| | Estimation of radiation dose received during treatment of in-stent restenosis using ionizing radiation☆Accepted 6 April 2005. Abstract BackgroundAngioplasty is a widely accepted procedure for the treatment of coronary artery disease. However, restenosis of the treated vessel occurs in 30% of patients within 6 months. Intravascular brachytherapy (IVB) is used to inhibit the formation of new tissue growth at the vessel treatment site. IVB protocols using either gamma ray or beta particle emitting isotopes have been tested and approved. However, very little data are available on resultant whole-body dose and the potential for long-term radiation effects. MethodsUsing thermoluminescence dosimetry (TLD) devices, specifically lithium fluoride (LiF) doped with Mg, Cu, and P, the radiation dose on the surface of patients undergoing IVB was measured. The TLDs were positioned on the body to obtain a measure of the gamma dose at selected anatomic locations. Additionally, the skin dose from fluoroscopy was estimated. ResultsMeasurements indicate that the average body dose on the skin surface from all TLDs, clinical requirements, and gamma source configurations varies from 0.95 mSv (95 mrem) at the head to 27.06 mSv (2706 mrem) at the sternal notch. For beta sources, the dose varied from 0.11 mSv (11.4 mrem) at the head to 0.49 mSv (49.5 mrem) at the sternal notch. The fluoroscopy contribution of dose to the body dose (15-min exposure time) was 0.10 mSv (10 mrem) at the head and 2.57 mSv (257 mrem) to the sternal notch. ConclusionsThe results suggest that surface skin exposures from gamma sources used in IVB pose acceptable risks considering the medical benefits of the procedures. 1. Introduction  Balloon angioplasty is a standard procedure for the treatment of coronary artery disease. Angioplasty involves passing a catheter into a blocked artery and inflating a small balloon to open a stenotic vessel to restore blood flow. In many of these procedures, a biocompatible metal stent is placed at the treated site to reinforce the arterial wall and keep the artery patent. In some cases, angioplasty promotes a wound healing response (neointimal hyperplasia), and within 6 months of angioplasty, approximately 30% of patients suffer from restenosis of the treated coronary artery [1], [2]. An artery has restenosed if the lumen of the treated arterial section narrows to less than 50% of the lumen diameter of adjacent vessel segments. Restenosis may result from a hyperplastic phenomenon such as scar tissue formation. The scar tissue is an attempt of the arterial wall to heal as a result of the microscopic damage induced by angioplasty. In response to the microscopic damage, smooth muscle cells are stimulated to divide and pass through the tear in the endothelial lining of the arterial wall and form scar tissue [2], [3]. Radiation is known to be effective in treating both malignant and benign diseases and hyperplastic conditions such as keloids, pterygium, and heterotopic ossification [4]. Presumably, radiation has the same lethal and inhibitory effects on the rapidly dividing smooth muscle cells that make scar tissue in arterial vessels [3], [4]. The radiation modality used to inhibit coronary artery restenosis is known as intravascular brachytherapy (IVB). Brachytherapy consists of placing a source of radioactivity in or near the afflicted tissue to give a localized treatment of radiation. In the case of IVB, radioactive sources are inserted in the artery lumen via catheters or stents. IVB has been found useful in inhibiting the formation of new tissue growth in such a way that there is a reduction in smooth muscle cells and thickness of the intimal tissue layer of the artery and, thus, a reduction in scar tissue formation [1], [2], [3], [4]. IVB protocols using either gamma ray or beta particle emitting radioisotopes have been tested and FDA approved. Whether IVB protocols are administered using gamma or beta radiation sources, certain dosimetry criteria must be met. The IVB dosimetry criteria includes (i) single acute fraction of 10–30 Gy to an arterial segment 2–4 cm in length, 2–5 mm diameter, and 0.5–3.0 mm thick; (ii) high dose volume localized to the region of angioplasty, with a minimum dose to normal vessels and myocardium; and (iii) dose rates >2 Gy/min [2], [4]. In addition, the radioactive sources used must have dimensions, stiffness, and flexibility that are compatible for use with angioplasty catheters. To meet the above criteria, the ideal radioactive source requires a high specific activity, long half-life, and uniform dose distribution over a 2- to 3-mm distance [2]. Clinical trials have been performed using iridium-192, phosphorus-32, and strontium-90/ytrium-90, among others. At present, there is no ideal radioactive source and there are advantages and disadvantages to both the gamma ray and beta particle emitting sources used in the clinical trials, almost with an equal and opposite impact [2], [4]. The gamma source (Ir-192) easily penetrates target tissues with a greater homogeneity to the target volume than the beta sources do (P-32 and Sr-90/Y-90). However, the gamma radiation treatment takes longer to deliver—20 min as opposed to 3–5 min with the beta sources. Radiation safety and shielding issues present apparent problems when dealing with the high-energy gamma source, whereas the beta emitters are easily shielded, but clinically, the dose distribution diminishes rapidly from the source [3], [4]. Aside from thrombosis, no remarkable complications have occurred in treated patients [4]. However, as suggested by many investigators, several years of follow-up will be needed before ruling out late or long-term effects of IVB, such as pericardial disease, myocardial fibrosis, aneurysms, and cancer. With IVB, the body dose absorbed by the patient treated with gamma sources is excessive when compared with vascular brachytherapy procedures using beta emitters, simply by virtue of the radiation characteristics of gamma and beta sources. There are minimal data available on patient whole-body dose as a result of IVB, and subsequently, little is known about the potential long-term radiation effects, in particular radiation carcinogenesis. The purpose of this research is to estimate, experimentally, the radiation doses received by patients undergoing coronary artery restenosis inhibition using Ir-192. Historically, radiation has been used to treat malignancies for which, without radiation treatment mortality, is inevitable and the risk of secondary malignancies is well known and documented. Restenosis is not a malignant progression. Furthermore, the restenosis problem may necessitate repeated cardiac procedures, such as angioplasty, IVB, and bypass surgery, which not only carry an invasive risk but risk of additional radiation exposures due to clinical procedures that use fluoroscopy. Patients should be provided with a reasonable estimate of radiation dose and associated risk for an intended treatment to give informed consent. To express radiation risk, the effective dose equivalent1 (EDE) could be provided with a comparison of the EDE as a magnitude or fraction of background radiation or occupational dose. Without a good estimate of the radiation dose to the whole body, the health risks associated with IVB procedures are not realized. 2. Materials and methods  2.1. Theory Thermoluminescence dosimetry (TLD) was used for patient dose evaluation. More specifically, lithium fluoride (LiF) doped with Mg, Cu, and P was selected. The TLD elements are also known as LiF(Mg,Cu,P) and are available commercially as TLD-100H. In theory, inorganic crystals such as LiF doped with impurities that are exposed to ionizing radiation will emit light when heated. The movement of charges within an inorganic crystal exposed to ionizing radiation can be described by the energy band gap model. Radiation will elevate an electron from the valence band to the conduction band, leaving a hole in the valence band. The electron and hole may migrate through the crystal until they recombine or become trapped in the energy gap at crystal impurity sites. This process continues during exposure to ionizing radiation, with a subsequent build up of trapped electron and holes. The number of trapped electrons and holes is a measure of the number of electron–hole pairs formed by the radiation exposure. To determine the number of trapped holes and electrons, the TLD material is progressively heated. When a sufficient temperature is reached, the trapped electrons or holes gain enough thermal energy to overcome the trapping forces and are freed. When a freed electron recombines with a trapped hole, a visible light photon is emitted [5], [6]. 2.2. Materials The TL elements were provided by Bicron NE in the form of pellets with dimensions of 3.60 mm diameter×0.38 mm thick. Fifty pellets were available. TLD-100H was selected because of its near tissue equivalence, low fading rate, and dose linearity range, from 1 μGy to 10 Gy. A commercial TL reader was used to heat the TL elements and detect the emitted light. The light yield is recorded as a function of temperature—known as a glow curve. The peaks in the glow curve correspond to different trapped energy levels. The area under the glow curve represents the total number of emitted photons and thus represents a measure of the incident radiation or radiation dose. The dosimetric characteristics of TLD-100H are discussed in detail in Ref. [7]. The TL characteristics of TLD-100H that were particularly useful for this investigation included sensitivity, repeatability, energy response, linearity, and fading. Sensitivity is defined as the amount of light released by the phosphor per unit absorbed dose. The difference in sensitivity between any two dosimeters from the same batch should not exceed 30% [7]. The difference in sensitivity is an indicator of batch homogeneity. The batch homogeneity observed for the experimental TL elements was 0.908 to 1.19. The two TL elements exceeding ±15% uniformity range were not used for patient data analysis. Because TL elements do not have the same sensitivity as noted above, elemental correction coefficients (ECCi) were calculated and applied to each TL element. ECCi=<Q>/Qi where <Q> is the mean signal of all dosimeters and Qi is the individual signal (Harshaw Bicron 1993). The ECCi for each dosimeter was calculated for three independent irradiations2. The three values were averaged to yield each dosimeters unique ECCi,avg. The coefficient of variation for repeated evaluations of a dosimeter should be less than 7.5% [7]. The CV range observed from the experimental TL elements was 0.9% to 8.2%. The six TL elements exceeding 7.5% were not used for patient data analysis. A dosimeter has a good energy response if the response per exposure shows little change with photon energy. Detectors with an effective atomic number, Z, approximately that of air (7.64) show a good energy response. TLD-100H has an effective atomic number of 8.2. As result, there is an enhanced response at low photon energies (<30 keV) due to the predominance of photoelectric absorption. For the experiment, TL elements were exposed to photon energies of 0.13 to 1.06 MeV from the Irdium-192 and fluoroscopic X-rays of less than 80 kVp3. For TLD-100H, the dose response curve is linear–sublinear. The linearity range extends from 1 μGy to 10 Gy [7]. The observed dose range from the experiment was 1 μGy to 13 cGy. For the investigation, the time interval between exposure and readout would not be the same for each set of patient TL elements exposed. Therefore, the stability of the TL element is critical. Loss of stored signal would jeopardize the accuracy of measured absorbed dose. According to Ref. [7] and claims by Bicron, there has been no measurable fading in TLD-100H up to 2 months when stored at room temperature. TL elements from patients were read at 24 h and up to 2 weeks postirradiation. 2.3. Calibration of dosimeters To determine the absorbed dose, the TL elements were exposed to the expected dose range (0.1 to 10 mGy) using a cesium-137 beam at NIST in Gaithersburg, MD (cesium-137 #2752; 17.8794 μGy/s on 12/31/86; 13.225 μGy/s on 1/19/00). The dosimeters were mounted with an acrylic buildup of 3 mm on a Plexiglass block at 300 cm from the cesium-137 source. A calibration was also performed using iridium-192 (a NIST calibrated Ir-192 source; 0.07 μGy/s on 1/19/00). Dosimeters exposed to the iridium-192 source were mounted on a Plexiglass block at 96.97 cm from the source, with a 1-mm buildup, and exposed to a dose of 0.25 mGy. The dosimeters were calibrated in terms of the integral value of the TL glow curve per unit dose, mSv/nC. Dosimeters were irradiated to yield the following: 0.06, 0.09, 0.12, 0.14, 0.16, 0.19, 25, 0.37, 0.62, 0.86, 1.22, 1.83, 2.43, 3.64, 6.06, 8.48, and 12.11 mSv. The calibration factor to convert from signal (nC) to dose (mSv) is the slope of the calibration line (mSv/nC) and was determined to be 0.021. For cesium-137 and iridium-192, a conversion4 from air kerma to absorbed dose (Sv) in tissue at a 10-mm depth was applied to the calibration dosimeters. TL element packets were constructed to hold three TL elements. The packet was composed of a polyethylene terephthalate (PET) backing, cardboard divider, and acetate cover. The packet dimensions were 2.0×2.0 cm, with a total thickness of 0.8 mm. The TL packets were placed on the patients' skin surface at the left and right shoulders, sternal notch, zyphoid process, and forehead. The sampling locations were selected, in part, because of the proximity to radiosensitive organs and distance from the heart. In addition, the sampling locations are anatomical landmarks, which are easily reproduced. The TL elements were placed just prior to deployment of the Ir-192 source and removed once the source was retracted. TL elements were not shielded against fluoroscopic X-rays for two reasons. During the IVB procedure, fluoroscopy is only used to periodically check the position of the source. The fluoroscopy time while the source is dwelling is typically less than a minute. At the same time, the minimal dose from the fluoroscopy component does contribute to total dose of the intracoronary procedure. The TL elements were not exposed to the primary fluoroscopy beam. Therefore, the exposure from fluoroscopy as detected by the TL elements represents radiation dose from scattered X-radiation. Radiation exposure measurements were obtained from 48 patients participating in FDA-approved clinical trials (WRIST and GAMMA III) for coronary artery restenosis inhibition from January through July 2000. Research data were acquired from patients enrolled in both gamma and beta trials. Experimental measurements include data from 43 patients treated with Ir-192, 2 placebo patients, 2 aborted iridium-192 cases, and 1 patient treated with P-32. Patients undergoing treatment in the FDA-approved clinical trials were irradiated using a ribbon containing Ir-192 sources. The ribbons contained 10, 14, 17, 19, 21, or 23 seeds of iridium (manufactured by Best). The seeds are 3 mm long and spaced 4 mm from center to center. The length of the ribbon (or number of seeds) is selected by the clinician to cover the target lesion. The treatment protocol prescribes a dose of 14 Gy at 2 mm radially outward from the center of the source ribbon. For new sources, treatment times are approximately 20 min and become longer as the sources decay. The research included one patient treated with P-32. The P-32 source (manufactured by Guidant) is 20 mm long, with an activity of up to 600 mCi. Treatment times are approximately 2–4 min, depending on activity. The treatment protocol for P-32 prescribes a dose of 20 Gy at 1 mm from the centering balloon surface. 3. Results  Experimental dosimetry data were obtained during actual patient treatments for in-stent restenosis. The patient treatments were performed under FDA-approved clinical investigation procedures. The results and data that follow consider the peripheral radiation dose on the surface of patients from the iridium-192 and the skin dose from fluoroscopy, as recorded by the TLDs. In addition, in-air exposure around the patients from the gamma rays was estimated from ion chamber measurements. TLDs were placed on the skin surface to obtain a measure of the gamma dose at selected anatomic locations. TLDs were positioned on the left and right shoulders, sternal notch, forehead, and zyphoid process of 48 patient cases from January through July 2000. Of the 48 patients, 2 cases were aborted before the Ir-192 source was deployed, 2 cases were performed to assess placebo effects, and 1 case used a beta emitter, P-32. The remaining 43 cases were performed using Ir-192. The number of iridium seeds (10, 14, 17, 19, or 23) selected coincided with the length of the lesion treated. For the research, the average activity temporarily implanted was 307 mCi, with an average dwell time of 21 min. Patient gender was recorded for 41 of 48 patients, with 75% of the patients being male and 25%, female. The average patient age was 63 years and the average patient weight was 88.1 kg. The measurements indicate that the average body dose on the skin surface from all TLDs, clinical requirements, and gamma source configurations varies from 0.95 mSv at the head to 27.06 mSv at the sternal notch. The overall dose for each sampling location for the 43 iridium patients is presented in Table 1. The wide range of measured dose for each anatomical location from all patients is attributed to the placement of the TLDs, variation in patient size, and the coronary artery treated, as well the location of the lesion within the coronary artery. In addition to obtaining surface dose measurements with TLDs, in-air radiation exposure measurements using an ion chamber were taken around the patients during irradiation. The ion chamber measurements represent exposure rates from the Ir-192 source and not scattered X-radiation. Measurements were taken from the 43 Ir-192 cases. The average patient exposure rates at one foot from the patient's chest and left and right shoulders were 4.65±2.4 R/hr, 869±353, and 754±417 mR/hr, respectively. There are substantial variations in the recorded measurements made with the ion chamber primarily due to patient size and location of measurements. The typical areas surveyed for exposure are indicated in Fig. 1. For an IVB procedure, the total fluoroscopy time to include pre- and postgamma irradiation varies significantly from patient to patient. During the actual source dwell time, fluoroscopy is used to check the positioning of the catheter post source insertion and source positioning while dwelling. At most, fluoroscopy time in this portion of the procedure is 2 min, while total fluoroscopy time, on average, may be 18 min. The placebo cases represent a simulated brachytherapy procedure (for the purposes of clinical validation). The placebo data for this research were especially important because an assessment of the fluoroscopy dose could be made. Fluoroscopy times for the two placebo cases were each less than 2 min. Thus, the TLD measured exposure for the placebo cases represents the exposure received from fluoroscopy only. There were also two cases ultimately aborted before the source was inserted. The TL elements had been placed on the patients upon cue; however, just prior to source insertion, complications developed and the treatment with Ir-192 was aborted. Nonetheless, these aborted cases provide an estimation of the potential dose from fluoroscopy. For a beta/gamma source comparison, experimental dose data were obtained from one beta case. As expected, the dose distribution at even very short distances from the beta source is significantly lower than the gamma dose. For beta cases, the available activity is 600 mCi or less, with dwell times of only a few minutes. The exposure rate around the patient is minimal. Staff remains in the cardiac catheterization laboratory during treatment with the beta sources. Table 2 presents the measured fluoroscopy exposure (placebo and aborted cases) and the exposure from the beta case. For beta sources, the dose varied from 0.11 mSv at the head to 0.49 mSv at the sternal notch. The fluoroscopy contribution to the body dose (15-minexposure time) was 0.10 mSv to the head and 2.57 mSv to the sternal notch. | | |  | Location | Placebo patient 1 | Placebo patient 2 | 15-min fluoro (aborted case) | 3-min fluoro (aborted case) | Beta patient (p-32) |  |
|---|
 | Left shoulder | 0.14 | 0.20 | 1.95 | 0.26 | 0.25 |  |  | Right shoulder | 0.16 | 0.09 | 0.96 | 0.65 | 0.48 |  |  | Sternal notch | 0.16 | 0.26 | 2.57 | 0.51 | 0.50 |  |  | Head | 0.03 | 0.08 | 0.10 | 0.05 | 0.11 |  |  | Zyphoid | 0.08 | 0.11 | 0.39 | 0.19 | 0.24 |  |  | Average | 0.12 | 0.15 | 1.20 | 0.33 | 0.32 |  | | | |
4. Discussion  The dose distribution around sealed sources not only depends on distance and source size but on absorption in tissues and scattering by tissues as well. At distances less than 10 cm from the source, the decrease in dose may be described by the inverse square law. At these distances, tissue absorption decreases the dose and scattering increases the dose, resulting in an equal and opposite effect with no net influence on the dose distribution. At distances greater than 10 cm, the dose distribution is affected by absorption and scatter, which are no longer equal and opposite, and deviations from the inverse square law may be as great as 20%, depending on the energy of the source [8]. For the research, TL elements were placed at distances of 10 cm and greater from the source. The research did not intend to determine dose at distances proximal to the treated lesions, but rather, doses distally in an effort to estimate overall body dose on the skin surface. The investigator used the methods describe in Ref. [8] and depth dose charts provided by Best Industries for the iridium sources to calculate the dose at specified distances. The calculated dose is based on a prescribed dose of 14 Gy at 2.0 mm. The following formula from Ref. [8] was used to calculate the dose rate from an assumed point source: where Sk represents the source air kerma strength in μGy m 2 h −1, ( μen/ ρ) wa the average mass energy absorption of water to air, T( r) the ratio of exposure in water to exposure in air, and dose rate D( r) is in cGy h −1. The commonly used T(r) values are valid for a range of 1−10 cm. Ref. [8] establishes T(r) values for Co-60, Ir-192, and Cs-137 for distances of 10−60 cm. The calculated doses presented in Table 3 were computed from Eq. (1) for the patient procedures using 10, 14, and 17 seeds of Ir-192. The air kerma strength conversion factor used was 4.03 U mCi −1 (AAPM TG-43). Doses are reported in mGy. The average dose for all seed configurations at 10 cm is 48.20 mGy and 0.08 mGy at 60 cm. TL elements were placed on the sternal notch, left and right shoulders, zyphoid process, and forehead. In Table 4, the placement location of the patient TL elements and the average dose measured from patient data for each location are noted. The listed distances from the heart in Table 4 are presumed and represent a best estimate by the author. | | |  | Anatomical location | Distance from the heart (cm) | Measured dose (mSv) | Calculated dose (mGy) | Ratio (measured to calculated) |  |
|---|
 | Left shoulder | 20 | 8.12 | 8.55 | 0.950 |  |  | Right shoulder | 25 | 5.83 | 4.27 | 1.365 |  |  | Sternal notch | 10 | 27.06 | 48.20 | 0.561 |  |  | Head | 35 | 0.95 | 1.20 | 0.792 |  |  | Zyphoid process | 15 | 6.87 | 18.65 | 0.368 |  | | | |
Ratios for measured and calculated doses are presented in Table 4. The measured doses for the shoulders and head show adequate agreement with the calculated doses for the corresponding distances—an agreement within ±37%. Although the zyphoid and sternal notch deviated by as much as 44% and 63%, respectively, the calculated doses for these sampling distances fall within the observed range for the measured skin surface doses of these locations, as presented in Table 1. From the estimated doses by calculation, the overall average (data for 10–60 cm) is 7.59 mGy. The overall average dose, as measured on the skin surface by TLDs considering all anatomical locations, clinical requirements, and gamma source configurations, is 9.73 mSv. Ref. [3] reports that the effective dose using Monte Carlo code EGS4 from 20 Gy at 2 mm is 14.0 mSv. Theoretically, the effective dose from 10 Gy at 2 mm is 0.70 mSv. Interpolating the effective dose for 14 Gy at 2 mm yields and estimated effective dose of 9.80 mSv. Therefore, dose estimates, whether calculated or measured, present an overall body dose of less than 10 mSv. 4.1. Comparison of tissue doses from cardiac fluoroscopic procedures Biological effects for which the probability of the effect increases with dose without a threshold are known as stochastic effects. In radiation protection, carcinogenesis is the stochastic effect of concern. Restenosis is not a malignant disease. However, to treat restenosis, additional procedures including repeated angioplasty and bypass surgery may be necessary. These procedures carry a significant invasive risk and give rise to additional radiation exposure from fluoroscopy. Justification of using radiation to prevent restenosis as with IVB warrants a comparison of intracoronary procedures using radiation and dose received from fluoroscopic X-rays during angioplasty. Interventional X-ray procedures demand image quality, long fluoroscopy times, and many images to adequately visualize and access the vascular system. Therefore, patient doses in interventional radiology have the potential to be high and deterministic effects, such as skin burns, are a distinct possibility. Patient doses from fluoroscopy are typically reported as the entrance skin exposure (ESE). ESE is used to evaluate the risk for deterministic effects as well as an effective dose to quantify the probability of stochastic effects. For therapeutic cardiac procedures, such as angioplasty, the skin dose may range from 1.5 to 3.0 Gy and the effective dose, 5.0 to 13.0 mSv [3], [9], [10]. From the Handbook of Selected Tissue Doses for Fluoroscopic and Cineangiographic Examination of the Coronary Arteries, the FDA makes the estimates presented in Table 5. | | |  | Tissue | Tissue dose (mGy) |  |
|---|
 | Entrance skin exposure | 870 |  |  | Thyroid | 1.3 |  |  | Active bone marrow | 32 |  |  | Esophagus | 88 |  |  | Lung | 150 |  |  | Pancreas | 36 |  | | | |
From the experiment, the average total procedure fluoroscopy time was 18 min. The maximum fluoroscopic output permitted by federal regulations is 10 R/min. The output posted on the X-ray machine used for cardiac visualization was 3 R/min. Therefore, the average ESE for the patient cases from this experiment is 54 R. For doses greater than 100 R, the patient is at risk for a radiation skin burn [11]. The anatomical location for the body tissues in Table 5 correlates with the dosimeter locations used for patient TL placement in the experiment. (Such as, the left and right shoulders/clavicles are areas of active bone marrow. The thyroid and esophagus are in close proximity to the sternal notch, as well as the lung and pancreas to the zyphoid.) There is some correlation with the fluoroscopy tissue dose reported by the FDA and the upper range of the measured dose data, such as the lung at 150 mGy and the sternal notch at 130 mSv. The calculated and measured dose data and Monte Carlo estimates from Ref. [3] indicate that the brachytherapy procedure yields an effective dose (9.80 mSv) in the range observed for the interventional procedure (angioplasty) using fluoroscopy (5−13 mSv). The annual occupational limit on radiation exposure is based on the concept of EDE. The EDE concept employs risk coefficients to estimate cancer risks from radiation exposure. The annual limit of EDE for occupational workers is 0.05 Sv (5 rem), and organ doses are limited to 0.5 Sv (50 rem). Therefore, the occupational limit could be interpreted to indicate that a radiation worker who receives an EDE of less than 0.05 Sv has no greater chance of suffering from stochastic effects than do workers who are not exposed to ionizing radiation. Because radiotherapy patients are not radiation workers, they are excluded from the radiation dose limits. However, the concept of EDE is applicable when assessing excess risk to patients who are undergoing clinical procedures involving radiation. From the experiment, the overall average dose by physical measurement was 9.73 mSv. The estimated dose for all dosimeter locations by calculation was 7.59 mGy, and the EDE presumed by Monte Carlo methods is 9.80 mSv. The additional theoretical fatal cancer risk from IVB can be taken as the measured or calculated doses times 0.4×10−4/Sv. Thus, the total theoretical risk is on the order of 20.04%. Upon comparison with limits for occupational exposure (0.05 Sv) and exposure from background (3.60 mSv), the effective dose from IVB poses an acceptable risk. However, for the patient population at hand, additional dose accumulates from prior and subsequent procedures involving radiation and therefore increases the effective dose and increases the cancer risk in an additive fashion. 5. Conclusion  The results suggest that skin surface exposures from gamma sources used in IVB pose acceptable risks considering the medical benefits of the procedures. High energy gamma emitters, however, do present radiation protection challenges, and these are important from a health physics perspective and are important, considering that staff must be able to closely observe and communicate with patients undergoing IVB. In clinical applications, the effective dose concept more or less provides a mechanism of dose expression for comparing various treatments that use radiation as a predictor of future disease or outcome. The latency period for many cancers is about 20 years [12]. The increase of secondary cancers arising from IVB can reasonably be limited by the natural life expectancy of the patient population receiving IVB. Medical exposure, in essence, is subject to dose limitation in that unnecessary exposure should be avoided and necessary exposures should be justified in terms of benefits that would not otherwise have been received. The dose data presented in this research may serve to improve the risk–benefit discussion between the clinician and patient, minimize misperceptions, and help assure patient/research subject protection when obtaining informed consent. Acknowledgments  The author wishes to express sincere appreciation to Chris Soares at NIST for his continued support and assistance with all dosimetry aspects of this research. References  [1]. [1]Minnesota Health Technology Advisory Committee. 2001 Intracoronary Brachytherapy. Internet June 21, 2002. [2]. [2]In: Waksman R editors. Vascular brachytherapy. 2nd ed. New York: Futura Publishing; 1999;. [3]. [3]Schaart DR. Sealed catheter-based beta sources for intravascular brachytherapy. Delft (The Netherlands): DUP Science; 2002;. [4]. [4]Tripuraneni P, Jani S, Minar E, Leon M. Intravascular brachytherapy from theory to practice. London (UK): ReMEDICA Publishing; 2001;. [5]. [5]Kahn F. The physics of radiation therapy. 2nd ed. Baltimore (Md): Williams & Wilkins; 1994;. [6]. [6]McKeever SWS, Moscovitch M, Townsend PD. Thermoluminescence dosimetry materials: properties and uses. Ashford (Kent England): Nuclear technology Publishing; 1995;. [7]. [7]Moscovitch M. Personnel dosimetry using LiF:Mg, Cu, P. Radiat Prot Dosim. 1999;85:49–56. [8]. [8]Venselaar JLM, van der Giessen PH, Dries WJF. Measurement and calculation of the dose at large distances from brachytherapy sources: Cs-137, Ir-192, and Co-60. Med Phys. 1996;23:537–543. MEDLINE |
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[9]. [9]Ramakrishnan G, Padmanaghan V. Radiation doses to patients from X-ray examinations involving fluoroscopy. Indian J Radiol Imaging. 2001;11:181–184. [10]. [10]Huda W. Patient dose in radiology. www.ImagingEconomics.com/app/home/main.asp?. [11]. [11]Stern S, Renaud L, Zankl M. Handbook of selected tissue doses for fluoroscopy and cineangiopraphic examination of the coronary arteries. HHS Publication FDA. 1995;95–8289. [12]. [12]Neugut AI, Weinberg MD, Ahsan H, Mailman JD, Rescigno J. Carcinogenic effects of radiotherapy for breast cancer. Oncology. 1999;13. a Georgetown University, Washington, DC 20057, USA b Washington Hospital Center, Washington, DC 20010, USA Corresponding author. 4651 Lynn Burke Road, Monrovia, MD 21770, USA. Tel.: +1 410 872 4435; fax: +1 410 312 4184.
☆ There are no financial relationships between any of the authors and the subject matter. PII: S1553-8389(05)00032-1 doi:10.1016/j.carrev.2005.04.001 © 2005 Elsevier Inc. All rights reserved. | |
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