Exposure of medical personnel to radiation during radionuclide therapy practices

OBJECTIVES: Radioisotopes that emit beta radiation are used for the treatment of hepatocellular carcinoma, of arthritic patients (radiosynovectomy) and treatment of bone metastases with, respectively, I-labelled lipiodol, colloidal citrate of Y or and Sm-labelled EDTMP. Radiation energy of these radioisotopes that emit beta or beta and gamma radiation (from 300 to 2000 keV) leads to an increase in radiation dose received by nuclear medicine staff. In this paper we focused on clinical and laboratory staff exposure during these types of metabolic radiation therapies. METHODS: Cylindrical LiF thermoluminescence dosimeters were used to measure radiation-related whole-body doses (WBDs) and finger doses of the clinical staff. RESULTS: Exposure of the two radiopharmacists and three nurses taking part in I-labelled lipiodol, Y-colloid and Sm-EDTMP therapies, for 12 months in succession, were 146 microSv and 750 microSv, respectively, considering WBD, and 14.6 mSv and 6.5 mSv, respectively, considering finger doses. Extrapolated annual exposures (six radiosynovectomies per year) for the rheumatologists were estimated to be 21 microSv (WBD) and 13.2 mSv (finger dose). Extrapolated annual WBDs and finger doses (25 I-labelled lipiodol treatments per year) for radiologists were estimated to 165 microSv and 3.8 microSv, respectively. CONCLUSION: Fortunately, these doses were always lower than the limits reported in the European Directive EURATOM 96/29 05/13/1996 (WBD <20 mSv.year; finger dose: 500 mSv.year) but have to be added to those relative to other metabolic radiotherapies such as radioiodine treatments and new metabolic radiotherapies (Y-conjugated peptides or antibodies). Nevertheless, the global exposure of medical staff involved in all these clinical practices justifies dosimetry studies to validate protocols and radiation protection devices for each institution.     

Patient specific computer automated dosimetry calculations during therapy with In Octreotide

The aim of this study was to calculate the absorbed dose of 22 patients that were diagnosed for neuroendocrine tumours in liver and had received therapeutic dose of ¹¹¹In octreotide. In-111 Octreotide infusion, via intrahepatic catheterization is well established technique in our Institution in hepatocellular carcinoma and neuroendocrine tumours treatments. The patient specific dosimetry calculations, for this way of treatment, were based on anterior and posterior scintigraphy images that were acquired immediately after radiopharmaceutical infusion, through hepatic arterial port and at 24 and 48 h post-infusion. Gamma – camera was calibrated in order to estimate source organ activity considering count rate, patient’s body diameter and source organ size. The results showed that the tumour absorbed dose ranged from 2.5 to 18.4 mGy/MBq, depending on the lesion size. Patient specific dosimetry calculations helps the physician to optimize the planning of the treatment, avoid side effects to healthy tissue and assign administered dose to treatment results.     

Radiation doses from patients undergoing yttrium-90 silicate knee radiosynovectomy

The present study was undertaken because we could not find references related to the minimal radiation doses emitted from patients treated with (90)Y-silicate colloid ((90)Y-SC) for radiosynectomy (RS). Radiation doses from 16 patients treated with about 181+/-13 MBq (90)Y-SC for RS of knee synovitis were estimated by dose rate measurements performed within 10 min after the (90)Y-SC injection with a calibrated survey dose ratemeter at 0.5 m, 1 m and 2 m distances from the treated joint. The mean dose rate values from the patients after bg subtraction were 0.6+/-0.4 microSv/h at 0.5 m, 0.1+/-0.1 microSv/h at 1 m and 0.1 +/- 0.0 microSv/h at 2 m distance. Dose rates at a distance of 0.5 m were significantly correlated (P<0.02) with the patient's weight but not with the height or the injected activity. The assumed estimated maximum whole body doses from a treated patient were 55 microSv for persons living with the patient, 2.9-3.4 microSv for the nursing staff, 0.2-1.8 microSv for the therapist physician and 0.3-0.6 microSv for the technologist, involved in the whole procedure. The above values were lower than those published with the same methodology for alternative RS radiopharmaceuticals for knee synovitis like dysprosium-165 ferric hydroxide macroaggregate ((165)Dy-FHMA) or holmium-166 ((166)Ho-FHMA), as estimated with their typical injected activities. In conclusion our results demonstrate that in (90)Y-SC knee synovectomy, the whole body radiation doses to medical and non medical personnel were as expected well below the maximum annual dose limits for the public and professionals exposed to radiation.     

Preliminary data on biodistribution and dosimetry for therapy planning of somatostatin receptor positive tumours: comparison of (86)Y-DOTATOC and (111)In-DTPA-octreotide.

The somatostatin analogue (90)Y-DOTATOC (yttrium-90 DOTA- D-Phe(1)-Tyr(3)-octreotide) is used for treatment of patients with neuroendocrine tumours. Accurate pretherapeutic dosimetry would allow for individual planning of the optimal therapeutic strategy. In this study, the biodistribution and resulting dosimetric calculation for therapeutic exposure of critical organs and tumour masses based on the positron emission tomography (PET) tracer (86)Y-DOTATOC, which is chemically identical to the therapeutic agent, were compared with results based on the tracer commonly used for somatostatin receptor scintigraphy, (111)In-DTPA-octreotide (indium-111 DTPA- D-Phe(1)-octreotide, OctreoScan). Three patients with metastatic carcinoid tumours were investigated. Dynamic and static PET studies with 77-186 MBq (86)Y-DOTATOC were performed up to 48 h after injection. Serum and urinary activity were measured simultaneously. Within 1 week, but not sooner than 5 days, patients were re-investigated by conventional scintigraphy with (111)In-DTPA-octreotide (110-187 MBq) using an equivalent protocol. Based on the regional tissue uptake kinetics, residence times were calculated and doses for potential therapy with (90)Y-DOTATOC were estimated. Serum kinetics and urinary excretion of both tracers showed no relevant differences. Estimated liver doses were similar for both tracers. Dose estimation for organs with the highest level of radiation exposure, the kidneys and spleen, showed differences of 10.5%-20.1% depending on the tracer. The largest discrepancies in dose estimation, ranging from 23.1% to 85.9%, were found in tumour masses. Furthermore, there was a wide inter-subject variability in the organ kinetics. Residence times (tau(organs)) for (90)Y-DOTATOC therapy were: tau(liver) 1.59-2.79 h; tau(spleen) 0.07-1.68 h; and tau(kidneys) 0.55-2.46 h (based on (86)Y-DOTATOC). These data suggest that dosimetry based on (86)Y-DOTATOC and (111)In-DTPA-octreotide yields similar organ doses, whereas there are relevant differences in estimated tumour doses. Individual pretherapeutic dosimetry for (90)Y-DOTATOC therapy appears necessary considering the large differences in organ doses between individual patients. If possible, the dosimetry should be performed with the chemically identical tracer (86)Y-DOTATOC.     

Assessment of radiation safety instructions to patients based on measured dose rates following prostate brachytherapy

PURPOSE: To validate radiation safety instructions to patients and to evaluate the potential radiation doses to members of the public after (125)I or (103)Pd prostate implantation. METHODS AND MATERIALS: Radiation dose rate measurements were made in the immediate postoperative period on 636 consecutive patients with stage T1-T2 prostate cancer who underwent transperineal (125)I or (103)Pd implantation at Memorial Sloan-Kettering Cancer Center during the period from August 1995 through January 2003. RESULTS: The mean radiation dose rate at the anterior skin surface following a prostate implant was 37 microSv/hr for (125)I and 8 microSv/hr for (103)Pd. At 30 cm from the anterior skin surface, these dose rates were reduced to 6 microSv/hr for (125)I and 3 microSv/hr for (103)Pd. At 1 m from the anterior skin surface the dose rates from both types of implants were reduced to less than 1 microSv/hr. The effect of body weight on dose rates from (125)I sources was examined for a select sub-group of patients and the measured dose rate was found to decrease with increasing body weight. In another group of patients, dose rate measurements were made on both lateral skin surfaces and were less than 16.8 microSv/hr in all cases. Assuming a 33% occupancy factor and utilizing the mean measured dose rate for (125)I, the time required to reach an effective dose equivalent limit of 5 mSv for caregivers was estimated to be 19 days on contact with the skin surface. Using a similar calculation, the lifetime doses for (125)I at a distance of 30 cm from the anterior skin surface, as well as the lifetime doses for (103)Pd on contact with the skin surface and at 30 cm from the anterior skin surface can be shown to be less than 5 mSv. CONCLUSIONS: The large number of cases available for this study permits a validation of radiation safety recommendations and provides concrete information from which the permitted exposure times following implantation can be estimated. The data support the conclusion that patients treated with these implants do not represent a radiation risk to members of the public.     

Radiation dosimetry for 90Y-2IT-BAD-Lym-1 extrapolated from pharmacokinetics using 111In-2IT-BAD-Lym-1 in patients with non-Hodgkin's lymphoma.

Several monoclonal antibodies, including Lym-1, have proven effective for treatment of hematologic malignancies. Lym-1, which preferentially targets malignant lymphocytes, has induced therapeutic responses and prolonged survival in patients with non-Hodgkin's lymphoma (NHL) when labeled with 131. Because radiometal-labeled monoclonal antibodies provide higher tumor radiation doses than corresponding 131I-labeled monoclonal antibodies, the radiation dosimetry of 90Y-2-iminothiolane-2-[p-(bromoacetamido)benzyl]-1,4,7,10-tetraazacyc lododecane-N,N',N",N"'-tetraacetic acid-Lym-1 (90Y-21T-BAD-Lym-1) is of importance because of its potential for radioimmunotherapy. Although 90Y has attractive properties for therapy, its secondary bremsstrahlung is less suitable for imaging and pharmacokinetic studies in patients. Thus, the pharmacokinetic data obtained for 111In-21T-BAD-Lym-1 in patients with NHL were used to calculate dosimetry for 90SY-21T-BAD-Lym-1. METHODS: Thirteen patients with advanced-stage NHLwere given a preload dose of unmodified Lym-1 followed by an imaging dose of 111In-21T-BAD-Lym-1. Sequential imaging and blood and urine samples obtained for up to 10 d after infusion were used to assess pharmacokinetics. Using 111In pharmacokinetic data and 90Y physical constants, radiation dosimetry for 90Y-21T-BAD-Lym-1 was determined. RESULTS: The uptake of 111In-21T-BAD-Lym-1 in tumors was greater than uptakes in the lung and kidney but similar to uptakes in the liver and spleen. The biologic half-time in tumors was greater than in lungs. The mean radiation dose to tumors was 6.57 +/- 3.18 Gy/GBq. The mean tumor-to-marrow (from blood) radiation ratio was 66:1, tumor-to-total body was 13:1, and tumor-to-liver was 1:1. Images of 111In were of excellent quality; tumors and normal organs were readily identified. Mild and transient Lym-1 toxicity occurred in 3 patients. CONCLUSION: Because of the long residence time of 111In-2IT-BAD-Lym-1 in tumors, high 90Y therapeutic ratios (tumor-to-tissue radiation dose) were achieved for some tissues, but the liver also showed high uptake and retention of the radiometal.     

Biodistribution and radiation dosimetry of the amyloid imaging agent 11C-PIB in humans.

We investigated the biodistribution and radiation dosimetry of the PET amyloid imaging agent (11)C-PIB ((11)C-6-OH-BTA-1) (where BTA is benzothiazole) in humans. Previous radiation exposure estimates have been based on animal experiments. A dosimetry study in humans is essential for a balanced risk-benefit assessment of (11)C-PIB PET studies. METHODS: We used data from 16 different (11)C-PIB PET scans on healthy volunteers to estimate radiation exposure. Six of these scans were dynamic imaging over the abdominal region: 3 covering the upper abdomen and 3 covering the middle abdomen. On average, 489 MBq of (11)C-PIB (range, 416-606 MBq) were injected intravenously, and dynamic emission scans were recorded for up to 40 min. Two subjects had whole-body imaging over the entire body to illustrate the biodistribution. PET brain scans and blood and urine radioactivity measurements from our previous (11)C-PIB studies were also analyzed. Thirteen source organs and the remainder of the body were studied to estimate residence times and mean radiation-absorbed doses. The MIRD method was used to calculate the radiation exposure of selected target organs and the body as a whole. RESULTS: There is a high degree of consistency between our human data and previous biodistribution information based on baboons. In our study, the highest radiation-absorbed doses were received by the gallbladder wall (41.5 microGy/MBq), liver (19.0 microGy/MBq), urinary bladder wall (16.6 microGy/MBq), kidneys (12.6 microGy/MBq), and upper large intestine wall (9.0 microGy/MBq). The hepatobiliary and renal systems were the major routes of clearance and excretion, with approximately 20% of the injected radioactivity being excreted into urine. The effective radiation dose was 4.74 microSv/MBq. CONCLUSION: The established clinical dose of (11)C-PIB required for 3-dimensional PET amyloid imaging has an acceptable effective radiation dose. This dose is comparable with the average exposure expected in other PET brain receptor tracer studies. (11)C-PIB is rapidly cleared from the body, largely by the kidneys. From the viewpoint of radiation safety, these results support the use of (11)C-PIB in clinical PET studies.     

Multislice CT fluoroscopy: technical principles, clinical applications and dosimetry

PURPOSE: The aim of this study is describing fluoroscopic techniques with multislice CT during interventional procedures. We emphasize the technical principles of the multislice CT fluoroscopy and the relative advantages in clinical application, in comparison to single slice fluoroCT and conventional CT guided procedures. Other topics are dosimetry and patient's and operator's radioprotection. MATERIALS AND METHODS: We describe our experience in 60 cases of interventional procedures performed with CT fluoroscopy array for the TOSHIBA AQUILION-MULTI TSX-101A scanner that allows a real-time 3 slices simultaneous representation of the target: middle target slice, superior and inferior slices. Thirty nine biopsies, 5 abscess drainage, 12 shoulder arthrocentesis previous to arthro-MR and 4 hepatic neoplasm ablations have been performed during the last 9 months. For each procedure questionnaires have been used to evaluate: target organs, scan parameters, fluoroscopy techniques (continuous or spot) and total time of fluoroCT. Basing on these data and on the measurements made on a body phantom we calculated patient's and operator's radiation dose rate. RESULTS AND DISCUSSION: The real-time simultaneous representation of the middle target slice and the adjacent superior and inferior slices has always allowed an immediate identification of the needle tip and direction. The use of a needle holder has been determined by the needle type, the fluoroscopy technique (continuous or spot), the type of interventional procedure and the target. In our experience freehand spot fluoroscopy approach was easier, faster and with less radiation dose rate. 24 seconds were the mean fluoroscopy time for all different CT fluoroscopy modalities and procedures. The mean absorbed equivalent dose rate to patient's skin was 5300 microSv/s while the dose to operator's body and hand was respectively 0.3 microSv/s and 30 microSv/s. CONCLUSIONS: Multislice CT fluoroscopy, specially if performed by spot technique, leads to an acceptable radiation dose rate to patient and operator, is user friendly and guides interventional procedures with rapidity.     

Biodistribution and internal dosimetry of the 188Re-labelled humanized monoclonal antibody anti-epidemal growth factor receptor, nimotuzumab, in the locoregional treatment of malignant gliomas

OBJECTIVE: To evaluate the biodistribution, internal radiation dosimetry and safety of the 188Re-labelled humanized monoclonal antibody nimotuzumab in the locoregional treatment of malignant gliomas. METHODS: Single doses of 370 or 555 MBq of 188Re-labelled nimotuzumab were locoregionally administered to nine patients with recurrent high-grade gliomas, according to an approved dose-escalation study. SPECT, planar scintigraphy and magnetic resonance images were combined for dosimetric and pharmacokinetic studies. Blood and urine samples were collected to evaluate clinical laboratory parameters and for absorbed doses calculations. Biodistribution, internal dosimetry, human anti-mouse antibody response and toxicity were evaluated and reported. RESULTS: The 188Re-nimotuzumab showed a high retention in the surgically created resection cavity with a mean value of 85.5+/-10.3%ID 1 h post-injection. It produced mean absorbed doses in the tumour region of approximately 24.1+/-2.9 Gy in group I (patients receiving 370 MBq) and 31.1+/-6.4 Gy in group II (patients receiving 555 MBq); the normal organs receiving the highest absorbed doses were the kidneys, liver and urinary bladder. About 6.2+/-0.8%ID was excreted by the urinary pathway. The maximum tolerated dose was 370 MBq because two patients showed severe adverse effects after they received 555 MBq of 188Re-nimotuzumab. No patient developed human anti-mouse antibody response. CONCLUSIONS: A locoregional single dose of 188Re-labelled nimotuzumab of approximately 370 MBq could be used safely in the routine treatment of patients suffering with high-grade gliomas. The efficacy of this therapy needs to be evaluated in a phase II clinical trial.     

External exposure of hot cell operators in nuclear medicine

PURPOSE: The coming into effect of decrees No. 626/94, 242/96 and 230/95 has once again brought out the problem of the radiation exposure of hot cell operators in nuclear medicine. MATERIAL AND METHODS: With regard to the activity of the Division of Nuclear Medicine of the Istituto Nazionale Tumori in Milan, a map has been produced of the radiation fields in the hot cell in- and outside the working station by measuring the rate of exposure and evaluating the radiation energy using film dosimeters in multifilter containers. The individual doses were measured with film dosimeters for the sternum, the back of the hand and the wrist, and with thermoluminescent dosimeters for the fingers and forehead. The thermoluminescent ring was worn with the detector towards the palm and towards the back of the hand in order to identify the side that was exposed most; the film dosimeter on the sternum was worn both underneath and above the lead apron to reveal a possible reduction in overall exposure due to attenuation of the lower-energy components. RESULTS: The diffuse radiation field in the hot cell during the usual working activity amounts to 1 microSv/h. Assessment of the energy of the radiation fields within the working station revealed a higher energy (90 to 140 keV) in the source storage area than in the area where the syringes are prepared, the latter being affected by diffuse radiation with components of approximately 35, 90 and 110 keV. The hand of the operator is unevenly exposed to the diffuse radiation field and the fingers are more exposed than the back of the hand and the wrist: when the thermoluminescent ring was worn with the detector towards the palm of the hand the measured values did not show a higher exposure than when it was worn with the detector towards the back of the hand. The equivalent of the overall dose measured underneath the lead apron did not show any relevant reduction of the exposure due to attenuation of the lower-energy component (approx. 35 keV). We report the dosimetric findings regarding the total and partial exposure of four different operators during their regular weekly shift, with the dosimeters for the sternum, ring finger and forehead being replaced daily. The average equivalent of the dose to the hand for the manipulation of 37 GBq of 99mTc, measured with a thermoluminescent ring on the proximal phalanx of the ring finger, ranged 3.9 mSv to 2.0 mSv. Except in one case, the sternum and forehead proved to be well protected by the shielding of the working station. DISCUSSION: The operator who stay in the hot cell for 5 hours/week accumulates, due to the presence of diffuse radiation, 5 microSv/week to the whole body; when his/her hands are inside the working station for 2.5 hours/week in the most unfavorable conditions as regards the presence of radioactive sources, they will be exposed to 1250 microSv/week, independently of dose preparation. The exposure of hot cell personnel is highly dependent on the ergonomics of the operator (build, height, arm spread, hand size, etc.) with respect to the position of the apertures and the inspection windows of the working station; as a consequence, the three dosimetric values (exposure of the sternum, the hands and the forehead) cannot be correlated. The fingers are the most exposed part of the hand, which confirms the appropriateness of our choice of the thermoluminescent ring to measure the partial exposure of the hands. Our results have been compared with those reported in the literature and with statistical data relative to three years of regular activity (1994-1996), during which the hot cell operators were monitored according to the same parameters; female operators proved to be more exposed than males, with average yearly equivalents of the total dose of 2764 microSv and 860 microSv, respectively, and average yearly equivalents of the partial dose to the hands of 32,288 microSv and 9460 microSv, respectively. The average total partial dose equivalent rati     

Monoclonal antibody hapten radiopharmaceutical delivery

One hundred micrograms of monoclonal antibody (MoAb) CHA255 with a binding constant Kb of 4 X 10(9) was complexed with indium-111 labelled BLEDTA II, BLEDTA IV, benzyl EDTA, and an EDTA conjugate of Fab. The 24-h tumour and organ distribution of BALB/c mice bearing KHJJ tumours was studied for each compound alone, the antibody complex, and 3 h following a chelate chase of the antibody complex. Whole body biological half-life was measured for 7 days with and without a chelate chase for each antibody complex. The 24-h whole body counts dropped 20 to 60% and blood concentration fell over 89% within 3 h of administering the chelate chase. Theoretical equivalent human organ doses were calculated from the 24-h organ concentrations, effective half-life, and MIRD 11 S values (absorbed dose per cumulated activity). Liver and spleen were the target organs, with the dose ranging from 0.50 to 3.91 rads mCi-1. The reduction in organ radiation dose varied up to 95% following the chelate chase. Rapid selective renal clearance of chelate labelled radiopharmaceuticals by competitive inhibition (chelate chase) of their reversible binding to monoclonal antibodies enhances tumour imaging and improves the radiation dosimetry.     

Finger doses for staff handling radiopharmaceuticals in nuclear medicine

Radiation doses to the fingers of occupational workers handling 99mTc-labeled compounds and 131I for diagnostic and therapeutic procedures in nuclear medicine were measured by thermoluminescence dosimetry. METHODS: The doses were measured at the base of the ring finger and the index finger of both hands in 2 groups of workers. Group 1 (7 workers) handled 99mTc-labeled radiopharmaceuticals, and group 2 (6 workers) handled 131I for diagnosis and therapy. Radiation doses to the fingertips of 3 workers also were measured. Two were from group 1, and 1 was from group 2. RESULTS: The doses to the base of the fingers for the radiopharmacy staff and physicians from group 1 were observed to be 17+/-7.5 (mean+/-SD) and 13.4+/-6.5 microSv/GBq, respectively. Similarly, the dose to the base of the fingers for the 3 physicians in group 2 was estimated to be 82.0+/-13.8 microSv/GBq. Finger doses for the technologists in both groups could not be calculated per unit of activity because they did not handle the radiopharmaceuticals directly. Their doses were reported in millisieverts that accumulated in 1 wk. The doses to the fingertips of the radiopharmacy worker and the physician in group 1 were 74.3+/-19.8 and 53.5+/-21.9 microSv/GBq, respectively. The dose to the fingertips of the physician in group 2 was 469.9+/-267 microSv/GBq. CONCLUSION: The radiation doses to the fingers of nuclear medicine staff at our center were measured. The maximum expected annual dose to the extremities appeared to be less than the annual limit (500 mSv/y), except for a physician who handled large quantities of 131I for treatment. Because all of these workers are on rotation and do not constantly handle radioactivity throughout the year, the doses to the base of the fingers or the fingertips should not exceed the prescribed annual limit of 500 mSv.     

Preliminary data on biodistribution and dosimetry for therapy planning of somatostatin receptor positive tumours: comparison of 86Y-DOTATOC and 111In-DTPA-octreotide

The somatostatin analogue ⁹⁰Y-DOTATOC (yttrium-90 DOTA-D-Phe¹-Tyr³-octreotide) is used for treatment of patients with neuroendocrine tumours. Accurate pretherapeutic dosimetry would allow for individual planning of the optimal therapeutic strategy. In this study, the biodistribution and resulting dosimetric calculation for therapeutic exposure of critical organs and tumour masses based on the positron emission tomography (PET) tracer ⁸⁶Y-DOTATOC, which is chemically identical to the therapeutic agent, were compared with results based on the tracer commonly used for somatostatin receptor scintigraphy, ¹¹¹In-DTPA-octreotide (indium-111 DTPA-D-Phe¹-octreotide, OctreoScan). Three patients with metastatic carcinoid tumours were investigated. Dynamic and static PET studies with 77-186 MBq ⁸⁶Y-DOTATOC were performed up to 48 h after injection. Serum and urinary activity were measured simultaneously. Within 1 week, but not sooner than 5 days, patients were re-investigated by conventional scintigraphy with ¹¹¹In-DTPA-octreotide (110-187 MBq) using an equivalent protocol. Based on the regional tissue uptake kinetics, residence times were calculated and doses for potential therapy with ⁹⁰Y-DOTATOC were estimated. Serum kinetics and urinary excretion of both tracers showed no relevant differences. Estimated liver doses were similar for both tracers. Dose estimation for organs with the highest level of radiation exposure, the kidneys and spleen, showed differences of 10.5%-20.1% depending on the tracer. The largest discrepancies in dose estimation, ranging from 23.1% to 85.9%, were found in tumour masses. Furthermore, there was a wide inter-subject variability in the organ kinetics. Residence times (F_organs) for ⁹⁰Y-DOTATOC therapy were: F_liver 1.59-2.79 h; F_spleen 0.07-1.68 h; and F_kidneys 0.55-2.46 h (based on ⁸⁶Y-DOTATOC). These data suggest that dosimetry based on ⁸⁶Y-DOTATOC and ¹¹¹In-DTPA-octreotide yields similar organ doses, whereas there are relevant differences in estimated tumour doses. Individual pretherapeutic dosimetry for ⁹⁰Y-DOTATOC therapy appears necessary considering the large differences in organ doses between individual patients. If possible, the dosimetry should be performed with the chemically identical tracer ⁸⁶Y-DOTATOC.     

Comparison of oral iodine-131-cellulose and indium-111-DTPA as tracers for colon transit scintigraphy: analysis by colon activity profiles

In 11 normal subjects and 11 patients with a clinical diagnosis of constipation, oral 131I-cellulose and 111In-DTPA were compared simultaneously as tracers for radionuclide colon transit scintigraphy. Visual assessment of the images revealed no differences between tracers. Quantitation was performed using total and segmental percent retention and the derived value of clearance half-time. In addition, profiles of the activity distribution along the length of the colon were generated and the mean position of the activity in the colon calculated. For all indices, the results were similar in both normal subjects and constipated patients when comparing tracers, although marked differences were present between normal subjects and constipated patients for each tracer. Indium-111-DTPA was easy to administer and dosimetry was more acceptable than for 131I-cellulose, especially in constipated patients. It is concluded that 111In-DTPA is the preferred tracer for oral colon transit scintigraphy.     

Preliminary safety evaluation of a cyclotron facility for positron emission tomography imaging.

This work describes the design characteristics of a medical imaging centre which uses positron emission tomography, with a cyclotron for fluorine-18 and nitrogen-13 production, and which has provided experimental information on operational data recorded by area dosimetry since 1995. Doses to radiopharmacy and medical staff have been measured both in normal work and in some handling incidents. Data on radiation levels in the installation have also been obtained and related to design details and shielding. Area dosimetry was carried out using a five-stationary detector network, with a sampling rate of 2 min(-1), and by thermoluminescent dosimetry (TLD). Staff were also monitored by TLD, using extra chips for finger dosimetry and to duplicate individual whole-body dosimetry in order to measure doses in certain single operations. For normal work, average whole-body doses to radiopharmacy staff were between 0.03 and 0.28 mSv/month, wrist doses were between 0.42 and 2.67 mSv/month, and finger doses were between 1.4 and 7.7 mSv/day for the left hand and 0.8 and 2.4 mSv/day for the right hand; such variation reflects the differing expertise of staff and the role played by optimisation. Finger doses between 16 and 131 mSv were measured in handling incidents, and finger doses of 20.2 and 20.7 mSv for the left hand and 22.0 and 22.3 mSv for the right hand were measured during handling of a syringe without shielding, containing 3 GBq. For medical staff, contributions to the whole-body dose of 2.0 and 1.9 microSv/procedure were measured for injection and placing the patient on the examination couch, respectively. Dose measurement on the middle finger of the right hand gives an average of 70 microSv during the injection. The provisions regarding the shielding design have proved to be adequate and effective during a 3-year operational period. Operational doses to medical staff are comparatively low, while radiopharmacy staff are the most exposed. The finger doses in these professionals may exceed the annual limit, unless operational restrictions in daily practice are adopted. On-line area dosimetry records based on dose rate probes have proved to be effective both for monitoring radiation levels during the operation and for detecting changes in the behaviour of the facility in the irradiation process.     

Radiation exposure and radiation protection of the physician in iodine-131 Lipiodol therapy of liver tumours

Intra-arterial iodine-131 labelled Lipiodol therapy for liver cancer has been investigated for safety and efficacy over a number of years, but data on radiation exposure of personnel have remained unavailable to date. The aim of this study was to assess the radiation exposure of the physician during intra-arterial 131I-Lipiodol therapy for liver malignancies and to develop appropriate radiation protection measures and equipment. During 20 intra-arterial administrations of 131I-Lipiodol (1110-1924 MBq), radiation dose equivalents (RDE) to the whole body, fingers and eyes of the physician were determined for (a) conventional manual administration through a shielded syringe, (b) administration with an automatic injector and (c) administration with a lead container developed in-house. Administration by syringe resulted in a finger RDE of 19.5 mSv, an eye RDE of 130-140 microSv, and a whole-body RDE of 108-119 microSv. The injector reduced the finger RDE to 5 mSv. With both technique (a) and technique (b), contamination of angiography materials was observed. The container allowed safe transport and administration of the radiopharmaceutical from 4 m distance and reduced the finger RDE to <3 microSv and the eye RDE to <1 microSv during injection. During femoral artery compression, radiation exposure to the fingers reached 170 microSv, but the whole-body dose could be reduced from a mean RDE of 114 microSv to 14 microSv. No more contamination occurred. In conclusion, radiation exposure was high when 131I-Lipiodol was administered by syringe or injector, but was significantly reduced with the lead container.     

Dosimetry of digital panoramic imaging. Part I: Patient exposure

OBJECTIVES: To measure patient radiation dose during panoramic exposure with various panoramic units for digital panoramic imaging. METHODS: An anthropomorphic phantom was filled with thermoluminescent dosemeters (TLD 100) and exposed with five different digital panoramic units during ten consecutive exposures. Four machines were equipped with a direct digital CCD (charge coupled device) system, whereas one of the units used storage phosphor plates (indirect digital technique). The exposure settings recommended by the different manufacturers for the particular image and patient size were used: tube potential settings ranged between 64 kV and 74 kV, exposure times between 8.2 s and 19.0 s, at fuse current values between 4 mA and 7 mA. The effective radiation dose was calculated with inclusion of the salivary glands. RESULTS: Effective radiation doses ranged between 4.7 microSv and 14.9 microSv for one exposure. Salivary glands absorbed the most radiation for all panoramic units. When indirect and direct digital panoramic systems were compared, the effective dose of the indirect digital unit (8.1 microSv) could be found within the range of the effective doses for the direct digital units (4.7-14.9 microSv). CONCLUSIONS: A rather wide range of patient radiation doses can be found for digital panoramic units. There is a tendency for lower effective doses for digital compared with analogue panoramic units, reported in previous studies.     

Measurement of radiation exposure to a PET institution driver from patients injected with FDG

With the recent increase in FDG-PET examinations, concern has mounted regarding radiation exposure to hospital staff and the general public from patients injected with FDG. Because our PET institution is located 15 km from the hospital that provides these examinations, a driver has been designated to transport patients injected with FDG. This study was designed to measure the radiation dose to the driver from these patients (n=28) and to compare it with the estimated dose. A pocket dosimeter was used to measure radiation exposure to the driver. When the distances between the driver and patient were 1.1 m and 1.9 m, mean measured doses were 7.31 microSv and 2.26 microSv, respectively, while mean estimated doses were 8.61 microSv and 2.82 microSv, respectively, per trip. It was presumed that maximum radiation exposure per year was between 3.02 mSv (1.1 m) and 0.92 mSv (1.9 m). According to our data, the measured dose was 20% lower than the estimated dose. This discrepancy may be due to the difference between the volume source (measured dose) and point source (estimated dose).     

Effects of radiation therapy on oesophageal transit in patients with inner quadrant breast tumour

OBJECTIVES: The aim of this study was to evaluate quantitatively the effect of low doses of radiation therapy on the oesophageal transit in patients with inner quadrant breast carcinoma. METHODS: Eighteen female patients with locally advanced inner quadrant breast tumour were included in this study. A total dose of 5000 cGy in 25 fractions of 200 cGy was applied from four different treatment portals to all patients. Oesophageal motility was evaluated before and immediately after radiotherapy using oesophageal scintigraphy. The oesophageal transit times (ETTs) for the upper one-third, the lower two-thirds portion and the whole oesophagus were calculated. RESULTS: The upper one-third portion of the oesophagus received a mean dose of 600 cGy and the lower two-thirds portion received a mean dose of 1530 cGy as a result of 5000 cGy dose application. All of the patients developed grade 1 oesophageal toxicity. Post-radiation therapy ETT values were significantly higher compared to pre-radiation therapy ETT values (P<0.001). Before irradiation, ETT values for the upper one-third, distal two-thirds of the oesophagus and the whole oesophagus were 4.77+/-1.08, 11.22+/-2.85 and 11.61+/-2.97 s, respectively. After irradiation, ETT values for the upper one-third, distal two-thirds of the oesophagus and the whole oesophagus were 6.92+/-2.15, 23.30+/-5.65 and 23.74+/-5.70 s, respectively. CONCLUSIONS: Oesophageal transit seems to be affected by radiation even without a clinically significant oesophageal symptom and oesophageal scintigraphy allows sensitive, non-invasive and quantifiable assessment of the oesophageal transit time.     

Helical Tomotherapy-Based STAT RT: Dosimetric Evaluation for Clinical Implementation of a Rapid Radiation Palliation Program

Helical tomotherapy–based STAT radiation therapy (RT) uses an efficient software algorithm for rapid intensity-modulated treatment planning, enabling conformal radiation treatment plans to be generated on megavoltage computed tomography (MVCT) scans for CT simulation, treatment planning, and treatment delivery in one session. We compared helical tomotherapy–based STAT RT dosimetry with standard linac-based 3D conformal plans and standard helical tomotherapy–based intensity-modulated radiation therapy (IMRT) dosimetry for palliative treatments of whole brain, a central obstructive lung mass, multilevel spine disease, and a hip metastasis. Specifically, we compared the conformality, homogeneity, and dose with regional organs at risk (OARs) for each plan as an initial step in the clinical implementation of a STAT RT rapid radiation palliation program. Hypothetical planning target volumes (PTVs) were contoured on an anthropomorphic phantom in the lung, spine, brain, and hip. Treatment plans were created using three planning techniques: 3D conformal on Pinnacle³, helical tomotherapy, and helical tomotherapy–based STAT RT. Plan homogeneity, conformality, and dose to OARs were analyzed and compared. STAT RT and tomotherapy improved conformality indices for spine and lung plans (CI spine = 1.21, 1.17; CI lung = 1.20, 1.07, respectively) in comparison with standard palliative anteroposterior/posteroanterior (AP/PA) treatment plans (CI spine = 7.01, CI lung = 7.30), with better sparing of heart, esophagus, and spinal cord. For palliative whole-brain radiotherapy, STAT RT and tomotherapy reduced maximum and mean doses to the orbits and lens (maximum/mean lens dose: STAT RT = 2.94/2.65 Gy, tomotherapy = 3.13/2.80 Gy, Lateral opposed fields = 7.02/3.65 Gy), with an increased dose to the scalp (mean scalp dose: STAT RT = 16.19 Gy, tomotherapy = 15.61 Gy, lateral opposed fields = 14.01 Gy). For bony metastatic hip lesions, conformality with both tomotherapy techniques (CI = 1.01 each) is superior to AP/PA treatments (CI = 1.21), as expected. Helical tomotherapy–based STAT RT treatment planning provides clinically acceptable dosimetry, with conformality and homogeneity that is superior to standard linac-based 3D conformal planning and is only slightly inferior to standard helical tomotherapy IMRT dosimetry. STAT RT facilitates rapid treatment planning and delivery for palliative radiation of patients with metastatic disease, with relative sparing of adjacent OARs compared with standard 3D conformal plans.