Dynamic distribution and dosimetric evaluation of human non-specific immunoglobulin G labelled with 111In or 99Tcm

This study presents data on the dynamic distribution and dosimetry of 111In- and 99Tcm-labelled human non-specific immunoglobulin G (IgG), two recently developed radiopharmaceuticals for the detection of infection and inflammation. Five healthy volunteers were injected with 20-75 MBq 111In-IgG and seven patients were injected with 740 MBq 99Tcm-hydrazinonicotinamide derivative (HYNIC)-IgG. Blood samples, urine and feces were collected. Whole-body gamma camera imaging studies were performed. The activity in source organs was quantified using the conjugate view counting method and a partial background subtraction technique. Dosimetric calculations were performed using the MIRD technique. For 111In-IgG, the mean biological half-times in the blood were 0.90 and 46 h for the a- and b-phase, respectively. For 99Tcm-HYNIC-IgG, these half times were 0.46 and 45 h. For 111In-IgG, the mean cumulative urinary excretion in the first 48 h was 18% of the injected dose, while excretion in the feces was less than 2% of the injected dose. For 99Tcm-HYNIC-IgG, the whole-body retention was always 100% up to 24 h. The mean absorbed doses in the liver, spleen, kidneys, red marrow and testes from 111In-IgG were 0.8, 0.7, 1.2, 0.3 and 0.4 mGy MBq-1 respectively. The mean absorbed doses for 99Tcm-HYNIC-IgG to these organs were 16, 24, 15, 10 and 22 mu Gy MBq-1 respectively. The mean effective dose was 0.25 mSv MBq-1 and 8.4 mu Sv MBq-1 for 111In-IgG and 99Tcm-HYNIC-IgG respectively. In conclusion, the radiation absorbed doses for both 111In-IgG and 99Tcm-HYNIC-IgG are low and, therefore, these radiopharmaceuticals can be administered safely from a radiation risk perspective.     

Dosimetry of rhenium-186-labeled monoclonal antibodies: methods, prediction from technetium-99m-labeled antibodies and results of phase I trials

Rhenium-186 is a beta-emitting radionuclide that has been studied for applications in radioimmunotherapy. Its 137 keV gamma photon is ideal for imaging the biodistribution of the immunoconjugates and for obtaining gamma camera data for estimation of dosimetry. Methods used for determining radiation absorbed dose are described. We have estimated absorbed dose to normal organs and tumors following administration of two different 186Re-labeled immunoconjugates, intact NR-LU-10 antibody and the F(ab')2 fragment of NR-CO-02. Tumor dose estimates in 46 patients varied over a wide range, 0.4-18.6 rads/mCi, but were similar in both studies. Accuracy of activity estimates in superficial tumors was confirmed by biopsy. Prediction of 186Re dosimetry from a prior 99mTc imaging study using a tracer dose of antibody was attempted in the NR-CO-02 (Fab')2 study. Although 99mTc was an accurate predictor of tumor localization and the mean predicted and observed radiation absorbed doses to normal organs compared favorably, 186Re dosimetry could not be reliably predicted in individual patients. The methods described nevertheless provide adequate estimates of 186Re dosimetry to tumor and normal organs.     

Estimation of organ cumulated activities and absorbed doses on intakes of several 11C labelled radiopharmaceuticals from external measurement with thermoluminescent dosimeters

We have developed a method for obtaining the cumulated activities in organs from radionuclides, which are injected into the patient in nuclear medicine procedures, by external exposure measurement with thermoluminescent dosimeters (TLDs) which are attached to the patient's body surface close to source organs to obtain information on body-surface doses. As the surface dose is connected to the cumulated activities in source organs through radiation transmission in the human body which can be estimated with the aid of a mathematical phantom, the organ cumulated activities can be obtained by the inverse transform method. The accuracy of this method was investigated by using a water phantom in which several gamma-ray volume sources of known activity were placed to simulate source organs. We then estimated by external measurements the organ cumulated activities and absorbed doses in subjects to whom the radiopharmaceuticals 11C-labelled Doxepin, 11C-labelled YM09151-2 and 11C-labelled Benzotropin were administered in clinical nuclear medicine procedures. The cumulated activities in the brain obtained with TLDs for Doxepin and YM09151-2 are 63.6 +/- 6.2 and 32.1 +/- 12.0 kBq h MBq-1 respectively, which are compared with the respective values of 33.3 +/- 9.9 and 23.9 +/- 6.2 kBq h MBq-1 with direct PET (positron emission tomography) measurements. The agreement between the two methods is within a factor of two. The effective doses of Doxepin, YM09151-2 and Benzotropin are determined as 6.92 x 10(-3), 7.08 x 10(-3) and 7.65 x 10(-3) mSv MBq-1 respectively with the TLD method. This method has great advantages, in that cumulated activities in several organs can be obtained easily with a single procedure, and the measurements of body surface doses are performed simultaneously with the nuclear medicine procedure, as TLDs are too small to interfere with other medical measurements.     

Calculation of residence times and radiation doses using the standard PC software Excel

We developed a program which aims to facilitate the calculation of radiation doses to single organs and the whole body. IMEDOSE uses Excel to include calculations, graphical displays, and interactions with the user in a single general-purpose PC software tool. To start the procedure the input data are copied into a spreadsheet. They must represent percentage uptake values of several organs derived from measurements in animals or humans. To extrapolate these data up to seven half-lives of the radionuclide, fitting to one or two exponentional functions is included and can be checked by the user. By means of the approximate time-activity information the cumulated activity or residence times are calculated. Finally these data are combined with the absorbed fraction doses (S-values) given by MIRD pamphlet No. 11 to yield radiation doses, the effective dose equivalent and the effective dose. These results are presented in a final table. Interactions are realized with push-buttons and drop-down menus. Calculations use the Visual Basic tool of Excel. In order to test our program, biodistribution data of fluorine-18 fluorodeoxyglucose were taken from the literature (Meija et al., J Nucl Med 1991; 32:699-706). For a 70-kg adult the resulting radiation doses of all target organs listed in MIRD 11 were different from the ICRP 53 values by 1%+/-18% on the average. When the residence times were introduced into MIRDOSE3 (Stabin, J Nucl Med 1996; 37:538-546) the mean difference between our results and those of MIRDOSE3 was -3%+/-6%. Both outcomes indicate the validity of the present approach.     

Radiation dose estimates of 186Re-hydroxyethylidene diphosphonate for palliation of metastatic osseous lesions: an animal model study

A common complication in patients with breast or prostate cancer is bone metastases causing pain. New radionuclide therapy methods have recently been proposed for palliation, including 186Re-hydroxyethylidene diphosphonate (186Re-HEDP). This paper reports on the local development of 186Re-HEDP and the biodistribution studied in animals for eventual use in patients. Adult dose was computed assuming a 70 kg standard man. The 186Re was labelled to HEDP using standard techniques. The biodistribution in five Chacma baboons (Papio ursinus) was studied. Doses ranging from 39.4 to 44.9 MBq kg(-1) (mean 43.6 +/- 2.8 MBq kg[-1]) were administered, corresponding to an adult human dose of 2960 MBq (80 mCi). Whole-body images of the animals were obtained with a dual-headed scintillation camera on an hourly basis for 6 h post-injection and then daily for 3 days. The bone, soft tissue, kidneys and urinary bladder were considered source organs and data from these organs were used in a compartmental model to obtain the mean residence times of the radionuclide in the different source organs. Radiation dose estimates for 186Re-HEDP were subsequently obtained with the MIRDOSE 3 program. The estimated absorbed radiation doses to some of the organs (expressed in mGy MBq[-l]) were as follows: bone surface 1.69; kidneys 0.09; liver 0.04; ovaries 0.04; red marrow 0.75; total body 0.12; urinary bladder wall 0.43. 186Re-HEDP yielded an effective dose of 0.17 mSv MBq(-1). The radiation dose delivered to the bone marrow in this study did not cause any detrimental effect to the baboons, indicating that locally produced 186Re-HEDP is suitable for clinical use.     

Marrow toxicity and radiation absorbed dose estimates from rhenium-186-labeled monoclonal antibody

Estimates of radiation absorbed dose to the red marrow (RM) would be valuable in treatment planning for radioimmunotherapy if they could show a correlation with clinical toxicity. In this study, a correlation analysis was performed to determine whether estimates of radiation absorbed dose to the bone marrow could accurately predict marrow toxicity in patients who had received 186Re-labeled monoclonal antibody. METHODS: White blood cell and platelet count data from 25 patients who received 186Re-NR-LU-10 during Phase I radioimmunotherapy trials were analyzed, and the toxicity grade, the fraction of the baseline counts at the nadir (percentage baseline) and the actual nadir were used as the indicators of marrow toxicity. Toxicity was correlated with various predictors of toxicity. These predictors included the absorbed dose to RM, the absorbed dose to whole body (WB) and the total radioactivity administered. RESULTS: Percentage baseline and grade of white blood cells and platelets all showed a moderate correlation with absorbed dose and radioactivity administered (normalized for body size). The percentage baseline platelet count was the indicator of toxicity that achieved the highest correlation with the various predictors of toxicity (r = 0.73-0.79). The estimated RM absorbed dose was not a better predictor of toxicity than either the WB dose or the total radioactivity administered. There was substantial variation in the blood count response of the patients who were administered similar radioactivity doses and who had similar absorbed dose estimates. CONCLUSION: Although there was a moderately good correlation of toxicity with dose, the value of the dose estimates in predicting toxicity is limited by the patient-to-patient variability in response to internally administered radioactivity. In this analysis of patients receiving 186Re-labeled monoclonal antibody, a moderate correlation of toxicity with dose was observed but marrow dose was of limited use in predicting toxicity for individual patients.     

Method for determination of radiation effects in cosmonauts by board dosimeter readings made during orbital mission

A technique for calculating the SS MIR absorbed doses from the galactic cosmic rays, protons of the Earth's radiation belts and solar flares is described. Calculated daily doses for different compartments along the MIR main axis are compared with doses calculated for the location of board radiometer R-16 in various periods of solar activity. Maximal doses in MIR compartments (in the absence of phantom) were compared with the doses in referential depths of a spherical phantom representing the blood forming tissue, skin, enteric epithelium, and the absorbed dose in the dosimeter location. This comparison allows more precise estimation of radiation hazard to cosmonauts in space flight.     

A CT assisted method for absolute quantitation of internal radioactivity

A method is described for the determination of radioactivity (microCi or MBq) at an organ site within an object or patient. Using both anatomic image data (CT or MRI scans) and planar gamma camera images, activity at depth is determined using a matrix inversion method based on least squares. The result of the inversion analysis was the unknown set of n linear (uniform) activity densities representative of each organ within the phantom or patient. The problem was overdetermined since the number of unknown activity densities (microCi/cm) was much less than the number of analysis points (N) within the nuclear image. This method, defined as the CT assisted matrix inversion (CAMI) technique, was accurate to within 15% for a three "organ" plastic phantom, wherein the organs were right circular cylinders having activities of 74 to 508 microCi (or 2.74 MBq to 18.8 MBq). This accuracy included image quantitation effects, particularly assumptions concerning attenuation correction. The average absolute percent error of the estimated activity in four distinct radioactive volumes in the phantom was 9.8%. It was found that the background activity within the phantom was estimated to be too high if sampling regions near strong sources were used in the analysis (scatter effect). This was minimized by going at least 2 cm away from such sources. By applying the method to a monoclonal antibody clinical study, activities within the patient's major organs such as liver, spleen, and kidney could be estimated, even in cases where the organ could not be visualized. Here, the CAMI algorithm gave internally consistent results for the patient's left and right lung linear activity concentrations. The CAMI technique resolves the problem of tissue superimposition using depth information from 3-D CT and is applicable in cases where a number of organs overlap in the gamma camera image. Thus, the method should be generally useful to nuclear image quantitation and the estimation of absorbed radiation doses in patients. One particular application is the estimation of radiation doses in radioimmunotherapy (RIT).     

Conversion of ionization measurements to radiation absorbed dose in non-water density material

The radiation absorbed dose to non-water equivalent materials of interest in radiotherapy is the dose to lung and the dose to bone. The measurement and calculation of dose to the lung has been of great interest and much effort has gone into the development of accurate lung dose calculation methods. The radiation absorbed dose to the bone is usually not calculated and most absorbed dose calculations have been done without correcting for the presence of bone. For the lower megavoltage photon beams this may be appropriate, however, as the energy of the photon beam increases, the region of electronic disequilibrium becomes larger and pair production which depends on the atomic number of the material becomes significant. Therefore the bone will produce greater perturbations of the dose distribution. The dose to lung-equivalent material is uniquely obtained from ionization measurements. However, in bone-equivalent materials two different calculations of absorbed dose are possible: the absorbed dose to soft tissue plastic (polystyrene) within bone-equivalent material and the dose to the bone-equivalent material itself. Both can be calculated from ionization measurements in phantoms. These two calculations result in significantly different doses in a heterogeneous phantom composed of polystyrene and aluminium (a bone substitute). The dose to a thin slab of polystyrene in aluminium is much higher than the dose to the aluminium itself at the same depth in the aluminium. Monte Carlo calculations confirm that the calculation of dose to polystyrene in aluminium can be accurately carried out using existing dosimetry protocols. However, the conversion of ionization measurements to absorbed dose to high atomic number materials cannot be accurately carried out with existing protocols and appropriate conversion factors need to be determined.     

Effects of irradiation on the biomechanics of osseointegration. An experimental in vivo study in rats

The present study reports on the late effects of increasing doses of radiation on the biomechanics of commercially pure titanium implants (fixtures) installed in the proximal tibia in 26 rats. Twelve weeks after various doses (10, 20, 30, and 35 Gy) of irradiation, the fixtures were inserted into rat tibiae, and after another eight weeks these were tested mechanically in vivo. Acute dose dependent skin reactions developed after all doses except 10 Gy, but most subsided within two to three weeks. There was a statistically significant reduction in torsion but the pull-out load was not significantly reduced for single doses up to 30 Gy. Histological analysis showed that bone remodelling was impaired. Shear stresses and shear moduli were estimated for the bone-implant interface and in the surrounding bone tissue. These estimated stresses and moduli were not found to be correlated to the dose of radiation.     

New TIPS placement in pregnancy in recurrent esophageal varices hemorrhage--assessment of fetal radiation exposure

Recurrent variceal bleeding due to liver cirrhosis led to treatment with a transjugular intrahepatic portosystemic shunt (TIPS) in a pregnant woman at 20 weeks' gestation. Fetal radiation exposure was estimated to be less than 10 mSv. The use of a graduated catheter allowed measurement of field size and reliable determination of the patient's entrance dose. Radiation exposure of an approximated fetal dosage of 5.2 mSv did not justify abortion for medical reasons. Therefore, TIPS procedure is not generally contraindicated during pregnancy itself. TIPS placement may be a therapeutic option related to the severity of the underlying maternal disease, after radiation exposure of the fetus has been estimated.     

Human biodistribution and dosimetry of the PET perfusion agent copper-62-PTSM

Copper-62-pyruvaldehyde bis(N4-methyl)thiosemicarbazone (PTSM) has been proposed as a generator-produced radiopharmaceutical for perfusion imaging using PET. Several clinical studies have demonstrated the ability of 62Cu-PTSM to quantitate myocardial and cerebral perfusion in humans. Because 62Cu-PTSM is generator-produced, it can be provided to clinical centers without cyclotron availability and, therefore, represents a cost-effective, practical PET perfusion tracer for clinical applications. To assess the safety, time-dependent biodistribution, and whole-body and organ-specific absorbed radiation dose estimates of this tracer, a Phase I study of 62Cu-PTSM was performed using whole-body imaging with PET in 10 healthy volunteers and with the radiopharmaceutical delivered by a compact modular generator unit. METHODS: Five male and five female subjects underwent a series of clinical tests and head-to-midthigh, whole-body PET scans at three time points over 1 hr after intravenous injection of 62Cu-PTSM. Before injection of the tracer, PET transmission scans were performed and used to correct the emission data for attenuation. Final image data were expressed in units of mCi/cc. Using standard organ weights, the percent injected dose per organ was calculated. Biodistribution data were obtained at three different time points and from these data biological half-lives in different organs were determined for calculation of radiation absorbed dose estimates. RESULTS: The liver was seen as the critical organ receiving a dose of 0.0886 rad/mCi. This organ defined the maximum single injected dose at 56 mCi using the limit of 5 rads to a critical organ per study per year. The whole-body dose is 0.0111 rad/mCi, resulting in a 0.622 rad exposure with a maximum single injection dose. Only trace levels of activity were found in the urine, which suggests low levels of urinary excretion and bladder exposure. No significant clinical, electrocardiographic or laboratory abnormalities were seen after the injection of 62Cu-PTSM. CONCLUSION: Copper-62-PTSM is a clinically safe radiopharmaceutical with favorable dosimetry for human studies at injected doses significantly above those projected for use in clinical studies.     

Oligoradionuclidetherapy using radiolabelled antisense oligodeoxynucleotide phosphorothioates

Radiolabelled antisense oligodeoxynucleotides have been used for in vivo biokinetic studies in AIDS and cancer patients. The therapeutic possibilities are still unknown and the major question in therapeutic use of radio-oligonucleotide is the optimal source of radiation. We studied the pharmacokinetics and in vivo tissue distribution for oligodeoxynucleotide phosphorothioates by using the data from three different radionuclides: sulphur-35 (t1/2 = 87.4 days, maximum beta-energy = 167 keV), phosphorus-33 (t1/2 = 24.4 days, maximum beta-energy = 250 keV) and phosphorus-32 (t1/2 = 14.3 days, maximum beta-energy = 2270 keV). The absorbed doses of 32P-, 33P- and 35S-labelled oligonucleotides were estimated using the published biodistribution data for several oligonucleotides in two animal models for both tumour xenografts and AIDS. The local energy absorption of 33P turned out to be higher than that of 32P if the mass was smaller than approximately 300 micrograms, and the local absorption of 35S was higher than that of 32P when the mass was <80 micrograms. In a mouse tumour xenograft model an i.v. injected activity seemed to achieve sufficient radiation doses in the tumour: in a 1 g tumour 4.9 Gy for 32P, 5.1 Gy for 33P and 5.5 Gy for 35S were calculated when the kidney dose was kept as 5 Gy. In the same model in smaller tumours the doses were for a 1 mg tumour 0.73 Gy (32P), 5.1 Gy (33P) and 5.5 Gy (35S), and for a 1 microgram tumour 0.08 Gy (32P), 3.1 Gy (33P) and 3.9 Gy (35S). Thus, 33P and 35S have more beneficial radiotherapeutic characteristics than 32P. Relative advantage factors (33P and 35S versus 32P) for kidney and liver doses using these nuclides varied from 0.997 to 1.001 for a 1 g tumour and there was no difference in the radiation dose to normal organs. Therefore, we conclude that in oligonucleotide radiotherapy tumours >1 g should be treated with 32P, whereas smaller tumours should be treated with 33P or 35S. There is no significant difference between 33P and 35S, and either radionuclide could be selected according to labelling properties.     

Evidence into practice, experimentation and quasi experimentation: are the methods up to the task?

PURPOSE: To assess the suitability of the cytokinesis block micronucleus assay as a biological dosimeter following in-vivo radiation using cancer patients undergoing radiotherapy. METHODS: Blood from 4 healthy donors was irradiated in vitro with gamma-rays and the dose response of induced micronuclei in binucleate lymphocytes following cytokinesis block was determined. Micronucleus frequency was ascertained before and at intervals during radiotherapy treatment in 6 patients with various tumors in the pelvic region. Equivalent whole body doses (physical doses) at these times were calculated from radiation treatment plans and cumulative dose volume histograms. RESULTS: Linear dose response relationships were found for induced micronucleus frequency in lymphocytes resulting from both in-vitro and in-vivo irradiation. Doses resulting from in-vivo irradiation (biological doses) were estimated by substitution of micronucleus frequency observed in radiotherapy patients into the dose response curve from in-vitro irradiation of blood. The relationship between the biologically estimated dose (BD) and the calculated equivalent whole body dose (PD) was BD = 0.868 (+/- 0.043)PD + 0.117 (+/- 0.075). CONCLUSION: The micronucleus assay appears to offer a reliable and consistent method for equivalent whole body radiation dose estimation, although our findings should be confirmed using lymphocytes from radiotherapy patients with tumors at anatomical sites other than the pelvis. Except at doses lower than about ).4 Gy, the method yields dose estimates acceptably close to "true" physically determined doses. The assay can be performed relatively rapidly and can be used as a "first line" biological dosimeter in situations where accidental exposure to relatively high radiation doses has occurred.     

MIRD pamphlet No. 17: the dosimetry of nonuniform activity distributions--radionuclide S values at the voxel level. Medical Internal Radiation Dose Committee

The availability of quantitative three-dimensional in vivo data on radionuclide distributions within the body makes it possible to calculate the corresponding nonuniform distribution of radiation absorbed dose in body organs and tissues. This pamphlet emphasizes the utility of the MIRD schema for such calculations through the use of radionuclide S values defined at the voxel level. The use of both dose point-kernels and Monte Carlo simulation methods is also discussed. PET and SPECT imaging can provide quantitative activity data in voxels of several millimeters on edge. For smaller voxel sizes, accurate data cannot be obtained using present imaging technology. For submillimeter dimensions, autoradiographic methods may be used when tissues are obtained through biopsy or autopsy. Sample S value tabulations for five radionuclides within cubical voxels of 3 mm and 6 mm on edge are given in the appendices to this pamphlet. These S values may be used to construct three-dimensional dose profiles for nonuniform distributions of radioactivity encountered in therapeutic and diagnostic nuclear medicine. Data are also tabulated for 131I in 0.1-mm voxels for use in autoradiography. Two examples illustrating the use of voxel S values are given, followed by a discussion of the use of three-dimensional dose distributions in understanding and predicting biologic response.     

Irradiation to the thyroid gland at cardiac catheterization and angiocardiography in children

Irradiation to the thyroid gland was measured during cardiac catheterization in 16 infants and 30 children aged 1 to 13 years. The doses from fluoroscopy, full-scale angiocardiography, and cineradiography were measured separately with thermoluminescent dosimeters and, in addition, the exposure-area product was assessed during fluoroscopy with a transparent ionization chamber. Median value of the absorbed dose to the thyroid from the complete heart investigation was 370 mrad in infants and 260 mrad in children. The highest values and also the greatest range in dosage were observed in infants. The quotient of the thyroid-absorbed dose divided by the integral dose or the dose per exposed film area was also highest in infants, due to anatomical conditions. The absorbed dose to the thyroid during heart catheterization comes almost exclusively from scattered radiation. By appropriate examination technique this dose can be kept within acceptable limits.     

A study of patient radiation doses in interventional radiological procedures

Patient radiation doses received during interventional radiological procedures can be significant. To aid in the establishment of reference dose levels, a patient dose survey has been conducted of such procedures. A total of 288 non-coronary procedures (177 classified as diagnostic and 111 as therapeutic) were accrued into the study. For each procedure, the fluoroscopy screening time and the fluoroscopic and digital radiographic dose-area products were recorded in a computer database. For example, median dose-area product values (due to fluoroscopy and digital radiography combined) of 24.2, 27.9, 69.6 and 74.7 Gy cm2 were obtained for nephrostomy, biliary stent removal/insertion, cerebral angiography and percutaneous transhepatic cholangiography procedures. While the effective dose is not an accurate measure of patient risk, it is convenient for comparing the radiological risks associated with various procedures. Effective doses were estimated from the total dose-area products. The respective median estimated effective dose values for the four procedures noted above were 3.9, 4.5, 7.0 and 12.0 mSv. While an infrequently performed procedure at this institution (n = 4 during this survey), the transjugular intrahepatic portosystemic shunt (TIPS) procedure had the greatest median dose-area product and effective dose values: 347 Gy cm2 and 55.5 mSv, respectively. Excluding the extreme case of TIPS, it was found that among commonly-performed procedures, those that are categorized as therapeutic do not necessarily present a statistically significant greater radiation risk than those which are diagnostic. Comparisons between dose-area product values obtained from this study are made with data from other interventional radiology patient dose surveys and reasons for some differences noted are discussed.     

Induction of apoptotic cell death in human leukemic cell line, HL-60, by extremely low frequency electric magnetic fields: analysis of the possible mechanisms in vitro

An anthropomorphic Rando phantom was used to compare radiation doses sustained during helical and conventional axial CT of the pelvis. The values obtained with the Rando phantom were validated against cadaveric phantoms, and show good agreement. For the authors' particular CT unit, helical scanning was found to deliver a lower radiation dose than conventional axial scanning. This was most prominent at 1.0-s tube rotation times (average dose ratio 1.24). For realistic scanning parameters and exposure factors, the ratio of radiation dose to pelvic organs can be expected to lie in the range of 40-100 mGy. The whole-body effective dose (ED) depends on selection of scanning parameters and patients anatomy. In a favourable case scenario, the ED for CT scanning of the pelvis in a male can be expected to be between 10 and 20 mSv if the scrotum is not included in the radiation field, while the ED in a female will be approximately 20 mSv. An examination of scatter radiation fall-off curves from a single slice shows that the spread of scatter radiation is only marginally affected by slice thickness. A total of 10-12 cm of human soft tissue acts as a good barrier against internal scattered radiation. The use of such scatter fall-off curves, together with manufacturers' dosimetry specifications, allows a fast estimate of absorbed dose.     

Follow-up study of patients treated by x-ray epilation for tinea capitis. Estimation of the dose to the thyroid and pituitary glands and other structures of the head and neck

This study is a further investigation of radiation dose to various head structures in the children given X-ray therapy for tinea capitis (ringworm of the scalp). In this work, estimates of the dose to the thyroid and pituitary gland were obtained with lithium fluoride thermoluminescent dosemeters using a child's head phantom. Doses were also measured for the parotid gland and several skin sites where skin tumours developed in the irradiated cases. In a previous study, brain and scalp doses of 140 and 500-800 rad had been estimated for the treated group using this same head phantom. In this work dosemeters were also placed in the same brain locations so that comparisons could be obtained between the two studies. The thyroid dose was estimated to be 6 +/- 2 rad and the pituitary dose was 49 +/- 6 rad for the conventional tinea capitis treatment. The dose to the parotid gland was 39 rad and the dose to skin sites on the face and neck where tumours occurred ranged from 20 to 40 rad. The data for the thyroid adenoma response from this and other studies involving irradiation of children suggests a linear dose-response relationship within the first 30-40 years after exposure with a risk of about 0-04% per rad.     

Geographical distribution of radiation risks in The Netherlands

Risk assessment of exposure to sources of radiation is an important tool for national governments in regulating radionuclide emissions and thus reducing radiation doses for the general public. For this reason radiation doses from sources throughout The Netherlands have been analyzed. For sources with well-defined locations and doses that were thought to vary significantly throughout The Netherlands, radiation dose maps were produced. Average dose values were calculated or derived from the literature for doses considered to be evenly distributed throughout the country or for which no information on the geographical distribution of dose was available. Emission, dispersion, and individual dose were modeled for each source using various pathways and exposure routes. Indoor radon and gamma radiation from building materials generate the highest dose values. The highest human induced radiation doses for industries of which the doses showed to be geographically distributed are found in the cement industry, elemental phosphorus production, phosphoric acid production, and iron and steel production. Radiation dose from some of these sources has a very local peak and decreases rapidly with distance. The elemental phosphorus production causes relatively high radiation doses throughout a large part of The Netherlands. Cumulation of doses from various sources occurs, but these are often masked by doses from a few large industries.