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PubMed1989

Testing a combined radiation protection modality: chemical protector and local shielding.

The impact of combined radiation protection upon damage to critical organs-spleen, small intestine, and bone marrow was studied in adult rat males 3 days after whole-body exposure to 9.5 Gy gamma-ray dose. Adeturone, the chemical radioprotector used, was administered intraperitoneally at 1/17 of its LD50 dose. Local shielding of the abdomino-lumbal region was accomplished using a lead ring providing on average 28-30% attenuation of radiation exposure. This degree of physical abdomino-lumbal protection combined with adeturone (50 mg/kg) pretreatment resulted in mutual enhancement of the components' action, expansion of the chemical agent's therapeutic range, providing a combination with improved overall antiradiation properties.

Adenosine Triphosphate↗
PubMed1996

The present system of quantities and units for radiation protection.

The International Commission on Radiation Units and Measurements has over the last decade developed operational quantities, the ambient, directional and personal dose equivalent, suitable for the measurement of radiation fields in a variety of circumstances. Experience with the use of these quantities to represent the dose limitation quantities defined by the International Commission on Radiological Protection in 1977 has been an important part of recent radiation protection metrology. The definition by International Commission on Radiological Protection in 1991 of new limitation quantities, the equivalent dose and the effective dose has necessitated a redirection of this work. The metrology field has made good progress, however. It has found that for photons, at least above 50 keV, the effective dose can be measured by the ambient dose equivalent about as well as the former effective dose equivalent. Unfortunately, for neutrons the existing and already quite severe complications have been made somewhat worse by the new quantities although not any worse in the important region between 0.1 and 1 MeV. Neutron measurements over a broad energy range are the subject of extensive evaluation and some new suggestions as the metrology field wrestles with these problems. Values of wR constitute an important part of the International Commission on Radiological Protection recommendations. A brief history of the development of higher relative biological effectiveness values for fission neutrons and alpha particles leading to the selection of 20 for wR in each case, is provided.

Dose-Response Relationship, Radiation↗
PubMed2005

Genetic and epigenetic features in radiation sensitivity. Part II: implications for clinical practice and radiation protection.

Recent progress especially in the field of gene identification and expression has attracted greater attention to the genetic and epigenetic susceptibility to cancer, possibly enhanced by ionising radiation. This issue is especially important for radiation therapists since hypersensitive patients may suffer from adverse effects in normal tissues following standard radiation therapy, while normally sensitive patients could receive higher doses of radiation, offering a better likelihood of cure for malignant tumours. Although only a small percentage of individuals are "hypersensitive" to radiation effects, all medical specialists using ionising radiation should be aware of the aforementioned progress in medical knowledge. The present paper, the second of two parts, reviews human disorders known or strongly suspected to be associated with hypersensitivity to ionising radiation. The main tests capable of detecting such pathologies in advance are analysed, and ethical issues regarding genetic testing are considered. The implications for radiation protection of possible hypersensitivity to radiation in a part of the population are discussed, and some guidelines for nuclear medicine professionals are proposed.

Epigenesis, Genetic↗
PubMed1995

Application of the HSEF to assessing radiation risks in the practice of radiation protection.

The primary risk coefficients upon which exposure limits for radiation protection purposes are currently based are derived almost exclusively from cancer-induction data obtained from human populations exposed to radiations of low linear energy transfer. The question of higher linear energy transfer radiations is handled by means of quality factors derived from values for relative biological effectiveness obtained from animal data. However, the advent of microdosimetry has made it possible to establish hit size effectiveness functions from single-cell systems, both in vitro and in vivo. This type of function can substitute completely for the concept of relative biological effectiveness, Q and equivalent dose. A common basis for risk coefficients and the hit size effectiveness function lies in the fact that human cancers are monoclonal and thus single cell in origin. The present communication utilizes this common base as a means of extending the present low-linear energy transfer based risk coefficients to include carcinogenic responses from exposure in radiation fields of any one or mixed qualities, extending from the smallest to the largest linear energy transfers of practical consequence. In doing so, risks from ionizing radiations of any linear energy transfer may be predicted more accurately than at present.

Biophysical Phenomena↗
PubMed1992

[Radiation protection in diagnostic radiology].

For every diagnostical X-ray radiation exposure the applied dose has to be limited to the smallest possible value. Within the scope of a general Swiss survey it has been found that in the various medical practices and hospitals the applied doses varied quite strongly. The main reasons leading to an overdose were the operating conditions of the X-ray and film processing equipment, the film and foil materials and improper filming techniques. The applied single dose served as a measure for the radiation protection assessment of diagnostical X-ray exposures. To prevent this in the future, individual patients who are exposed to unnecessary radiation loads should be regularly checked in quality-ensuring tests.

Humans↗
PubMed2005

Radiation protection of DNA and membrane in vitro by extract of Hemidesmus indicus.

Radioprotective effect of H. indicus root extract on lipid peroxidation in rat liver microsomes and plasmid DNA was examined. Hemidesmus indicus (HI) root extract was found to protect microsomal membranes as evident from reduction in lipid peroxidation values. The extract could also protect DNA from radiation induced strand breaks.

Animals↗
PubMed2006

Radiation protection by deferiprone in animal models.

The effectiveness of deferiprone (L1) in removing depleted uranium (DU) and protecting animals from radiation exposure was examined. Rats that had received 2 mg/kg DU via intramuscular injection were orally administered 100, 200 or 400 mg/kg L1 for 3 days. In all of the groups, significant increases in urinary DU excretion and decreases in DU concentration in the injected muscle were observed, indicating that L1 combined with DU and DU was excreted in the urine. No significant increase in the amount of DU in the excreta or decrease in DU concentration in organs other than the muscles was found. As a preliminary test, the effectiveness of L1 in reducing radiation damage was examined in mice injected with 400 mg/kg L1 and rats administered orally with 200 and 400 mg/kg L1 before and just after x-ray exposure. The results were inconclusive.

Administration, Oral↗
PubMed1985

Lauriston S. Taylor Lecture. Limitation and assessment in radiation protection.

Protection against ionizing radiation can follow two fundamentally different approaches. In limitation, the maximum permissible dose equivalent is selected on the basis of worst-case assumptions on the shape of dose-effect curves and the influence of other factors (dose distribution, relative biologic effectiveness, etc.). This system has the restricted aim of ensuring that radiation exposure results in risks below stipulated levels. In assessment, the functional relation and the numeric values required for risk estimation are postulated. This permits statements of the absolute values of risks, not only for the maximum permissible dose equivalent but also for any lesser dose equivalents. The principal concept underlying the assessment system is that of incoherence: lack of interdependence between the effects of dose increments and lack of interdependence between the effects on the constituent cells and organs of the body. The notion of incoherence and the choices of numeric values of risks are subject to substantial doubts. They must nevertheless be adopted when risk estimation cannot be avoided.

Animals↗
PubMed1991

Radiation protection and restoration by the synthetic 163-171 nonapeptide of human interleukin 1 beta.

We have previously reported that the synthetic nonapeptide VQGEESNDK, position 163-171 of human interleukin 1 (IL-1 beta), when injected in immunodepressed mice, shows immunorestorative activity similar to that of the whole protein, but with no IL-1-like inflammatory effects [Frasca et al., J. Immunol. 141, 2651-2655 (1988)]. In the present study we have compared the protective and restorative activities of the nonapeptide and human recombinant (hur) IL-1 beta on the survival of lethally irradiated mice. When mice were given a single injection of different doses of the nonapeptide or hurIL-1 beta 20 h before total-body irradiation, both molecules increased the percentage survival of mice exposed to 750 or 850 cGy, but not to 950 cGy. The nonapeptide, however, is less effective than hurIL-1 beta and displays a different dose-response relationship, suggesting that the two molecules act through different radioprotective pathways. When mice were injected with the nonapeptide or hurIL-1 beta immediately after exposure to 850 cGy, the percentage survival was also increased but restoration was lower than protection in both cases. The nonapeptide was also less effective than hurIL-1 beta in restoration, but the two molecules displayed a comparable dose-response relationship as if they shared similar mechanisms. These findings indicate that the 163-171 nonapeptide is able to protect from lethal radiation injury and to restore viability. The nonapeptide appears less effective than hurIL-1 beta but does not exhibit the IL-1-like side effects of the whole molecule.

Adjuvants, Immunologic↗
PubMed1978

Radiation protection philosophy: bioethical problems and priorities.

The evolution of radiation protection philosophy over the past thirty years calls attention to an urgent need to review and revise current radiation control programs with respect to the ethical problems and priorities they reflect. One problem is the environmental crisis-mentality escalating already rising expectations in our affluent society about levels of safety. A second problem is the propriety or impropriety of using cost/benefit/risk quantifications in setting priorities in public health protection. A threefold ethical justification for risk-assessment methodology challenges our government regulatory agency system as presently chartered and operationally conducted.

Environmental Pollution↗
PubMed2001

Radiation protection in interventional radiology.

There is growing concern regarding the radiation dose delivered during interventional procedures, particularly in view of the increasing frequency and complexity of these techniques. This paper reviews the radiation dose levels currently encountered in interventional procedures, the consequent risks to operators and patients and the dose reduction that may be achieved by employing a rigorous approach to radiation protection.

Fluoroscopy↗
PubMedDate not supplied

Prostate brachytherapy with iodine-125 seeds: radiation protection issues.

AIMS AND BACKGROUND: Brachytherapy for prostate cancer by means of permanently implanted 125I sources is a well established procedure. An increasing number of patients all over the world are treated with this modality. When the technique was introduced at our institution, radiation protection issues relative to this technique were investigated in order to comply with international recommendations and national regulations. Particular attention was paid to the need for patient shielding after discharge from hospital. METHODS: The effective and equivalent doses to personnel related to implantation, the effective dose to patient relatives as computed by a developed algorithm, the air kerma strength values for the radioactive sources certified by the manufacturer compared with those measured by a well chamber, and the effectiveness of lead gloves in shielding the hands were evaluated. RESULTS: The effective dose to the bodies of personnel protected by a lead apron proved to be negligible. The mean equivalent doses to the physician's hands was 420 microSv for one implant; the technician's hands received 65 microSv. The mean air kerma rate measured at the anterior skin surface of the patient who had received an implant was 55 microGy/h (range, 10-115) and was negligible with lead protection. The measured and certified air kerma strength for125I seeds in RAPID Strand corresponded within a margin of +/- 5%. The measured attenuation by lead gloves in operative conditions was about 80%. We also defined the recommendations to be given to the patient at discharge. CONCLUSIONS: The exposure risks related to brachytherapy with 125I to operators and public are limited. However, alternation of operators should be considered to minimize exposure. Patient-related measurements should verify the dose rate around the patient to evaluate the need for shielding and to define appropriate radiation protection recommendations.

Adenocarcinoma↗
PubMed2006

Extended conversion coefficients for use in radiation protection of the embryo and fetus against external neutrons from 10 MeV to 100 GeV.

External neutron exposure is of concern in the environment and in some workplaces. Dose assessments for neutrons frequently rely on fluence-to-absorbed dose conversion coefficients. A problem of concern in radiation protection is exposure of pregnant women to ionizing radiation because of the high radiosensitivity of the embryo and fetus. While neutron fluence-to-dose conversion coefficients for adults are recommended in ICRP publications and ICRU reports, conversion coefficients for embryos and fetuses are not given in the publications. This study uses the Monte Carlo code MCNPX to determine mean absorbed doses to the embryo and fetus when the mother is exposed to neutron fields. A previous study has dealt with neutrons from 1 eV to 10 MeV. In this study, monoenergetic neutrons ranging from 10 MeV to 100 GeV are considered. The irradiation geometries include antero-posterior, postero-anterior, lateral, rotational, and isotropic. At each of these standard irradiation geometries, absorbed doses to the fetal brain and body are calculated for the embryo of 8 wk and the fetus of 3, 6, or 9 mo. Neutron fluence-to-absorbed dose conversion coefficients are derived for the four prenatal ages. The results showed that the fetus at about 3 mo of prenatal age should receive more radiation protection to prevent long-term brain damage. During prenatal life, the fetus generally receives the highest absorbed dose per unit neutron fluence for antero-posterior irradiation. In cases where the irradiation geometry is not specified or not adequately known, conversion coefficients of AP-irradiation can therefore be used in a conservative dose assessment of fetus exposure to external neutrons.

Body Burden↗
PubMed1999

An application of the NCRP screening techniques to atmospheric radon releases from the former feed materials production center near Fernald, Ohio. National Council on Radiation Protection and Measurements.

The National Council on Radiation Protection and Measurements has published a series of screening models for releases of radionuclides to the environment. These models have been used to prioritize radionuclides being considered in environmental dose reconstructions. The NCRP atmospheric models are also accepted by the U.S. Nuclear Regulatory Commission for demonstrating compliance with the constraint on releases of airborne radioactive materials to the environment from licensees other than power reactors. This study tested the NCRP atmospheric techniques by comparing annual average predicted air concentrations of radon with measured radon concentrations at 14 locations 43 m to 598 m downwind of the former U.S. Department of Energy Feed Materials Production Center (FMPC) near Fernald, Ohio, for the period 2 July 1985 to 2 July 1986. Predictions were made using five different sets of meteorological data as input: (1) NCRP default values; (2) composite FMPC site data; (3) data from the Greater Cincinnati Airport; (4) data from the Dayton, Ohio, airport; and (5) data collected at Miami University, located near Oxford, Ohio. Following are the respective medians and ranges of the ratio of the predicted to observed annual radon air concentrations for each of these sources of meteorological data: (1) 5.2, 0.9-54; (2) 1.4, 0.1-8.2; (3) 0.7, 0.1-7.2; (4) 0.7, 0.1-8.4; and (5) 0.6, 0.1-10. The stated goal of the NCRP models is to predict doses that do not underpredict actual doses by greater than a factor of 10. In this comparison, all of the meteorological data produced air concentration predictions that meet this criteria. However, to ensure that final doses meet this criterion, one would need to carefully evaluate all assumptions used to calculate dose from each of these air concentrations.

Air Pollution, Radioactive↗