Dose evaluation of a flat-panel detector system

We compared the INNOVA2000 (INNOVA), which has a flat panel detector system, and the Advantx LCLP (LCLP), which has a conventional I. I. system, in terms of the dependence of phantom thickness on patient surface dose (surface dose) and receptor entrance dose (entrance dose). We examined the reduction in surface dose and entrance dose by using an additional filter and shortening the patient detector distance (PDD). The surface dose rate for fluoroscopy with INNOVA was 73.8-63.5%, and the reduction rate was high at a phantom thickness of less than 20 cm compared with LCLP, but such a reduction could not be expected at a phantom thickness of more than 30 cm, depending on maximum dose rate. The rate of reduction in surface dose in the case of exposure was considerably low at a phantom thickness of about 20 cm, while the other's (5, 10, 15, 25, 30 cm) reduction rates were about 40%. The length of PDD with INNOVA was shortened by 5 cm compared with LCLP. As a result, we obtained a reduction rate of surface dose of 11-15%, while the entrance dose was 10% lower. The reduction rate achieved with an additional filter was 43-60% in surface dose rate in fluoroscopy, whereas that of surface dose for exposure was about 50% at phantom thicknesses up to 20 cm, but remained just 25% thereafter. The results indicated that the reduction of surface dose with INNOVA could be changed by means of the phantom thickness, and we consider the effect achieved by the addition of a filter to be the main factor.     

Evaluation of an exposed-radiation dose on a dual-source cardiac computed tomography examination with a prospective electrocardiogram-gated fast dual spiral scan

We evaluated exposed-radiation doses on dual-source cardiac computed tomography (CT) examinations with prospective electrocardiogram (ECG)-gated fast dual spiral scans. After placing dosimeters at locations corresponding to each of the thoracic organs, prospective ECG-gated fast dual spirals and retrospective ECG-gated dual spiral scans were performed to measure the absorbed dose of each organ. In the prospective ECG-gated fast dual spiral scans, the average absorbed doses were 5.03 mGy for the breast, 9.96 mGy for the heart, 6.60 mGy for the lung, 6.48 mGy for the bone marrow, 9.73 mGy for the thymus, and 4.58 mGy for the skin. These values were about 5% of the absorbed doses for the retrospective ECG-gated dual spiral scan. However, the absorbed dose differed greatly at each scan, especially in the external organs such as the breast. For effective and safe use of the prospective ECG-gated fast dual spiral scan, it is necessary to understand these characteristics sufficiently.     

Reduction of radiation dose for cerebral angiography using flat panel detector of direct conversion type: a vascular phantom study

BACKGROUND AND PURPOSE: Compared with image intensifier television (I.I.-TV) system, an angiography system using the flat panel detector (FPD) of direct conversion type has a high spatial resolution, which may improve image quality, reduce patient exposure, or both. Our purpose was to evaluate the detection of simulated aneurysmal blebs under dose reduction with the FPD system in comparison with the I.I.-TV system. MATERIALS AND METHODS: A vascular phantom was designed to simulate various intracranial aneurysms with and without blebs, and this phantom was filled with 3 different concentrations of contrast material (300, 150, and 100 mg I/mL). 2D digital subtraction angiography (DSA) at low-dose mode of FPD system was compared with 2D DSA at a standard-dose mode of FPD system and a conventional mode of I.I.-TV system. Data analysis was based on 171 observations (57 aneurysms [20 with bleb and 37 without bleb] x 3 contrast material concentrations) by each of 7 radiologists, and the detection performances of blebs were compared using a receiver operating characteristic (ROC) analysis. RESULTS: The mean dose measurements with a phantom during 2D DSA were 0.36 mGy/frame with low-dose mode of FPD system, 0.72 mGy/frame with standard-dose mode of FPD system and 0.76 mGy/frame with I.I.-TV system. The mean Az at 100 mg I/mL was significantly higher for low-dose mode of FPD than for conventional-dose mode of I.I.-TV mean Az, 0.85 versus 0.56; P < .01), though differences were not significant with 150 and 300 mg I/mL between both systems. CONCLUSION: The FPD system allows a considerable dose reduction during 2D DSA without loss of the image quality.     

Absorbed radiation dose of the female breast during diagnostic multidetector chest CT and dose reduction with a tungsten-antimony composite breast shield: preliminary results

AIM: To determine the absorbed radiation dose to the female breast during chest computed tomography (CT), and whether a custom-designed breast shield can reduce that dose. MATERIALS AND METHODS: Bilateral breast phantoms were combined with an anthropomorphic torso phantom. Each breast phantom contained 20 thermoluminescent dosimeter (TLD) cavities. Eight cavities were used per phantom. Absorbed radiation was measured using TLD 100 s. Three-stacked TLDs comprised a set. Three sets of three TLDs were positioned at eight designated locations and three depths (surface; 1 cm; 4 cm). One set of three TLDs was positioned at eight additional designations, 1cm deep. Each breast was divided anatomically into quadrants. In total, 32 TLD sets/96 TLDs were deployed. The breast-torso phantom was consecutively imaged using a 16-detector array CT machine. Subsequently, 32 new TLD sets were similarly placed, the phantom re-imaged in a likewise manner, but with the application of a tungsten-antimony composite breast shield. TLD readings were averaged and calculated. RESULTS: Average absorbed radiation doses for unshielded right and left breast phantoms ranged from 13.83-19.36 mGy, and 14-20.47 mGy, respectively. The absorbed dose in the shielded right and left breast was reduced to 6.64-8.12 mGy, and 6.7-8.03 mGy, respectively. Average absorbed radiation doses based on the depth for the unshielded breasts ranged from 15.4-18.3 mGy. Shielding reduced this dose to 7-7.9 mGy. Unshielded absorbed radiation doses based on anatomic quadrants ranged from 17.5-18.9 mGy. Shielding reduced this dose to 7-7.5 mGy. CONCLUSIONS: The average absorbed radiation dose to the unshielded female breast phantom is approximately 14-20 mGy. An externally applied shield can reduce this absorbed dose by 56-61%.     

Lens of the eye: radiation dose in balloon dacryocystoplasty

PURPOSE: To evaluate the absorbed radiation dose to the lens of the eye, which is the critical organ in the primary beam during fluoroscopically guided transluminal balloon dilation of the lacrimal drainage system (balloon dacryocystoplasty) for obstructive epiphora and to evaluate the possibility of deterministic radiation effect on the lens. MATERIALS AND METHODS: The radiation dose to the lens of the eye during balloon dacryocystoplasty (which includes pre- and postintervention dacryocystography) was measured in 10 consecutive patients by using thermoluminescent dosimeters on the lids of both eyes as close as possible to the lenses. A C-arm angiographic unit coupled with a digital imaging system was used, with similar exposure and geometric parameters in all cases. RESULTS: The mean radiation dose to the lens of the treated eye was 4.6 mGy +/- 2.2 (dose range, 1.9-9.1 mGy) and to that of the untreated eye was 38.5 mGy +/- 17.5 (dose range, 14.7-67.8 mGy). CONCLUSION: The lens of the untreated eye receives a higher dose than that of the treated eye because of its closer proximity to the x-ray tube in a lateral projection. In the lens, even the highest measured radiation dose (67.8 mGy) still was well below the deterministic threshold for lens opacity and cataract formation.     

Evaluation of a MOSFET radiation sensor for the measurement of entrance surface dose in diagnostic radiology

A patient dosimetry system using MOSFET technology (Thomson and Neilson Electronics Ltd, Canada) is evaluated for entrance surface dose measurements in diagnostic radiology. The system sensitivity for the standard MOSFET detector coupled to a high sensitivity bias supply was measured to be 1 mV mGy-1. Response of a new high sensitivity dosemeter was measured to be 3 mV mGy-1. The minimum detectable entrance surface dose at which a single measurement can be made with less than 25% total uncertainty at the 95% confidence level was estimated to be 4 mGy for the standard dosemeter and 1.5 mGy for the new high sensitivity dosemeter. The dosemeters were found to be linear with absorbed dose in air, linear with dose rate and reproducible, although they showed some energy dependence across the diagnostic energy range. The system is also compared with thermoluminescent dosimetry (TLD) as a tool for the measurement of entrance surface dose in diagnostic radiology. MOSFET detectors are considered to have advantages over TLD dosemeters with the instant readout of entrance surface dose. These dosemeters do have the disadvantage that they are visible in radiographs, they have a finite shelf life and can only accumulate absorbed dose up to a limiting value after which the dosemeters can no longer be used.     

CT of the head by use of reduced current and kilovoltage: relationship between image quality and dose reduction

BACKGROUND AND PURPOSE: CT is a frequent examination that is performed using ionizing radiation. We sought to assess image-quality changes on CT scans of the head when the radiation dose is reduced by changing tube current and kilovoltage. METHODS: A formalin-fixed cadaver was examined in conventional and helical mode by use of two CT-scanners. Surface dose was measured with standard scanning parameters, and after reduction of tube current and kilovoltage. Five experienced examiners independently evaluated subjective image quality. RESULTS: In the conventional mode, the highest surface dose was 83.2 mGy (scanner 1: helical mode, 55.6 mGy), and 66.0 mGy (scanner 2: helical mode, 55.9 mGy). By changing kVp and mAs, a dose reduction of up to 75% (scanner 1), and 60% (scanner 2) was achieved. No observable differences in image quality between scans obtained with doses from 100% to 60% of standard settings were noted. Ten of 20 images obtained with the highest dose and 13 of 20 images obtained with lowest dose (19-29.4 mGy) were reliably identified by subjective quality assessment. Scans produced with a surface dose of less than 30 mGy were judged uninterpretable. CONCLUSION: Standard parameters used in cranial CT are oriented toward best image quality. A dose reduction up to 40% may be possible without loss of diagnostic image quality.     

Quantification of the whole-body distribution of PET radiopharmaceuticals,applied to 3-N-([18F]fluoroethyl)spiperone

Using a multi slice whole body PET scanner PC4096-15WB, diagnostic measurements of the cerebral distribution of the D₂ receptor ligand 3-N-([¹⁸F]fluoroethyl)spiperone were extended to quantify the biodistribution of this PET radiopharmaceutical. As a rotating line source was used for measured attenuation correction, transmission scans could be combined with emission scans even after injection of the tracer. Only 1 of the total administered dose (TAD) was found in the whole brain at 180 min, but the striatum and pituitary were still excellently delineated. Urinary bladder, gall bladder, and liver were the organs with the highest TAD ranging from 6% to 25%. The gall bladder is the critical organ with an absorbed dose of about 200 mGy/kBq followed by the urinary bladder and liver with 83 and 66 mGy/kBq, respectively. In the rest of the body radioactivity was evenly distributed. The total body dose was found to be 11.9 mGy/kBq.     

In vivo absorbed dose measurements in mammography using a new real-time luminescence technique

A dosimetry system based on radioluminescence (RL) and optically stimulated luminescence (OSL) from carbon doped aluminium oxide (Al2O3:C) crystals was developed for in vivo absorbed dose measurements in mammography. A small cylindrical crystal of Al2O3:C (diameter 0.48 mm and length 2 mm) was coupled to the end of a 1 mm diameter optical fibre cable. Owing to their small size and characteristic shape, these probes can be placed on the body surface in the field of view during the examination, without compromising the reading of the mammogram. Our new technique was tested with a mammography unit (Siemens Mammomat 3000) and screen-film technique over a range of clinically relevant X-ray energies. The results were compared with those obtained from an ionization chamber usually used for the determination of absorbed dose in mammography. The reproducibility of measurements was around 3% (1 standard deviation) at 4.5 mGy for both RL and OSL data. The dose response was found to be linear between 4.5 mGy and 30 mGy. The energy dependence of the system is around 18% between 23 kV and 35 kV. In vivo measurements were performed during three patient examinations. It was shown that entrance and exit doses could be measured. The presence of the small probes did not significantly interfere with the diagnostic quality of the images. Entrance doses estimated by RL/OSL results agreed within 3% with entrance surface dose values calculated from the ionization chamber measurements. These results indicate a considerable potential for use in routine control and in vivo dose measurements in mammography.     

3D cerebral angiography: radiation dose comparison with digital subtraction angiography

BACKGROUND AND PURPOSE: As the use of 3D rotational angiography (3D RA) for the evaluation of cerebral vasculature becomes more widespread, it is important to evaluate this imaging method's effect on patient radiation dose. The purpose of the study is to measure 3D RA radiation dose as compared with biplanar digital subtraction angiography (DSA). METHODS: The distribution and peak skin dose were measured for 3D RA and biplanar DSA by using an anthropomorphic skull phantom. In addition, the cumulative incident dose, summed over all images in each acquisition, was determined. Measurements were acquired for our facility's standard 3D RA acquisition mode (25 degrees /s rotational speed; 162 total frames) and other available acquisition mode selections. RESULTS: For 3D RA, the skin dose was found to be distributed across the back and sides of the skull with the peak skin dose located at the center of the back of the skull. The peak skin dose for the standard 3D RA acquisition mode was 15 mGy. For a biplanar DSA run, the peak skin dose was 58 mGy, also located at the back of the skull. The cumulative incident dose for the standard 3D RA acquisition mode was 33 mGy, compared with 53 mGy for biplanar DSA. CONCLUSION: The patient radiation dose for 3D RA is significantly lower than for biplanar DSA, by nearly a factor of 4 in peak skin dose and 40% lower in cumulative incident dose.     

Biodistribution and radiation dosimetry of [<Superscript>123</Superscript>I]ADAM in healthy human subjects: preliminary results

[(123)I]ADAM [2-((2-((dimethylamino)methyl)phenyl)thio)-5-iodophenylamine (ADAM)] has recently been shown to be a very promising imaging ligand for the detection of serotonin transporters (SERT) in human brain, because of its high specificity for SERT. [(123)I]ADAM has previously been used only for animal studies. In this work, we investigated the radiation dosimetry and biodistribution of [(123)I]ADAM based on whole-body scans in healthy human volunteers. Following the administration of 196+/-20 MBq (range 157-220 MBq) [(123)I]ADAM, serial whole-body images were performed up to 24 h. Estimates of radiation absorbed dose were calculated using the MIRDOSE 3.0 program with a dynamic bladder model. Twelve source organs were considered in estimating absorbed radiation doses for organs of the body. The highest absorbed organ doses were found to the lower large intestine wall (8.3.10(-2) mGy/MBq), kidneys (5.2.10(-2) mGy/MBq), urinary bladder wall (4.9.10(-2) mGy/MBq) and thyroid (4.3.10(-2) mGy/MBq). The effective dose was estimated to be 2.2.10(-2) mSv/MBq. The results suggest that [(123)I]ADAM is of potential value as a tracer for single-photon emission tomography imaging of serotonin receptors in humans, with acceptable dosimetry and high brain uptake.     

Dosimetry of rhenium-188 diethylene triamine penta-acetic acid for endovascular intra-balloon brachytherapy after coronary angioplasty

To examine the possibility of using rhenium-188 diethylene triamine penta-acetic acid (DTPA) for endovascular intra-balloon brachytherapy after angioplasty, dose distribution around the balloon was calculated and validated by film dosimetry. Medical internal radiation dosimetry (MIRD) was calculated assuming that the balloon had ruptured and that the contents had been released into the systemic circulation. 188Re-perrhenate eluate from the 188W/188Re generator was concentrated using an ion column and used to label DTPA. The dose distribution around the angioplasty balloon (20 mm length, 3 mm diameter cylinder) was estimated by Monte Carlo simulation using the EGS4 code. The time required for 17.6 Gy to be absorbed at 1 mm from the balloon's surface following application of 3700 MBq/ml of 188Re was found to be 278 s. Fifty percent of the energy was deposited in the first millimetre of the vessel wall from the balloon's surface. The calculated radiation absorbed dose agreed with that measured by film dosimetry, which was performed using a water phantom, with errors ranging from 9.4% to 17%. Upon balloon rupture the total amount of 188Re-DTPA was presumed to enter the systemic circulation. The resulting radiation absorbed dose was calculated using the MIRDOSE3 program and residence times obtained from dogs and amounted to 0.0056 mGy/MBq to the whole body and 4.56 mGy/MBq to the urinary bladder. The absorbed dose of 188Re-DTPA to the whole body was one-tenth of that of 188Re-perrhenate. A window-based program was developed to calculate the exposure time and the radiation dose absorbed as a function of the 188Re concentration and the arbitrary distance from the balloon to the surrounding tissues. We conclude that 188Re-DTPA is easy to prepare, safe to use and suitable for intra-balloon brachytherapy after coronary angioplasty.     

全数字乳腺X线3种摄影模式的影像质量和辐射剂量比较

目的 探讨全数字乳腺X线摄影(FFDM)不同摄影模式影像质量与辐射剂量的比较研究.方法 用全数字乳腺X线摄影的对比度优先模式(CNT)、标准模式(STD)及辐射剂量优先模式(DOSE)对FLUKE NA 18-220乳腺模体进行摄影,摄影采用自动曝光模式(AEC),记录摄影条件和辐射剂量.由4位影像学医师在相同条件下进行软阅读,并按照美国放射学会(ACR)的评分标准对模体中的钙化点、尼龙纤维、肿块灶进行评分.结果 标准模式、辐射剂量优先模式及对比度优先模式的模体影像评分值分别是11.5、11.0和14.5,标准模式及辐射剂量优先模式与对比度优先模式的影像质量差异有统计学意义(F=41.321,P＜0.05).标准模式与辐射剂量优先模式之间影像质量差异无统计学意义,但两种模式的辐射剂量却不相同,其表面入射剂量分别是4.5和3.15 mGy,腺体平均剂量(AGD)分别是1.18和0.78 mGy.结论 全数字乳腺摄影的辐射剂量优先模式和标准模式适合大多数被检者,特别是辐射剂量优先模式.对比度优先模式应严格控制使用.

Abstract：

Objective To study the difference of image quality and radiation dose between different exposure modes with full-field digital mammography (FFDM).Methods The Fluke18-220mammographic phantom was exposed by FFDM system with different exposure modes at automatic exposure control ( AEC ) ,including contrast mode,standard mode and dose mode,and the exposure factors and radiation dose were recorded.The images on monitor with the best window width and window level were read by four independent radiologists.The images of specks groups,nylon fibers and masses was assessed by the four experienced readers at the criterion of American College of Radiology.Results The detection of specks groups,nylon fibers and masses were statistically different at the contrast mode and standard mode (F =41.321,P ＜ 0.05),further at the contrast mode and dose mode.The detection of specks groups、nylon fibers and masses were not statistically different( P ＞ 0.05 ) at standard mode and dose mode,but the radiation doses were different.The ESD at standard mode and dose mode was 4.5 and 3.15 mGy,respectively.The AGD of standard mode and dose mode was 1.18 mGy and 0.78 mGy,respectively.Conclusions The standard mode and dose mode of FFDM might be fit for most patients,especially at the dose mode.Contrast mode of FFDM should be strictly controled in use.     

Survey of computed tomography technique and radiation dose in Sudanese hospitals

The purpose of this study was to survey technique and radiation absorbed dose in CT examinations of adult in Sudan and to compare the results with the reference dose levels. Questionnaire forms were completed in nine hospitals and a sample of 445 CT examinations in patients. Information on patient, procedure, scanner, and technique for common CT examinations were collected. For each facility, the radiation absorbed dose was measured on CT dose phantom measuring 16 cm (head) and 32 cm (body) in diameter and was used to calculate the normalized CT air kerma index. Volume CT air kerma index (CVOL), CT air kerma-length product (PKL,CT) values were calculated using the measured normalized CT air kerma index and questionnaire information. The effective dose, E estimates was determined by using PKL,CT measurements and appropriate normalized coefficients. Assuming the sample to offer a fair representative picture of CT practice patterns in Sudan, the mean CVOL and PKL,CT values were comparable or below the reference doses: 65 mGy and 758 mGy cm, respectively at head CT; 11.5 mGy and 327 mGy cm, respectively at chest CT; 11.6 mGy and 437 mGy cm, respectively at abdominal CT; and 11.0 mGy and 264 mGy cm, respectively at pelvis CT. Estimated effective doses were 1.6, 4.6, 6.6 and 4.0 mSv, respectively. The study offered a first national dose survey and provided a mean for quality control and optimization of CT practice within the country.     

The 3rd international intercomparison on EPR tooth dosimetry: Part 1, general analysis.

The objective of the 3rd International Intercomparison on Electron Paramagnetic Resonance (EPR) Tooth Dosimetry was the evaluation of laboratories performing tooth enamel dosimetry below 300 mGy. Participants had to reconstruct the absorbed dose in tooth enamel from 11 molars, which were cut into two halves. One half of each tooth was irradiated in a 60Co beam to doses in the ranges of 30-100 mGy (5 samples), 100-300 mGy (5 samples), and 300-900 mGy (1 sample). Fourteen international laboratories participated in this intercomparison programme. A first analysis of the results and an overview of the essential features of methods applied in different laboratories are presented. The relative standard deviation of results of all methods was better than 27% for applied doses in the range of 79-704 mGy. In the analysis of the unirradiated tooth halves 8% of the samples were identified as outliers with additional absorbed dose above background dose.     

Radiation protection in the use of tracers in radioguided breast surgery

PURPOSE: Recent techniques in nuclear medicine have permitted to implement new procedures useful in surgery. Among these, the procedures for locating sentinel lymph nodes and nonpalpable breast lesions are of great interest. The protocols for the location of the sentinel lymph node and for the radioguided location of occult lesions developed at the European Institute of Oncology (IEO, Milan) are based on the administration of radiopharmaceuticals labelled with Technetium-99m (99mTc). We evaluated the dosimetric data relative to patients and hospital personnel to assess whether specific radiation protection procedures are needed. MATERIAL AND METHODS: Fifty patients with nonpalpable breast lesions and 50 patients with suspected lymph node involvement were enrolled in this study. All the patients underwent surgery the day after in-loco administration of the radiopharmaceutical (11 MBq of 99mTc). The absorbed dose to the hospital personnel was estimated from the air kerma rate measured by ionization chamber at different distances from the patients at 0 and 16 hours after the radiopharmaceutical administration. In order to evaluate radiation protection for patients, absorbed doses were measured positioning thermoluminescent dosimeters on the patient's skin for about 16 hours. In the operating room, activity was measured on some excised tissues (lymph nodes and tumors) and on surgical instruments. RESULTS: Absorbed doses were very low for the clinical staff also in case of prolonged patient assistance. After 100 cases, the surgeon mean absorbed dose to the hands and mean effective dose were .45 mGy and .09 mGy, respectively. These values correspond to 1% of the annual dose limit to the hands and to 10% of the annual equivalent effective dose recommended for the population (ICRP 60 and law by decree 230/95). The absorbed dose to healthy tissues of the patients were lower than 1 mGy (mean values: contralateral breast: .9 mGy; abdomen .45 mGy). The mean activity detected in the excised tissues was 9 kBq and 900 kBq in the sentinel lymph nodes and in the tumor lesions (injection site), respectively. The activity detected on the surgical instruments, higher on gauzes (< 100 kBq), was negligible. CONCLUSIONS: From the radiation protection point of view, the data support the validity of our protocols. Absorbed doses to the hospital personnel are low and require neither a radiation protection control nor a classification of exposed workers as classes A or B. Special containers for radioactive wastes are necessary in the administration room but not in the operating room, where the levels of possible contamination are negligible.     

Long-term irradiation of a marine fish, the plaice Pleuronectes platessa: an assessment of the effects on size and composition of the testes and of possible genotoxic changes in peripheral erythrocytes.

PURPOSE: Previous investigation showed the very significant effects of chronic gamma-radiation on plaice testes at mean absorbed dose rates as low as 1.3 mGy h(-1) given over a period of 168 days (accumulated dose 4.7 Gy). The present paper examines the effects on the testes of exposure to even lower dose rates of gamma-radiation given over periods of 73 days or 197 days. In addition, the use of micronucleus counts and flow-cytometric measurement of nuclear DNA content in samples of peripheral blood for monitoring genotoxic effects has been assessed. MATERIALS AND METHODS: In Experiment 1, adult male plaice were exposed at mean absorbed dose rates of 0.25, 0.5 or 1.2 mGy h(-1) for 73 days (mean accumulated doses of 0.43, 0.85 and 2.03 Gy, respectively) and in Experiment 2 to 0.24, 0.5 or 1.0 mGy h(-1) for 197 days (mean accumulated doses of 1.07, 2.24 and 4.57 Gy, respectively). At termination the testes were removed, weighed and sections were prepared and examined histometrically. In addition, in Experiment 2, blood samples were taken during exposure and at termination. Blood smears were scored for micronuclei and samples processed and examined for nuclear DNA content by flow cytometry. RESULTS: Significant reductions in testis weight were seen in all radiation groups after 197 days of exposure, which were predominantly due to decreased amounts of sperm. In plaice killed after 73 days (at an earlier stage of spermatogenesis), there were no significant differences in weight compared with controls but amounts of spermatogonia were significantly reduced in irradiated fish. CONCLUSIONS: Exposure to dose rates as low as 0.24 mGy h(-1) of gamma-radiation given over a period of 197 days significantly reduced the weights of plaice testes, this being consequent on reductions in the amounts of sperm. Although there was some evidence of radiation affecting the numbers of spermatogonia it was not possible to determine the primary target for radiation damage which eventually caused the sperm reductions. Along with the related work described by Greenwood and Knowles (1996) this is the first investigation of a marine fish and it indicates that plaice testes are probably more radiosensitive than those previously described in tropical fish and of a similar radiosensitivity to mammalian testes. Although significant effects were observed after the lowest dose rate used of 0.24 mGy h(-1), this is still a factor of about 400 times greater than the estimated absorbed dose rate to plaice testes in the north-east Irish Sea off Sellafield at the present time. Micronucleus counts and flow-cytometric analysis of blood DNA both failed to show any evidence of genotoxic damage.     

Radiation dosimetry estimates of [18F]-fluoroacetate based on biodistribution data of rats

We estimated the dosimetry of [(18)F]fluoroacetate (FAC) with the method established by MIRD based on biodistribution data of rats. We selected some important organs and computed their residence time, their absorbed doses and effective dose with the (%ID(Organ)) (human) data using OLINDA/EXM 1.1 program. We observed the highest absorbed doses in the heart wall (0.025mGy/MBq) and the lowest in skin (0.0079mGy/MBq). The total mean absorbed doses and the effective doses were 0.011mGy/MBq and 0.014mSv/MBq, respectively. A 370-MBq injection of FAC leads to an estimated effective dose of 5.2mSv. The potential radiation risk associated with FAC/PET imaging is well within the accepted limits.     

Evaluation of patient entrance dose rate of interventional X-ray equipment

Because interventional radiology (IVR) procedures are being performed with increasing frequency, patient X-ray exposure dose for X-ray fluoroscopic and radiographic procedures should not be ignored. In order to avoid excessive X-ray exposure, exposure dose rate limits are specified in the Japanese Industrial Standards (JIS) and by civil law at 50 mGy/min for usual fluoroscopy and 125 mGy/min for high-dose fluoroscopy. In the present study, we examined the difference in patient incident dose rate before and after using an X-ray generator that satisfied the above requirements. For incident dose to the image intensifier (I.I.), we investigated the differences between continuous and pulsed fluoroscopy, the effects of additional filters (Ta: tantalum, Al: aluminum), and the form of the X-ray spectrum. For pulsed fluoroscopy using PMMA (polymethyl-methacrylate), the maximum patient incident dose rates of usual and high-dose fluoroscopy were 59 mGy/min and 151 mGy/min, respectively. With regard to I.I. incident dose, saturation was observed beginning at a PMMA of 20 cm, and the X-ray dose was insufficient. In terms of the difference in patient incident dose rate with Ta and Al filters, the dose rate with the Ta filter was approximately 50% lower than that with the Al filter except for the saturation area. Concerning the X-ray spectrum, it was considered that a Ta filter not only minimizes patient X-ray exposure (because Ta reduces soft X-rays more effectively than Al) but also minimizes scattered X-rays because it filters out hard X-rays, leading to improved image quality. However, the use of the filter is appropriate only when a sufficient I.I. incident dose can be ensured. Specifically, the use of the filter under saturation conditions can lead to deterioration in image quality. Therefore, IVR X-ray systems must be equipped with an appropriate filter for reducing X-ray exposure while maintaining a sufficient I.I. incident dose rate.     

Radiation dose to the testes after 131I therapy for ablation of postsurgical thyroid remnants in patients with differentiated thyroid cancer.

Radioiodine-131 is used in differentiated thyroid cancer (DTC) for ablation of postsurgical thyroid remnants and destruction of metastases. The question may be raised of whether 131I treatment of DTC in male patients may give an irradiation dose to the testes that could impair fertility. Few data in the literature concern the dose absorbed by the testes after 1311 therapy for DTC. Because 131I kinetics may be altered by the hypothyroid condition commonly present at the time of treatment and by the radioiodinated iodoproteins released by the damaged thyroid tissue, the dose values reported in the International Commission on Radiological Protection (ICRP) tables for euthyroid men may not be appropriate. To clarify this problem, three male subjects undergoing 131I therapy for ablation of thyroid remnants shortly after thyroidectomy for DTC were studied. METHODS: The mean administered activity was 1256 MBq, and the duration of the study was 2 wk. The gamma dose was measured by thermoluminescent dosimeters (TLDs) applied to the lower poles of the testes. Correction factors were calculated for the distance of the TLD from the center of the testes and for attenuation by the testes of the gamma rays reaching the TLD. After correction, the gamma dose to the testes ranged from 21 to 29 mGy. The gamma dose calculated by the Medical Internal Radiation Dose (MIRD) method from blood and urine samples was similar (18-20 mGy) to that measured by TLDs. The beta dose was estimated by the MIRD method from blood activity and testicular volume and ranged between 14 and 31 mGy. Results: The total (beta and gamma) doses to testes were 30, 33 and 43 microGy/MBq in the three subjects. CONCLUSION: These values are close to those derived from the ICRP tables (26-37 microGy/MBq 131I) for euthyroid subjects. The present data indicate that significant irradiation is delivered to the testes after the administration of the 131I ablative dose to thyroidectomized patients. The relevance of the radiation absorbed by testes on fertility remains to be established.