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PubMed2000

On the application of a radiation weighting factor for alpha particles in protection of non-human biota.

Radiation protection standards for non-human biota have been expressed in terms of absorbed dose. In calculating dose to biota, some investigators have modified the absorbed dose due to alpha particles by a factor of 20, based on the radiation weighting factor used in protection of humans, to account for the greater effectiveness of these radiations in producing biological damage. However, this value is intended to apply to stochastic health effects, primarily cancers, whereas deterministic effects have been the primary concern in protection of biota. Based on an analysis by the International Commission on Radiological Protection, the deterministic radiation weighting factor for alpha particles appears to lie in the range of about 5-10. Given the potential importance of this weighting factor in determining allowable levels of alpha-emitting radionuclides in the environment, regulatory authorities must be impressed with the need to develop an appropriate value for use in protection of biota. There also is a need to express doses and dose limits for biota in terms of a quantity other than absorbed dose and to develop an appropriate name for the biologically significant dose to biota.

Alpha Particles↗
PubMed2001

Determination and use of the monetary values of the averted person-sievert for use in radiation protection decisions in Hungary.

The monetary value of the averted dose is a key element in the implementation of the optimization principle both in radiation praxis and intervention. The main concept of this principle is to select options so as to maintain exposures at a reasonable level. The feature of this concept is to look for the minimal total cost, i.e., the sum of the costs of protection and health detriment. In its publications, ICRP emphasized the need for developing models which also take into account the "subjective" aspects of health detriment in the optimization process, such as the perception of risk by individuals and the need to put more emphasis on equity in the distribution of individual doses. This paper proposes a modified alpha-value model based on CEPN's model (Centre d'Etude sur L'Evaluation de la Protection dans le Domaine Nucleaire) to put more emphasis on recently published considerations about the smaller effects of the portion of collective dose derived from small doses. The parameters of the monetary value of unit collective dose averted, which is a key element of this type of model, can be estimated by means of approaches like human capital (HC) and willingness to pay (WTP) from the point of view of economic theories. The present study summarizes the results achieved by WTP among the radiation specialists mainly from the Paks Nuclear Power Plant, Hungary. The aim of the effort was to determine the value of a statistical life and the monetary value of a unit person-sievert associated with averted occupational exposure due to ionizing radiation. To apply the WTP method, a questionnaire has been prepared on the basis of the one introduced by CEPN in the late 1990's. The investigations show that the value of US$6,200 person-Sv(-1) seems to be acceptable for the alphabase-value for the occupational situation in Hungary in 1999. WTP assessments should be applied with caution since the economic level of the country, the workplace surveyed, and the computational methods affect the results. In addition, achieving a high level safety culture must rely on international cooperation both from the theoretical and practical viewpoints, and international markets affect the associated costs. Therefore the monetary requirements cannot always be assessed solely on a national basis.

Cost-Benefit Analysis↗
PubMed2001

Radiographic operations and safety in the Nigerian petroleum industry.

This work reports on a radiation safety study of the use of radioactive sources and radiation-producing machines for radiographic purposes in the Nigerian Petroleum Industry. It is a part of a wider study on the level of safety in the use of radiation in the country-a study that covered the manufacturing and petroleum industries. The survey assessment is based on minimum requirements for radiological safety, on a scale of 0-100, to protect personnel, the public, and the environment from artificial radiation sources. The survey result shows that the level of safety in the use of radiation-emitting machines for radiographic purposes is scored at 52, while it is 66 in the use of radioisotopes. Consequently, the level of safety in radiographic practices in the Nigerian Petroleum Industry is about 60% of the ideal.

Extraction and Processing Industry↗
PubMed2001

Statistical data evaluation in mobile gamma spectrometry: an optimization of on-line search strategies in the scenario of lost point sources.

There is a potential risk that hazardous radioactive sources could enter the environment, e.g., via satellite debris, smuggled radioactive goods, or lost metal scrap. From a radiation protection point of view there is a need for rapid and reliable methods for locating and identifying sources. The methods could also be used to locate hot spots after radioactive fallout. Carborne and airborne gamma spectrometry systems are suitable for the task. This work focuses on a situation where the radionuclide to search for is known, which is not an unlikely scenario. The possibility that the source is located near a road can be high, and thus motivating a carborne spectrometer system. The main object is to optimize on-line statistical methods in order to achieve a high probability for locating the point source and still have reasonably few false alarms caused by variations in the natural background radiation. Data were obtained from a carborne 3-L NaI(Tl) detector and two point sources located at various distances from the road. The nuclides used were 137Cs and 131I. Spectra were measured stationary on the road. From these measurements we have reconstructed counts in spectral windows applicable to different speed and sampling times; the time 3 s and speeds 32 and 54 km h(-1) are used in this work. The maximum distance a source can be located from the road and still be detected is estimated with four different statistical analysis methods. This distance is called the critical distance, CD. The method is applied on gross counts in the full energy peak spectral window. For each method alarm levels have been calculated from background data obtained in Scania (Skåne), in the south of Sweden. The results show large differences in CD. With the best approach, the two sources could be detected from about 180 m (137Cs, 6 GBq) and 170 m (131I, 4.5 GBq).

Automobiles↗
PubMed2001

Fluence-to-dose conversion coefficients based on the VIP-Man anatomical model and MCNPX code for monoenergetic neutrons above 20 MeV.

A new set of fluence-to-absorbed dose and fluence-to-effective dose conversion coefficients has been calculated for high-energy neutrons using a whole-body anatomical model, VIP-Man, developed from the high-resolution transversal color photographic images of the National Library of Medicine's Visible Human Project. Organ dose calculations were performed using the Monte Carlo code MCNPX for 20 monoenergetic neutron beams between 20 MeV and 10,000 MeV under 6 different irradiation geometries: anterior-posterior, posterior-anterior, left lateral, right lateral, isotropic, and rotational. For neutron Monte Carlo calculations, results based on an image-based whole-body model were not available in the literature. The absorbed dose results for 24 major organs of VIP-Man are presented in the form of tables and selected figures that compare with those based on simplified mathematical phantoms reported in the literature. VIP-Man yields up to 40% larger values of effective dose and many organ doses, thus suggesting that the results reported in the past may not be conservative.

Humans↗
PubMed2001

Influences of parameter uncertainties within the ICRP 66 respiratory tract model: particle deposition.

Risk assessment associated with the inhalation of radioactive aerosols requires as an initial step the determination of particle deposition within the various anatomic regions of the respiratory tract. The model outlined in ICRP Publication 66 represents to date one of the most complete overall descriptions of not only particle deposition, but of particle clearance and local radiation dosimetry of lung tissues. In this study, a systematic review of the deposition component within the ICRP 66 respiratory tract model was conducted in which probability density functions were assigned to all input parameters. These distributions were subsequently incorporated within a computer code LUDUC (LUng Dose Uncertainty Code) in which Latin hypercube sampling techniques are used to generate multiple (e.g., 1,000) sets of input vectors (i.e., trials) for all of the model parameters needed to assess particle deposition within the extrathoracic (anterior and posterior), bronchial, bronchiolar, and alveolar-interstitial regions of the ICRP 66 respiratory tract model. Particle deposition values for the various trial simulations were shown to be well described by lognormal probability distributions. Geometric mean deposition fractions from LUDUC were found to be within approximately +/- 10% of the single-value estimates from the LUDEP computer code for each anatomic region and for particle diameters ranging from 0.001 to 50 microm. In all regions of the respiratory tract, LUDUC simulations for an adult male at light exertion show that uncertainties in particle deposition fractions are distributed only over a range of about a factor of approximately 2-4 for particle sizes between 0.005 to 0.2 microm. Below 0.005 microm, uncertainties increase only for deposition within the alveolar region. At particle sizes exceeding 1 microm, uncertainties in the deposition fraction within the extrathoracic regions are relatively small, but approach a factor of 20 for deposition in the bronchial region. Deposition fractions for particles above 1 microm become very uncertain within the deeper regions of the lungs (bronchiolar and alveolar-interstitial).

Body Height↗
PubMed2001

Tracking occupational doses of transient workers.

A number of radioactive material licensees in the United States are unaware that they are required to track the occupational doses their radiation workers receive outside thieir facilities. As a result, these licensees may be cited for not tracking offsite occupational doses and quite possible for allowing some individuals to exceed the annual limits established by regulatory agencies. The accounting of occupational doses to "transient" workers is a difficult task. Unfortunately, written guidance to assist licensees on how to properly address this issue is not available. This paper was developed to raise awareness among radiation safety professionals of the need to establish effective measures to properly track transient worker exposures and maintain compliance with regulatory limits.

Humans↗
PubMed2002

Summary of stationary and personal air sampling measurements made during a plutonium glovebox decommissioning project.

Workplace air sampling was performed during the decommissioning of a previously active plutonium glovebox facility located at Argonne National Laboratory. Personal air samplers (PAS) were used to measure breathing zone activity concentrations of workers engaged in size-reducing contaminated gloveboxes. Stationary air samplers (SAS) were used to measure the work area activity concentrations and test their application in providing representative sampling of breathing zone activity concentrations. The relative response of these samplers (PAS:SAS) was tracked during the course of the decommissioning work, with results yielding favorable agreement to within a factor of +/-5. A cascade impactor was used to determine the particle size distribution of workplace aerosols. The average activity median aerodynamic diameter (AMAD) was estimated to be 3.0 microm, with a corresponding geometric standard deviation of 2.4. A gas-flow proportional counter was utilized to measure the gross alpha activity collected on both the SAS glass fiber and the PAS cellulose fiber filters. A subset of this filter group was subsequently analyzed using an alpha spectrometer post radiochemical processing and isotopic separation. The quantity of alpha activity measured on the SAS filters was generally within +/-30% of the alpha spectrometry measurements. However, measurements made of the activity present on the PAS cellulose fiber filters were consistently underestimated using a gas-flow proportional counter, suggesting a small correction factor of 15-20% to account for the absorption of alpha particle emissions.

Air Pollutants, Occupational↗
PubMed2002

A new approach to a site radiological control manual.

The Pantex Plant significantly revised its Radiological Control Manual to improve its usability, streamline plant procedures, and clarify conflicting guidance. This article overviews the process used to develop the new Radiological Control Manual.

Humans↗
PubMed2002

Determination of the physical and chemical properties, biokinetics, and dose coefficients of uranium compounds handled during nuclear fuel fabrication in France.

The introduction of new ICRP recommendations, especially the new Human Respiratory Tract Model (HRTM) in ICRP Publication 66 led us to focus on some specific parameters related to industrial uranium aerosols collected between 1990 and 1999 at French nuclear fuel fabrication facilities operated by COGEMA, FBFC, and the CEA. Among these parameters, the activity median aerodynamic diameter (AMAD), specific surface area (SSA), and parameters describing absorption to blood f(r), s(r) and s(s) defined in ICRP Publication 66 were identified as the most relevant influencing dose assessment. This study reviewed the data for 25 pure and impure uranium compounds. The average value of AMAD obtained was 5.7 microm (range 1.1-8.5 microm), which strongly supports the choice of 5 microm as the default value of AMAD for occupational exposures. The SSA varied between 0.4 and 18.3 m2 g(-1). For most materials, values of the absorption parameters f(r), s(r), and s(s) derived from the in vitro experiments were generally consistent with those derived from the in vivo experiments. Using average values for each pure compound allowed us to classify UO2 and U3O8 as Type S, mixed oxides, UF4, UO3 and ADU as Type M, and UO4 as Type F based on the ICRP Publication 71 criteria. Dose coefficients were also calculated for each pure compound, and average values for each type of pure compound were compared with those derived using default values. Finally, the lung retention kinetics and urinary excretion rates for inhaled U03 were compared using material-specific and default absorption parameters, in order to give a practical example of the application of this study.

Adsorption↗
PubMed2002

The international atom: evolution of radiation control programs.

Under the Atoms for Peace program, Turkey received a one MWt swimming pool reactor in 1962 that initiated a health physics program for the reactor and a Radiation Control Program (RCP) for the country's use of ionizing radiation. Today, over 13,000 radiation workers, concentrated in the medical field, provide improved medical care with 6,200 x-ray units, including 494 CAT scanners, 222 radioimmunoassay (RIA) labs and 42 radiotherapy centers. Industry has a large stake in the safe use of ionizing radiation with over 1,200 x-ray and gamma radiography and fluoroscopic units, 2,500 gauges in automated process control and five irradiators. A 48-person RCP staff oversees this expanded radiation use. One incident involving a spent 3.3 TBq (88 Ci) 60Co source resulted in 10 overexposures but no fatalities. Taiwan received a 1.6 MWt swimming pool reactor in 1961 and rapidly applied nuclear technology to the medical and industrial fields. Today, there are approximately 24,000 licensed radiation workers in nuclear power field, industry, medicine and academia. Four BWRs and two PWRs supply about 25% of the island's electrical power needs. One traumatic event galvanized the RCP when an undetermined amount of 60Co was accidentally incorporated into reinforcing bars, which in turn were incorporated into residential and commercial buildings. Public exposures were estimated to range up to 15 mSv (1.3 rem) per annum. There were no reported ill effects, except possibly psychological, to date. The RCP now has instituted stringent control measures to ensure radiation-free dwellings and work places. Albania's RCP is described as it evolved since 1972. Regulations were promulgated which followed the IAEA Basic Safety Standards of that era. With 525 licenses and 600 radiation workers, the problem was not in the regulations per se but in their enforcement. The IAEA helped to upgrade the RCP as the economy evolved from one that was centrally planned economy to a free market economy. As this transition takes place, public radiation exposures in the medical field will continue to be high until the old x-ray equipment is phased out. A small conscientious health physics staff works with limited resources to keep radiation exposures at acceptable levels. These three country RCPs, as they have evolved, have some commonality. Today, all radiation installations are licensed, both for radioactive material and x-ray equipment. Radiation workers are individually licensed or registered. All RCPs have, or are striving to have, their radiation regulations conform to ICRP 60 recommendations as spelled out in the Basic Safety Standard (1996). Finally, all three countries have as yet to find a permanent solution for their radioactive waste.

Calibration↗
PubMed2002

A whole body counting facility in a remote Enewetak Island setting.

The U.S. Department of Energy (DOE) has recently implemented a series of strategic initiatives to address long-term radiological surveillance needs at former U.S. test sites in the Marshall Islands. The plan is to engage local atoll communities in developing shared responsibilities for implementing radiation protection programs for resettled and resettling populations. As part of this new initiative, DOE agreed to design and construct a radiological laboratory on Enewetak Island, and help develop the necessary local resources to maintain and operate the facility. This cooperative effort was formalized in August 2000 between the DOE, the Republic of the Marshall Islands (RMI), and the Enewetak/Ujelang Local Atoll Government (EULGOV). The laboratory facility was completed in May 2001. The laboratory incorporates both a permanent whole body counting system to assess internal exposures to 137Cs, and clean living space for people providing 24-h void urine samples. DOE continues to provide on-going technical assistance, training, and data quality review while EULGOV provides manpower and infrastructure development to sustain facility operations on a full-time basis. This paper will detail the special construction, transportation and installation issues in establishing a whole body counting facility in an isolated, harsh environmental setting.

Body Burden↗
PubMed2002

Field comparison of the sampling efficacy of two smear media: cotton fiber and kraft paper.

Two materials were compared in field tests at the Defense Waste Processing Facility: kraft paper (a strong, brown paper made from wood pulp prepared with a sodium sulfate solution) and cotton fiber. Based on a sampling of 46 pairs of smears, the cotton fiber smears provide a greater sensitivity. The cotton fiber smears collected an average of 44% more beta activity than the kraft paper smears and 29% more alpha actvity. Results show a greater sensitivity with cotton fiber over kraft paper at the 95% confidence level. Regulatory requirements for smear materials are vague. The data demonstrate that the difference in sensitivity of smear materials could lead to a large difference in reported results that are subsequently used for meeting shipping regulations or evaluating workplace contamination levels.

Radiation Monitoring↗
PubMed2005

Medical health physics: a review.

Medical health physics is the profession dedicated to the protection of healthcare providers, members of the public, and patients from unwarranted radiation exposure. Medical health physicists must be knowledgeable in the principles of health physics and in the applications of radiation in medicine. Advances in medical health physics require the definition of problems, testing of hypotheses, and gathering of evidence to defend changes in health physics practice and to assist medical practitioners in making changes in their practices as appropriate. Advances in radiation medicine have resulted in new modalities and procedures, some of which have significant potential to cause serious harm. Examples included in this review include radiologic procedures that require very long fluoroscopy times, radiolabeled monoclonal antibodies, and intravascular brachytherapy. This review summarizes evidence that supports changes in consensus recommendations, regulations, and health physics practices associated with recent advances in radiology, nuclear medicine, and radiation oncology. Medical health physicists must continue to gather evidence to support intelligent but practical methods for protection of personnel, the public, and patients as modalities and applications evolve in the practice of medicine.

Health Physics↗
PubMed1991

Radiation dose rates from adult patients undergoing nuclear medicine investigations.

Adult patients undergoing nuclear medicine investigations may subsequently come into close contact with members of the public and hospital staff. In order to expand the available dosimetry and derive appropriate recommendations, dose rates were measured at 0.1, 0.5 and 1.0 m from 80 adult patients just before they left the nuclear medicine department after undergoing one of eight 99Tcm studies, an 123I thyroid, an 111In leucocyte or a 201Tl cardiac scan. The maximum departure dose rates at these distances of 150, 30 and 7.3 microSv h-1 were greater than those found in similar published studies of adult and paediatric patients. To limit the dose to an infant to less than 1 mSv, an 111In leucocyte scan is the only investigation for which it may be necessary to restrict close contact between the infant and a radioactive parent, depending on the dose rate near the surface of the patient, the parent's habits and how fretful is the infant. It is unlikely that a ward nurse will receive a dose of 60 microSv in a working day if caring for just one radioactive adult patient, unless the patient is classified as totally helpless and has undergone a 99Tcm marrow, bone or brain scan. The data and revised calculations of effective exposure times based on a total close contact time of 9 h in every 24 h period should allow worst case estimates of radiation dose to be made and recommendations to be formulated for other circumstances, including any future legislative changes in dose limits or derived levels.

Adult↗