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The effect of high-linear energy transfer ions on the electron paramagnetic resonance signal induced in alanine.

Microcrystalline samples of L-alanine irradiated with energetic high-LET cobalt and iron ions had different EPR spectra compared to alanine samples irradiated with low-LET photons. The differences in the shapes of the EPR spectra and their dependence on the microwave power are related to the differences in the microwave power saturation of the radicals induced by the various types of ionizing radiation. The changes in the shape of the EPR spectra, which were caused by increasing microwave power, were more pronounced in samples irradiated with low-LET radiation than with high-LET particles. This effect showed a long-term stability and can be used to monitor radiation quality.

Alanine↗

The impact of ICRP/ICRU quantities on high energy neutron dosimetry: a review.

Unlike other fields of toxicology, radiation protection has a dual system of quantities, one set for assessment and the derivation of authorised limits and another set for monitoring radiation performance and compliance. Neutrons are an important or dominant constituent of the radiation field around high energy accelerators and the evolution of the radiation protection quantities used to measure neutrons is described. In 1990 ICRP introduced a new quantity, the effective dose. E. with which to express its protection limits. E represented a radical departure from previous advice of the Commission, particularly in the manner by which it weighted the absorbed dose deposited by high LET radiations. This advice had profound consequences for neutron dosimetry. Over the past decade analyses have revealed logical flaws and inconsistencies in the definition of effective dose. These are briefly discussed with most emphasis being placed on inconsistencies in radiation weighting. Suggestions are made with a view to resolving these inconsistencies.

Neutrons↗

[Characteristics and results of the determination of the doses of internal irradiation of the thyroid gland in the population of contaminated districts of the Byelorussian Republic].

The authors provide the results of studying the reconstruction of individual doses of thyroid radiation among the community living in polluted areas of the Byelorussian Republic according to radiation monitoring data and with regard to the nature of radioactive pollution of the land. Every individual result of estimating the degree of thyroid radiation was characterized by 3 magnitudes: the lower and upper limit of possible values and by the intermediate (basic) value. The authors hold that studies of the correlations between the values of individual doses of thyroid radiation and different parameters of the radiation situation in every region will promote further specification of individual doses of thyroid radiation.

Accidents↗

Development of a rotating X-ray shutter for coronary angiography using synchrotron radiation.

The first clinical examination using a two-dimensional imaging system of coronary angiography with monochromated synchrotron radiation was carried out at the National Laboratory for High Energy Physics in May 1996. A rotating X-ray shutter was developed to produce a pulsed X-ray beam with 2-6 ms of beam spill to suppress image blurring, at a frequency of 30 Hz. A performance test of the X-ray shutter using synchrotron radiation was carried out, and it was verified that the shutter had satisfactory specifications for clinical applications. With this X-ray shutter the monitored radiation dose in clinical examinations was consistent with theoretical expectations and kept within a reasonable level of radiation protection.

Journal Article↗

Blue light stimulated luminescence in calcium fluoride, its characteristics and implications in radiation dosimetry.

Strong optically stimulated luminescence (OSL), stimulated by blue light, has been observed, for the first time, in natural calcium fluoride (CaF(2)) phosphor, used as thermoluminescence dosemeters. Traps responsible for all three thermoluminescence (TL) peaks appearing upto 300 degrees C, i.e. 126, 196 and 264 degrees C, were observed to contribute to the blue light stimulated luminescence (BLSL) in CaF(2). When the areas under the respective curves (BLSL and TL) were measured, the BLSL measured at room temperature was found to be approximately 1.8 times the TL output of the dosimetry peak that appeared at approximately 264 degrees C. However, when measured after thermally annealing the first two TL peaks, the BLSL signal was found to be 0.26 times the TL output of the dosimetry peak at 264 degrees C. This paper describes the characteristics of the BLSL signal using linearly modulated OSL after subjecting the phosphor to different annealing treatments. Feasibility studies to assess the usefulness of BLSL in CaF(2) for environmental radiation monitoring are also discussed.

Calcium Fluoride↗

Radiation shielding design for a hot repair facility.

A new repair and decontamination area is being built to support operations at the demonstration fuel cycle facility for the Integral Fast Reactor program at Argonne National Laboratory's site at the Idaho National Engineering Laboratory. Provisions are made for remote, glove wall, and contact maintenance on equipment removed from hot cells where spent fuel will be electrochemically processed and recycled to the Experimental Breeder Reactor-II. The source for the shielding design is contamination from a mix of fission and activation products present on items removed from the hot cells. The repair facility also serves as a transfer path for radioactive waste produced by processing operations. Radiation shields are designed to limit dose rates to no more than 5 microSv h-1 (0.5 mrem h-1) in normally occupied areas. Point kernel calculations with buildup factors have been used to design the shielding and to position radiation monitors within the area.

Facility Design and Construction↗

Occupational Exposure in Nuclear Medicine and PET.

Purpose: With the increasing use of 18F-fluorodeoxyglucose (FDG) positron emission tomography (PET) for scanning in oncology in our center, a radiation dose survey was performed to determine the impact on staff exposure. Conventional nuclear medicine procedures such as gallium scan, bone scans, and sestamibi cardiac scans are used for comparative purposes.Procedure: Patients were measured using a hand-held radiation monitor (Victoreen 450-P) at various distances and times that replicate typical patient contact scenarios in the Diagnostic Imaging Department.Results: We present our findings from the survey and the implications these have on staff radiation exposure. The data suggest that emerging oncologic techniques such as PET, high dose gallium-67, and high dose Tl-201 do not represent a significantly greater occupational radiation hazard than conventional nuclear medicine procedures.

Journal Article↗

[beta-Radiation exposure with (188)Re-labelled pharmaceuticals].

AIM: The number of therapies with radiopharmaceuticals labelled with (188)Re is increasing requiring the documentation of the beta radiation exposure Hp(0.07) of the staff at all working and production sites and during the application and follow-up of the patient according to the new German Radiation Protection Law (StrlSchV). However, data for beta-radiation exposure are rare. Therefore, we determined the personal dose Hp(0.07) of the skin of the hands handling (188)Re radiopharmaceuticals to identify steps of high radiation exposure and to optimize working conditions. METHOD: Thermoluminescence dosimeters (TLD 100) were fixed to the fingertips of the radiochemist, the physician and the nurse and compared to official ring dosimeters. In addition, to monitor radiation exposure continuously readable electronic beta- and gamma dosimeters EPD (Siemens) were used. At eight days in which therapies were performed these readings were evaluated. RESULTS: Considering one therapy with a (188)Re-labelled radiopharmaceutical the middle finger of the radiochemist (production) and the physician (application) showed a radiation burden of 894 and 664 muSv/GBq, respectively. The cumulative dose of the fingertips after eight days of therapy was 249 and 110 mSv for the radiochemist and physician, respectively. A cumulative finger dose after eight days of therapy of 17 and 38 muSv/GBq was found for physician and nurse leading to a Hp(0.07) of 3 and 6 mSv, respectively. Preparing the radiopharmaceutical labelled with 20GBq of (188)Re the reading of the personal electronic dosimeter of the radiochemist showed a gamma-dose rate Hp(10) of 55 muSv/h and a beta-dose rate Hp(0.07) of 663 muSv/h which are obviously not representative for the true radiation dose to the skin of the fingertips. CONCLUSION: During therapy with (188)Re-labelled radiopharmaceuticals the true radiation dose to the skin of the finger tips exceeds by far the readings of the official ring dosimeters as well as the continuously readable beta- and gamma dosimeters. This means a risk in exceeding the radiation limit of 500 mSv/a given in the German Radiation Protection Law ( section sign55 StrSchV) primarily in the working field of the radiochemist and the administering physician.

Beta Particles↗

The evaluation of a gastric bile probe.

The purpose of this study was to validate a new technique for measuring duodenogastric bile reflux in the human subject. A custom built cadmium telluride gamma detector (Radiation Monitoring Devices, Mass), small enough to be passed into the oesophagus and stomach, was developed and tested for sensitivity to 99Tcm and 75Se radioisotopes. When immersed in radiolabelled water, the detector was capable of measuring gamma radiation in quantities as low as 0.1 microCi (0.0037 MBq) per ml. Two patients (A and B) with endoscopically proven bile reflux, and three normal volunteers (C, D and E) underwent oesophageal manometry to map the position of the lower oesophageal sphincter (LOS). The gamma probe was passed via the nose, to a position in the gastric fundus, 5 cm below the LOS. Each subject was placed supine under a gamma camera (Siemens LFOV 37 ZLC head), centred on the epigastrium. A 4 mCi (148 MBq) dose of radiolabelled 99Tcm-HIDA was administered intravenously, and simultaneous internal/external scanning was performed for between 45 and 90 min. Internal gamma probe data was transferred by a screened cable to a Memolog 600 portable recorder, using a 5 s counting interval, and from the gamma camera to a Nodecrest Micas III computer, using a 15 s counting interval. Gamma camera counts from a region of interest over the fundus of the stomach were then correlated with counts from the internal probe using a linear regression analysis program on the Nodecrest. The internal gamma probe functioned well at body temperature in the acidic gastric environment. Radiolabelled bile refluxed into the stomach during HIDA scanning in three out of the five subjects (one patient and two normal volunteers). There was a strong correlation between internal and external gamma counts (A, r = +0.79; C, r = +0.53; E, r = +0.54; P greater than 0.01). In the other two cases, there was no bile reflux, but still a significant correlation between internal and external gamma counts (B, r = +0.89; D, r = +0.75; P greater than 0.01). The mean correlation coefficient for the series of five cases was +0.70. We conclude firstly that the newly developed internal gamma detector is capable of measuring the reflux of radiolabelled bile into the human stomach and, secondly, that bile reflux may occur in normal subjects as well as those with upper gastrointestinal pathology.

Aged↗

Radioactive materials in recycled metals.

In recent years, the metal recycling industry has become increasingly aware of an unwanted component in metal scrap--radioactive material. Worldwide, there have been 35 instances where radioactive sources were unintentionally smelted in the course of recycling metal scrap. In some cases contaminated metal consumer products were distributed internationally. In at least one case, serious radiation exposures of workers and the public occurred. Radioactive material appearing in metal scrap includes sources subject to licensing under the Atomic Energy Act and also naturally occurring radioactive material. U.S. mills that have smelted a radioactive source face costs resulting from decontamination, waste disposal, and lost profits that range from 7 to 23 million U.S. dollars for each event. To solve the problem, industry and the government have jointly undertaken initiatives to increase awareness of the problem within the metal recycling industry. Radiation monitoring of recycled metal scrap is being performed increasingly by mills and, to a lesser extent, by scrap processors. The monitoring does not, however, provide 100% protection. Improvements in regulatory oversight by the government could stimulate improved accounting and control of licensed sources. However, additional government effort in this area must be reconciled with competing priorities in radiation safety and budgetary constraints. The threat of radioactive material in recycled metal scrap will continue for the foreseeable future and, thus, poses regulatory policy challenges for both developed and developing nations.

Brachytherapy↗

Mutation frequency of Dictyostelium discoideum spores exposed to the space environment.

Two strains of cellular slime mold Dictyostelium discoideum, a radiosensitive mutant and the parental wild-type strain, were used to investigate the effects of cosmic radiation on viability and mutation frequency at the spore stage for about 9 days in Space Shuttle of NASA. We measured little effect of space environment on viability and cell growth in the both strains as compared to ground controls. The mutation frequency of the flown spores were similar to that of ground control. These results suggest that there could be no effect of cosmic radiation, containing high linear energy transfer radiation at about 0.9 mSv/day as detected by real-time radiation monitoring device on the induction of mutation at the spore stage.

Animals↗

Occupational radiation dose associated with Rb-82 myocardial perfusion positron emission tomography imaging.

BACKGROUND: We determined staff radiation dose during rest and stress rubidium 82 myocardial perfusion positron emission tomography (PET) imaging. METHODS AND RESULTS: Patients received 1,587 +/- 163 MBq (42.9 +/- 4.4 mCi) Rb-82 during rest or pharmacologic stress. A pressurized ion chamber was used to monitor radiation exposure in 50 examinations. For comparison, staff exposure during pharmacologic stress in 20 other patients receiving 1,204 +/- 55.5 MBq (32.54 +/- 1.5 mCi) technetium 99m 2-methoxy isobutyl isonitrile (MIBI) was measured. For Rb-82 infusion and PET acquisition, the mean dose was 0.45 +/- 0.25 microSv (0.045 +/- 0.025 mrem). Exposure for routine stress testing at variable distances from the patient was equivalent to background. Similar exposure for pharmacologic stress testing through 7 minutes after injection of Tc-99m MIBI at variable distances was 1.075 +/- 0.32 microSv (0.108 +/- 0.03 mrem). However, exposure for stress tests starting 7 minutes after Rb-82 infusion at 0.5 m was estimated at 0.4 microSv (0.04 mrem). To determine the potential radiation dose for those responding to a medical emergency or otherwise in close proximity to a patient, we measured the mean cumulative dose at 0.5 m from 0 to 7 minutes of Rb-82 infusion, which resulted in 19.1 +/- 5.8 microSv (1.9 +/- 0.58 mrem). CONCLUSIONS: Radiation doses for all tasks during routine Rb-82 stress-rest PET are lower than measured Tc-99m MIBI values. However, the radiation dose in close proximity to the patient during or immediately after Rb-82 infusion can be considerably higher, underscoring the need for strict attention to source distance and contact times.

Exercise↗

The radiological accident in Goiânia: the initial remedial actions.

The removal of a 50.9-TBq 137Cs source from a radiation therapy facility in Goiânia gave rise to a radiological accident in September 1987 whose proportions were aggravated by the 16-d interval from the beginning of a series of acts that resulted in the contamination of people and areas, to the moment of identification and seeking of aid. Data gathered from the declarations of persons involved in the accident, matched with the medical assessment and radiation monitoring of areas affected, made it possible to determine procedures for care of victims and for decontaminating operations of these areas. The priorities of these procedures were to provide care to victims and eliminate critical paths by which other persons might be affected by exposure to radiation or contamination. This paper presents (1) remedial actions taken during the first weeks, (2) management problems associated with the accident, and (3) lessons learned from this episode that are of benefit to us and, hopefully, to others.

Accidents↗

Occupational exposures to radiofrequency radiation (18-31 MHz) from F dielectric heat sealers.

The National Institute for Occupational Safety and Health (NIOSH) has initiated an epidemiologic study to evaluate whether or not radiofrequency (RF) radiation in the 10--100 MHz range has any effects on the reproductive functions of exposed workers. Initial investigations indicated that a suitable population for this study might exist in industries utilizing RF dielectric heat sealers. To estimate exposure levels of RF heat sealer operators, NIOSH made exposure measurements for 82 operators in 13 facilities with a Narda Broadband Isotropic Radiation Monitor, Model 25540 with an electric (E) field probe. Model 8644 and a magnetic (H) field probe, Model 8635. The geometric mean of the maximum measured exposures was at least 200 V/m for the E-field and 0.094 A/m for the H-field. The Occupational Safety and Health Administration (OSHA) exposure standard for RF radiation in the range of 10--100,000 MHz is 10 mW/cm2 as averaged over any 0.1-hour period. This value corresponds to an exposure of 200 V/m for the E-field and 0.5 A/m for the H-field. NIOSH found that 55% of the heat sealer operators were exposed to levels for the E-field above 200 V/m; for the H-field, 21% of the operators were exposed to levels above 0.5 A/m. For the heat sealers evaluated, the frequencies ranged from 18 to 31 MHz. On the basis of these environmental data, RF heat sealer operators experience a wide range of exposures both above and below the OSHA standard. The exposure range is sufficiently broad to make these operators adequate candidates for epidemiologic study.

Environmental Exposure↗

Revealing lymphoma growth and the efficacy of immune cell therapies using in vivo bioluminescence imaging.

Cancer therapeutics have achieved success in the treatment of a variety of malignancies, however, relapse of disease from small numbers of persistent tumor cells remains a major obstacle. Advancement of treatment regimens that effectively control minimal residual disease and prevent relapse would be greatly accelerated if sensitive and noninvasive assays were used to quantitatively assess tumor burden in animal models of minimal residual disease that are predictive of the human response. In vivo bioluminescence imaging (BLI) is an assay for the detection of small numbers of cells noninvasively and enables the quantification of tumor growth within internal organs. Fusion genes that encode bioluminescent and fluorescent reporter proteins effectively couple the powerful in vivo capabilities of BLI with the subset-discriminating capabilities of fluorescence-activated cell sorting. We labeled 2 murine lymphoma cell lines with dual function reporter genes and monitored radiation and chemotherapy as well as immune-based strategies that employ the tumorcidal activity of ex vivo-expanded CD8(+) natural killer (NK)-T cells. Using BLI we were able to visualize the entire course of malignant disease including engraftment, expansion, metastasis, response to therapy, and unique patterns of relapse. We also labeled the effector NK-T cells and monitored their homing to the sites of tumor growth followed by tumor eradication. These studies reveal the efficacy of immune cell therapies and the tempo of NK-T cell trafficking in vivo. The complex cellular processes in bone marrow transplantation and antitumor immunotherapy, previously inaccessible to investigation, can now be revealed in real time in living animals.

Animals↗

Cancer incidence in a population potentially exposed to radium-226 at Dalgety Bay, Scotland.

Cancer incidence in the Dalgety Bay area of Fife, Scotland, was examined following the detection of radium-226 particles by routine radiation monitoring. The study was confounded by rapid population growth, demographic change and the relatively high socioeconomic status of the Dalgety Bay population. Health Board Primary Care Division records were used to calculate population estimates and Carstairs deprivation score was used to adjust for socioeconomic characteristics. In the period 1975-90, 211 residents were registered as having cancer compared with 214.21 expected from Scottish national rates. Of specific cancers possibly associated with radiation, the incidence of stomach, liver, lung, bone, prostate, bladder and kidney cancer and lymphoma were lower than expected while colon, rectum, pancreas, skin, breast and thyroid cancer and multiple myeloma and leukaemia were higher. There were three cases of childhood leukaemia compared with 1.22 expected. The only statistically significant differences observed were for pancreas (11 cases, O/E 2.28), lung (25 cases, O/E 0.65) and non-melanoma skin (36 cases, O/E 1.50). Stomach cancer was of borderline statistical significance (four cases, O/E 0.40). Adjustments for socioeconomic factors accounted for the apparently low incidence of stomach and lung cancer and, to a lesser extent, skin cancer, which remained of borderline statistical significance. Results in relation to pancreas cancer were unchanged. The observations of raised incidence of pancreas and skin cancer arose in the context of a survey of 17 cancer sites, from which the finding of two or more statistically significant results is not unusual (P = 0.21), and the numbers of cases involved were small. The epidemiological evidence for an association between radiation exposure and pancreas cancer risk is weak. Stronger evidence exists for an association with skin cancer. In the present study the anatomical distribution of the 36 cases was similar to that found elsewhere in Scotland.

Adolescent↗

Luminescence dosimetry using building materials and personal objects.

There is a growing public awareness of the risk of accidental radiation exposure due to ageing nuclear power installations, illegal dumping of nuclear waste and terrorist activities, and of the consequential health risks to populations in addition to social and economic disturbance extending beyond national boundaries. In the event of catastrophic incidents where no direct radiation monitoring data are available, the application of retrospective dosimetry techniques such as luminescence may be employed with materials from the immediate environment to confirm values of cumulative gamma dose to compare with or augment computational modeling calculations. Application of the method to post-Chernobyl studies has resulted in the development of new procedures using fired building materials with the capability to measure cumulative doses owing to artificial sources of gamma radiation as low as 20 mGy. Combined with Monte Carlo simulations of photon transport, values of cumulative dose in brick can be presented in a form suitable for use in dose-reconstruction efforts. Recent investigations have also shown that certain types of cementitious building material, including concrete, mortar and plaster, and personal objects in the form of telephone cards containing microchips and dental ceramics have the potential to be used for retrospective dosimetry. Examples of the most recent research concerning new materials and examples of application to sites in the Former Soviet Union are discussed.

Construction Materials↗

Radiology instruction and use of ionizing radiation in U.S. dental schools.

In fall 1980, the Commission on Dental Accreditation of the American Dental Association conducted a comprehensive survey of radiology instruction and the use of ionizing radiation in dental education. All 60 dental schools in the United States responded to the survey. Data were collected on course objectives, course content, clock hours of instruction, radiology content in other clinical courses, the number, educational background, and years of teaching experience of radiology faculty, clinical requirements in radiology and the measures used to assess student competency, and the use of radiographs in providing patient care. Attention was directed to practices used in monitoring radiation protection and hygiene. These data provide a frame of reference for evaluating the status of radiology instruction at the respective schools. More important, they provide faculty with a baseline for determining what changes, if any, are needed in the current radiology curriculum.

Clinical Competence↗