necessary to determine the risks. To accomplish this, a field test was conducted under real working conditions in 26 different welding shops. The airborne activity generated through welding, and through grinding of electrodes, was measured using personal air samplers. Stationary samplers were also used. The filters' samples were evaluated by means of direct alpha spectrometry with proportional counting and by means of gamma spectrometry following neutron activation. The results clearly showed that considerable intake can occur during both alternating-current welding and electrode grinding, if no suction systems are used. The range of 232Th intakes to welders were estimated from 0.1 Bq y(-1) to 144 Bq y(-1) during welding and from 0.02 Bq y(-1) to 30.2 Bq y(-1) during grinding. In 6 of the 26 cases the recent annual limit on intake derived from the most recent ICRP publications was exceeded--in the worst case it was exceeded by a factor of 10--if it is assumed that the persons studied were not exposed workers (not routinely monitored for radiation exposure). When the significantly more restrictive German limits are applied, the amounts by which the limits were exceeded were even greater. Because many qualified welders have very long careers, the risks can thus be considerable. The paper also discusses parameters that influence exposure, and it presents a catalogue of recommended measures for dosage reduction.
A study was performed to characterize hand extremity doses received by a laboratory researcher performing a metabolic cell labeling procedure using 10-cm-diameter cell culture dishes containing GBq amounts of 32P-orthophosphate. Specifically, the optimal location for placement of thermoluminescent dosimeters on the extremities was determined as was the phase (time frame) during the cell labeling procedure when the highest dose was received. The cell labeling procedure was divided into four phases. Thermoluminescent dosimeters were placed on three fingers of each hand at the start of each phase and after the completion of that phase, collected, and sent to the processor. It was determined that in the case of this right-handed worker, the left-hand index finger should be used for determining the maximum extremity dose. The time frame during which the highest extremity dose was received was the cell lysis phase. Acrylic shielding was fabricated, which significantly reduced worker extremity dose.
In decommissioning medical research buildings at this institution, most areas surveyed were not contaminated above NRC 1993 release limits. Most contamination found was fixed. Wipe tests were inefficient at assessing removable contamination. An initial approach to surveying such a facility should begin with limited sampling emphasizing fixed contamination detection. Recent NRC guidance on decommissioning suggests that the requirements are becoming less stringent for medical facilities. This seems to support our limited decommissioning survey strategy for medical research buildings where radioisotopes have been used.
The work of Fong and Alvarez is easily extended for counting when paired counting is not employed. It remains true in the general case that the precision of a counting method can be no less than about 30% at the LLD and so it is desirable to have decision levels at least several times larger than the LLD so that measurements have sufficient precision to make valid decisions.
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