Radiation Exposure Of Personnel Research Articles

Strahlenhygiene in der medizinischen Röntgenbildgebung

In order to secure and continually improve radiation protection standards in the field of medical X-ray imaging, the German X-Ray Ordinance requires that each individual examination be properly justified and that any procedure undertaken be optimized. Diagnostic reference levels have been introduced in Germany as a measure of optimization for common and/or high-dose X-ray procedures, and are regularly checked for compliance by the competent Medical Experts Office. A prerequisite for the implementation of these regulatory requirements is the determination of readily measurable dose quantities. They also form the basis for the estimation of organ doses and of the effective dose for exposure and risk assessment. The aim of this paper is to describe the essential dosimetric concepts and methods used for the assessment of radiographic, fluoroscopic, and CT procedures. In addition, practical measures for reducing the radiation exposure of patients and personnel will be discussed.

Neutron measurements around a TN85-type storage cask with high-active waste

Abstract Several types of casks have been deposited in the German interim storage facility for spent fuel assemblies and vitrified high-active waste (HAW) at Gorleben since 1995, most of them of the CASTOR® type. In 2008 a delivery of 11 TN85-type casks arrived. They belong to the Transnuclear/Areva cask family and, compared to the flasks of the German (GNS) CASTOR® type, they differ in the neutron shielding design. Generally, radiation exposure of personnel during transportation and storage of casks containing spent fuel and vitrified waste is caused by mixed photon/neutron fields. Frequently, especially at casks for vitrified waste from reprocessing, neutrons are the major component of radiation exposure. Spectrometric and dosimetric investigations were made around a cask of the TN85-type. Neutron fluence spectra and reference values of the ambient dose equivalent H*(10) were measured by means of a Bonner sphere spectrometer (BSS) at several locations on the cask surface and in its environment. Moreover, commercial area dosemeters, LB6411 neutron monitors and conventional AD 6-type photon dosemeters were used. In addition, the responses of two electronic personal dosemeters for mixed fields (EPD-N2, DMC 2000GN) and a TLD albedo dosemeter were investigated. The neutron spectra obtained from the BSS are presented and compared with former measurements at CASTOR® type casks. The relative responses of the LB6411 survey meter and the individual dosemeters are discussed. The LB6411 monitor indicates H*(10) around the TN85 cask with tolerable measuring uncertainties. The personal dosemeters provide acceptable results for photons but overestimate the neutron dose considerably.

Real-time dose assessment and visualization of radiation field for EAST tokamak

The Experimental Advanced Superconducting Tokamak (EAST) device began operation in 2006. A radiation protection work has been paid more and more attention with discharge pulse length increase. A system named radiation virtual simulation for dosimetry (RVIS) using virtual reality (VR) technology has been developed to improve the efficiency of maintenance work, and decrease the radiation exposure of maintenance personnel. The RVIS can be used to evaluate workload in radiation environments, optimize the maintenance plan and visualize three-dimensional (3D) dose rate distribution. The original 3D dose rate distribution in shielded hall was calculated rapidly to use as a basis for dose evaluation and 3D dose field visualization. The RVIS improves on the original work to give more effective dose evaluation and dynamic visualization of the dose field during EAST experiment campaigns.

Radiation exposure of patients and personnel from a PET/CT procedure with 18F-FDG

The positron emission tomography (PET)/computed tomography (CT) camera is a combination of a PET camera and a CT. The image from the PET camera is based on the detection of radiation that is emitted from a radioactive tracer, which has been given to the patient as an intravenous injection. The radiation that is emitted from the radioactive tracer is more energetic than any other radiation used in medical diagnostic procedures and this requires special radiation protection routines. The CT image is based on the detection of radiation produced from an X-ray tube and transmitted through the patient. The radiation exposure of the personnel during the CT procedure is generally very low. Regarding radiation exposure of the patient, it is important to notice whether a CT scan has been performed prior to the PET/CT in order to avoid any unnecessary irradiation. The total effective dose to the patient from a PET/CT procedure is approximately 10 mSv. The major part comes from internal irradiation due to radiopharmaceuticals within the patients (e.g. (18)F-FDG: approximately 6-7 mSv), and a minor part is due to the CT scan (low-dose CT scan: approximately 2-4 mSv). If a full diagnostic CT investigation is performed, the effective dose may be considerably higher. If the patient is pregnant, a PET/CT procedure should be avoided or postponed, unless it is vital for the patient. An interruption in breastfeeding is not necessary after a PET/CT procedure of the nursing mother. Close contact between the patient and a small child should however be avoided for a couple of hours after the administration of the radiopharmaceutical. The radiation dose to the personnel arises mainly due to handling of the radiopharmaceuticals (syringe withdrawal, injection, waste handling, etc.) and from close contact to the patient. This radiation dose can be limited by using the inverse-square law, i.e. by using the fact that the absorbed dose decreases substantially with increasing distance between the radiation source and the personnel.

Radiation protection measurements around a 12 MeV mobile dedicated IORT accelerator

The aim of this study is to investigate radioprotection issues that must be addressed when dedicated accelerators for intraoperative radiotherapy (IORT) are used in operating rooms. Recently, a new version of a mobile IORT accelerator (LIAC Sordina SpA, Italy) with 12 MeV electron beam has been implemented. This energy is necessary in some specific pathology treatments to allow a better coverage of thick lesions. At an electron energy of 10 MeV, leakage and scattered x-ray radiation (stray radiation) coming from the accelerator device and patient must be considered. If the energy is greater than 10 MeV, the x-ray component will increase; however, the most meaningful change should be the addition of neutron background. Therefore, radiation exposure of personnel during the IORT procedure needs to be carefully evaluated. In this study, stray x-ray radiation was measured and characterized in a series of spherical projections by means of an ion chamber survey meter. To simulate the patient during all measurements, a polymethylmethacrylate (PMMA) slab phantom with volume 30 x 30 x 15 cm3 and density 1.19 g / cm3 was used. The PMMA phantom was placed along the central axis of the beam in order to absorb the electron beams and the tenth value layer (TVL) and half value layer (HVL) of scattered radiation (at 0 degrees, 90 degrees, and 180 degrees scattering angles) were also measured at 1 m of distance from the phantom center. Neutron measurements were performed using passive bubble dosimeters and a neutron probe, specially designed to evaluate ambient dose equivalent H*(10). The x-ray equivalent dose measured at 1 m along the beam axis at 12 MeV was 260 microSv/Gy. The value measured at 1 m at 90 degrees scattering angle was 25 microSv/Gy. The HVL and TVL values were 1.1 and 3.5 cm of lead at 0 degrees, and 0.4 and 1 cm at 90 degrees, respectively. The highest equivalent dose of fast neutrons was found to be at the surface of the phantom on the central beam axis (2.9 +/- 0.6 microSv/Gy), while a lower value was observed below the phantom (1.6 +/- 0.3 microSv/Gy). The neutron dose equivalent at 90 degrees scattering angle and on the floor plane on the beam axis below the beam stopper was negligible. Our data confirm that neutron exposure levels around the new dedicated IORT accelerator are very low. Mobile shielding panels can be used to reduce x-ray levels to below regulatory levels without necessarily providing permanent shielding in the operating room.

Benchmark Test of the FLUKA Monte Carlo Code for Residual Production with 500 and 950 MeV/u Uranium Beams on Copper and Stainless Steel Targets

The activation of structures and surroundings of new high-intensity heavy-ion accelerators like the Facility for Antiproton and Ion Research (FAIR) is an important issue. Monte Carlo codes such as FLUKA allow the prediction of the production of individual radioactive isotopes and the induced radioactivity that causes the main contribution to the radiation exposure of personnel. The work is a benchmark study of activation predictions for uranium beams with 500 and 950 MeV/u deposited in copper and stainless steel targets. Precise gamma spectrometry measurements for isotope identification have been carried out with a HPGe detector. All gamma-emitting radionuclides with half-lives of more than 2 days that contribute significantly to the residual dose rates have been studied. The benchmark study shows that FLUKA is a suitable code for the prediction of induced radioactivity at medium-energy heavy-ion accelerators.

Depleted zinc: Properties, application, production

The addition of ZnO, depleted in the Zn-64 isotope, to the water of boiling water nuclear reactors lessens the accumulation of Co-60 on the reactor interior surfaces, reduces radioactive wastes and increases the reactor service-life because of the inhibitory action of zinc on inter-granular stress corrosion cracking. To the same effect depleted zinc in the form of acetate dihydrate is used in pressurized water reactors. Gas centrifuge isotope separation method is applied for production of depleted zinc on the industrial scale. More than 20 years of depleted zinc application history demonstrates its benefits for reduction of NPP personnel radiation exposure and combating construction materials corrosion.

Unipedicular Balloon Kyphoplasty for the Treatment of Osteoporotic Vertebral Compression Fractures: Early Results

The traditional bipedicular kyphoplasty was proved to be safe and effective for the treatment of pain associated with osteoporotic vertebral compression fractures (VCFs). Nevertheless, unilateral kyphoplasty would be an attractive alternative to the traditional bipedicular kyphoplasty owing to theoretical speed, safety, and less expense; thus far, the biomechanical testing showed that experimental unilateral kyphoplasty had properties comparable with bipedicular kyphoplasty. To date, no clinical data are available regarding the efficacy and safety of unilateral balloon kyphoplasty. In this prospective observational study, the clinical and radiographic outcomes of the unipedicular (unilateral) balloon kyphoplasty in osteoporotic VCFs are evaluated. Three hundred and seventeen kyphoplasty procedures were performed in 142 patients with osteoporotic VCFs using the unilateral technique. This technique involves the unilateral cannulation of the center of the vertebral body and the placement of a single balloon tamp. To evaluate improvement in pain and physical function, preoperative and postoperative scores of visual analog scale (VAS), SF-36, and Oswestry Disability Index (ODI) were compared at 3 and 12 months postoperatively. Complications related to the procedure and cement extravasation rates were recorded. Height restoration and overall coronal and sagittal spinal alignment were assessed preoperatively and postoperatively. Significant improvement on the VAS, SF-36 scores, and ODI was noted at 3 months postoperatively; these results were preserved at the 12-month follow-up for the 30 patients who completed the SF-36 questionnaire (VAS/ODI scores were available only for 19 of the 30 patients also showing sustained improvement). No complication was recorded; 34 cases (10.73%) of cement extravasation were all asymptomatic. Mean middle height restoration was found 48.9%; when vertebral levels treated were stratified into 2 groups, with or without height restoration (90.1% and 9.9% of all levels, respectively), corrected mean middle height restoration was found 54%. No lateral wedging or changes in the coronal alignment was observed in the unipedicular group. Unipedicular (unilateral) extrapedicular kyphoplasty is both a safe and efficacious alternative to the traditional bipedicular kyphoplasty for the treatment of painful osteoporotic VCFs. As a technique, it is faster, less expensive, and involves less radiation exposure for the surgical suite personnel.

Long-term fade study of the DT-702 LiF: Mg,Cu,P TLD

LiF thermoluminescent dosemeters (TLDs) are used by the US Navy to record radiation exposure of personnel. The Model DT-648 LiF:Mg,Ti TLD has been replaced by a new Model DT-702 LiF:Mg,Cu,P TLD. The DT-648 was used for many years and has undergone extensive testing to identify its pre- and post-irradiation fade operating characteristics. Studies have shown that the addition of copper increases the thermoluminesence sensitivity of the TLD for improved low-level radiation monitoring. This study evaluates various fading characteristics of the new copper-doped dosemeter using current equipment for processing of TLDs and calibrating to a National Institute of Standards and Technology standard source. The 57-week study took place at the Naval Dosimetry Center, Bethesda, MD, USA. TLDs were stored for various lengths of time before and after being exposed to a National Institute of Standards and Technology calibrated radiation sources. TLDs were then processed using current US Navy instructions and the resulting dose compared with the calibrated exposure. Both loss of signal and loss of sensitivity were evaluated. The results of this study have shown that the DT-702 TLD has no statistically significant change in sensitivity or change in signal with up to 57 weeks of pre- or post-irradiation time. The results of this study will increase the accuracy of exposure record keeping for the Navy and will allow longer issue periods. This will increase flexibility with international and domestic shipping procedures, as well as reduce workload requirements for dosimetry processing.

New methods for testing cyclotron carbon stripper foils

Carbon foils are used in cyclotrons and other accelerators to strip electrons from fast ions, enabling the extraction or further acceleration of those ions. Lifetimes of stripper foils (extractor foils) need to be as long as possible to maximize the efficiency of accelerator use and minimize radiation exposure of maintenance personnel. A foil's useful lifetime is determined in part by operating temperatures, manufacturing method, and mounting method. We used two methods to test foils in a simulated accelerator environment. These methods involve the heating in vacuum to temperature ranges 500–1750 and 500–4000 K. Either kind of testing can be done in a few minutes instead of the days or weeks typically needed in a cyclotron. Such tests show clearly that foils manufactured by different methods have different responses to elevated temperatures. Because of this fact, optimum mounting techniques depend on the foil type. Results to date are summarized.

COMPARISON OF TRANSPLENIC MULTIDETECTOR CT PORTOGRAPHY TO MULTIDETECTOR CT‐ANGIOGRAPHY IN NORMAL DOGS

We evaluated transplenic injection of iodinated contrast medium for computed tomography (CT) assessment of the portal vasculature. Specific aims were to: (1) establish a protocol for transplenic transplenic CT portography using a 40-row multidetector scanner; (2) compare transplenic CT portography to dual-phase CT angiography in terms of image quality, opacification of the portal system, and contrast enhancement of the portal vasculature and liver; (3) compare personnel exposure during transplenic CT portography and transplenic portal scintigraphy. Seven juvenile dogs underwent transplenic portal scintigraphy, CT angiography, and transplenic CT portography. Transplenic portal scintigraphy and CT angiography were performed using previously established protocols. For transplenic CT portography, a 20- or 22 gauge needle attached to an extension set was placed into the splenic parenchyma using CT guidance. Iodinated contrast medium (175 mg I/ml) was administered, and CT acquisition was started at the time of the injection. Transplenic CT portography was simple, rapid and provided more intense enhancement of the splenic and portal veins, with a lower contrast medium dose (median dose: 525 mg I for transplenic CT portography, 7700 mg I for CT angiography), but caused inconsistent intrahepatic portal branches and parenchymal opacification due to streamlining and streak artifacts. Despite significantly lower attenuation values in the portal vein, CT angiography provided sufficient enhancement for vessel identification and more consistent parenchymal hepatic enhancement. Personnel radiation exposure rate was higher during transplenic CT portography (0.0725 mSv/min) compared with transplenic portal scintigraphy (0.000125 mSv/min). As transplenic CT portography requires an average injection time of 1 min per study; over 650 [corrected] studies must be performed before reaching the maximum permissible whole body dose of 0.05 [corrected] Sv.

Transbronchial Biopsy Guided by Low-Dose MDCT: A New Approach for Assessment of Solitary Pulmonary Nodules

The objective of our study was to determine whether transbronchial bronchoscopic biopsy of solitary pulmonary nodules under CT guidance using a low-dose protocol can increase diagnostic yield in patients who had undergone unsuccessful conventional bronchoscopic biopsy. We included 33 consecutive patients (25 men; mean age +/- SD, 64 +/- 9.6 years) with solitary pulmonary nodules at different sites and with a lesion-to-pleura distance of at least 2 cm who previously underwent conventional bronchoscopy that did not result in histologic diagnosis. All patients were prospectively investigated with transbronchial bronchoscopic biopsy under MDCT guidance. Examinations were performed with the patient in conscious sedation using a low-dose protocol (80 kV, 20 mAs, 5-mm collimation, 10-mm slices). The position of the tip of the biopsy device was confirmed and documented before biopsies were performed. All specimens were examined by standard histopathologic techniques. The effective radiation dose was calculated for every patient. The diagnostic yield was 24 in 33 selected patients (overall accuracy, 72.7%): 13 (54%) had primary lung cancer and 11 (46%) had benign diagnoses. The formal operative characteristics were sensitivity, 59%; specificity, 100%; positive predictive value, 100%; and negative predictive value, 55%. The final diagnoses of the remaining nine patients in whom transbronchial bronchoscopic biopsy was not diagnostic were non-small cell lung cancer (n = 3); small cell lung cancer (n = 3); and alveolar carcinoma, carcinoid tumor, and hemorrhaged bulla (n = 1 each). All nonmalignant diagnoses were confirmed by 6 months radiographic and clinical follow-up. The mean duration of the procedure was 39 +/- 15 minutes, and the average effective dose was 0.7 mSv (range, 0.5-1.1 mSv). One case of pulmonary hemorrhage (3%) occurred after the procedure. MDCT-guided transbronchial bronchoscopic biopsy is a promising and safe tool for the diagnostic pathway of solitary pulmonary nodules in previously undiagnosed patients. Image quality was sufficient with low-dose protocols, which resulted in low radiation exposure for patients and personnel.

The EPR: A clear step forward in dose reduction and radiation protection

For the European Pressurized Water Reactor (EPR) a large effort was made to improve the plant design with respect to radiation protection using the experience gained during the design of former generations of pressurized water reactor (PWR) in France and Germany, and their current operation. Keeping the radiation exposure of personnel to an acceptable level is one of the main objectives of the EPR design. Both the individual and the collective doses are considered.Internationally comparable limits based on recommendations of the International Commission on Radiological Protection (ICRP) have been established for individual doses. These limits describe the framework within which the individual dose shall be kept as low as possible, applying the principles:•Justification: No practice involving exposures to radiation should be adopted unless it produces sufficient benefit to the exposed individuals or to society to offset the radiation detriment it causes.•Optimization: In relation to any particular source within a practice, the magnitude of individual doses, the number of people exposed, and the likelihood of incurring exposures where these are not certain to be received should all be kept as low as reasonably achievable (ALARA), economic and social factors being taken into account.•Limitation: The exposure of individuals resulting from the combination of all the relevant practices is subject to dose limits.The paper describes the design provision and measures introduced in the plant design to achieve the above described goals.They are in essence:•measures to avoid or to reduce sources of radiation;•layout aspects;•provisions made in the component design with respect to ease of operation and maintenance management;•improved possibilities of decontamination;•use of operating experience for design improvements.The radiation protection layout principles compiled on the basis of safe operating experience gained from the existing pressurized water reactors in France and Germany are used to develop an improved plant design with respect to radiation protection aspects and dose optimization.Summary: The European Pressurized Water Reactor is an evolutionary third-generation pressurized water reactor with a rating in the 1600 MWe class. Its development was started in 1992 by Framatome and Siemens, whose nuclear activities were combined in January 2001 to form Framatome ANP, now AREVA NP. Being the product of intense bilateral cooperation the EPR combines the technological accomplishments of the world's two leading PWR product lines—the French N4 reactors in operation at Chooz and Civeaux and the Konvoi reactors in operation at Neckarwestheim, Emsland and Isar in Germany. From the very start, development of the EPR was focused on improving plant safety and economics even further and also a large effort was made to improve the plant design with respect to radiation protection. Keeping the doses received by operating and maintenance personnel to a level far below the limiting values was one of the main objectives of the EPR design. Both the individual and the collective doses are considered in this article.

A system for the calculation and visualisation of radiation field for maintenance support in nuclear power plants

A system has been developed to improve the efficiency of maintenance work while decreasing the radiation exposure of maintenance personnel in nuclear power plants. The input data for dose rate calculation are automatically generated by using computer-aided design data. Changes for the input data corresponding to the progress of maintenance work, such as installation of a radiation shield and removal of a component, are easily input interactively on a graphical user interface (GUI). A new method was proposed which searches the sets of source and detector points between which gamma-ray attenuation is changed by the component movement. The calculation is performed only for the changed sets, so that the change of the three-dimensional dose rate distribution is calculated rapidly according to the work progress. The dose rate distribution and the radiation exposure of maintenance personnel are displayed three-dimensionally in colour with plant components and pipes on the GUI.

RADIATION EXPOSURE AND THE UROLOGIST: WHAT ARE THE RISKS?

Endourology is established in urology practice with routine use of fluoroscopic guidance. Medical personnel are rarely exposed to direct radiation exposure but secondary exposure occurs via radiation scatter. There are few reports on scatter radiation exposure and the subsequent risk to medical personnel involved in urological fluoroscopic procedures. We review the risks of scatter radiation exposure to medical personnel with reference to the routine use of fluoroscopic imaging in urological practice. We measured staff radiation exposure during a series of ureteral endourological procedures using LiF:Mg,Ti thermoluminescent dosimeters placed at the extremities of the operating surgeon, the assistant and the scrub nurse. Doses for percutaneous nephrolithotomy (PCNL) procedures were calculated by extrapolating from the ureteral procedure thermoluminescent dosimeter data. Theoretical scattered radiation dose rates were also calculated. The average ureteral procedure fluoroscopy time was 78 seconds with an exposure rate of 71 kV, 2.4 mA. The surgeon received the highest radiation exposure with the lower leg (11.6 +/- 2.7 microGy) and foot (6.4 +/- 1.8 microGy) receiving more radiation than the eyes (1.9 +/- 0.5 microGy) and hands (2.7 +/- 0.7 microGy). For a predicted annual caseload of 50 ureteral cases, the dose received does not exceed 0.12% of the Ionising Radiations Regulations 1999 annual dose limit for adult workers. Radiation exposure during PCNLs is higher but does not exceed 2% of the annual dose limits even if 50 PCNLs are performed annually. Fluoroscopic screening results in radiation exposure of medical personnel. The estimate of maximum scatter radiation exposure to the surgeon for 50 PCNL procedures a year did not exceed 10 mGy. This amount is less than 2% of permissible annual limits of equivalent dose to the extremities. Medical personnel should be aware of scatter radiation risks and minimize radiation exposure when involved in fluoroscopic screening procedures.

Protective aprons in imaging departments: manufacturer stated lead equivalence values require validation

The composition of protective aprons worn by X-ray personnel to shield against secondary radiation is changing. Lead is being replaced by either lead-free or composite (lead with other high atomic numbered elements) materials. These newer aprons are categorised by manufacturers in terms of lead equivalent values, but it is unclear how these stated values compare with actual lead equivalent values. In this work, the actual lead equivalence of 41 protective aprons from four manufacturers, all specified as having 0.25 mm lead equivalence, were investigated with transmission experiments at 70 and 100 kVp. All aprons were in current use. The aprons were screened for defects, and age, weight and design was recorded along with details of associated quality assurance (QA). Out of the 41 protective aprons examined for actual lead equivalence, 73% were outside tolerance levels, with actual levels in some aprons demonstrating less than half of the nominal values. The lack of compatibility between actual and nominal lead equivalent values was demonstrated by aprons from three of the four manufacturers investigated. The area of the defects found on screening of the protective aprons were within recommendations. The results highlight the need for acceptancy and ongoing checks of protective aprons to ensure that radiation exposure of imaging personnel is kept to a minimum.

Study on the cavitation erosion behavior of Fe-based hardfacing alloys containing Mn, Ti and V for replacing Co-based Stellite 6

Stellite 6 has been used as hardfacing material of valve components in nuclear power plant industry and other applications. Stellite 6 contains more than 60 wt % Co and it was recognized that Stellite 6 used in valve hardfacing is one of the main sources of Co, which is the major contributor to build up the radiation field in nuclear power plants. Thus it is largely responsible for the occupational radiation exposure of plant maintenance personnel. Also the price of Co is expensive and highly varying. Therefore, there have been many efforts to develop Co-free hardfacing alloy We have also developed Fe-based new alloy, of which sliding wear and cavitation erosion resistance were almost equivalent to those of Stellite 6. In the present study, the effects of Mn, Ti and V on the cavitation erosion behavior of the alloy were investigated. The Fe-based new alloy containing V had similar cavitation erosion resistance to Stellite 6 but the others containing Mn and Ti were inferior to Stellite 6.

Radiation exposure to operating room personnel during transperineal interstitial permanent prostate brachytherapy

Purpose: To identify factors associated with radiation exposure (RE) to operating room personnel during transperineal interstitial permanent prostate brachytherapy (TIPPB). Methods and Materials: Between May 1998 and December 2000, 155 patients underwent TIPPB with fluoroscopic and ultrasound guidance. Data for each case included: operating room time (OT), anesthesia time (AT), fluoroscopy time (FT), number and type of seed implanted, total seed activity, and resident participation. Results: Personnel RE per case, FT, OT, and AT decreased as case number increased. Whole body badge dose per case decreased from a mean of 0.15±0.01 mSv (15±1 mrem) in 1998 to 0.074±0.011 mSv (7±1 mrem) in 2000. Average FT per case decreased from a mean of 17:27 min (range, 10:40–28:23) in 1998 to 12:08 min (range, 6:40–31:00) in 2000. Resident participation was associated with increased FT. Mean whole body and ring badge doses for the treating radiation oncologist were 0.0076 mSv/min (0.76 mrem/min) and 0.05 mSv/min (5.26 mrem/min) of FT, respectively. Conclusions: FT was the predominant factor that related to RE during TIPPB. Treating radiation oncologists were exposed to less than 20 mSv per 100 cases, significantly less than other fluoroscopically guided procedures. Nonetheless, appropriate radiation exposure precautions during TIPPB should continue.

On-line monitoring of instrument channel performance in nuclear power plant using PEANO

On-Line monitoring evaluates instrument channel performance by assessing its consistency with other plant indications. Industry and EPRI experience at several plants has shown this overall approach to be very effective in identifying instrument channels that are exhibiting degrading or inconsistent performance characteristics “On-Line Monitoring of Instrument Channel Performance by EPRI (2000)”.On-Line monitoring of instrument channels provides information about the condition of the monitored channels through accurate, more frequent monitoring of each channel's performance over time. This type of performance monitoring is a methodology that offers an alternate approach to traditional time-directed calibration. On-line monitoring of these channels can provide an assessment of instrument performance and provide a basis for determining when adjustments are necessary. Elimination or reduction of unnecessary field calibrations can reduce associated labor costs, reduce personnel radiation exposure and reduce the potential for miss-calibration.PEANO “A Neuro-Fuzzy Model Applied to Full Range Signal Validation of PWR Nuclear Power Plant Data by Fantoni (2000)” is a system for on-line calibration monitoring developed in the years 1995–2000 at the Institutt for energiteknikk (IFE), Norway, which makes use of Artificial Intelligence techniques for its purpose. The system has been tested successfully in Europe in off-line tests with EDF (France), Tecnatom (Spain) and ENEA (Italy). PEANO is currently installed and used for on-line monitoring at the HBWR reactor in Halden. This paper describes the results of performance tests on PEANO with real data from a US PWR plant, in the framework of a co-operation among IFE, EPRI and Edan Engineering, to evaluate the potentials of PEANO for future installations in US nuclear plants.

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.