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Sample records for routine radiation release

  1. Building shielding effects on radiation doses from routine radionuclide releases

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1977-01-01

    In calculating population doses from the release of radionuclides to the atmosphere, it is usually assumed that man spends all of his time outdoors standing on a smooth infinite plane. Realistically, however, man spends most of the time indoors, so that substantial reductions in radiation doses may result compared with the usual estimates. Calculational models were developed to study the effects of building structures on radiation doses from routine releases of radionuclides to the atmosphere. Both internal dose from inhaled radionuclides and external photon dose from airborne and surface-deposited radionuclides are considered. The effect of building structures is described quantitatively by a dose reduction factor, which is the ratio of the dose inside a structure to the corresponding dose with no structure present. The internal dose from inhaled radionuclides is proportional to the radionuclide concentration in the air. Assuming that the outdoor airborne concentration is constant with time, the time-dependence of the indoor airborne concentration in terms of the structure air ventilation rate, the deposition velocities for radionuclides on the inside floor, walls, and ceiling, and the radioactive decay constant, were calculated

  2. Effects of building structures on radiation doses from routine releases of radionuclides to the atmosphere

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1978-01-01

    Realistic assessments of radiation doses to the population from routine releases of radionuclides to the atmosphere require consideration of man's largely indoor environment. The effect of a building structure on radiation doses is described quantitatively by a dose reduction factor, which is the ratio of the dose to a reference individual inside a structure to the corresponding dose with no structure present. We have implemented models to estimate dose reduction factors for internal dose from inhaled radionuclides and for external photon dose from airborne and surface-deposited radionuclides. The models are particularly useful in radiological assessment applications, since dose reduction factors may readily be estimated for arbitrary mixtures and concentrations of radionuclides in the atmosphere and on the ground. The model for inhalation dose reduction factors accounts for radioactive decay, air ventilation into and out of the structure, and deposition of radionuclides on inside surfaces of the structure. External dose reduction factors are estimated using the point-kernel integration method including consideration of buildup in air and the walls of the building. The potential importance of deposition of radionuclides on inside surfaces of a structure on both inhalation and external dose reduction factors has been demonstrated. Model formulation and the assumptions used in the calculations are discussed. Results of model-parameter sensitivity studies and estimates of dose reduction factors for radionuclides occurring in routine releases from an LWR fuel reprocessing plant are presented. (author)

  3. Evaluation of the dose assessment models for routine radioactive releases to the environment

    International Nuclear Information System (INIS)

    Rossi, J.

    1998-05-01

    The aim of the work was to evaluate the needs of development concerning the dose calculation models for routine releases and application of the models for exceptional release situations at the NPP plants operated by Imatran Voima Ltd. and Teollisuuden Voima Ltd. in Finland. First, the differences of the calculation models concerning input data, models themselves and output are considered. Subsequently some single features like importance of nuclides in exposure pathways due to change of the release composition, dose calculation for children and importance of time period of particle releases are considered. The existing dose calculation model used by the radiation safety authorities is aimed at a tool for checking the results from calculations of doses arising from routine releases by the power companies. Characteristics of an independent, foreign model and its suitability for safety authorities for dose calculations of releases in normal operation is also assessed. The needs of improvements in the existing calculation models and characteristics of a comprehensive model for safety authorities are discussed as well

  4. Nuclear decay data for radionuclides occurring in routine releases from nuclear fuel cycle facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kocher, D.C.

    1977-08-01

    This report gives tabulations of the atomic and nuclear radiations emitted by 240 radionuclides. Most of the radionuclides are those expected to occur in routine releases of effluents from nuclear fuel cycle facilities. For each radionuclide are given the half-life and recommended values for the energies, intensities, and equilibrium absorbed-dose constants for each of the atomic and nuclear radiations. Also given are the daughter radionuclides produced and recommended values for decay branching ratios, where applicable. The radioactivity decay chains and branching ratios are displayed in diagram form.

  5. Nuclear decay data for radionuclides occurring in routine releases from nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1977-08-01

    This report gives tabulations of the atomic and nuclear radiations emitted by 240 radionuclides. Most of the radionuclides are those expected to occur in routine releases of effluents from nuclear fuel cycle facilities. For each radionuclide are given the half-life and recommended values for the energies, intensities, and equilibrium absorbed-dose constants for each of the atomic and nuclear radiations. Also given are the daughter radionuclides produced and recommended values for decay branching ratios, where applicable. The radioactivity decay chains and branching ratios are displayed in diagram form

  6. Dose-rate conversion factors for external exposure to photon and electron radiation from radionuclides occurring in routine releases from nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1980-01-01

    Dose-rate conversion factors for external exposure to photon and electron radiation are calculated for 240 radionuclides of potential importance in routine releases from nuclear fuel cycle facilities. Exposure modes considered are immersion in contaminated air, immersion in contaminated water, and irradiation from a contaminated ground surface. For each exposure mode, dose-rate conversion factors for photons and electrons are calculated for tissue-equivalent material at the body surface of an exposed individual. Dose-rate conversion factors for photons only are calculated for 22 body organs. (author)

  7. EMERALD-NORMAL, Routine Radiation Release and Dose for PWR Design Analysis and Operation Analysis

    International Nuclear Information System (INIS)

    Gillespie, S.G.; Brunot, W.K.

    1976-01-01

    1 - Description of problem or function: EMERALD-NORMAL is designed for the calculation of radiation releases and exposures resulting from normal operation of a large pressurized water reactor. The approach used is similar to an analog simulation of a real system. Each component or volume in the plant which contains a radioactive material is represented by a subroutine which keeps track of the production, transfer, decay, and absorption of radioactivity in that volume. During the course of the analysis, activity is transferred from subroutine to subroutine in the program as it would be transferred from place to place in the plant. Some of this activity is then released to the atmosphere and to the discharge canal. The rates of transfer, leakage, production, cleanup, decay, and release are read as input to the program. Subroutines are also included which calculate the off-site radiation exposures at various distances for individual isotopes and sums of isotopes. The program contains a library of physical data for the forty isotopes of most interest in licensing calculations, and other isotopes can be added or substituted. Because of the flexible nature of the simulation approach, the EMERALD-NORMAL program can be used for most calculations involving the production and release of radioactive material. These include design, operation, and licensing studies. 2 - Method of solution: Explicit solutions of first-order linear differential equations are included. In addition, a subroutine is provided which solves a set of simultaneous linear algebraic equations. 3 - Restrictions on the complexity of the problem: Many parameters and systems included in the program, particularly the radiation waste-treatment system, are unique to the PG and E Diablo Canyon PWR plant. Maxima of: 50 isotopes, 9 distances, 16 angular sectors, 1 operating period, 1 reactor power level

  8. User's Manual: Routines for Radiative Heat Transfer and Thermometry

    Science.gov (United States)

    Risch, Timothy K.

    2016-01-01

    Determining the intensity and spectral distribution of radiation emanating from a heated surface has applications in many areas of science and engineering. Areas of research in which the quantification of spectral radiation is used routinely include thermal radiation heat transfer, infrared signature analysis, and radiation thermometry. In the analysis of radiation, it is helpful to be able to predict the radiative intensity and the spectral distribution of the emitted energy. Presented in this report is a set of routines written in Microsoft Visual Basic for Applications (VBA) (Microsoft Corporation, Redmond, Washington) and incorporating functions specific to Microsoft Excel (Microsoft Corporation, Redmond, Washington) that are useful for predicting the radiative behavior of heated surfaces. These routines include functions for calculating quantities of primary importance to engineers and scientists. In addition, the routines also provide the capability to use such information to determine surface temperatures from spectral intensities and for calculating the sensitivity of the surface temperature measurements to unknowns in the input parameters.

  9. ESTE AI (Annual Impacts) - the program for calculation of radiation doses caused by effluents in routine releases to the atmosphere and to the hydrosphere

    International Nuclear Information System (INIS)

    Carny, P.; Suchon, D.; Smejkalova, E.; Fabova, V.

    2009-01-01

    ESTE AI is a program for calculation of radiation doses caused by effluents in routine releases to the atmosphere and to the hydrosphere. Doses to the members of critical groups of inhabitants in the vicinity of NPP are calculated and as a result, critical group is determined. The program enables to calculate collective doses as well. Collective doses to the inhabitants living in the vicinity of the NPP are calculated. ESTE AI calculates doses to the whole population of Slovakia from the effluents of the specific plant. In this calculation, global nuclides are included and assumed, as well. The program enables to calculate and to document beyond-border radiological impacts of effluents caused by routine operation of NPP. ESTE AI was approved by the 'Public Health Authority of the Slovak Republic' and is used as legal instrument by Slovenske elektrarne a.s., NPP Bohunice. (authors)

  10. ESTE AI (Annual Impacts) - the program for calculation of radiation doses caused by effluents in routine releases to the atmosphere and to the hydrosphere

    International Nuclear Information System (INIS)

    Carny, P.; Suchon, D.; Smejkalova, E.; Fabova, V.

    2008-01-01

    ESTE AI is a program for calculation of radiation doses caused by effluents in routine releases to the atmosphere and to the hydrosphere. Doses to the members of critical groups of inhabitants in the vicinity of NPP are calculated and as a result, critical group is determined. The program enables to calculate collective doses as well. Collective doses to the inhabitants living in the vicinity of the NPP are calculated. ESTE AI calculates doses to the whole population of Slovakia from the effluents of the specific plant. In this calculation, global nuclides are included and assumed, as well. The program enables to calculate and to document beyond-border radiological impacts of effluents caused by routine operation of NPP. ESTE AI was approved by the 'Public Health Authority of the Slovak Republic' and is used as legal instrument by Slovenske elektrarne a.s., NPP Bohunice. (authors)

  11. Radiation dose monitoring in the clinical routine

    Energy Technology Data Exchange (ETDEWEB)

    Guberina, Nika [UK Essen (Germany). Radiology

    2017-04-15

    Here we describe the first clinical experiences regarding the use of an automated radiation dose management software to monitor the radiation dose of patients during routine examinations. Many software solutions for monitoring radiation dose have emerged in the last decade. The continuous progress in radiological techniques, new scan features, scanner generations and protocols are the primary challenge for radiation dose monitoring software systems. To simulate valid dose calculations, radiation dose monitoring systems have to follow current trends and stay constantly up-to-date. The dose management software is connected to all devices at our institute and conducts automatic data acquisition and radiation dose calculation. The system incorporates 18 virtual phantoms based on the Cristy phantom family, estimating doses in newborns to adults. Dose calculation relies on a Monte Carlo simulation engine. Our first practical experiences demonstrate that the software is capable of dose estimation in the clinical routine. Its implementation and use have some limitations that can be overcome. The software is promising and allows assessment of radiation doses, like organ and effective doses according to ICRP 60 and ICRP 103, patient radiation dose history and cumulative radiation doses. Furthermore, we are able to determine local diagnostic reference doses. The radiation dose monitoring software systems can facilitate networking between hospitals and radiological departments, thus refining radiation doses and implementing reference doses at substantially lower levels.

  12. Effects of indoor residence on radiation doses from routine releases of radionuclides to the atmosphere

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1980-01-01

    Dose reduction factors from indoor residence during routine releases of radionuclides to the atmosphere were studied using models that are suitable for application to arbitrary source terms. Dose reduction factors for internal exposure to inhaled radionuclides account for air ventilation and deposition on inside building surfaces. Estimated internal dose reduction factors are approx. 0.2 to 0.8 for particulates and 0.07 to 0.4 for radioiodine. Dose reduction factors for external photon exposure from airborne and surface-deposited sources are based on the point-kernel integration method. Values for source terms from a fuel reprocessing plant and a hypothetical reactor accident are within a factor of 2 of the value 0.5 adopted by the US Nuclear Regulatory Commission (NRC) for population dose assessments. For the release at Three Mile Island nuclear station, however, the external dose reduction factor may be an order of magnitude less than the value adopted by the NRC

  13. Development, validation and routine control of a radiation process

    International Nuclear Information System (INIS)

    Kishor Mehta

    2010-01-01

    Today, radiation is used in industrial processing for variety of applications; from low doses for blood irradiation to very high doses for materials modification and even higher for gemstone colour enhancement. At present, radiation is mainly provided by either radionuclides or machine sources; cobalt-60 is the most predominant radionuclide in use. Currently, there are several hundred irradiation facilities worldwide. Similar to other industries, quality management systems can assist radiation processing facilities in enhancing customer satisfaction and maintaining and improving product quality. To help fulfill quality management requirements, several national and international organizations have developed various standards related to radiation processing. They all have requirements and guidelines for development, validation and routine control of the radiation process. For radiation processing, these three phases involve the following activities. Development phase includes selecting the type of radiation source, irradiation facility and the dose required for the process. Validation phase includes conducting activities that give assurance that the process will be successful. Routine control then involves activities that provide evidence that the process has been successfully realized. These standards require documentary evidence that process validation and process control have been followed. Dosimetry information gathered during these processes provides this evidence. (authors)

  14. Development and Validation of a National System for Routine Monitoring of Mortality in People Recently Released from Prison.

    Directory of Open Access Journals (Sweden)

    Stuart A Kinner

    Full Text Available People released from prison are at increased risk of death. However, no country has established a system for routine monitoring of mortality in this population. The aims of this study were to (a evaluate a system for routine monitoring of deaths after release from prison in Australia and (b estimate the number of deaths annually within 28 and 365 days of prison release from 2000 to 2013.Persons released from prison and deaths were identified in records held by Centrelink, Australia's national provider of unemployment benefits. Estimates generated in this manner were compared with those from a study that probabilistically linked correctional records with the National Death Index (NDI, for each calendar year 2000 to 2007. Using Centrelink data, national estimates of mortality within 28 and 365 days of release were produced for each calendar year 2000 to 2013.Compared with estimates based on linkage with the NDI, the estimated crude mortality rate based on Centrelink records was on average 52% lower for deaths within 28 days of release and 24% lower for deaths within 365 days of release. Nationally, over the period 2000 to 2013, we identified an average of 32 deaths per year within 28 days of release and 188 deaths per year within 365 days of release. The crude mortality rate for deaths within both 28 and 365 days of release increased over this time.Using routinely collected unemployment benefits data we detected the majority of deaths in people recently released from prison in Australia. These data may be sufficient for routine monitoring purposes and it may be possible to adopt a similar approach in other countries. Routine surveillance of mortality in ex-prisoners serves to highlight their extreme vulnerability and provides a basis for evaluating policy reforms designed to reduce preventable deaths.

  15. A 'Puff' dispersion model for routine and accidental releases

    International Nuclear Information System (INIS)

    Grsic, Z.; Rajkovic, B.; Milutinovic, P.

    1999-01-01

    A Puff dispersion model for accidental or routine releases is presented. This model was used as a constitutive part of an automatic meteorological station.All measured quantities are continuously displayed on PC monitor in a digital and graphical form, they are averaging every 10 minutes and sending to the civil information center of Belgrade. In the paper simulation of a pollutant plume dispersion from The oil refinery 'Pancevo', on April 18 th 1999 is presented. (author)

  16. Dose estimation and prediction of radiation effects on aquatic biota resulting from radioactive releases from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Blaylock, B.G.; Witherspoon, J.P.

    1975-01-01

    Aquatic organisms are exposed to radionuclides released to the environment during various steps of the nuclear fuel cycle. Routine releases from these processes are limited in compliance with technical specifications and requirements of federal regulations. These regulations reflect I.C.R.P. recommendations which are designed to provide an environment considered safe for man. It is generally accepted that aquatic organisms will not receive damaging external radiation doses in such environments; however, because of possible bioaccumulation of radionuclides there is concern that aquatic organisms might be adversely affected by internal doses. The objectives of this paper are: to estimate the radiation dose received by aquatic biota from the different processes and determine the major dose-contributing radionuclides, and to assess the impact of estimated doses on aquatic biota. Dose estimates are made by using radionuclide concentration measured in the liquid effluents of representative facilities. This evaluation indicates the potential for the greatest radiation dose to aquatic biota from the nuclear fuel supply facilities (i.e., uranium mining and milling). The effects of chronic low-level radiation on aquatic organisms are discussed from somatic and genetic viewpoints. Based on the body of radiobiological evidence accumulated up to the present time, no significant deleterious effects are predicted for populations of aquatic organisms exposed to the estimated dose rates resulting from routine releases from conversion, enrichment, fabrication, reactors and reprocessing facilities. At the doses estimated for milling and mining operations it would be difficult to detect radiation effects on aquatic populations; however, the significance of such radiation exposures to aquatic populations cannot be fully evaluated without further research on effects of chronic low-level radiation. (U.S.)

  17. Alanine/ESR dosimetry system for routine use in radiation processing

    International Nuclear Information System (INIS)

    Kojima, T.; Haruyama, Y.; Tachibana, H.; Tanaka, R.; Okamoto, J.; Hara, H.; Kashiwazaki, S.

    1993-01-01

    A new alanine-polystyrene(PS) dosimeter prepared with simplified molding procedure and an automatic desk-top dose-reader of alanine dosimeter were developed for the purpose of routine use. Combination of these two allows us to apply a reliable alanine/ESR dosimetry system to routine dosimetric process control in industrial gamma radiation processing. (Author)

  18. MAXDOSE-SR: A routine release atmospheric dose model used at SRS

    International Nuclear Information System (INIS)

    Simpkins, A.A.

    2000-01-01

    MAXDOSE-SR is a PC version of the dosimetry code MAXIGASP, which was used to calculate doses to the maximally exposed offsite individual for routine atmospheric releases of radioactive material at the Savannah River Site (SRS). Complete code description, verification of models, and user's manual have been included in this report. Minimal input is required to run the program, and site specific parameters are used when possible

  19. Routine medicare and radiation exposure. Introductory remarks

    International Nuclear Information System (INIS)

    Hirata, Hideki; Saito, Tsutomu

    2013-01-01

    As an introduction of the title series, outlines of radiation in physics, chemistry, biochemistry, biological effect and protection are explained from the clinical doctors' aspect of routine medicare, and of radiation exposure in which people's interest is raised after the Fukushima Nuclear Power Plant Accident in 2011. For physics, ionizing effects of radiation are described in relation to its quantum energy transfer and its medical utilization like imaging and radiotherapy. Then mentioned in brief is the radiation from elements consisting of human body, cosmic ray and background radiation from the earth, with reference to natural and standardized limits of exposure doses. Radiations from 226 Rn and 40 K are explained as an instance of environmental natural sources together with the concepts of radioactive decay series/scheme, of internal exposure, of hazard like double strand break (DSB) and of medical use such as boron neutron capture therapy (BNCT). For an artifact radiation source, shown are fission products of 235 U by neutron, first yielded in 1945. Evidence of evolution in biochemical repair mechanisms of DSB is explained with a comparison of irradiated drosophila mutation where linear non-threshold (LNT) hypothesis is proposed, and human non-homologous end joining and homologous recombination. Historical process of occupational, medical, public exposures and their protection is finally described from the discovery of X-ray in 1895 to the first ICRP publication in 1958 via the A-bomb explosion in 1945. (T.T.)

  20. Properties of electret ionization chambers for routine dosimetry in photon radiation fields

    International Nuclear Information System (INIS)

    Doerschel, B.; Pretzsch, G.

    1985-01-01

    The main properties of photon routine dosemeters are their energy and angular dependence as well as their measuring range and accuracy. The determination of radiation exposure from dosemeter response is based on the choice of an appropriate conversion factor taking into account the influence of body backscattering on the dosemeter response. Measuring range and accuracy of an electret ionization chamber first of all depend on electret stability, methods of charge measurement, and geometry of the chamber. The dosemeter performance is described for an electret ionization chamber which was designed for application to routine monitoring of radiation workers. (author)

  1. Release of the radioactive patient following radiation therapy

    International Nuclear Information System (INIS)

    Powers, J.; Cancer Board, A.

    2004-01-01

    Patients walk out of medical facilities containing as much as a complete therapeutic dose of radiation on a daily basis. This presents a significant challenge to the radiation protection community, as most patients have no prior education related to radiation and may not have the aptitude to assimilate such knowledge. In the case of targeted radiation therapy in which radionuclides are used to selectively target the cancer, patients are typically released only after adequate elimination and decay of the radionuclide administered. Established modalities of targeted radiotherapy include the use of iodine for thyroid cancer, strontium for bone pain, phosphorous for haematological diseases, 131I-mIBG for neuroblastoma, and most recently Y-90 labelled monoclonal antibodies for lymphoma. In the case of permanent implants, implants of encapsulated radioactive sources are left permanently in the tissues, thus patients are released containing their complete therapeutic dose. Isotopes used in permanent implants include I-125, Pd-103 and Au-198. Radiation safety considerations for both cases, the release of a patient who has received targeted radiotherapy, and the release of a patient who has received a permanent implant, will be discussed. A summary of applicable regulations will serve as a starting point for each of the following considerations; i) Security and source control ii) Instructions to patient and family members iii) Risk to the public As the incidence of cancer increases, and the popularity of targeted radiotherapy and permanent seed implants grows, the event of having an untrained person in possession of a therapeutic dose of radiation becomes more and more common. It is essential to stop and examine the risk of this practice, whether current strategies to reduce the risk to an acceptable level are indeed effective, and whether control over these sources is even feasible. (Author)

  2. Release of the radioactive patient following radiation therapy

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J.; Cancer Board, A.

    2004-07-01

    Patients walk out of medical facilities containing as much as a complete therapeutic dose of radiation on a daily basis. This presents a significant challenge to the radiation protection community, as most patients have no prior education related to radiation and may not have the aptitude to assimilate such knowledge. In the case of targeted radiation therapy in which radionuclides are used to selectively target the cancer, patients are typically released only after adequate elimination and decay of the radionuclide administered. Established modalities of targeted radiotherapy include the use of iodine for thyroid cancer, strontium for bone pain, phosphorous for haematological diseases, 131I-mIBG for neuroblastoma, and most recently Y-90 labelled monoclonal antibodies for lymphoma. In the case of permanent implants, implants of encapsulated radioactive sources are left permanently in the tissues, thus patients are released containing their complete therapeutic dose. Isotopes used in permanent implants include I-125, Pd-103 and Au-198. Radiation safety considerations for both cases, the release of a patient who has received targeted radiotherapy, and the release of a patient who has received a permanent implant, will be discussed. A summary of applicable regulations will serve as a starting point for each of the following considerations; i) Security and source control ii) Instructions to patient and family members iii) Risk to the public As the incidence of cancer increases, and the popularity of targeted radiotherapy and permanent seed implants grows, the event of having an untrained person in possession of a therapeutic dose of radiation becomes more and more common. It is essential to stop and examine the risk of this practice, whether current strategies to reduce the risk to an acceptable level are indeed effective, and whether control over these sources is even feasible. (Author)

  3. Performance of Models in Radiological Impact Assessment for Normal Operation. Report of Working Group 1 Reference Methodologies for Controlling Discharges of Routine Releases of EMRAS II Topical Heading Reference Approaches for Human Dose Assessment. Environmental Modelling for Radiation Safety (EMRAS II) Programme

    International Nuclear Information System (INIS)

    2017-01-01

    This publication provides the results from Working Group 1, on Reference Methodologies for Controlling Discharges of Routine Releases, of the IAEA’s EMRAS II (Environmental Modelling for Radiation Safety) programme, which ran from 2009 to 2011. This Working Group carried out an intercomparison of methods used for assessing radiological impacts to people and the environment due to authorized releases of radionuclides during normal operation of nuclear facilities. Three important types of exposure scenarios were considered, those related to atmospheric, marine and river releases. The publication describes the details of the hypothetical radioactive release scenarios, the environmental pathways considered, the environmental transfer models applied, the calculation methods and the results obtained. An analysis of the results and the main findings and conclusions relevant for the use of the described input data and methodologies in regulatory applications is included. The publication also presents considerations on selection of the ‘representative person’ and a summary of the different approaches in some States for the regulatory control of radioactive discharges. Input data is included in the annex.

  4. ESTIMATION OF ROUTINE DISCHARGE OF RADIONUCLIDES ON POWER REACTOR EXPERIMENTAL RDE

    Directory of Open Access Journals (Sweden)

    P.M. Udiyani

    2017-02-01

    Full Text Available Experimental power reactor (RDE which is planned to be constructed by BATAN is a kind of High Temperature Gas Cooled Reactor (HTGR with 10 MWth power. HTGR is a helium gas-cooled reactor with TRISO-coated fuel that is able to confine fission products remained in the core. Although the fission products released into the environment are very small, in order to comply the regulations the study about environmental radiation on normal or routine operation condition need to be performed. Estimation of radiology in the environment involves the source term released into the environment under routine operation condition. The purpose of this study is to estimate the source term released into the environment based on postulation of normal or routine operations of RDE. The research approach starts with an assumption that there are defects and impurities in the TRISO fuel because of limitation during the fabrication. Mechanism of fission products release from the fuel to the environment was created based on the safety features design of RDE. Radionuclides inventories in the reactor were calculated using ORIGEN-2 whose library has been modified for HTGR type, and the assumptions of defects of the TRISO fuel and release fraction for each compartment of RDE safety system used a reference parameter. The results showed that the important source terms of RDE are group of noble gases (Kr and Xe, halogen (I, Sr, Cs, H-3, and Ag. Activities of RDE source terms for routine operations have no significant difference with the HTGR source terms with the same power. Keywords: routine discharge, radionuclide, source term, RDE, HTGR

  5. Guidelines for the Calibration of Routine Dosimetry Systems for use in Radiation Processing

    DEFF Research Database (Denmark)

    Sharpe, Peter; Miller, Arne

    A set of guidelines has been developed to assist in the calibration of routine dosimetry systems for use in industrial radiation processing plants. Topics covered include the calibration of equipment, the performance of calibration irradiations and the derivation of mathematical functions...

  6. Development and calibration of a routine dosimetry system for radiation processing

    International Nuclear Information System (INIS)

    Ferreira, Danilo Cardenuto

    2013-01-01

    The development and calibration of a routine dosimetry system based on commercial, low cost photodiode (SFH 206) are presented in this work. The dosimeter probe was designed to operate unbiased in the direct current mode. The radiations were performed with Cobalt-60 Panoramic Irradiator facility in the dose-rate range of 8.1 Gy/h - 125 Gy/h. The photocurrents generated in the device, in each dose-rate, were registered with a digital electrometer and stored during the exposure time. The current response of the diode was measured as a function of the time in steps from 1 Gy up to 200 Gy with accumulated dose up to 15 kGy. In this range, the dose-response of the diode, given by the charge as function of dose, was linear with correlation coefficient better than 0.998. These results were compared with those obtained using Gafchromic film dosimetry often used in routine. To monitor possible gamma radiation effects produced on the diode, the current and charge sensitivities were measured as a function of the absorbed dose. For doses up to 15 kGy, it was not observed any radiation damage what confirms the reproducibility of the diode response better than 3 %. Finally, due to the small experimental errors ( 5% ) and good spatial resolution of the diode it was possible to measure the transit dose due to the movement of the Cobalt-60 radioactive source as well the dose rate mapping in the Panoramic Irradiator. (author)

  7. Controlled release of biofunctional substances by radiation-induced polymerization

    International Nuclear Information System (INIS)

    Yoshida, M.; Kumakura, M.; Kaetsu, I.

    1978-01-01

    The release behaviour of a drug from flat circular capsules obtained by radiation-induced polymerization at low temperatures and with different hydrophilic properties has been studied. The effect of various factors on release property was investigated. The release process could be divided into three parts, an initial quick release stage, stationary state release stage and a retarded release stage. Release behaviour in the stationary state was examined using Noyes-Whitney and Higuchi equations. It was shown that the hydrophilic property of polymer matrix expressed by water content was the most important effect on diffusion and release rate. Rigidity of the polymer may also affect diffusivity. The first quick release step could be attributed to rapid dissolution of drug in the matrix surface due to polymer swelling. (author)

  8. Radiation Dose Measurements in Routine X Ray Examinations

    International Nuclear Information System (INIS)

    Osman, H.; Sulieman, A.; Suliman, I.I.; Sam, A.K.

    2011-01-01

    The aim of current study was to evaluate patients radiation dose in routine X-ray examinations in Omdurman teaching hospital Sudan.110 patients was examined (134) radiographs in two X-ray rooms. Entrance surface doses (ESDs) were calculated from patient exposure parameters using DosCal software. The mean ESD for the chest, AP abdomen, AP pelvis, thoracic spine AP, lateral lumber spine, anteroposterior lumber spine, lower limb and for the upper limb were; 231±44 Gy,453± 29 Gy, 567±22 Gy, 311±33 Gy,716±39 Gy, 611±55 Gy,311±23 Gy, and 158±57 Gy, respectively. Data shows asymmetry in distribution. The results of were comparable with previous study in Sudan.

  9. Commercial power silicon devices as possible routine dosimeters for radiation processing

    International Nuclear Information System (INIS)

    Fuochi, P.G.; Lavalle, M.; Gombia, E.; Mosca, R.; Kovacs, A.V.; Hargittai, P.; Vitanza, A.; Patti, A.

    2001-01-01

    The use of silicon devices as possible radiation dosimeters has been investigated in this study. A bipolar power transistor in TO126 plastic packaging has been selected. Irradiations, with doses in the range from 50 Gy up to 5 kGy, have been performed at room temperature using different radiation sources ( 60 Co g source, 2.5, 4 and 12 MeV electron accelerators). Few irradiations with g rays were also done at different temperatures. A physical parameter, T, related to the charge carrier lifetime, has been found to change as a function of irradiation dose. This change is radiation energy dependent. Long term stability of the electron irradiated transistors has been checked by means of a reliability test ('high temperature reverse bias', HTRB) at 150 deg. C for 1000 h. Deep level transient spectroscopy (DLTS) measurements have been performed on the irradiated devices to identify the recombination centres introduced by the radiation treatment. The results obtained confirm that these transistors could be used as routine radiation dosimeters in a certain dose range. More work needs to be done particularly with g rays in the low dose region (50-200 Gy) and with low energy electrons. (author)

  10. Assessment of radiological consequences of routine releases in a site with various nuclear facilities

    International Nuclear Information System (INIS)

    Lucinio, Elena Albeira Guirado

    2003-01-01

    This work evaluates the radiological consequences of a nuclear site with a complex of fuel enrichment, conversion, reconversion facilities and a nuclear reactor. A methodology recommended by the Commission of the European Communities (CEC) is used and implemented in the PC-CREAM computer code. This code is composed of six linked modules, which describe the transfer of radionuclides to the environment, the pathways on which people may be exposed to radiation, and the radiological consequences. Radiation doses to a selected population are evaluated taking into account atmospheric and aquatic releases. (author)

  11. Atmospheric dispersion models of radioactivity releases

    International Nuclear Information System (INIS)

    Oza, R.B.

    2016-01-01

    In view of the rapid industrialization in recent time, atmospheric dispersion models have become indispensible 'tools' to ensure that the effects of releases are well within the acceptable limits set by the regulatory authority. In the case of radioactive releases from the nuclear facility, though negligible in quantity and many a times not even measurable, it is required to demonstrate the compliance of these releases to the regulatory limits set by the regulatory authority by carrying out radiological impact assessment. During routine operations of nuclear facility, the releases are so low that environmental impact is usually assessed with the help of atmospheric dispersion models as it is difficult to distinguish negligible contribution of nuclear facility to relatively high natural background radiation. The accidental releases from nuclear facility, though with negligible probability of occurrence, cannot be ruled out. In such cases, the atmospheric dispersion models are of great help to emergency planners for deciding the intervention actions to minimize the consequences in public domain and also to workout strategies for the management of situation. In case of accidental conditions, the atmospheric dispersion models are also utilized for the estimation of probable quantities of radionuclides which might have got released to the atmosphere. Thus, atmospheric dispersion models are an essential tool for nuclear facility during routine operation as well as in the case of accidental conditions

  12. Radiation monitoring handbook for visits by nuclear powered warships to Australian ports

    International Nuclear Information System (INIS)

    Woods, D.A.

    1995-09-01

    The purpose of this handbook is to detail the Radiation Monitoring (RMG) roles and procedures, and to provide technical and background information useful to RMG personnel. It has been written on the assumption that all members of the RMG have had appropriate radiation safety (Health Physics) training. Separate standing procedures, for both routine and emergency activities, are required for each port. These are incorporated in Port Safety Plans and specify the routine monitoring requirements for individual berths or anchorages and the procedures to be followed after indication of a reactor accident to a nuclear powered warship. A Visit Operation Order, issued for each Nuclear Powered warships (NPW) visit, presents information specific to that visit. Routine monitoring is performed to confirm normal conditions. The objectives of emergency radiation monitoring are: to provide early detection of a reactor accident of sufficient severity to possibly cause a major release of fission products to the environment; to determine the nature and extent of any fission product release; to provide information to assist in evaluating the accident; to assess the need and extent of required countermeasures; and to determine when the release has terminated and when affected areas have returned to normal

  13. Influence of radiation defects on tritium release parameters from Li2O

    International Nuclear Information System (INIS)

    Grishmanov, V.; Tanaka, S.; Yoneoka, T.

    1998-01-01

    The study of the influence of radiation defects on tritium release behavior from polycrystalline Li 2 O was performed by simultaneous measurements of the luminescence emission and tritium release. It was found that the radiation defects in Li 2 O introduced by electron irradiation cause the retention of tritium. It is thought that the tritium recovery is affected by the formation of a Li-T bond, which is tolerant of high temperatures. The retardation of tritium decreases with increasing absorbed dose in the dose range from 50 to 140 MGy. The aggregation of radiation defects at high irradiation doses is considered to be responsible for the decrease of the interaction of tritium with radiation defects. The mechanism of the interaction of radiation defects with tritium is discussed. (orig.)

  14. RADCHARM++: A C++ routine to compute the electromagnetic radiation generated by relativistic charged particles in crystals and complex structures

    Energy Technology Data Exchange (ETDEWEB)

    Bandiera, Laura; Bagli, Enrico; Guidi, Vincenzo [INFN Sezione di Ferrara and Dipartimento di Fisica e Scienze della Terra, Università degli Studi di Ferrara, Via Saragat 1, 44121 Ferrara (Italy); Tikhomirov, Victor V. [Research Institute for Nuclear Problems, Belarusian State University, Minsk (Belarus)

    2015-07-15

    The analytical theories of coherent bremsstrahlung and channeling radiation well describe the process of radiation generation in crystals under some special cases. However, the treatment of complex situations requires the usage of a more general approach. In this report we present a C++ routine, named RADCHARM++, to compute the electromagnetic radiation emitted by electrons and positrons in crystals and complex structures. In the RADCHARM++ routine, the model for the computation of e.m. radiation generation is based on the direct integration of the quasiclassical formula of Baier and Katkov. This approach allows one taking into account real trajectories, and thereby the contribution of incoherent scattering. Such contribution can be very important in many cases, for instance for electron channeling. The generality of the Baier–Katkov operator method permits one to simulate the electromagnetic radiation emitted by electrons/positrons in very different cases, e.g., in straight, bent and periodically bent crystals, and for different beam energy ranges, from sub-GeV to TeV and above. The RADCHARM++ routine has been implemented in the Monte Carlo code DYNECHARM++, which solves the classical equation of motion of charged particles traveling through a crystal under the continuum potential approximation. The code has proved to reproduce the results of experiments performed at the MAinzer MIkrotron (MAMI) with 855 MeV electrons and has been used to predict the radiation spectrum generated by the same electron beam in a bent crystal.

  15. Radiation-induced increase in the release of amino acids by isolated, perfused skeletal muscle

    International Nuclear Information System (INIS)

    Schwenen, M.

    1989-01-01

    Local exposure of the hindquarter of the rat to 15Gy of gamma-radiation resulted, 4-6h after irradiation, in increased release of amino acids by the isolated, perfused hindquarter preparation, 70% of which is skeletal muscle. This increase in release involves not only alanine and glutamine, but also those amino acids not metabolized by muscle and, therefore, released in proportion to their occurrence in muscle proteins. Because metabolic parameters and content of energy-rich phosphate compounds in muscle remain unchanged, it is unlikely that general cellular damage is the underlying cause of the radiation-induced increase in amino acid release. The findings strongly favour the hypothesis that increased availability of amino acids results from enhanced protein break-down in skeletal muscle which has its onset shortly after irradiation. This radiation-induced disturbance in protein metabolism might be one of the pathogenetic factors in the aetiology of radiation myopathy. (author)

  16. Radiation curing of intelligent coating for controlled release and permeation

    International Nuclear Information System (INIS)

    Nakayama, Hiroshi; Kaetsu, Isao; Uchida, Kumao; Sakata, Shoei; Tougou, Kazuhide; Hara, Takamichi; Matsubara, Yoshio

    2002-01-01

    Intelligent membranes for pH and temperature-responsive drug releases were developed by coating and curing of polymer-drug composite film with electrolyte or N-isopropyl acrylamide curable mixture. It was proved that those intelligent membranes showed the stimule-sensitive and responsive release functions and could be produced efficiently by radiation curing processing with a conveyer system

  17. MODARIA WG5: Towards a practical guidance for including uncertainties in the results of dose assessment of routine releases

    Energy Technology Data Exchange (ETDEWEB)

    Mora, Juan C. [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas - CIEMAT (Spain); Telleria, Diego [International Atomic Energy Agency - IAEA (Austria); Al Neaimi, Ahmed [Emirates Nuclear Energy Corporation - ENEC (United Arab Emirates); Blixt Buhr, Anna Ma [Vattenfall AB (Sweden); Bonchuk, Iurii [Radiation Protection Institute - RPI (Ukraine); Chouhan, Sohan [Atomic Energy of Canada Limited - AECL (Canada); Chyly, Pavol [SE-VYZ (Slovakia); Curti, Adriana R. [Autoridad Regulatoria Nuclear - ARN (Argentina); Da Costa, Dejanira [Instituto de Radioprotecao e Dosimetria - IRD (Brazil); Duran, Juraj [VUJE Inc (Slovakia); Galeriu, Dan [Horia Hulubei National Institute of Physics and Nuclear Engineering - IFIN-HH (Romania); Haegg, Ann- Christin; Lager, Charlotte [Swedish Radiation Safety Authority - SSM (Sweden); Heling, Rudie [Nuclear Research and Consultancy Group - NRG (Netherlands); Ivanis, Goran; Shen, Jige [Ecometrix Incorporated (Canada); Iosjpe, Mikhail [Norwegian Radiation Protection Authority - NRPA (Norway); Krajewski, Pawel M. [Central Laboratory for Radiological Protection - CLOR (Poland); Marang, Laura; Vermorel, Fabien [Electricite de France - EdF (France); Mourlon, Christophe [Institut de Radioprotection et de Surete Nucleaire - IRSN (France); Perez, Fabricio F. [Belgian Nuclear Research Centre - SCK (Belgium); Woodruffe, Andrew [Federal Authority for Nuclear Regulation - FANR (United Arab Emirates); Zorko, Benjamin [Jozef Stefan Institute (Slovenia)

    2014-07-01

    MODARIA (Modelling and Data for Radiological Impact Assessments) project was launched in 2012 with the aim of improving the capabilities in radiation dose assessment by means of acquisition of improved data for model testing, model testing and comparison, reaching consensus on modelling philosophies, approaches and parameter values, development of improved methods and exchange of information. The project focuses on areas where uncertainties remain in the predictive capability of environmental models, emphasizing in reducing associated uncertainties or developing new approaches to strengthen the evaluation of the radiological impact. Within MODARIA, four main areas were defined, one of them devoted to Uncertainty and Variability. In this area four working groups were included, Working Group 5 dealing with the 'uncertainty and variability analysis for assessments of radiological impacts arising from routine discharges of radionuclides'. Whether doses are estimated by using measurement data, by applying models, or through a combination of measurements and calculations, the variability and uncertainty contribute to a distribution of possible values. The degree of variability and uncertainty is represented by the shape and extent of that distribution. The main objective of WG5 is to explore how to consider uncertainties and variabilities in the results of assessment of doses in planned situations for controlling the impact of routine releases from radioactive and nuclear installations to the environment. The final aim is to produce guidance for the calculation of uncertainties in these exposure situations and for the presentation of such results to the different stakeholders. To achieve that objective the main tasks identified were: to find tools and methods for uncertainty and variability analysis applicable to dose assessments in routine radioactive discharges, to define scenarios where information on uncertainty and variability of parameters is available

  18. Radiation monitoring handbook for visits by nuclear powered warships to Australian ports

    Energy Technology Data Exchange (ETDEWEB)

    Woods, D.A

    1995-09-01

    The purpose of this handbook is to detail the Radiation Monitoring (RMG) roles and procedures, and to provide technical and background information useful to RMG personnel. It has been written on the assumption that all members of the RMG have had appropriate radiation safety (Health Physics) training. Separate standing procedures, for both routine and emergency activities, are required for each port. These are incorporated in Port Safety Plans and specify the routine monitoring requirements for individual berths or anchorages and the procedures to be followed after indication of a reactor accident to a nuclear powered warship. A Visit Operation Order, issued for each Nuclear Powered warships (NPW) visit, presents information specific to that visit. Routine monitoring is performed to confirm normal conditions. The objectives of emergency radiation monitoring are: to provide early detection of a reactor accident of sufficient severity to possibly cause a major release of fission products to the environment; to determine the nature and extent of any fission product release; to provide information to assist in evaluating the accident; to assess the need and extent of required countermeasures; and to determine when the release has terminated and when affected areas have returned to normal Prepared on behalf of the Visiting Ship Panel (Nuclear), Department of Defence; 11 refs., 11 tabs., 21 figs.

  19. Comparison of the COMRADEX-IV and AIRDOS-EPA methodologies for estimating the radiation dose to man from radionuclide releases to the atmosphere

    International Nuclear Information System (INIS)

    Miller, C.W.; Hoffman, F.O.; Dunning, D.E. Jr.

    1981-01-01

    This report presents a comparison between two computerized methodologies for estimating the radiation dose to man from radionuclide releases to the atmosphere. The COMRADEX-IV code was designed to provide a means of assessing potential radiological consequences from postulated power reactor accidents. The AIRDOS-EPA code was developed primarily to assess routine radionuclide releases from nuclear facilities. Although a number of different calculations are performed by these codes, three calculations are in common - atmospheric dispersion, estimation of internal dose from inhalation, and estimation of external dose from immersion in air containing gamma emitting radionuclides. The models used in these calculations were examined and found, in general, to be the same. Most differences in the doses calculated by the two codes are due to differences in values chosen for input parameters and not due to model differences. A sample problem is presented for illustration

  20. Drug release control in delivery system for biodegradable polymer drugs by γ-radiation

    International Nuclear Information System (INIS)

    Yoshioka, Sumie; Azo, Yukio; Kojima, Shigeo

    1997-01-01

    Characterizations of the drug release from microsphere and hydrogel preparation made from biodegradable polymers were investigated aiming at development of a drug delivery system which allows an optimum drug delivery and the identification of the factors which control its delivery. Poly-lactic acid microspheres containing 10% of progesterone were produced from poly DL-lactic acid and exposed to γ-ray at 5-1000 kGy. And its glass transition temperature (Tg) was determined by differential scanning calorimetry. The temperature was gradually lowered with an increase in the dose of radiation. Tg of the microsphere exposed at 1000 kGy was lower by 10degC compared with the untreated one, showing that Tg control is possible without changing the size distribution of microsphere. Then, the amount of progesterone released from microsphere was determined. The release rate of the drug linearly increased with a square root of radiation time. These results indicate that the control of drug release rate is possible through controling the microsphere's Tg by γ-ray radiation. (M.N.)

  1. Controlled release of potassium chloride from radiation-polymerized copolymer matrices

    International Nuclear Information System (INIS)

    Yoshida, Masaru; Kumakura, Minoru; Kaetsu, Isao

    1979-01-01

    Release behavior of potassium chloride (KCl) from the flat circular copolymer composites, obtained by radiation-induced polymerization at low temperatures, was studied. The release rate agreed with the first-order kinetics based on the Noyes-Whitney equation in relation to the swelling of the composites. Release profiles of KCl from copolymer composites was affected by monomer composition between hydroxyethyl acrylate (HEA) and polyfunctional glass-forming monomers such as 2-hydroxyethyl methacrylate (HEMA), diethylene glycol dimethacrylate (DGDA), and trimethylolpropane trimethacrylate (TMPT) owing to change of swelling property of copolymers. The release rate decreased at HEA-poor composition in any system. In the case of hydrophobic comonomer system such as glycidyl methacrylate (GMA) and DGDA, release profile of KCl showed a minimum at 50% GMA-50% DGDA monomer composition. (author)

  2. Radiation Measurement And Risk Estimation For Pediatric Patients During Routine Diagnostic Examination

    International Nuclear Information System (INIS)

    Bushra, E.; Sulieman, A.; Osman, H.

    2011-01-01

    The aim of the present work was to evaluate Entrance Surface Dose (ESD) to the patient using Thermo luminescence dosimeters (TLD) during some common routine pediatrics X-ray examinations in main pediatrics hospitals in Sudan. ESD and Effective Dose (E) for pediatrics have been carried out for 250 patients undergoing five different examinations. The mean ESD ranged for neonates ranged between 0.17 mGy-0.30 mGy per radiograph with scattered thyroid dose 0.01 to 0.19 mGy. The risk of radiation induced cancer of was 0.13 x 10-6.

  3. Mechanisms of the induction of apoptosis mediated by radiation-induced cytokine release

    International Nuclear Information System (INIS)

    Babini, G.; Bellinzona, V.E.; Baiocco, G.; Ottolenghi, A.; Morini, J.; Mariotti, L.; Unger, K.

    2015-01-01

    The aim of the present work was to investigate the mechanisms of radiation-induced bystander signalling leading to apoptosis in non-irradiated co-cultured cells. Cultured non-transformed cells were irradiated, and the effect on the apoptosis rate on co-cultured non-irradiated malignant cells was determined. For this, two different levels of the investigation are presented, i.e. release of signalling proteins and transcriptomic profiling of the irradiated and non-irradiated co-cultured cells. Concerning the signalling proteins, in this study, the attention was focussed on the release of the active and latent forms of the transforming growth factor-β1 protein. Moreover, global gene expression profiles of non-transformed and transformed cells in untreated co-cultures were compared with those of 0.5-Gy-irradiated non-transformed cells co-cultured with the transformed cells. The results show an effect of radiation on the release of signalling proteins in the medium, although no significant differences in release rates were detectable when varying the doses in the range from 0.25 to 1 Gy. Moreover, gene expression results suggest an effect of radiation on both cell populations, pointing out specific signalling pathways that might be involved in the enhanced induction of apoptosis. (authors)

  4. Controlled release of biofunctional substances by radiation-induced polymerization

    International Nuclear Information System (INIS)

    Yoshida, M.; Kumakura, M.; Kaetsu, I.

    1978-01-01

    The controlled release of potassium chloride from flat circular matrices made by radiation-induced polymerization of a glass-forming monomer at low temperatures has been studied. The water-particle phase content formed in a poly(diethylene glycol dimethacrylate) matrix was controlled by the addition of polyethylene glycol 600. The dispersed water-particle phase content in the matrix was estimated directly and by scanning electron microscopic observations. The release of potassium chloride from the matrix increased linearly with the square root of time. The water content of the matrix had an important effect on the release rate which increases roughly in proportion to water content. This effect can be attributed to the apparent increase of the rate of drug diffusion. (author)

  5. An interferon-gamma release assay test performs well in routine screening for tuberculosis

    DEFF Research Database (Denmark)

    Vestergaard Danielsen, Allan; Fløe, Andreas; Lillebæk, Troels

    2014-01-01

    Introduction: A positive interferon-gamma release assay (IGRA) is regarded as proof of latent Mycobacterium tuberculosis infection. We conducted an evaluation of the IGRA test “T-SPOT.TB” to test its performance during clinical routine use by analysing the positivity rate and odds, effect of season...... and sensitivity. Material and methods: Data from T-SPOT.TB testing together with age and test indications (anti-tumour necrosis factor alpha (TNFα) candidate, contact investigation or suspicion of tuberculosis (TB)) were combined with mycobac­teria culture results. Results: A total of 1,809 patients were tested....... Conclusive results were achieved for 1,780 patients (98.4%). Among these, 4.6% of anti-TNFα candidates, 19.3% of contacts and 24.4% of TB suspects tested positive. Compared with anti-TNFα candidates, the odds for a positive result were significantly higher for contact investigations (odds ratio (OR), mean...

  6. SU-E-P-11: Comparison of Image Quality and Radiation Dose Between Different Scanner System in Routine Abdomen CT

    Energy Technology Data Exchange (ETDEWEB)

    Liao, S; Wang, Y; Weng, H [Chiayi Chang Gung Memorial Hospital of The C.G.M.F, Puzi City, Chiayi County, Taiwan (China)

    2015-06-15

    Purpose To evaluate image quality and radiation dose of routine abdomen computed tomography exam with the automatic current modulation technique (ATCM) performed in two different brand 64-slice CT scanners in our site. Materials and Methods A retrospective review of routine abdomen CT exam performed with two scanners; scanner A and scanner B in our site. To calculate standard deviation of the portal hepatic level with a region of interest of 12.5 mm x 12.5mm represented to the image noise. The radiation dose was obtained from CT DICOM image information. Using Computed tomography dose index volume (CTDIv) to represented CT radiation dose. The patient data in this study were with normal weight (about 65–75 Kg). Results The standard deviation of Scanner A was smaller than scanner B, the scanner A might with better image quality than scanner B. On the other hand, the radiation dose of scanner A was higher than scanner B(about higher 50–60%) with ATCM. Both of them, the radiation dose was under diagnostic reference level. Conclusion The ATCM systems in modern CT scanners can contribute a significant reduction in radiation dose to the patient. But the reduction by ATCM systems from different CT scanner manufacturers has slightly variation. Whatever CT scanner we use, it is necessary to find the acceptable threshold of image quality with the minimum possible radiation exposure to the patient in agreement with the ALARA principle.

  7. SU-E-P-11: Comparison of Image Quality and Radiation Dose Between Different Scanner System in Routine Abdomen CT

    International Nuclear Information System (INIS)

    Liao, S; Wang, Y; Weng, H

    2015-01-01

    Purpose To evaluate image quality and radiation dose of routine abdomen computed tomography exam with the automatic current modulation technique (ATCM) performed in two different brand 64-slice CT scanners in our site. Materials and Methods A retrospective review of routine abdomen CT exam performed with two scanners; scanner A and scanner B in our site. To calculate standard deviation of the portal hepatic level with a region of interest of 12.5 mm x 12.5mm represented to the image noise. The radiation dose was obtained from CT DICOM image information. Using Computed tomography dose index volume (CTDIv) to represented CT radiation dose. The patient data in this study were with normal weight (about 65–75 Kg). Results The standard deviation of Scanner A was smaller than scanner B, the scanner A might with better image quality than scanner B. On the other hand, the radiation dose of scanner A was higher than scanner B(about higher 50–60%) with ATCM. Both of them, the radiation dose was under diagnostic reference level. Conclusion The ATCM systems in modern CT scanners can contribute a significant reduction in radiation dose to the patient. But the reduction by ATCM systems from different CT scanner manufacturers has slightly variation. Whatever CT scanner we use, it is necessary to find the acceptable threshold of image quality with the minimum possible radiation exposure to the patient in agreement with the ALARA principle

  8. Origin of cell surface proteins released from Micrococcus radiodurans by ionizing radiation

    International Nuclear Information System (INIS)

    Mitchel, R.E.J.

    1975-01-01

    The exposure of Micrococcus radiodurans to sublethal doses of ionizing radiation causes the release of certain proteins into the surrounding medium. As estimated by sodium dodecyl sulfate-polyacrylamide gel electrophoresis, these proteins range from approximately 20,000 to 125,000 daltons. At least some of the proteins, including an exonuclease, have a surface location and appear to originate from the lipid-rich midwall layer. The exonuclease has two functionally distinct locations, one with its active site available to external substrate and a second with the active site masked from the exterior. Ionizing radiation releases both the masked and unmasked activity into the surrounding medium

  9. Effect of electromagnetic radiation on the release of tritium from a fusion reactor

    International Nuclear Information System (INIS)

    Causey, R.A.

    1982-01-01

    Electromagnetic radiation may play an important role in determining the amount of tritium that passes through the first wall of a fusion reactor. Photons enhance the outgassing of hydrogen from metal surfaces and therefore lower the surface concentration. The diffusion coefficient for hydrogen in metals is also increased by photon interactions. The importance of these processes on the tritium release depends on the actual conditions that will exist in the fusion reactor. Because electromagnetic radiation stimulates the release of tritium from traps, it could also affect the tritium inventory in the first wall. The effects of electromagnetic radiation on hydrogen in metals have been reviewed. Because electrons are produced by high energy photons, the effect of electrons on hydrogen has also been included

  10. Routine sanitary radiation monitoring

    International Nuclear Information System (INIS)

    Marej, A.N.

    1984-01-01

    Hygienic bases and organization principles of radiation monitoring realized in the process of operation of nuclear power engineering enterprises are considered. The monitoring is aimed at prevention from a negative effect of ionizing radiations on public heath. It is achieved by solution of the following tasks: realization of control over radioactive waste disposal into environment, control over the level of radioactive substance content in evironmental objects, control over external and internal irradiation of population assessment of environmental radiactivity of certain regions and of the territory of the country with the subsequent informing the corresponding organizations and population

  11. Radiation protection: A correction

    International Nuclear Information System (INIS)

    1972-01-01

    An error in translation inadvertently distorted the sense of a paragraph in the article entitled 'Ecological Aspects of Radiation Protection', by Dr. P. Recht, which appeared in the Bulletin, Volume 14, No. 2 earlier this year. In the English text the error appears on Page 28, second paragraph, which reads, as published: 'An instance familiar to radiation protection specialists, which has since come to be regarded as a classic illustration of this approach, is the accidental release at the Windscale nuclear centre in the north of England.' In the French original of this text no reference was made, or intended, to the accidental release which took place in 1957; the reference was to the study of the critical population group exposed to routine releases from the centre, as the footnote made clear. A more correct translation of the relevant sentence reads: 'A classic example of this approach, well-known to radiation protection specialists, is that of releases from the Windscale nuclear centre, in the north of England.' A second error appeared in the footnote already referred to. In all languages, the critical population group studied in respect of the Windscale releases is named as that of Cornwall; the reference should be, of course, to that part of the population of Wales who eat laver bread. (author)

  12. Tritium release kinetics of Li{sub 2}O with radiation defects

    Energy Technology Data Exchange (ETDEWEB)

    Grishmanov, V; Tanaka, Satoru [Tokyo Univ. (Japan). Faculty of Engineering

    1998-03-01

    The study of an influence of radiation defects on tritium release behavior from polycrystalline Li{sub 2}O was performed by the in-pile and out-of-pile tritium release experiments. The samples were pre-irradiated by accelerated electrons to various absorbed doses up to 140 MGy and then exposed to the fluence of 10{sup 17} thermal neutrons/m{sup 2}. The radiation defects introduced by electron irradiation in Li{sub 2}O cause the retention of tritium. The linear temperature increase of the electron-irradiated samples disclosed two tritium release peaks: first starts at {approx}600 K with the maximum at {approx}800 K and second appears at {approx}950 K with the maximum at {approx}1200 K. It is thought that the tritium release at high temperatures (> 950 K) is due to the thermal decomposition of LiT. In order to further investigated the formation of lithium hydrides, the diffuse-reflectance Fourier transform infrared (FTIR) absorption spectroscopy was applied. The Li{sub 2}O powder was irradiated by electron accelerator under D{sub 2} containing atmosphere (N{sub 2} + 10% D{sub 2}). An absorption band specific to the Li{sub 2}O was observed at 668 cm{sup -1} and attributed to the Li-D stretching vibration. (author)

  13. Quality control through dosimetry at a contract radiation processing facility

    International Nuclear Information System (INIS)

    Du Plessis, T.A.; Roediger, A.H.A.

    1985-01-01

    Reliable dosimetry procedures constitute a very important part of process control and quality assurance at a contract gamma radiation processing facility that caters for a large variety of different radiation applications. The choice, calibration and routine intercalibration of the dosimetry systems employed form the basis of a sound dosimetry policy in radiation processing. With the dosimetric procedures established, detailed dosimetric mapping of the irradiator upon commissioning (and whenever source modifications take place) is carried out to determine the radiation processing characteristics and peformance of the plant. Having established the irradiator parameters, routine dosimetry procedures, being part of the overall quality control measures, are employed. In addition to routine dosimetry, independent monitoring of routine dosimetry is performed on a bi-monthly basis and the results indicate a variation of better than 3%. On an annaul basis the dosimetry systems are intercalibrated through at least one primary standard dosimetry laboratory and to date a variation of better than 5% has been experienced. The company also participates in the Pilot Dose Assurance Service of the International Atomic Energy Agency, using the alanine/ESR dosimetry system. Routine calibration of the instrumentation employed is carried out on a regular basis. Detailed permanent records are compiled on all dosimetric and instrumentation calibrations, and the routine dosimetry employed at the plant. Certificates indicating the measured absorbed radiation doses are issued on request and in many cases are used for the dosimetric release of sterilized medical and pharmaceutical products. These procedures, used by Iso-Ster at its industrial gamma radiation facility, as well as the experience built up over a number of years using radiation dosimetry for process control and quality assurance are discussed. (author)

  14. Safety consequences of the release of radiation induced stored energy

    International Nuclear Information System (INIS)

    Prij, J.

    1994-08-01

    Due to the disposal of HLW in a salt formation gamma energy will be deposited in the rock salt. Most of this energy will be converted into heat, whilst a small part will create defects in the salt crystals. Energy is stored in the damaged crystals. Due to uncertainties in the models and differences in the disposal concepts the estimated values for the stored energy range from 10 to 1000 J/g in the most heavily damaged crystals close to the waste containers. The amount of radiation damage decays exponentially with increasing distance from the containers and at distances larger than 0.2 m the stored energy can be neglected. Given the uncertainties in the model predictions and in the possible release mechanism an instantaneous release of stored energy cannot be excluded completely. Therefore the thermo-mechanical consequences of a postulated instantaneous release of an extremely high amount of radiation induced stored energy have been estimated. These estimations are based on the quasi-static solutions for line and point sources. To account for the dynamic effects and the occurrence of fractures an amplification factor has been derived from mining experience with explosives. A validation of this amplification factor has been given using post experimental observations of two nuclear explosions in a salt formation. For some typical disposal concepts in rock salt the extent of the fractured zone has been estimated. It appeared that the radial extent of the fractured zone is limited to 5 m. Given the much larger distance between the individual boreholes and the distance between the boreholes and the boundary of the salt formation (more than 100 m), the probability of a release of radiation induced stored energy creating a pathway for the nuclides from the containers to the groundwater, is extremely low. The radiological consequences of a groundwater intrusion scenario induced by this very unprobable pathway are bounded by the 'standard' groundwater intrusion

  15. Estimation of daily solar radiation from routinely observed meteorological data in Chongqing, China

    International Nuclear Information System (INIS)

    Li Maofen; Liu Hongbin; Guo Pengtao; Wu Wei

    2010-01-01

    Solar radiation is a very important and major variable in crop simulation models. However, it is measured at a very limited number of meteorological stations worldwide. Models were developed to estimate daily solar radiation in Chongqing, one of the most important agricultural areas in China. Several routinely observed meteorological variables including daily maximum and minimum temperatures, daily mean dew point temperature, fog and rainfall had been obtained, investigated and analyzed from 1986 to 2000 for Chongqing. The monthly mean daily solar radiation at this location ranged from a maximum of 15.082 MJ m -2 day -1 in August and a minimum of 3.042 MJ m -2 day -1 in December. A newly developed model that included all selected variables proved the best method with a RMSE value of 2.522 MJ m -2 day -1 . The best performed models for different seasons were further evaluated according to divide-and-conquer principle. The model using all selected variables provided the best estimates of daily solar radiation in winter and autumn with RMSE values of 1.491 and 2.037 MJ m -2 day -1 , respectively. The method involving temperatures and rainfall information could be used to estimate daily solar radiation in summer with a RMSE value of 3.163 MJ m -2 day -1 . The model using temperature, rainfall and dew point data performed better than other models in spring with a RMSE value of 2.910 MJ m -2 day -1 .

  16. Comparison of the regulatory models assessing off-site radiological dose due to the routine releases of tritium

    International Nuclear Information System (INIS)

    Hwang, W. T.; Kim, E. H.; Han, M. H.; Choi, Y. H.; Lee, H. S.; Lee, C. W.

    2005-01-01

    Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO). A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEWTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment

  17. Simple method for routine check of the constancy of radiation quality of bremsstrahlung emitted by therapeutic particle accelerators

    Energy Technology Data Exchange (ETDEWEB)

    Rassow, J; Eipper, H H; Krause, K [Essen Univ. (Gesamthochschule) (Germany, F.R.). Abt. fuer Klinische Strahlenphysik; Staedtisches Krankenhaus Koeln-Merheim (Germany, F.R.). Roentgeninstitut und Strahlenklinik)

    1977-05-01

    The constancy of the radiation quality of therapeutically employed particle accelerators has to be checked at weekly intervals. Any change in radiation quality may have considerable therapeutic effects owing to its influence on dose distribution. It is recommended that measurements be made instead of, or in addition to, the axial reference-point measurement at 5 and 15 cm depth in the phantom, at 5 cm depth in the beam axis and at a reference-point about 1 cm within the geometric edge of the field, for checking the constancy of the radiation quality of bremsstrahlung. Only then, if routine checks carried out for the axial and the lateral reference-point dose ratios do not show any deviations greater than e.g. +-2 %, radiation quality is deemed to have remained sufficiently constant for radiotherapeutical applications.

  18. Maxdose-SR and popdose-SR routine release atmospheric dose models used at SRS

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, G. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Trimor, P. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-07-28

    MAXDOSE-SR and POPDOSE-SR are used to calculate dose to the offsite Reference Person and to the surrounding Savannah River Site (SRS) population respectively following routine releases of atmospheric radioactivity. These models are currently accessed through the Dose Model Version 2014 graphical user interface (GUI). MAXDOSE-SR and POPDOSE-SR are personal computer (PC) versions of MAXIGASP and POPGASP, which both resided on the SRS IBM Mainframe. These two codes follow U.S. Nuclear Regulatory Commission (USNRC) Regulatory Guides 1.109 and 1.111 (1977a, 1977b). The basis for MAXDOSE-SR and POPDOSE-SR are USNRC developed codes XOQDOQ (Sagendorf et. al 1982) and GASPAR (Eckerman et. al 1980). Both of these codes have previously been verified for use at SRS (Simpkins 1999 and 2000). The revisions incorporated into MAXDOSE-SR and POPDOSE-SR Version 2014 (hereafter referred to as MAXDOSE-SR and POPDOSE-SR unless otherwise noted) were made per Computer Program Modification Tracker (CPMT) number Q-CMT-A-00016 (Appendix D). Version 2014 was verified for use at SRS in Dixon (2014).

  19. Radiation crosslinked hydrogels as sustained release drug delivery systems

    International Nuclear Information System (INIS)

    Pekala, W.; Rosiak, J.; Rucinska-Rybus, A.; Burczak, K.; Galant, S.; Czolczynska, T.

    1986-01-01

    Radiation methods have been used for: i/modification of vascular prostheses, ii/ obtaining burn dressing materials enabling controlled drug release, iii/ the preparation of polymer ocular insert discs. The surface of polyester vascular prostheses, has been modified by deposition of acrylamide and inducing its polymerization in the solid state by γ-radiation. As a result of this treatment, tightness of the prosthesis walls and its surface hydrophilicity have been improved. Toxicological examinations and blood hemolysis studies of modified prostheses showed its good biocompatibility. Various burn dressings have been prepared and the most promising of all investigated turned to be composition consisting of a cotton gauze base and an active polyacrylamide hydrogel layer with addition of glycerin and immobilized Provital/protein preparation/. Preliminary clinical evaluations of this particular dressing showed that the process of burn healing is indeed fast and fully satisfactory. Ocular insert discs made of polymer and containing pilocarpin hydrochloride which is released at controlled rate have been prepared. It has been found that high hydrophilicity and good swelling properties of the ocular insert discs made possible to incorporate pilocarpin hydrochloride into hydrogel matrix. This work has been carried out under IAEA research contract RB 3379/R-1 POL. (author)

  20. Generic models and parameters for assessing the environmental transfer of radionuclides from routine releases

    International Nuclear Information System (INIS)

    1982-01-01

    This report is addressed to national regulatory bodies and technical and administrative personnel responsible for performing environmental impact analyses, in particular for generic assessments of doses to most exposed individuals from routine releases of radioactive effluents to atmospheric and aquatic environments. The concern of society in general for the quality of the environment and the realization that all human activities have some environmental effect, in which actions and reactions are coupled in a complex but predictable manner, have led to the development of a procedure for environmental impact analysis. This procedure is a predictive one, which tries to forecast probable environmental effects before some action, such as the construction and operation of a nuclear power station, is decided upon. The method of prediction is by the application of models that attempt to describe the environmental processes in mathematical terms in order to produce a quantitative result which can be used in the decision-making process

  1. Non-routine activities in RP Group in 1995

    International Nuclear Information System (INIS)

    Hoefert, M.; Stevenson, G.R.

    1996-01-01

    The activities not directly concerned with the daily routine, but nevertheless essential to ensure a steady progress in radiation protection at CERN, concern mostly tests and intercomparisons of existing methods (quality control), development of new ideas, methods, and instruments. New projects, another non-routine activity, require in most cases profound studies to prove their feasibility with respect to radiation protection requirements. All these activities are documented in Divisional Reports, Internal Reports and Technical Memoranda, and are listed

  2. Usefulness of radiatively obtained acrylamide polymers for production of drug forms with controlled release of the therapeutic component

    International Nuclear Information System (INIS)

    Mosiniak, T.; Switek, W.

    1988-01-01

    Using 60 Co gamma radiation as a factor initiating polymerization and cross-linking of polymers, polyacrylamide matrices were formed with the following therapeutic agents: aspirin, amidopyrin, sodium salicylate. Gamma radiation doses ranged from 3.5 to 22.5 kGy, dose rate was 0.138 Gy x s -1 . Kinetics of the therapeutic agent release from the matrix polymers was determined by measurement of per cent of the drug release in the course of time and calculations of release rate constants. The preparations containing slowly released drugs were obtained. 12 figs., 2 tabs., 11 refs. (author)

  3. A development of computer code for evaluating internal radiation dose through ingestion and inhalation pathways

    International Nuclear Information System (INIS)

    Lee, Jeong Ho; Lee, Chang Woo; Choi, Yong Ho; Chun, Ki Jung; Kim, Kook Chan; Kim, Sang Bok; Kim, Jin Kyu

    1991-07-01

    The computer codes were developed to evaluate internal radiation dose when radioactive isotopes released from nuclear facilities are taken through ingestion and inhalation pathways. Food chain models and relevant data base representing the agricultural and social environment of Korea are set up. An equilibrium model-KFOOD, which can deal with routine releases from a nuclear facility and a dynamic model-ECOREA, which is suitable for the description of acute radioactivity release following nuclear accident. (Author)

  4. Emissions and doses from sources of ionising radiation in the Netherlands: radiation policy monitoring

    International Nuclear Information System (INIS)

    Eleveld, H.; Pruppers, M.

    2002-01-01

    In 1997 the Ministry of Housing, Spatial Planning and the Environment requested RIVM to develop an information system for policy monitoring. One of the motives was that the European Union requires that the competent authorities of each member state ensure that dose estimates due to practices involving exposure to ionising radiation are made as realistic as possible for the population as a whole and for reference groups in all places where such groups may occur. Emissions of radionuclides and radiation to the environment can be classified as follows: (1) emissions to the atmosphere, (2) emissions to the aquatic system and (3) emission of external radiation from radioactive materials and equipment that produces ionising radiation. Released radioactivity is dispersed via exposure pathways, such as the atmosphere, deposition on the ground and farmland products, drinking water, fish products, etc. This leads to radiation doses due to inhalation, ingestion and exposure to external radiation. To assess the possible radiation doses different kinds of models are applied, varying from simple multiplications with dispersion coefficients, transfer coefficients and dose conversion coefficients to complex dispersion models. In this paper an overview is given of the human-induced radiation doses in the Netherlands. Also, trends in and the effect of policy on the radiation dose of members of the public are investigated. This paper is based on an RIVM report published recently. A geographical distribution of radiation risks due to routine releases for a typical year in the Netherlands was published earlier

  5. HOTSPOT, Field Evaluation of Radiation Release from Nuclear Accident

    International Nuclear Information System (INIS)

    2001-01-01

    1 - Description of program or function: The HOTSPOT Health Physics codes were created to provide Health Physics personnel with a fast, field-portable calculational tool for evaluating accidents involving radioactive materials. HOTSPOT codes are a first-order approximation of the radiation effects associated with the atmospheric release of radioactive materials. HOTSPOT programs are reasonably accurate for a timely initial assessment. More importantly, HOTSPOT codes produce a consistent output for the same input assumptions and minimize the probability of errors associated with reading a graph incorrectly or scaling a universal nomogram during an emergency. Four general programs, PLUME, EXPLOSION, FIRE, and RESUSPENSION, calculate a downwind assessment following the release of radioactive material resulting from a continuous or puff release, explosive release, fuel fire, or an area contamination event. Other programs deal with the release of plutonium, uranium, and tritium to expedite an initial assessment of accidents involving nuclear weapons. Additional programs estimate the dose commitment from inhalation of any one of the radionuclides listed in the database of radionuclides, calibrate a radiation survey instrument for ground survey measurements, and screening of plutonium uptake in the lung. The HOTSPOT codes are fast, portable, easy to use, and fully documented. HOTSPOT supports color high resolution monitors and printers for concentration plots and contours. The codes have been extensively used by the DOS community since 1985. Version 8 allows users to add their own custom radionuclide library and to create custom radionuclide mixtures. It also includes wet deposition to approximate the enhanced plume depletion and ground deposition due to the effects of rain. Additional release geometry options for TRITIUM RELEASE and GENERAL PLUME were added, as well as several other enhancements and improvements. See info (f1) from the main HOTSPOT menu for additional

  6. Perspective on radiation from the nuclear power industry

    International Nuclear Information System (INIS)

    Cohen, B.L.

    1990-01-01

    Methods for estimating the risk of radiation induced cancer mortality to members of the public are outlined for each element of the nuclear power industry - reactor accidents, routine releases from nuclear plants, transport, mining and milling of uranium, and escape of buried radioactive waste (high level and low level). The results are compared with mortality risks from the air pollution and chemical carcinogens released into the ground in generating the same amount of electricity by coal burning - the latter are thousands of times larger. Radiation from nuclear power is also 1,000 times smaller than that from radon in homes. The amount of money spent to avert a death from nuclear power radiation is in the billion dollar range, whereas lives could be saved from radon in homes for 0.00001 times that cost. Medical screening and highway safety programs can save lives for a similarly low cost

  7. Ultraviolet radiation stimulates the release of arachidonic acid from mammalian cells in culture

    International Nuclear Information System (INIS)

    De Leo, V.A.; Hanson, D.; Weinstein, I.B.; Harber, L.C.

    1985-01-01

    C3H 10T1/2 cells in culture were prelabelled with [ 3 H]arachidonic acid and exposed to UVB radiation. Almost immediately after irradiation cells released labelled arachidonate metabolites into media in a dose dependent manner. This release was inhibited by removing calcium ions from the system and by the addition of dexamethasone and parabromophenacyl bromide to the system. This suggests that the UVB stimulated release of arachidonic acid from membrane phospholipids is, in part, mediated by a phospholipase A 2 enzyme system. Thin layer chromatographic examination of media extracts revealed a dose dependent UVB stimulation of prostaglandin production by cultured cells. (author)

  8. Loss of covalently linked lipid as the mechanism for radiation-induced release of membrane-bound polysaccharide and exonuclease from Micrococcus radiodurans

    International Nuclear Information System (INIS)

    Mitchel, R.E.J.

    1981-01-01

    The mechanism of γ-radiation-induced release of polysaccharide and exonuclease from the midwall membrane of Micrococcus radiodurans has been examined. These two components appear to be released independently, but by very similar processes. Direct analysis of radiation-released polysaccharide indicated the absence of an alkali-labile neutral lipid normally present in the native material. Radiation-induced release therefore probably results from the radiolytic cleavage of a covalently linked lipid which normally serves to anchor these substances to the membrane. The absence of a natural membrane-bound carotenoid had no effect on the rate of release of these components. Likewise, the absence of exonuclease in an exonuclease minus mutant did not influence the release of polysaccharide. It is suggested that the major pathway of radical transfer from the initiating .OH and culminating in the cleavage of the neutral lipid anchor may not be via the membrane

  9. Summary of estimated doses and risks resulting from routine radionuclide releases from fast breeder reactor fuel cycle facilities

    International Nuclear Information System (INIS)

    Miller, C.W.; Meyer, H.R.

    1985-01-01

    A project is underway at Oak Ridge National Laboratory to assess the human health and environment effects associated with operation of Liquid Metal Fast Breeder Reactor fuel cycle. In this first phase of the work, emphasis was focused on routine radionuclide releases from reactor and reprocessing facilities. For this study, sites for fifty 1-GW(e) capacity reactors and three reprocessing plants were selected to develop scenarios representative of US power requirements. For both the reactor and reprocessing facility siting schemes selected, relatively small impacts were calculated for locality-specific populations residing within 100 km. Also, the results of these analyses are being used in the identification of research priorities. 13 refs., 2 figs., 3 tabs

  10. 32 CFR 701.121 - Processing “routine use” disclosures.

    Science.gov (United States)

    2010-07-01

    ... DEPARTMENT OF THE NAVY DOCUMENTS AFFECTING THE PUBLIC DON Privacy Program § 701.121 Processing “routine use... be in writing and state that it is being made under a “routine use” established by a specific PA... and maintain a disclosure accounting of the information released. (See § 701.111.) (b) Failure to cite...

  11. Cancer near the Three Mile Island nuclear plant: radiation emissions.

    Science.gov (United States)

    Hatch, M C; Beyea, J; Nieves, J W; Susser, M

    1990-09-01

    As a public charge, cancers among the 159,684 residents living within a 10-mile (16-km) radius of the Three Mile Island nuclear plant were studied relative to releases of radiation during the March 28, 1979, accident as well as to routine plant emissions. The principal cancers considered were leukemia and childhood malignancies. Estimates of the emissions delivered to small geographic study tracts were derived from mathematical dispersion models which accounted for modifying factors such as wind and terrain; the model of accident emissions was validated by readings from off-site dosimeters. Incident cancers among area residents for the period 1975-1985 (n = 5,493) were identified by a review of the records at all local and regional hospitals; preaccident and postaccident trends in cancer rates were examined. For accident emissions, the authors failed to find definite effects of exposure on the cancer types and population subgroups thought to be most susceptible to radiation. No associations were seen for leukemia in adults or for childhood cancers as a group. For leukemia in children, the odds ratio was raised, but cases were few (n = 4), and the estimate was highly variable. Moreover, rates of childhood leukemia in the Three Mile Island area are low compared with national and regional rates. For exposure to routine emissions, the odds ratios were raised for childhood cancers as a whole and for childhood leukemia, but confidence intervals were wide and included 1.0. For leukemia in adults, there was a negative trend. Trends for two types of cancer ran counter to expectation. Non-Hodgkin's lymphoma showed raised risks relative to both accident and routine emissions; lung cancer (adjusted only indirectly for smoking) showed raised risks relative to accident emissions, routine emissions, and background gamma radiation. Overall, the pattern of results does not provide convincing evidence that radiation releases from the Three Mile Island nuclear facility influenced

  12. Evaluation of the influence of UV/IR radiation on iron release from ferritin

    International Nuclear Information System (INIS)

    Gritzkov, M.; Kochev, V.; Vladimirova, L

    2010-01-01

    In the present work the influence of UV/IR radiation on the iron-releasing process from ferritin is investigated. The ferritins are a family of iron-storing proteins playing a key role in the biochemical reactions between iron and oxygen-processes of exclusive importance for the existence of all living organisms. The iron is stored within the ferritin core in the form of insoluble crystals containing Fe(III). Therefore for its release, the mineral matrix has to be decomposed, usually through a reduction of Fe(III) to Fe(II). Our study considers the action of UV/IR radiation on the structure of the protein molecule. Eventual changes in the ferritin conformation under the irradiation could result in the change of channel forming regions responsible for the iron efflux. This can be assess by the quantity of Fe (II) obtained in a subsequent mobilization procedure evoked by exogenous reducing agents. In our case the content of the reduced iron is determined electrochemically by the method of potentiometric titration. As already was shown, this method promises to become highly useful for quantitative evaluation of released Fe 2+ . (Author)

  13. Release of bound residues of atrazine from soils through autoclaving and gamma radiation sterilization

    International Nuclear Information System (INIS)

    Nakagawa, L.E.; Andréa, M.M.

    1997-01-01

    The sterilization methods are particularly important to study the influence of microorganisms on the pesticide dissipation in soils. This study, conducted in the laboratories of the Instituto Biológico of São Paulo in august 1996, tested the influence of two methods of soil sterilization - moist heat (autoclaving) and γ radiation - on the release of nonextractable or bound residues. It was studied, as example, bound residues of the herbicide atrazine in two types of soil (gley humic and dark red latosol). In the soil samples submitted to the moist heat sterilization, the recovery of the previously bound residues as reextractable residues was 5.6 and 5.9 times higher than in the control soils, not submitted to any sterilization process. Therefore, the method itself released the residues, indicating that the autoclaving is not the most appropriate method for studies on the influence of microorganisms on the release of bound residues. Otherwise, the γ radiation did not modify the residues recovery when compared to the controls. (author) [pt

  14. Controlled release fertilizers using superabsorbent hydrogel prepared by gamma radiation

    International Nuclear Information System (INIS)

    Elbarbary, Ahmed M.; Ghobashy, Mohamed Mohamady

    2017-01-01

    Superabsorbent hydrogels (PVP/CMC) based on polyvinylpyrrolidone (PVP)/carboxylmethyl cellulose (CMC) of different copolymer compositions were prepared by gamma radiation. Factors affecting the gel content (%) and the swelling ratio (g/g) of hydrogel such as irradiation dose as well as copolymer composition were investigated. With increasing the CMC content in PVP/CMC hydrogels, increases the swelling and improves the water retention capability. The high swelling ratio was observed at copolymer composition of PVP/CMC (60/40). Fast swelling of the hydrogels was obtained after 20 min. The effect of different fertilizers and buffers of different pH's on equilibrium swelling of hydrogels was investigated. Fertilizers such as urea, monopotassium-phosphate (MPK), and nitrogen-phosphate-potassium (NPK) were loaded onto the hydrogel to supply nitrogen, potassium and phosphorous nutrients. PVP/CMC hydrogels retained 28-36% after 72 h and slow retention was noticed up to 9 days. The swelling of hydrogel in fertilizer solutions is lower than that in water. The hydrogels showed adsorption desorption of fertilizers which governs by slow release property. The release rate of urea is much higher 10 times than that of phosphate. After 3 days, urea released 60%, while phosphate released 10-12%. The applicability of PVP/CMC hydrogels in the agricultural fields shows greater growth effect on zea maize plants. The growth of zea maize plant in soil mixed with PVP/CMC hydrogels loaded fertilizers is greater than untreated soil. The slow release fertilize, the high swelling and the slow water retention behaviors of PVP/CMC hydrogels encourage their use as safer release systems for fertilizers and as soil conditioner in agricultural applications.

  15. Controlled release fertilizers using superabsorbent hydrogel prepared by gamma radiation

    Energy Technology Data Exchange (ETDEWEB)

    Elbarbary, Ahmed M.; Ghobashy, Mohamed Mohamady [Atomic Energy Authority, Nasr City (Egypt). National Center for Radiation Research and Technology (NCRTT)

    2017-07-01

    Superabsorbent hydrogels (PVP/CMC) based on polyvinylpyrrolidone (PVP)/carboxylmethyl cellulose (CMC) of different copolymer compositions were prepared by gamma radiation. Factors affecting the gel content (%) and the swelling ratio (g/g) of hydrogel such as irradiation dose as well as copolymer composition were investigated. With increasing the CMC content in PVP/CMC hydrogels, increases the swelling and improves the water retention capability. The high swelling ratio was observed at copolymer composition of PVP/CMC (60/40). Fast swelling of the hydrogels was obtained after 20 min. The effect of different fertilizers and buffers of different pH's on equilibrium swelling of hydrogels was investigated. Fertilizers such as urea, monopotassium-phosphate (MPK), and nitrogen-phosphate-potassium (NPK) were loaded onto the hydrogel to supply nitrogen, potassium and phosphorous nutrients. PVP/CMC hydrogels retained 28-36% after 72 h and slow retention was noticed up to 9 days. The swelling of hydrogel in fertilizer solutions is lower than that in water. The hydrogels showed adsorption desorption of fertilizers which governs by slow release property. The release rate of urea is much higher 10 times than that of phosphate. After 3 days, urea released 60%, while phosphate released 10-12%. The applicability of PVP/CMC hydrogels in the agricultural fields shows greater growth effect on zea maize plants. The growth of zea maize plant in soil mixed with PVP/CMC hydrogels loaded fertilizers is greater than untreated soil. The slow release fertilize, the high swelling and the slow water retention behaviors of PVP/CMC hydrogels encourage their use as safer release systems for fertilizers and as soil conditioner in agricultural applications.

  16. Ionizing radiation damage in Micrococcus radiodurans cell wall: release of polysaccharide

    International Nuclear Information System (INIS)

    Mitchel, R.E.J.

    1976-01-01

    Sublethal 60 Co γ-irradiation of the bacterium Micrococcus radiodurans in aqueous suspension results in a loss of up to 6 percent of its cellular dry weight and 30 percent of its wet weight. In the process some specific cell wall polysaccharides, including a polymer of glucose and N-acylated glucosamine, are released into the surrounding medium. These polysaccharides appear to originate from a hydrophobic site in the middle, lipid-rich, cell wall layer. The damage to this layer which results in the release of these and other polymers may be due to a disruption of this hydrophobic site. The polysaccharide containing glucose and N-acylated glucosamine exists as a high molecular weight polymer in unirradiated cells, but irradiation causes some degradation prior to release. In a free state this polysaccharide is considerably less sensitive to radiolytic degradation than in a bound state. Free radicals generated from surrounding water by ionizing radiation initiate the release, hydroxyl radicals being the most important species. Oxygen protects the cell wall against loss of the polysaccharides, apparently by a mechanism which does not depend on the ability of O 2 to scavenge hydrogen atoms and aqueous electrons

  17. Estimated routine radiation doses to transportation workers in alternative spent-fuel transportation systems

    International Nuclear Information System (INIS)

    Schneider, K.J.; Smith, R.I.; Daling, P.M.; Ross, W.A.; McNair, G.W.

    1988-01-01

    The federal system for the management of spent fuel and high-level radioactive waste includes the acceptance by the US Department of Energy (DOE) of the spent fuel or waste loaded in casks at the reactor or other waste generators, its transportation to a repository, and its handling and final emplacement in the repository. The DOE plans to implement a transportation system that is safe, secure, efficient, and cost-effective and will meet applicable regulatory safety and security requirements. The DOE commissioned the Pacific Northwest Laboratory (PNL) to develop estimates of the routine radiation doses that would result from the operation of a system postulated using current designs and practices. From that evaluation, PNL identified activities/operations that result in the higher fraction of doses, proposed conceptual alternatives that would effectively reduce such exposures, and evaluated the cost-effectiveness of such alternatives. The study is one of a series used in making overall system design and operational decisions in the development of the DOE's spent-fuel/high-level waste transportation system. This paper contains the highlights from the PNL study of the estimated radiation doses to the transportation workers in a postulated reference transportation system and potential alternatives to that system

  18. Dose assessment on natural radiation, natural radionuclide, and artificial radionuclide released by Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Hosoda, Masahiro; Tokonami, Shinji; Furukawa, Masahide

    2012-01-01

    Various radionuclides are distributed in environmental materials such as soil, rock, and water. People are exposed every day to natural radiation. According to the UNSCEAR 2008 report, Sources of Ionizing Radiation, natural radiation sources are categorized as terrestrial gamma-rays, radon, cosmic rays and food. The effective dose from radon, thoron and its decay products is about 50% of all natural radiation exposure. Consciousness of the Japanese public toward radiation exposure has significantly increased since the start of the Fukushima Dai-ichi Nuclear Power Station accident. In this paper, the nationwide survey and dose estimation for terrestrial gamma-rays and radon are summarized. External dose from artificial radionuclides released by the Fukushima accident are also reported. (author)

  19. Release of doxorubicin from hydrogels of poly-2-hydroxyethyl methacrylate-co-acrylamide obtained by gamma radiations

    International Nuclear Information System (INIS)

    Rodriguez Rodriguez, A.; Rapado Paneque, M.; Covac Peniche, C.

    2013-01-01

    The release matrixes used were a hydrogel based on HEMA-co-AAm copolymers obtained by gamma radiation; the synthesis was conducted by varying the absorbed dose with the same composition, with the aim to establish the swelling behavior according to the absorbed dose in synthesis. Similarly was settled release profiles of doxorubicin. The mechanism of drug diffusion was established. (Author)

  20. Literature survey: health effects of radiation

    International Nuclear Information System (INIS)

    Tveten, U.; Garder, K.

    This report was originally written as a chapter of a report entitled 'Air pollution effects of electric power generation, a literature survey', written jointly by the Norwegian Institute for Air Research (NILU) and the Institutt for Atomenergi (IFA). (INIS RN242406). A survey is presented of the health effects of radiation. It has not, however, been the intention of the authors to make a complete list of all the literature relevant to this subject. The NILU/IFA report was meant as a first step towards a method of comparing the health effects of electric power generation by fission, gas and oil. Consequently information relevant to quantification of the health effects on humans has been selected. It is pointed out that quantitative information on the health effects of low radiation and dose rates, as are relevant to routine releases, does not exist for humans. The convention of linear extrapolation from higher doses and dose rates is used worldwide, but it is felt by most that the estimates are conservative. As an example of the use of the current best estimates, a calculation of normal release radiation doses is performed. (Auth.)

  1. XOQDOQ: computer program for the meteorological evaluation of routine effluent releases at nuclear power stations. Final report

    International Nuclear Information System (INIS)

    Sagendorf, J.F.; Goll, J.T.; Sandusky, W.F.

    1982-09-01

    Provided is a user's guide for the US Nuclear Regulatory Commission's (NRC) computer program X0QDOQ which implements Regulatory Guide 1.111. This NUREG supercedes NUREG-0324 which was published as a draft in September 1977. This program is used by the NRC meteorology staff in their independent meteorological evaluation of routine or anticipated intermittent releases at nuclear power stations. It operates in a batch input mode and has various options a user may select. Relative atmospheric dispersion and deposition factors are computed for 22 specific distances out to 50 miles from the site for each directional sector. From these results, values for 10 distance segments are computed. The user may also select other locations for which atmospheric dispersion deposition factors are computed. Program features, including required input data and output results, are described. A program listing and test case data input and resulting output are provided

  2. Releases of radioactivity at the Savannah River Plant, 1954--1985

    International Nuclear Information System (INIS)

    Zeigler, C.C.; Lawrimore, I.B.

    1988-07-01

    Radioactive releases from Savannah River Plant (SRP) facilities to air, water and earthen seepage basins have been monitored and tabulated throughout the history of the site. The purpose of this report is to provide a source of data on routine releases of radioactivity to air, water and seepage basins that can be used for analyses of trends, environmental impact, etc. As used in this report, routine radioactive releases means radioactive materials that are released through established effluents from process facilities. This report provides a summary of radioactive releases that inflects the release values contained m records and documents from startup through 1985

  3. Probabilistic siting analysis of nuclear power plants emphasizing atmospheric dispersion of radioactive releases and radiation-induced health effects

    International Nuclear Information System (INIS)

    Savolainen, Ilkka

    1980-01-01

    A presentation is made of probabilistic evaluation schemes for nuclear power plant siting. Effects on health attributable to ionizing radiation are reviewed, for the purpose of assessment of the numbers of the most important health effect cases in light-water reactor accidents. The atmospheric dispersion of radioactive releases from nuclear power plants is discussed, and there is presented an environmental consequence assessment model in which the radioactive releases and atmospheric dispersion of the releases are treated by the application of probabilistic methods. In the model, the environmental effects arising from exposure to radiation are expressed as cumulative probability distributions and expectation values. The probabilistic environmental consequence assessment model has been applied to nuclear power plant site evaluation, including risk-benefit and cost-benefit analyses, and the comparison of various alternative sites. (author)

  4. Involvement of hydroxyl radicals in the release by ionizing radiation of a cell surface nuclease from Micorcoccus radiodurans

    International Nuclear Information System (INIS)

    Mitchel, R.E.J.

    1975-01-01

    The ionizing radiation-induced release of a surface exonuclease from Micrococcus radiodurans is to a large extent inhibited by the removal of water. Irradiation of a cell suspension saturated with O 2 (an effective aqueous electron and hydrogen atom scavenger) allows the same release as irradiation in the presence of N 2 . Ethanol (a good hydroxyl radical scavenger) protects the enzyme from release. These data suggest that hydroxyl radicals produced by the radiolysis of water are important releasing agents. Hydroxyl radicals produced by the ultraviolet decomposition of H 2 O 2 were effective in releasing the enzyme

  5. Routine medicare and radiation exposure (3) biology about radiation exposure for its understanding

    International Nuclear Information System (INIS)

    Saito, Tsutomu; Hirata, Hideki

    2013-01-01

    Radiation-induced biological responses are easily explained as follows. The process of cancer formation is on the hypothesis of multi-step carcinogenesis of the initiation, promotion and progression. Radiation is an exogenous physical initiator. Physical process of ionization in biomaterials by radiation occurs within the time of 10 -12 sec order, which resulting in chemical process (10 -6 sec) leading to tissue response or to cancerous change (several tens hours to several decades). Direct and indirect effects on DNA are yielded with the high LET (linear energy transfer) radiation and low, through OH-radical formation, respectively. Double strand break of DNA induced by radiation is repaired by the error-free homologous recombination or error-prone non-homologous end-joining. At the early phase of the damage, DNA damage response begins to work for repairing, and when the response is inoperable, cellular response is induced to lead radiation apoptosis as an exclusion mechanism of abnormal cells. The biological effects differ even at the same dose of different radiations when their LET is different, and relative biological effectiveness (RBE) is used. For correction of the stochastic radiation effect, the radiation weighting factor (W R ) is used for conversion to the single photon beam dose that ICRP defines as the equivalent dose (H T , Sv). ICRP (Pub. 103) also recommends the use of RBE (Gy) for the definitive effect. Radiation effects are known to be modified by such phenomena as the bystander effect, cluster damage of DNA, radiation adaptation, hormesis, dose rate effect and non-tumor inducing dose. ICRP employs linear non-threshold (LNT) hypothesis for low dose and low dose rate carcinogenesis. (T.T.)

  6. Radically Reducing Radiation Exposure during Routine Medical Imaging

    Science.gov (United States)

    Exposure to radiation from medical imaging in the United States has increased dramatically. NCI and several partner organizations sponsored a 2011 summit to promote efforts to reduce radiation exposure from medical imaging.

  7. Environmental and health impacts of February 14, 2014 radiation release from the nation's only deep geologic nuclear waste repository.

    Science.gov (United States)

    Thakur, P; Lemons, B G; Ballard, S; Hardy, R

    2015-08-01

    The environmental impact of the February 14, 2014 radiation release from the nation's only deep geologic nuclear waste repository, the Waste Isolation Pilot Plant (WIPP) was assessed using monitoring data from an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC). After almost 15 years of safe and efficient operations, the WIPP had one of its waste drums rupture underground resulting in the release of moderate levels of radioactivity into the underground air. A small amount of radioactivity also escaped to the surface through the ventilation system and was detected above ground. It was the first unambiguous release from the WIPP repository. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. The accelerated air monitoring campaign, which began following the accident, indicates that releases were low and localized, and no radiation-related health effects among local workers or the public would be expected. The highest activity detected was 115.2 μBq/m(3) for (241)Am and 10.2 μBq/m(3) for (239+240)Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m(3) of (241)Am and 5.8 μBq/m(3) of (239+240)Pu at a monitoring station located approximately one kilometer northwest of the WIPP facility. CEMRC's recent monitoring data show that the concentration levels of these radionuclides have returned to normal background levels and in many instances, are not even detectable, demonstrating no long-term environmental impacts of the recent radiation release event at the WIPP. This article presents an evaluation of almost one year of environmental monitoring data that informed the public that the levels of radiation that got out to the environment were very low and did not, and will not harm anyone or have any long-term environmental consequence. In terms of radiological risk at or in the vicinity of the

  8. Routine Responses to Disruption of Routines

    Science.gov (United States)

    Guha, Mahua

    2015-01-01

    "Organisational routines" is a widely studied research area. However, there is a dearth of research on disruption of routines. The few studies on disruption of routines discussed problem-solving activities that are carried out in response to disruption. In contrast, this study develops a theory of "solution routines" that are a…

  9. Methods For Calculating Thyroid Doses to The Residents Of Ozersk Due to 131I Releases From The Stacks of The Mayak Production Association

    Energy Technology Data Exchange (ETDEWEB)

    Rovny, Sergey I.; Mokrov, Y.; Stukalov, Pavel M.; Beregich, D. A.; Teplyakov, I. I.; Anspaugh, L. R.; Napier, Bruce A.

    2009-10-23

    The Mayak Production Association (MPA) was established in the late 1940s in accordance with a special Decree of the USSR Government for the production of nuclear weapons. In early years of MPA operation, due to the lack of experience and absence of effective methods of RW management, the enterprise had extensive routine (designed) and non-routine (accidental) releases of gaseous radioactive wastes to the atmosphere. These practices resulted in additional technogenic radiation exposure of residents inhabiting populated areas near the MPA. The primary objective of ongoing studies under JCCRER Project 1.4 is to estimate doses to the residents of Ozersk due to releases of radioactive substances from the stacks of MPA. Preliminary scoping studies have demonstrated that releases of radioactive iodine (131I) from the stacks of the Mayak Radiochemical Plant represented the major contribution to the dose to residents of Ozersk and of other nearby populated areas. The behavior of 131I in the environment and of 131I migration through biological food chains (vegetation-cows-milk-humans) indicated a need for use of special mathematical models to perform the estimation of radiation doses to the population. The goal of this work is to select an appropriate model of the iodine migration in biological food chains and to justify numerical values of the model parameters.

  10. Preparation and its drug release property of radiation-polymerized poly(methyl methacrylate) capsule including potassium chloride

    International Nuclear Information System (INIS)

    Yoshida, Masaru; Kumakura, Minoru; Kaetsu, Isao

    1979-01-01

    Porous flat circular capsules including KCl as a drug were prepared by radiation-induced polymerization of methyl methacrylate at room temperature in the presence of polyethylene glycol No. 600. The porous structure can be controlled by the methyl methacrylate-polyethylene glycol No. 600 composition. The amount of drug released was linearly related to the square root of time. The magnitude of drug release increased roughly in proportional to the water content of capsule, which can be related to porosity in the capsule. (author)

  11. The enhanced radiation response of an in vitro tumour model by cyanide released from hydrolysed amygdalin

    International Nuclear Information System (INIS)

    Biaglow, J.E.; Durand, R.E.

    1978-01-01

    Any inhibition of oxygen consumption by respiring cells should result in indirect radiosensitization of the more centrally located hypoxic cells of a tumour. Amygdalin (D-mandelonitrile-β-D-glucosido-6-β-D-glucoside) when hydrolysed by the enzyme β-D-glucoside glycohydrolase (β-glucosidase) releases the respiratory inhibitor cyanide. A study has been made of the conditions for enhancing the gamma radiation response of multi-cell spheroids of V79 cells by cyanide or by cyanide released by enzymatic hydrolysis of amygdalin. Amygdalin hydrolysis was monitored by the increase in absorbancy at 250nm (production of benzaldehyde). Oxygen utilization was recorded by an oxygen electrode. The respiratory effects produced by the additon of amygdalin to cell suspensions containing β-glucosidase were immediate and essentially the same as those obtained by adding the equivalent amounts of KCN to the cell suspensions. The radio-resistant 'tail' of the survival curve of multi-cell spheroids was reduced in the presence of cyanide (added directly or secondarily released). The radiation response of the spheroids in the presence of cyanide was slightly greater than that for reoxygenation alone. (U.K.)

  12. Radiation protection requirements in the limitation of the release of radioactive effluents

    International Nuclear Information System (INIS)

    Beninson, D.

    1978-01-01

    The paper summarizes the requirements of radiation protection, as presented in the new ICRP recommendation, in relation to the limitation of the release of radioactive effluents. The concepts of effective dose equivalent and collective dose equivalent are used in the presentation of the optimization procedures and the dose limitation to individuals. The dose commitment is used for the procedures applied to control future exposures. An appendix describes the basic concepts and quantities used in assessments of human exposures and risks. (author)

  13. EMERALD, Radiation Release and Dose after PWR Accident for Design Analysis and Operation Analysis

    International Nuclear Information System (INIS)

    Brunot, W.K.; Fray, R.R.; Gillespie, S.G.

    1988-01-01

    1 - Description of problem or function: The EMERALD program is designed for the calculation of radiation releases and exposures resulting from abnormal operation of a large pressurized water reactor (PWR). The approach used in EMERALD is similar to an analog simulation of a real system. Each component or volume in the plant which contains a radioactive material is represented by a subroutine which keeps track of the production, transfer, decay and absorption of radioactivity in that volume. During the course of the analysis of an accident, activity is transferred from subroutine to subroutine in the program as it would be transferred from place to place in the plant. For example, in the calculation of the doses resulting from a loss-of-coolant accident the program first calculates the activity built up in the fuel before the accident, then releases some of this activity to the containment volume. Some of this activity is then released to the atmosphere. The rates of transfer, leakage, production, cleanup, decay, and release are read in as input to the program. Subroutines are also included which calculate the on-site and off-site radiation exposures at various distances for individual isotopes and sums of isotopes. The program contains a library of physical data for the twenty-five isotopes of most interest in licensing calculations, and other isotopes can be added or substituted. Because of the flexible nature of the simulation approach, the EMERALD program can be used for most calculations involving the production and release of radioactive materials during abnormal operation of a PWR. These include design, operational, and licensing studies. 2 - Method of solution - Explicit solutions of first-order linear differential equations are included. In addition, a subroutine is provided which solves a set of simultaneous linear algebraic equations. 3 - Restrictions on the complexity of the problem - Maxima of: 25 isotopes, 7 time periods, 15 volumes or components, 10

  14. Model to estimate the local radiation doses to man from the atmospheric release of radionuclides (LWBR development program)

    International Nuclear Information System (INIS)

    Rider, J.L.; Beal, S.K.

    1977-04-01

    A model was developed to estimate the radiation dose commitments received by people in the vicinity of a facility that releases radionuclides into the atmosphere. This model considers dose commitments resulting from immersion in the plume, ingestion of contaminated food, inhalation of gaseous and suspended radioactivity, and exposure to ground deposits. The dose commitments from each of these pathways is explicitly considered for each radionuclide released into the atmosphere and for each daughter of each released nuclide. Using the release rate of only the parent radionuclide, the air and ground concentrations of each daughter are calculated for each position of interest. This is considered to be a significant improvement over other models in which the concentrations of daughter radionuclides must be approximated by separate releases

  15. [Effect of UV-B radiation on release of nitrogen and phosphorus from leaf litter in subtropical region in China].

    Science.gov (United States)

    Song, Xin-Zhang; Zhang, Hui-Ling; Jiang, Hong; Yu, Shu-Quan

    2012-02-01

    The release of nitrogen and phosphorus from leaf litter of six representative species, Cunninghamia lanceolata, Pinus massoniana, Schima superba, Cinnamanun camphora, Cyclobalanopsis glauca and Castanopsis eyeri, was investigated with litterbag method under ambient and reduced UV-B radiation (22.1% below ambient) treatments in subtropical region. The results showed that, the N dynamics exhibited three patterns: immobilization, mineralization-immobilization and mineralization-immobilization-mineralization. P dynamics also exhibited three different patterns: mineralization, immobilization-mineralization-immobilization and no large change. Compared with ambient treatment, the reduced treatment significantly delayed the N release from C. eyeri and P release from both C. glanca and C. eyeri (Plitter decomposition. The C: P ratios can partly explain the P dynamics during decomposition. The more works need to be done to better understand the role of UV-B radiation in the forest ecosystem in humid subtropical China under global environment change.

  16. Radiation research contracts: Distribution of fission products in the biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Schoenfeld, T [Vienna University, First Chemical Institute, Vienna (Austria)

    1959-04-15

    Protection against ionizing radiation given off in nuclear transformations is one of the foremost safety problems in all atomic energy operations. While every effort is being made to prevent reactors, processing plants and all other installations from releasing radioactive materials into the biosphere - air, water and earth - under any foreseeable conditions, small amounts of it are actually released into man's living space. Undoubtedly, this will continue to be so, at least for the time being. For example, low activity liquid wastes from some chemical processing plants are decontaminated in special processes, but traces of fission products remain in the liquids finally discharged on the ground or to nearby waterways. In some installations low and medium activity liquid wastes are even released on the ground or into swamps without prior decontamination. It is also to be expected that in accidents larger amounts of fission products may occasionally be released. To make the routine release of small amounts of fission products safe and to be able to estimate the possible effect of larger releases in accidents, a considerable amount of information is required

  17. Radiation research contracts: Distribution of fission products in the biosphere

    International Nuclear Information System (INIS)

    Schoenfeld, T.

    1959-01-01

    Protection against ionizing radiation given off in nuclear transformations is one of the foremost safety problems in all atomic energy operations. While every effort is being made to prevent reactors, processing plants and all other installations from releasing radioactive materials into the biosphere - air, water and earth - under any foreseeable conditions, small amounts of it are actually released into man's living space. Undoubtedly, this will continue to be so, at least for the time being. For example, low activity liquid wastes from some chemical processing plants are decontaminated in special processes, but traces of fission products remain in the liquids finally discharged on the ground or to nearby waterways. In some installations low and medium activity liquid wastes are even released on the ground or into swamps without prior decontamination. It is also to be expected that in accidents larger amounts of fission products may occasionally be released. To make the routine release of small amounts of fission products safe and to be able to estimate the possible effect of larger releases in accidents, a considerable amount of information is required

  18. Radiological impact from airborne routine discharges of Coal-Fired power plant

    International Nuclear Information System (INIS)

    Norasalwa Zakaria; Rohyiza Baan; Kathiravale, Sivapalan

    2010-01-01

    Radioactivity exists everywhere in nature. We are exposed to intense and continuous natural radiation coming from the sun, cosmic radiation, telluric radiation and even to the internal radiation of our own body. The fly ash emitted from burning coal for electricity by a power plant carries into the surrounding environment 100 times more radiation than a nuclear power plant producing the same amount of energy. This paper presents the information of studies on the radiological impact from airborne routine discharge of coal-fired power plants. (author)

  19. Routine dental x-ray : a health hazards

    International Nuclear Information System (INIS)

    Parthasarathy, K.S.

    1978-01-01

    In orthopantography (OPG) technique, a single panoramic x-ray replaces a dozen or so conventional x-ray exposures required for a full-mouth examination. OPG, thus, reduces radiation dose to the patients. However, the very simplicity of the OPG technique may lead to its misuse. The dentists are tempted to take too many OPG films and thus exposing the patients unnecessarily to X radiation. Dentists are advised against making dental x-radiography a routine part of examinations. Greater care should be exercised particularly in the case of children while using OPG. (M.G.B.)

  20. Aspects of radiation exposure amongst the population after release of radionuclides from terminal stores

    International Nuclear Information System (INIS)

    Proehl, G.; Mueller, H.; Paretzke, H.G.

    1989-08-01

    The release of radionuclides from terminal stores may lead to the contamination of ground water lying close to the surface, after the radionuclides have migrated within the covering rock. Use of this water can result in radiation exposure for human beings along many exposure pathways. In order to assess the radiation exposure from these exposure pathways the model ECOSYS-87-B was developed, as an extension of ECOSYS (Jacobi et al. 1985). On the basis of a standardized contamination of the ground water, the potential radiation exposure of a one-year-old and an adult are calculated, under the assumption that the entire food supply of these persons was produced using radioactively contaminated water. Special questions on the transfer of radionuclides in food chains are discussed, and, in particular, the mineral content of the water and the influence of the chemical form of the radionuclides dissolved in the ground water on their transfer within the food chain are explained. There is also a study of the extent to which various physiologically-based nutritional habits influence the radiation exposure of a human being. Various criteria for the evaluation of radiation exposure are discussed. (orig./HP) [de

  1. Radiation safety assessment and development of environmental radiation monitoring technology; standardization of input parameters for the calculation of annual dose from routine releases from commercial reactor effluents

    Energy Technology Data Exchange (ETDEWEB)

    Rhee, I. H.; Cho, D.; Youn, S. H.; Kim, H. S.; Lee, S. J.; Ahn, H. K. [Soonchunhyang University, Ahsan (Korea)

    2002-04-01

    This research is to develop a standard methodology for determining the input parameters that impose a substantial impact on radiation doses of residential individuals in the vicinity of four nuclear power plants in Korea. We have selected critical nuclei, pathways and organs related to the human exposure via simulated estimation with K-DOSE 60 based on the updated ICRP-60 and sensitivity analyses. From the results, we found that 1) the critical nuclides were found to be {sup 3}H, {sup 133}Xe, {sup 60}Co for Kori plants and {sup 14}C, {sup 41}Ar for Wolsong plants. The most critical pathway was 'vegetable intake' for adults and 'milk intake' for infants. However, there was no preference in the effective organs, and 2) sensitivity analyses showed that the chemical composition in a nuclide much more influenced upon the radiation dose than any other input parameters such as food intake, radiation discharge, and transfer/concentration coefficients by more than 102 factor. The effect of transfer/concentration coefficients on the radiation dose was negligible. All input parameters showed highly estimated correlation with the radiation dose, approximated to 1.0, except for food intake in Wolsong power plant (partial correlation coefficient (PCC)=0.877). Consequently, we suggest that a prediction model or scenarios for food intake reflecting the current living trend and a formal publications including details of chemical components in the critical nuclei from each plant are needed. Also, standardized domestic values of the parameters used in the calculation must replace the values of the existed or default-set imported factors via properly designed experiments and/or modelling such as transport of liquid discharge in waters nearby the plants, exposure tests on corps and plants so on. 4 figs., 576 tabs. (Author)

  2. The magnitude and relevance of the February 2014 radiation release from the Waste Isolation Pilot Plant repository in New Mexico, USA

    Energy Technology Data Exchange (ETDEWEB)

    Thakur, P. [Carlsbad Environmental Monitoring & Research Center, 1400 University Drive, Carlsbad, NM, 88220 (United States); Lemons, B.G.; White, C.R. [AECOM, Carlsbad Operations, Carlsbad, NM, 88220 (United States)

    2016-09-15

    After almost fifteen years of successful waste disposal operations, the first unambiguous airborne radiation release from the Waste Isolation Pilot Plant (WIPP) was detected beyond the site boundary on February 14, 2014. It was the first accident of its kind in the 15-year operating history of the WIPP. The accident released moderate levels of radioactivity into the underground air. A small but measurable amount of radioactivity also escaped to the surface through the ventilation system and was detected above ground. The dominant radionuclides released were americium and plutonium, in a ratio consistent with the known content of a breached drum. The radiation release was caused by a runaway chemical reaction inside a transuranic (TRU) waste drum which experienced a seal and lid failure, spewing radioactive materials into the repository. According to source-term estimation, approximately 2 to 10 Ci of radioactivity was released from the breached drum into the underground, and an undetermined fraction of that source term became airborne, setting off an alarm and triggering the closure of seals designed to force exhausting air through a system of filters including high-efficiency-particulate-air (HEPA) filters. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment, if any. This article attempts to compile and interpret analytical data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and by a compliance-monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP), LLC., in response to the accident. Both the independent and the WIPP monitoring efforts concluded that the levels detected were very low and localized, and no radiation-related health effects among local workers or the public would be

  3. Measurements of plume geometry and argon-41 radiation field at the BR1 reactor in Mol, Belgium

    International Nuclear Information System (INIS)

    Drews, M.; Joergensen, H.; Lauritzen, Bent; Mikkelsen, T.; Aage, H.K.; Korsbech, U.; Bargholz, K.; Rojas-Palma, C.; Ammel, R. van

    2002-02-01

    An atmospheric dispersion experiment was conducted using a visible tracer along with the routine releases of 41 Ar from the BR1 air-cooled research reactor in Mol. In the experiment, simultaneous measurements of the radiation field from the 41 Ar decay, the meteorology, the 41 Ar source term and plume geometry were performed. The visible tracer was injected into the reactor emission stack, and the plume cross section determined by Lidar scanning of the released aerosols. The data collected in the exercise provide a valuable resource for atmospheric dispersion and dose rate modeling. (au)

  4. Pressure-sensitive release mechanism for radiosonde applications

    International Nuclear Information System (INIS)

    Kulhanek, F.C.

    1975-01-01

    As part of the 1975 planetary boundary layer field experimental program, miniature radiosondes attached to pilot balloons were released into the atmosphere for routine sampling of the vertical temperature distribution. A new releasing mechanism used to continue sampling during descent by parachute is described

  5. Regulatory supervision of the radiation protection and release during the dismantling of the German NPP Wuergassen

    International Nuclear Information System (INIS)

    Boerchers, F.; Hillberg, M.

    2003-01-01

    The NPP Wuergassen (KWW) is a commercial, single unit boiling water reactor with a capacity of 670 MW el . It was commissioned by PreussenElektra and constructed by AEG/KWU between 1968 and 1971. This NPP was finally shut down in 1994. The decommissioning, started in April 1997, is still under progress. Up to now, approx. 9,500 Mg of various materials (e.g. metal scrap, cable, concrete) have been deconstructed and released from the site. In this paper we describe the contribution from the authority and the independent expert during the radiological characterisation, the dismantling work, and the material flow up to the release. Special focus will be on the necessary control steps and the documentation regarding the dismantling work and the procedure of release. There is always a close fit between the radiation protection and the release of material on the basis of the radiological characterisation. (authors)

  6. Should the lateral chest radiograph be routinely performed?

    International Nuclear Information System (INIS)

    Osman, Fatuma; Williams, Imelda

    2014-01-01

    Background: The chest x-ray is one of the most common plain film radiographic examinations performed. Inclusion of the lateral chest radiograph varies internationally and nationally across radiology departments and states in Australia. Search strategy: A search strategy of the databases Cochrane Library, Ovid Medline/Medline, PubMed, Scopus and Science Direct was conducted. The results were restricted to those published between 1985 and 2013 and those published in English. The following search terms were used: ‘lateral chest’, ‘radiograph’, ‘digital radiography’, ‘chest x-ray’, ‘plain film radiography’, ‘ionising radiation’. The results were restricted to publications with these terms in the title, abstract and/or keywords. Main findings: There are few national or international guidelines pertaining to the inclusion of the lateral chest x-ray as routine. Primary concerns are the increased radiation dose associated with the additional chest view and reduction of medical imaging services cost. Modern digital imaging systems result in a lower radiation dose. The diagnostic yield of the lateral chest x-ray is highly dependent on the clinical indications of the patient. Further research into the routine inclusion of the lateral chest x-ray is recommended. Conclusion: Review of the literature suggests that the lateral chest radiograph should not be performed routinely unless clinically indicated

  7. PARMELA-B A new version of PARMELA with coherent synchrotron radiation effects and a finite difference space charge routine

    CERN Document Server

    Koltenbah, B E C; Greegor, R B; Dowell, D H

    2002-01-01

    Recent interest in advanced laser light sources has stimulated development of accelerator systems of intermediate beam energy, 100-200 MeV, and high charge, 1-10 nC, for high power FEL applications and high energy, 1-2 GeV, high charge, SASE-FEL applications. The current generation of beam transport codes which were developed for high-energy, low-charge beams with low self-fields are inadequate to address this energy and charge regime, and better computational tools are required to accurately calculate self-fields. To that end, we have developed a new version of PARMELA, named PARMELA_B and written in Fortran 95, which includes a coherent synchrotron radiation (CSR) routine and an improved, generalized space charge (SC) routine. An electron bunch is simulated by a collection of macro-particles, which traverses a series of beam line elements. At each time step through the calculation, the momentum of each particle is updated due to the presence of external and self- fields. The self-fields are due to CSR and S...

  8. Application of radiations to development of controlled release drugs and diagnostic drugs

    International Nuclear Information System (INIS)

    Yoshida, Masaru

    1990-01-01

    The report briefly outlines various biological materials developed by the author by means of chemical reactions and processing techniques using radiations. They include testosterone release materials for artificial spermary, controlled anticancer medicine release materials, in vivo degrading materials (parabolic, linear or S-shape degradation-time curve), functional particles with activated functional groups, targeting materials, substances for immunity diagnosis, and other 'intelligent' materials. Intelligent materials, like human organs, respond to specific stimuli from the external environment. Some components such as amino acids and nucleic acids are converted into acryloyl or methacryloyl derivatives to allow the material to show various functions. Methacryloyl-L-proline polymer in an aqueous system, for example, shows an reversible thermal response to changes in the water temperature, that is, swelling and shrinking at low and high temperature, respectively. The mechanism of the thermal response of its copolymer wiht hydroxypropylmethacrylate can be interpreted as resulting from the formation of a surface regulating layer. (N.K.)

  9. Duty health physicist program at Byron Nuclear Power Station - a cost-effective way to manage routine plant health physics activities

    International Nuclear Information System (INIS)

    Goldsmith, D.G.; Carey, T.R.

    1987-01-01

    The Duty Health Physicist Program at Byron Station was established to deal with routine health physics tasks and provide an interface between frontline and upper radiation-chemistry management. The program consists of a weekly rotation of selected members of the health physics staff into the duty health physicist position to handle the assigned duty tasks. The tasks include, but are not limited to, daily isotopic and air sample review, effluent release package review, maximum permissible concentration calculations, dose approvals, as-low-as-reasonably-achievable action review of pending jobs, and general availability to answer questions and address problems in health-physics-related areas of plant operation. The daily attendance of the duty health physicist at the radiation-chemistry and station plan-of-the-day meetings has increased the overall presence and visibility of the health physics program to upper station management and other station departments. Since its inception in July of 1985, the Duty Health Physics Program has been a major contributor to the observed 50% reduction in reportable personnel errors in the radiation-chemistry department

  10. Radiation shielding provided by residential houses in Japan in reactor accidents accompanied with atmospheric release

    International Nuclear Information System (INIS)

    Yamaguchi, Yasuhiro; Minami, Kentaro

    1991-01-01

    The present report describes the radiation shielding effect of houses in Japan against the radioactive cloud resulting from a major reactor accident accompanied with atmospheric release. The shielding factor of houses, the ratio of indoor exposure rate to outdoor one, has been studied for the semi-infinite and finite clouds which contain γ-emitting radionuclides released from a reactor facility. The shielding factor of houses against γ-rays from the radioactive cloud decreases gradually with release delay time and keeps a minimum during the period from 50 to 1000 hours after reactor shutdown while 133 Xe predominates in the cloud. Radioiodines mixed in the cloud raise slightly the shielding factor, and the factor depends little on the shape of the cloud. A set of shielding factors for the use of emergency planning was consequently proposed as 0.4 for simple ferroconcrete residential house and 0.9 for other ordinary ones. (author)

  11. Effect of radiofrequency radiation from Wi-Fi devices on mercury release from amalgam restorations.

    Science.gov (United States)

    Paknahad, Maryam; Mortazavi, S M J; Shahidi, Shoaleh; Mortazavi, Ghazal; Haghani, Masoud

    2016-01-01

    Dental amalgam is composed of approximately 50% elemental mercury. Despite concerns over the toxicity of mercury, amalgam is still the most widely used restorative material. Wi-Fi is a rapidly using local area wireless computer networking technology. To the best of our knowledge, this is the first study that evaluates the effect of exposure to Wi-Fi signals on mercury release from amalgam restorations. Standard class V cavities were prepared on the buccal surfaces of 20 non-carious extracted human premolars. The teeth were randomly divided into 2 groups (n = 10). The control group was stored in non-environment. The specimens in the experimental groups were exposed to a radiofrequency radiation emitted from standard Wi Fi devices at 2.4 GHz for 20 min. The distance between the Wi-Fi router and samples was 30 cm and the router was exchanging data with a laptop computer that was placed 20 m away from the router. The concentration of mercury in the artificial saliva in the groups was evaluated by using a cold-vapor atomic absorption Mercury Analyzer System. The independent t test was used to evaluate any significant differences in mercury release between the two groups. The mean (±SD) concentration of mercury in the artificial saliva of the Wi-Fi exposed teeth samples was 0.056 ± .025 mg/L, while it was only 0.026 ± .008 mg/L in the non-exposed control samples. This difference was statistically significant (P =0.009). Exposure of patients with amalgam restorations to radiofrequency radiation emitted from conventional Wi-Fi devices can increase mercury release from amalgam restorations.

  12. Cancer near the Three Mile Island nuclear plant: Radiation emissions

    International Nuclear Information System (INIS)

    Hatch, M.C.; Beyea, J.; Nieves, J.W.; Susser, M.

    1990-01-01

    As a public charge, cancers among the 159,684 residents living within a 10-mile (16-km) radius of the Three Mile Island nuclear plant were studied relative to releases of radiation during the March 28, 1979, accident as well as to routine plant emissions. The principal cancers considered were leukemia and childhood malignancies. Estimates of the emissions delivered to small geographic study tracts were derived from mathematical dispersion models which accounted for modifying factors such as wind and terrain; the model of accident emissions was validated by readings from off-site dosimeters. Incident cancers among area residents for the period 1975-1985 (n = 5,493) were identified by a review of the records at all local and regional hospitals; preaccident and postaccident trends in cancer rates were examined. For accident emissions, the authors failed to find definite effects of exposure on the cancer types and population subgroups thought to be most susceptible to radiation. No associations were seen for leukemia in adults or for childhood cancers as a group. For leukemia in children, the odds ratio was raised, but cases were few (n = 4), and the estimate was highly variable. Moreover, rates of childhood leukemia in the Three Mile Island area are low compared with national and regional rates. For exposure to routine emissions, the odds ratios were raised for childhood cancers as a whole and for childhood leukemia, but confidence intervals were wide and included 1.0. For leukemia in adults, there was a negative trend. Trends for two types of cancer ran counter to expectation. Non-Hodgkin's lymphoma showed raised risks relative to both accident and routine emissions; lung cancer (adjusted only indirectly for smoking) showed raised risks relative to accident emissions, routine emissions, and background gamma radiation

  13. Assessment of pediatrics radiation dose from routine x-ray ...

    African Journals Online (AJOL)

    Background: Given the fact that children are more sensitive to ionizing radiation than adults,with an increased risk of developing radiation-induced cancer,special care should be taken when they undergo X-ray examinations. The main aim of the current study was to determine Entrance Surface Dose (ESD) to pediatric ...

  14. Perspex in the verification routines for accelerator beam

    International Nuclear Information System (INIS)

    Paredes G, L.; Genis S, R.

    1998-01-01

    It is analyzed the use of a perspex solid phantom, adequately referred to a water phantom, as an auxiliary alternative for the daily stability verification routines or constance of radiation beam, as an option in the case of radiotherapy installations with high charge of accelerator working and with basic dosimetry equipment. (Author)

  15. PARMELA sub B a new version of PARMELA with coherent synchrotron radiation effects and a finite difference space charge routine

    CERN Document Server

    Koltenbah, B E C; Greegor, R B; Dowell, D H

    2002-01-01

    Recent interest in advanced laser light sources has stimulated development of accelerator systems of intermediate beam energy, 100-200 MeV, and high charge, 1-10 nC, for high power FEL applications and high energy, 1-2 GeV, high charge, SASE-FEL applications. The current generation of beam transport codes which were developed for high-energy, low-charge beams with low self-fields are inadequate to address this energy and charge regime, and better computational tools are required to accurately calculate self-fields. To that end, we have developed a new version of PARMELA, named PARMELA sub B and written in Fortran 95, which includes a coherent synchrotron radiation (CSR) routine and an improved, generalized space charge (SC) routine. An electron bunch is simulated by a collection of macro-particles, which traverses a series of beam line elements. At each time step through the calculation, the momentum of each particle is updated due to the presence of external and self-fields. The self-fields are due to CSR an...

  16. Synthesis and characterization of superabsorbent polymer prepared by radiation-induced graft copolymerization of acrylamide onto carboxymethyl cellulose for controlled release of agrochemicals

    International Nuclear Information System (INIS)

    Hemvichian, Kasinee; Chanthawong, Auraruk; Suwanmala, Phiriyatorn

    2014-01-01

    Superabsorbent polymer (SAP) was synthesized by radiation-induced grafting of acrylamide (AM) onto carboxymethyl cellulose (CMC) in the presence of a crosslinking agent, N,N′-methylenebisacrylamide (MBA). The effects of various parameters, such as dose, the amount of CMC, AM, MBA and ionic strength on the swelling ratio were investigated. In order to evaluate its controlled release potential, SAP was loaded with potassium nitrate (KNO 3 ) as an agrochemical model and its potential for controlled release of KNO 3 was studied. The amount of released KNO 3 was analyzed by an inductively coupled plasma mass spectrometry (ICP–MS). The results from controlled release experiment agreed very well with the results from swelling experiment. The synthesized SAP was characterized by Fourier transform infrared spectroscopy (FTIR) and thermogravimetric analysis (TGA). The obtained SAP exhibited a swelling ratio of 190 g/g of dry gel. - Highlights: • SAP was synthesized by radiation-induced grafting of AM onto CMC. • The synthesized SAP exhibited a maximum swelling ratio of 190 g/g. • The potential of SAP for controlled release of KNO 3 was studied. • The amount of KNO 3 released increased with increasing loading percentage of SAP. • SAP's swelling ratio decreased as the ionic strength of the medium increased

  17. Is radiation-induced ovarian failure in rhesus monkeys preventable by luteinizing hormone-releasing hormone agonists?: Preliminary observations

    International Nuclear Information System (INIS)

    Ataya, K.; Pydyn, E.; Ramahi-Ataya

    1995-01-01

    With the advent of cancer therapy, increasing numbers of cancer patients are achieving long term survival. Impaired ovarian function after radiation therapy has been reported in several studies. Some investigators have suggested that luteinizing hormone-releasing hormone agonists (LHRHa) can prevent radiation-induced ovarian injury in rodents. Adult female rhesus monkeys were given either vehicle or Leuprolide acetate before, during, and after radiation. Radiation was given in a dose of 200 rads/day for a total of 4000 rads to the ovaries. Frequent serum samples were assayed for estradiol (E 2 ) and FSH. Ovariectomy was performed later. Ovaries were processed and serially sectioned. Follicle count and size distribution were determined. Shortly after radiation started, E 2 dropped to low levels, at which it remained, whereas serum FSH level, which was low before radiation, rose soon after starting radiation. In monkeys treated with a combination of LHRHa and radiation, FSH started rising soon after the LHRHa-loaded minipump was removed (after the end of radiation). Serum E 2 increased after the end of LHRHa treatment in the non-irradiated monkey, but not in the irradiated monkey. Follicle counts were not preserved in the LHRHa-treated monkeys that received radiation. The data demonstrated no protective effect of LHRHa treatment against radiation-induced ovarian injury in this rhesus monkey model. 58 refs., 2 figs., 1 tab

  18. Impacts of uranium-utilization improvements on light-water-reactor radionuclide releases

    International Nuclear Information System (INIS)

    Aaberg, R.L.

    1981-08-01

    This report discusses potential changes to radionuclide releases as a result of uranium-saving plant modifications and altered operating practices. Only releases to the environment from routine operation are considered; releases resulting from abnormal conditions outside the technical specifications covering plant operation are not considered

  19. Gamma-H2AX biodosimetry for use in large scale radiation incidents: comparison of a rapid ‘96 well lyse/fix’ protocol with a routine method

    Directory of Open Access Journals (Sweden)

    Jayne Moquet

    2014-03-01

    Full Text Available Following a radiation incident, preliminary dose estimates made by γ-H2AX foci analysis can supplement the early triage of casualties based on clinical symptoms. Sample processing time is important when many individuals need to be rapidly assessed. A protocol was therefore developed for high sample throughput that requires less than 0.1 ml blood, thus potentially enabling finger prick sampling. The technique combines red blood cell lysis and leukocyte fixation in one step on a 96 well plate, in contrast to the routine protocol, where lymphocytes in larger blood volumes are typically separated by Ficoll density gradient centrifugation with subsequent washing and fixation steps. The rapid ‘96 well lyse/fix’ method reduced the estimated sample processing time for 96 samples to about 4 h compared to 15 h using the routine protocol. However, scoring 20 cells in 96 samples prepared by the rapid protocol took longer than for the routine method (3.1 versus 1.5 h at zero dose; 7.0 versus 6.1 h for irradiated samples. Similar foci yields were scored for both protocols and consistent dose estimates were obtained for samples exposed to 0, 0.2, 0.6, 1.1, 1.2, 2.1 and 4.3 Gy of 250 kVp X-rays at 0.5 Gy/min and incubated for 2 h. Linear regression coefficients were 0.87 ± 0.06 (R2 = 97.6% and 0.85 ± 0.05 (R2 = 98.3% for estimated versus actual doses for the routine and lyse/fix method, respectively. The lyse/fix protocol can therefore facilitate high throughput processing for γ-H2AX biodosimetry for use in large scale radiation incidents, at the cost of somewhat longer foci scoring times.

  20. Performance test of dosimetric services in the EU member states and Switzerland for the routine assessment of individual doses (photon, beta and neutron)

    DEFF Research Database (Denmark)

    Bordy, J.M.; Stadtmann, H.; Ambrosi, P.

    2000-01-01

    of the dosimetry of routine services. It was assumed that each service would have already done a type test before performing routine dosimetry: the radiation fields were chosen to simulate, as far as possible, workplace radiation fields by mixing combining energies and incident angles. The results of photon...... for External Radiation. The other two papers are included in this issue of Radiation Protection Dosimetry....

  1. Measurement of ionizing radiations for the orthodontics diagnosis

    International Nuclear Information System (INIS)

    Serrano Rivas, Karla; Coste Murillo, Pedro; Gatica Arias, Gabriela; Rodriguez Alfaro, Keilor; Shedden Rojas, Carol; Viquez Nunez, Laura; Zuniga Leon, Jessica

    2005-01-01

    The amount of radiation which is subjected a child during the taking of x-rays of routine for the orthodontics diagnosis is analyzed. The study was made to 26 children (men and women) between 7 and 13 years of age with healthy teething. During the taking of different radiographs a thermoluminescent crystal of lithium fluoride was positioned beforehand in the place of entrance of the ray. Itself proceeded to read the crystals in the Laboratorio de Fisica Nuclear de la Universidad de Costa Rica. Later the comparisons with the standards already established at worldwide level were made. As main conclusions obtained are that taboo in existence at present on x-rays do not include ionizing radiations for the orthodontics use and that the anterior-posterior radiographs are those that release more photons followed of the cephalometric radiography. (author) [es

  2. An investigation of fission models for high-energy radiation transport calculations

    International Nuclear Information System (INIS)

    Armstrong, T.W.; Cloth, P.; Filges, D.; Neef, R.D.

    1983-07-01

    An investigation of high-energy fission models for use in the HETC code has been made. The validation work has been directed checking the accuracy of the high-energy radiation transport computer code HETC to investigate the appropriate model for routine calculations, particularly for spallation neutron source applications. Model calculations are given in terms of neutron production, fission fragment energy release, and residual nuclei production for high-energy protons incident on thin uranium targets. The effect of the fission models on neutron production from thick uranium targets is also shown. (orig.)

  3. Effluent release limits, sources and control

    International Nuclear Information System (INIS)

    Swindell, G.E.

    1977-01-01

    Objectives of radiation protection in relation to releases. Environmental transfer models for radionuclides. Relationship between releases, environmental levels and doses to persons. Establishment of release limits: Limits based on critical population group concept critical pathway analysis and identification of critical group. Limits based on optimization of radiation protection individual dose limits, collective doses and dose commitments 1) differential cost benefit analysis 2) authorized and operational limits taking account of future exposures. Monitoring of releases to the environment: Objectives of effluent monitoring. Typical sources and composition of effluents; design and operation of monitoring programmes; recording and reporting of monitoring results; complementary environmental monitoring. (orig.) [de

  4. Influence of the rate of conversion of HT and HTO on projected radiation doses from release of molecular tritium

    International Nuclear Information System (INIS)

    Jacobs, D.G.; Easterly, C.E.; Phillips, J.E.

    1979-01-01

    Releases of tritium in the past have been largely in the form of tritiated water, and the projected radiation doses could be estimated by assuming tritium behaviour to parallel that of water. There is increasing interest in potential releases of tritium in the form of HT because of significant recent advances in fusion reactor research. Several recent studies have shown that bacteria containing the enzyme hydrogenase can catalyse the conversion of HT to HTO at rates several orders of magnitude faster than the rates measured in atmospheric systems. Rates of conversion in the soil have been combined with estimates of rates of permeation of HT into the soil and with global and local models depicting tritium transport and cycling. The results suggest that for the expected conversion rates, the impact on projected radiation doses should be relatively minor. (author)

  5. Non-routine activities in RP Group in 1998

    International Nuclear Information System (INIS)

    Hoefert, M.; Foerkel-Wirth, D.; Otto, T.; Silari, M.; Stevenson, G.R.

    1999-01-01

    This chapter describes activities not directly concerned with the daily routine. These activities are nevertheless an important part of the Group's work as they encompass new projects and developments that require, in most cases, profound studies to prove their feasibility with respect to the radiation protection issues involved. In addition, there are technical and organizational developments in a quest not only to keep the standard of radiation protection at CERN high, but to ensure its constant improvement. All these activities are documented in Divisional Reports, Internal Reports and Technical Memoranda, and are listed in the tables of this chapter

  6. SU-F-19A-08: Optimal Time Release Schedule of In-Situ Drug Release During Permanent Prostate Brachytherapy

    International Nuclear Information System (INIS)

    Cormack, R; Ngwa, W; Makrigiorgos, G; Tangutoori, S; Rajiv, K; Sridhar, S

    2014-01-01

    Purpose: Permanent prostate brachytherapy spacers can be used to deliver sustained doses of radiosentitizing drug directly to the target, in order to enhance the radiation effect. Implantable nanoplatforms for chemo-radiation therapy (INCeRTs) have a maximum drug capacity and can be engineered to control the drug release schedule. The optimal schedule for sensitization during continuous low dose rate irradiation is unknown. This work studies the optimal release schedule of drug for both traditional sensitizers, and those that work by suppressing DNA repair processes. Methods: Six brachytherapy treatment plans were used to model the anatomy, implant geometry and calculate the spatial distribution of radiation dose and drug concentrations for a range of drug diffusion parameters. Three state partial differential equations (cells healthy, damaged or dead) modeled the effect of continuous radiation (radiosensitivities α,β) and cellular repair (time tr) on a cell population. Radiosensitization was modeled as concentration dependent change in α,β or tr which with variable duration under the constraint of fixed total drug release. Average cell kill was used to measure effectiveness. Sensitization by means of both enhanced damage and reduced repair were studied. Results: Optimal release duration is dependent on the concentration of radiosensitizer compared to the saturation concentration (csat) above which additional sensitization does not occur. Long duration drug release when enhancing α or β maximizes cell death when drug concentrations are generally over csat. Short term release is optimal for concentrations below saturation. Sensitization by suppressing repair has a similar though less distinct trend that is more affected by the radiation dose distribution. Conclusion: Models of sustained local radiosensitization show potential to increase the effectiveness of radiation in permanent prostate brachytherapy. INCeRTs with high drug capacity produce the greatest

  7. Evaluating the radiation environment around a nuclear power station with unmonitored radionuclide release

    International Nuclear Information System (INIS)

    Bondarev, A.A.; Dibobes, I.K.; Pyuskyulan, K.I.

    1986-01-01

    This paper describes the radiation monitoring system at (RMS) at the Armenian nuclear power station; the environmental monitoring program includes measuring the gamma radiation around the station, determining radionuclide contents in air and fallout, and also in surface water and ground water, in water plants and bottom sediments, in soil and plants and also in local agricultural products. The RMS monitors gas-aerosol releases and effluents from the station. The radius of the monitored zone is 25 km. The gamma radiation is measured by IKS dosemeters and SRP-68-01 portable instruments. The air is monitored by six stationary aspriation systems at distances of 1, 5, 6, 11, 14, 15 and 50 km and 28 planchette cells. The RMS records virtually all the mean monthly and mean annual fluctuations in the global background. In seven years of operation at the Armenian station, only Ca 137 and Sr 90 from global fallout together with Be 7 of cosmogenic origin have been observed in air apart from two cases. In 1981, air samples taken with the aspirators and combined over a quarter showed Ce 141, Ce 144, Ru 106, Ru 103, Nb 95 and Zr 95. The concentrations of these are presented

  8. User's guide to GASPAR code (a computer program for calculating radiation exposure to man from routine air releases of nuclear reactor effluents). Technical report

    International Nuclear Information System (INIS)

    Eckerman, K.F.; Congel, F.J.; Roecklein, A.K.; Pasciak, W.J.

    1980-06-01

    The document is a user's guide for the GASPAR code, a computer program written for the evaluation of radiological impacts due to the release of radioactive material to the atmosphere during normal operation of light water reactors. The GASPAR code implements the radiological impact models of NRC Regulatory Guide 1.109, Revision 1, for atmospheric releases. The code is currently used by NRC in reactor licensing evaluations to estimate (1) the collective or population dose to the population within a 50-mile radius of a facility, (2) the total collective dose to the U.S. population, and (3) the maximum individual doses at selected locations in the vicinity of the plant

  9. Preparation of microspheres for slow release drug by radiation-induced suspension polymerization and their properties

    International Nuclear Information System (INIS)

    Yoshida, Masaru; Asano, Masaharu; Kaetsu, Isao

    1982-01-01

    The polymer microspheres containing drugs as drug delivery system were made by means of suspension-polymerization by radiation at low temperature by using glass-forming monomers which have stable supercooling properties and large polymerizability at low temperature. The particle distribution depended on the kind of monomer. It was found that the entrapping yield of drug in polymer microspheres increased with increasing viscosity of monomer and that the maximum value on the particle size distribution curve was also shifted to large particle diameter side. In the case of trimethylolpropane trimethacrylate monomer (43 cps), TMPT, the entrapping yield of drug reached 74% and the maximum value in particle size distribution curve appeared in the neighborhood of 105 to 210 mu m ranges. On the other hand, those values in neopentyl glycol dimethacrylate monomer (4 cps) were 12% in former and 44 -- 105 mu m in the latter. The release phenomenon of drugs from polymer microspheres was investigated. for example, the cumulative amount of mitomycin C (water soluble drug) released from TMPT polymer microsphere was about 90% after 30-day dissolution, while in the case of water-insoluble drug such as testosterone the amount of release was about 49% after 40-day dissolution. In all cases, the release rate is constant during the experimental period. Therefore, it was concluded that the release of drugs from polymer microspheres obtained in this study is possible over the long periods. (author)

  10. Environmental radiation monitoring on the CERN sites during 1995

    International Nuclear Information System (INIS)

    Moritz, L.; Wittekind, D.

    1996-01-01

    The CERN environmental monitoring programme covers the Meyrin and Prevessin sites, the six isolated islands (BA1, BA2, BA3, BA4, BA5, BA6) along the SPS Main Ring, the neutrino cave (BA7), and the seven surface areas PA2-PA8 specific to LEP. The results of the routine environmental monitoring programme enable CERN's compliance with national regulations of the host states and CERN's own Radiation Protection Policy to be assessed. Part I of this Annual Report describes the results of measurements which are relevant for assessing the radiological impact of CERN operations on the environment and the population living in the vicinity of the CERN sites. Measurements of radioactivity released into the atmosphere and into water, as well as measurements of stray radiation at or near the CERN site boundaries are reported

  11. Evaluation of radiological releases from the Tomsk-7 accident

    Energy Technology Data Exchange (ETDEWEB)

    Lussie, W.G.

    1995-10-01

    On April 6, 1993, there was an uncontrolled release of radioactive material from the fuel reprocessing plant at the Siberian Chemical Combine in Tomsk. The release resulted from the rupture of an over-pressurized feed adjustment tank and subsequent explosion that destroyed the walls and roof of the operating gallery. Radioactive material was released through a 150 meter stack, as well as through the destroyed walls and roof. Relatively stable atmospheric conditions prevailed and a light snow was falling. The radiation release was not excessive, but the spread of radioactive material was compounded by the explosion. Radiation was detected about 26 km from the source. This paper summarizes the information available in the US regarding the release and, using reasonable assumptions, compares the calculated ground activity and radiation levels with the reported measured values.

  12. Evaluation of radiological releases from the Tomsk-7 accident

    International Nuclear Information System (INIS)

    Lussie, W.G.

    1995-01-01

    On April 6, 1993, there was an uncontrolled release of radioactive material from the fuel reprocessing plant at the Siberian Chemical Combine in Tomsk. The release resulted from the rupture of an over-pressurized feed adjustment tank and subsequent explosion that destroyed the walls and roof of the operating gallery. Radioactive material was released through a 150 meter stack, as well as through the destroyed walls and roof. Relatively stable atmospheric conditions prevailed and a light snow was falling. The radiation release was not excessive, but the spread of radioactive material was compounded by the explosion. Radiation was detected about 26 km from the source. This paper summarizes the information available in the US regarding the release and, using reasonable assumptions, compares the calculated ground activity and radiation levels with the reported measured values

  13. Assessment of patient radiation doses during routine diagnostic radiography examinations

    International Nuclear Information System (INIS)

    Adam, Asim Karam Aldden Adam

    2015-11-01

    Medical applications of radiation represent the largest source of exposure to general population. Accounting for 3.0 mSv against an estimated 2.4 mSv from a natural back ground in United States. The association of ionizing radiation an cancer risk is assumed to be continuos and graded over the entire range of exposure, The objective of this study is to evaluate the patient radiation doses in radiology departments in Khartoum state. A total of 840 patients ? during two in the following hospitals Khartoum Teaching Hospital (260 patients), Fedail specialized hospital ( 261 patients). National Ribat University hospital ( 189 patients) and Engaz hospital (130 patients). Patient doses were measured for 9 procedures. The Entrance surface Air Kerma (ESAK) was quantified using x-ray unit output by Unifiers xi dose rate meter( Un fore inc. Billdal. Sweden) and patient exposure parameters. The mean patient age. Weight and Body Mass index (BMI) were 42.6 year 58/4 kg and 212 kg/m respectively. The mean patient doses, kv and MAS and E.q was 0.35 mGy per procedures 59.9 volt 19.8 Ampere per second 0.32 Sv . Patient doses were comparable with previous studies. Patient radiation doses showed considerable difference between hospitals due to x- ray systems exposure settings and patient weight. Patient are exposed to unnecessary radiation.(Author)

  14. In vivo release of FT-207 from irradiation polymerized composites

    International Nuclear Information System (INIS)

    Xie Huaijiang; Kou Qinghe; Song Juzhong; Peng Tao; Chen Xiaohui; Zhang Dexi

    1999-01-01

    Polymer-drugs composite with long periods of controlled slow release was made by radiation induced polymerization in room temperature. In experiment in vivo, the composite was implanted subcutaneously the back of rabbits. The concentration of 1-(2-tetrahydrofuryl)-5-fluorouracil (FT-207) was determined by HPLC. The results of test showed that the concentration of serum drug is 1.0 μg/mL after 1 week in the polymer-drug composites group. The drug concentration of tissue surrounding the composites is 76.2 +- 10.4 μg/mL. The drug concentration in the far organ (e.g.the lung 1.2 +- 0.5 μg/mL) is lower than the tissue surrounding the composite. The serum drug is higher and shorter time by the routine methods. The serum concentration of FT-207 is lower an retarded by implanted

  15. Master schedule for CY-1982 Hanford environmental surveillance routine program

    International Nuclear Information System (INIS)

    Blumer, P.J.; Sula, M.J.; Eddy, P.A.

    1981-12-01

    This report provides the current schedule of data collection for the routine environmental surveillance program at the Hanford Site. The environmental surveillance program objectives are to evaluate and report the levels of radioactive and nonradioactive pollutants in the Hanford environs, as required in DOE Order 5484.1. The routine sampling schedule provided does not include samples which are planned to be collected during FY-1982 in support of special studies or for quality control purposes. In addition, the routine program outlined in this schedule is subject to modification during the year in response to changes in Site operations, program requirements, or unusual sample results. Sampling schedules are presented for the following: air; Columbia River; sanitary water; surface water; ground water; foodstuffs; wildlife; soil and vegetation; external radiation measurements; portable instrument surveys; and surveillance of waste disposal sites

  16. Effect of growth hormone-releasing factor on growth hormone release in children with radiation-induced growth hormone deficiency

    International Nuclear Information System (INIS)

    Lustig, R.H.; Schriock, E.A.; Kaplan, S.L.; Grumbach, M.M.

    1985-01-01

    Five male children who received cranial irradiation for extrahypothalamic intracranial neoplasms or leukemia and subsequently developed severe growth hormone (GH) deficiency were challenged with synthetic growth hormone-releasing factor (GRF-44), in an attempt to distinguish hypothalamic from pituitary dysfunction as a cause of their GH deficiency, and to assess the readily releasable GH reserve in the pituitary. In response to a pulse of GRF-44 (5 micrograms/kg intravenously), mean peak GH levels rose to values higher than those evoked by the pharmacologic agents L-dopa or arginine (6.4 +/- 1.3 ng/mL v 1.5 +/- 0.4 ng/mL, P less than .05). The peak GH value occurred at a mean of 26.0 minutes after administration of GRF-44. These responses were similar to those obtained in children with severe GH deficiency due to other etiologies (peak GH 6.3 +/- 1.7 ng/mL, mean 28.0 minutes). In addition, there was a trend toward an inverse relationship between peak GH response to GRF-44 and the postirradiation interval. Prolactin and somatomedin-C levels did not change significantly after the administration of a single dose of GRF-44. The results of this study support the hypothesis that cranial irradiation in children can lead to hypothalamic GRF deficiency secondary to radiation injury of hypothalamic GRF-secreting neurons. This study also lends support to the potential therapeutic usefulness of GRF-44 or an analog for GH deficiency secondary to cranial irradiation

  17. Savannah River Site Ingestion Pathway Methodology Manual for Airborne Radioactive Releases

    Energy Technology Data Exchange (ETDEWEB)

    Vincent, A.W. III

    2001-01-03

    This manual documents a recommended methodology for determining the ingestion pathway consequences of hypothetical accidental airborne radiological releases from facilities at the Savannah River Site. Both particulate and tritiated radioactive contaminants are addressed. Other approaches should be applied for evaluation of routine releases.

  18. Radiation doses due to natural radon gas releases from the final disposal facility of spent fuel

    International Nuclear Information System (INIS)

    Vesterbacka, K.; Arvela, H.

    1998-03-01

    Building an underground repository for the spent nuclear fuel increases releases of natural radon gas. In the report the radon releases, the resulting doses as well as the radon concentration in the repository air are investigated. There are four optional building locations for the underground repository and three different strategies of construction. Optional sites are Olkiluoto of Eurajoki, Romuvaara of Kuhmo, Haestholmen of Loviisa and Kivetty of Aeaenekoski. The most significant radon sources in the underground repository are the rockwalls and the groundwater leaking to the repository. High groundwater radon concentrations can increase significantly radon concentration in the repository air despite the groundwater leak rate is low. The radon source strength from the rockwalls, groundwater and macadam spreaded on the floor of the repository is estimated in this report. Using these results the radon concentration in the repository is calculated for several air exchange rates. Data from petrological studies performed at the optional building sites as well as the measurement data of the Radiation and Nuclear Safety Authority has been utilized. Rough approximations were needed when estimating the radon source strength. The estimated total radon source strength varies between 1 - 600 MBq/h depending on the repository construction strategy. Repository indoor air radon concentration with no air exchange varies between 0,7 - 120 kBq/m 3 . Using the most probable estimates on radon source strength, the allowed indoor radon concentration of 400 Bq/m 3 at workplaces is achieved by using the air exchange rate of 0,5 l/h in every optional repository. Repository exhaust air and the pile of macadam increases the radon levels in the environment. The radiation dose to the critical person depends on the open volume of the repository. The annual radiation dose calculated from the most probable radon source strength at the distance of 500 metres is below 0,005 mSv at all sites

  19. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, H.D.; Lee, Y.B.; Lee, W.Y.; Park, D.W.; Chung, B.G.

    1980-01-01

    For the KAERI site, various environmental samples were collected three times a month, and the natural environmental radiation levels were also measured at each sampling point. Measurements for gross alpha and beta radioactivities of the samples were routinely measured for all samples. Strontium-90 concentrations were also analysed for the fallout and air samples collected daily basis on the roof of the main building. Accumulated exposure including the possibility of determination of low level environmental radiation field by employing thermoluminescent dosimeter, CaSO 4 : Dsub(y)-0.4 teflon disc type, at 6 posts in on-site of the KAERI. As for Kori site, at 19 points of ON, OFF-site, and at the same time the environmental radiation exposure rate at each sampling point were measured. Several environmental samples such as surface soil, pine needles, water samples, milk sample and pasture samples were collected and analysed on a quarterly basis. As a result of the survey it can be said that no significant release of radiation to the environment due to the operations of nuclear facilities including research reactor at the KAERI and power reactor at the Kori has been found during the period of the survey and monitoring. (author)

  20. Biological in situ Dose Painting for Image-Guided Radiation Therapy Using Drug-Loaded Implantable Devices

    International Nuclear Information System (INIS)

    Cormack, Robert A.; Sridhar, Srinivas; Suh, W. Warren; D'Amico, Anthony V.; Makrigiorgos, G. Mike

    2010-01-01

    Purpose: Implantable devices routinely used for increasing spatial accuracy in modern image-guided radiation treatments (IGRT), such as fiducials or brachytherapy spacers, encompass the potential for in situ release of biologically active drugs, providing an opportunity to enhance the therapeutic ratio. We model this new approach for two types of treatment. Methods and Materials: Radiopaque fiducials used in IGRT, or prostate brachytherapy spacers ('eluters'), were assumed to be loaded with radiosensitizer for in situ drug slow release. An analytic function describing the concentration of radiosensitizer versus distance from eluters, depending on diffusion-elimination properties of the drug in tissue, was developed. Tumor coverage by the drug was modeled for tumors typical of lung stereotactic body radiation therapy treatments for various eluter dimensions and drug properties. Six prostate 125 I brachytherapy cases were analyzed by assuming implantation of drug-loaded spacers. Radiosensitizer-induced subvolume boost was simulated from which biologically effective doses for typical radiosensitizers were calculated in one example. Results: Drug distributions from three-dimensional arrangements of drug eluters versus eluter size and drug properties were tabulated. Four radiosensitizer-loaded fiducials provide adequate radiosensitization for ∼4-cm-diameter lung tumors, thus potentially boosting biologically equivalent doses in centrally located stereotactic body treated lesions. Similarly, multiple drug-loaded spacers provide prostate brachytherapy with flexible shaping of 'biologically equivalent doses' to fit requirements difficult to meet by using radiation alone, e.g., boosting a high-risk region juxtaposed to the urethra while respecting normal tissue tolerance of both the urethra and the rectum. Conclusions: Drug loading of implantable devices routinely used in IGRT provides new opportunities for therapy modulation via biological in situ dose painting.

  1. Determination of radiation doses caused by release into the atmosphere by nuclear power plants, based on measurement of emission and immission

    International Nuclear Information System (INIS)

    Ekler, B.; Deme, S.

    2006-01-01

    The radiation impact of nuclear facilities, and the nuclear power plants as well, can be determined by using two methods. The first one calculates the dose of critical group of population based on the release, meteorological and hydrological parameters. The second method gives an estimate of the additional dose caused by the nuclear facility from the radiological measurements in the environment. This article compares this two methods for the release in the atmosphere, and gives an estimate of the relative error. The comparison can be applied for cases when the atmospheric pollution is released from a point type source, so for the conventional power plants as well. (author)

  2. Impact assessment of radionuclides released to environment from the European Spallation Source

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, S.; Andersson, K. [Technical University of Denmark (Denmark); Ene, D. [European Spallation Soure AB - ESS, Lund (Sweden)

    2014-07-01

    The European Spallation Source (ESS) is a large science and technology infrastructure project currently under construction in Lund, Sweden, with operation planned by 2019. The facility design and construction includes a linear proton accelerator, a heavy-metal target station, neutron instruments, laboratories, and a data management and software development centre. During operation the ESS will produce a wide range of radionuclides via spallation and activation processes. Radiological assessments are needed to ensure that operational discharges and releases from potential incidents/accidents are within acceptable limits. The spectrum of radionuclides produced at ESS is quite different from that produced in nuclear power plants and assessment work has therefore been challenged by lack of information on less well-known radionuclides. Traditional assessment methodologies have been applied focusing on releases to air and public sewer systems and calculating radiation doses to representative persons living in and near Lund close to the ESS site. Exposure pathways considered include external radiation from radionuclides in air, external radiation from radionuclides deposited on ground and skin, inhalation of radionuclides and ingestion of locally produced contaminated food. Atmospheric dispersion has been simulated with the Gaussian plume model which is considered adequate within a few kilometres. Effects of release height have been investigated and site specific values of other parameters such as wind speed, wind direction, rain fall etc. have been used. Contamination of food has been calculated from the (ECOSYS) food dose model used in the RODOS and ARGOS decision support systems. The food dose model does not contain specific data for a number of ESS relevant radionuclides, e.g. {sup 7}Be, {sup 32}P and {sup 35}S. The data required include mobility of these isotopes, soil-to-plant concentration ratios and equilibrium transfer factors of daily intake by ingestion of meat

  3. Radiation preparation of drug carriers based on poly(N-isopropylacrylamide) hydrogels, their loading capacities and controlled release rates for dexamethasone and tegafur

    International Nuclear Information System (INIS)

    Hoang Dang Sang; Nguyen Van Binh; Tran Bang Diep; Nguyen Thi Thom; Hoang Phuong Thao; Pham Duy Duong; Tran Minh Quynh

    2015-01-01

    Thermo-sensitive hydrogels have great potential in some applications. In order to use as the drug delivery systems, the hydrogels should be biocompatibility. New polymers with more biocompatibility and better biodegradability, and environmental friendly crosslinking agents would be necessary for the successful drug carriers. Poly (N-isopropylacrylamide-co-dimethylacrylamide) based hydrogels have been prepared from the admixture solutions of N-isopropylacrylamide (NIPA) and N,N’-dimethyl acrylamide (DMA) by radiation copolymerization and crosslinking at radiation dose of 20 kGy as reported in our previous study. Water swelling behaviour of the resulting hydrogels were much depended on their nature such as initial ratio of NIPA and DMA. The drug-loaded hydrogels were prepared by merging hydrogel in the solutions containing corresponding drugs. Loading capacity of the hydrogels were about 48.6 and 95.7 mg per g dried hydrogel for dexamethasone and tegafur. The release studies showed that the presence of ions in simulated body fluid and temperature of the solution much affecting to in vitro release behaviors of hydrogels for dexamethasone and tegafur. The release rates were fast for both drug models. The result also revealed that these drug carriers were biocompatibility without skin irritation, suggested the drug-loaded hydrogels may be used as controlled release drug delivery systems. (author)

  4. Compilation of documented computer codes applicable to environmental assessment of radioactivity releases

    International Nuclear Information System (INIS)

    Hoffman, F.O.; Miller, C.W.; Shaeffer, D.L.; Garten, C.T. Jr.; Shor, R.W.; Ensminger, J.T.

    1977-04-01

    The objective of this paper is to present a compilation of computer codes for the assessment of accidental or routine releases of radioactivity to the environment from nuclear power facilities. The capabilities of 83 computer codes in the areas of environmental transport and radiation dosimetry are summarized in tabular form. This preliminary analysis clearly indicates that the initial efforts in assessment methodology development have concentrated on atmospheric dispersion, external dosimetry, and internal dosimetry via inhalation. The incorporation of terrestrial and aquatic food chain pathways has been a more recent development and reflects the current requirements of environmental legislation and the needs of regulatory agencies. The characteristics of the conceptual models employed by these codes are reviewed. The appendixes include abstracts of the codes and indexes by author, key words, publication description, and title

  5. Microcapsular imaging of malignant tumors and radiation induced release of liquid-core microcapsules for their treatment

    International Nuclear Information System (INIS)

    Harada, S.; Ehara, S.; Ishii, K.; Sato, T.; Enatsu, M.; Kamiya, T.; Sera, K.; Goto, S.

    2013-01-01

    Full text: Purpose: Basing on the study of PIXE and Micro PIXE camera, microcapsules of 2 types were designed: (1) CT detectable anti-αvβ3 (E[c(RGDfK)] 2 , microcapsules containing P-selectin and P-selectin glycoprotein ligand-1 (PSGL-1) to observe malignant tumors via αvβ3-antigen-antibody accumulation, and (2) malignant tumors-treating microcapsules that release anticancer drug on irradiation and have a high affinity to P-selectin. To test the ability of these microcapsules for imaging malignant tumors and for treating them, we subject C3He/N mice with MM48 tumor to 2 radiotherapy sessions. Methods and Materials: For the first session, microcapsules were prepared by spraying a mixture of 4.0% alginate, 3.0% hyaluronic acid, and 1 μg E[c(RGDfK)] 2 , (αvβ3 antibody) into 0.5 mmol FeCI 2 , supplemented with 1 μg P-selectin. Microcapsules for the second session were produced by spraying the above-mentioned mixture with 5mg carboplatin into 0.5 mol/L FeCI 2 , containing 0.1 μmol/L of PSGL-1 and the FcSv antibody against P-selectin [1]. In the first session, the microcapsules were intravenously injected, and 6 h later, the incipient metastatic foci were observed using CT. Subsequently, a 10- or 20-Gy 60 Co γ-radiation dose was administered. In the second session, 1 x 10 10 microcapsules were intravenously injected 1 h before P-selectin expression peaked; the microcapsules were allowed to interact with P-selectin for 1-6 h after irradiation in order to deliver sufficient microcapsules. The second session was conducted in a similar manner to the first. The releasing of P-selectin or carboplatin were imaged using micro PIXE camera. The amount of carboplatin (Pt containing anticancer drug) were quantified, using PIXE. Results. The capsule and liquid core sizes (φ) were 2.3 ± 0.92 m and 1.6 ± 0.6 m, respectively. The injected anti-αvβ3 E[c(RGDfK)] 2 , microcapsules accumulated in the vascular endothelium of the incipient metastasis, and their kinetics and

  6. Comparison of two oestrus synchronisation protocols administered to dairy cows during routine reproduction services

    DEFF Research Database (Denmark)

    Viora, L; Denwood, M; Ellis, K

    2015-01-01

    Progesterone-based oestrus synchronisation protocols are frequently used for treatment of cows presented for examination during routine reproduction management service. This study aimed to evaluate the effect of the addition of gonadotrophin-releasing hormone (GnRH) at the start of a progesterone......-based oestrus synchronisation protocol for cows presented for examination during routine veterinary service on a commercial dairy farm over 10 months. Overall 139 animals were retained in the study, of which 78 received a standard progesterone-based treatment (STD) and 61 received the same treatment...

  7. Environmental radiation monitoring results for the period 1984-95 in and around Variable Energy Cyclotron Centre, Calcutta

    International Nuclear Information System (INIS)

    Basu, A.S.; Khasnabis, B.K.; Bar, M.

    1997-04-01

    Variable Energy Cyclotron (VEC) located at Bidhan Nagar, Calcutta is being used for accelerating charged particles and does not contribute to any radioactive releases to the environment. However, it being a nuclear facility, the area surrounding the facility is being routinely monitored for background radiation exposure using thermoluminescent dosimeters. This report gives the summary of the results of the survey carried out over a period of 12 years, 1984-1995. It is observed that the general radiation background in areas far removed from the facility (up to 25 km) is higher than that existing within the boundaries of VEC centre (160±21 mR/year as against 121±20 mR/year)

  8. Hybrid emergency radiation detection: a wireless sensor network application for consequence management of a radiological release

    Science.gov (United States)

    Kyker, Ronald D.; Berry, Nina; Stark, Doug; Nachtigal, Noel; Kershaw, Chris

    2004-08-01

    The Hybrid Emergency Radiation Detection (HERD) system is a rapidly deployable ad-hoc wireless sensor network for monitoring the radiation hazard associated with a radiation release. The system is designed for low power, small size, low cost, and rapid deployment in order to provide early notification and minimize exposure. The many design tradeoffs, decisions, and challenges in the implementation of this wireless sensor network design will be presented and compared to the commercial systems available. Our research in a scaleable modular architectural highlights the need and implementation of a system level approach that provides flexibility and adaptability for a variety of applications. This approach seeks to minimize power, provide mission specific specialization, and provide the capability to upgrade the system with the most recent technology advancements by encapsulation and modularity. The implementation of a low power, widely available Real Time Operating System (RTOS) for multitasking with an improvement in code maintenance, portability, and reuse will be presented. Finally future design enhancements technology trends affecting wireless sensor networks will be presented.

  9. Acute radiation effects on the content and release of plasminogen activator activity in cultured aortic endothelial cells

    International Nuclear Information System (INIS)

    Ts'ao, C.H.; Ward, W.F.

    1985-01-01

    Confluent monolayers from three lines of bovine aortic endothelial cells were exposed to a single dose of 10 Gy of 60 Co γ rays. Seventy-two hours later, the morphology of the irradiated and sham-irradiated monolayers was examined, and cellular DNA and protein contents were determined. In addition, the release of plasminogen activator (PA) activity into the culture media and PA activity in the cell lysates were assayed. DNA and protein contents in the irradiated monolayers were reduced to 43-50% and 72-95% of the control levels, respectively. These data indicate that radiation induced cell loss (detachment and/or lysis) from the monolayer, with hypertrophy of surviving (attached) cells to preserve the continuity of the monolayer surface. Total PA activity (lysate plus medium) in the irradiated dishes was reduced to 50-75% of the control level. However, when endothelial PA activity was expressed on the basis of DNA content, the irradiated monolayers from two of the three cell lines contained significantly more PA activity than did sham-irradiated monolayers. These data suggest that fibrinolytic defects observed in irradiated tissues in situ may be attributable at least in part to a radiation-induced inhibition of PA release by vascular endothelial cells

  10. WE-FG-BRA-02: Docetaxel Eluting Brachytherapy Spacers for Local Chemo-Radiation Therapy in Prostate Cancer

    Energy Technology Data Exchange (ETDEWEB)

    Belz, J [Northeastern University, Boston, MA (United States); Kumar, R; Sridhar, S [Northeastern University & Dana Farber Cancer Institute, Boston, MA (United States); Makrigiorgos, G; Nguyen, P [Dana Farber Cancer Institute, Boston, MA (United States); D’Amico, A [Brigham & Women’s Hospital, Boston, MA (United States); Cormack, R [Harvard Medical School, Boston, MA (United States)

    2016-06-15

    Purpose: We propose an innovative combinatorial treatment strategy of Local ChemoRadiation Therapy (LCRT) using a sustained drug delivery platform in the form of a spacer to locally radio-sensitize the prostate with Docetaxel (DTX) enabling a synergistic cure with the use of lower radiation doses. These biodegradable spacers are physically similar to the inert spacers routinely used in prostate brachytherapy but are now loaded with formulations of DTX. Methods: Spacers were loaded with ∼500µg Docetaxel (DTX) for prostate cancer studies. The implants were characterized in vitro using SEM and HPLC. The release kinetic studies were carried out in buffer (pH 6.0) at 37°C. Subcutaneous PC3 tumors were xenografted in nude mice. Prostate cancer studies were done with and without radiation using SARRP at 5Gy, 10Gy, and 15Gy. Drug-loaded implants were injected once intratumorally using an 18G brachytherapy needle. Results: The release study in vitro showed a highly sustained release for multiple weeks at therapeutically relevant doses. The monotherapy with local DTX spacer showed sustained tumor inhibition compared to empty implants and an equivalent DTX dose given systemically. At 40 days, 89% survival was observed for mice treated with DTX implants compared with 0% in all other treatment groups. The combined treatment with local DTX spacer and radiation (10Gy) showed the highest degree of tumor suppression (significant tumor growth inhibition by day 90). The control mice showed continuous tumor growth and were scarified by day 56. Groups of mice treated with DTX-spacer or radiation alone showed initial tumor suppression but growth continued after day 60. A larger experiment is ongoing. Conclusion: This approach provides localized delivery of the chemotherapeutic sensitizer directly to the tumor and avoids the toxicities associated with both brachytherapy and current systemic delivery of docetaxel. Sustained release of DTX is an effective chemotherapy option alone or

  11. GEWEX SRB Shortwave Release 4

    Science.gov (United States)

    Cox, S. J.; Stackhouse, P. W., Jr.; Mikovitz, J. C.; Zhang, T.

    2017-12-01

    The NASA/GEWEX Surface Radiation Budget (SRB) project produces shortwave and longwave surface and top of atmosphere radiative fluxes for the 1983-near present time period. Spatial resolution is 1 degree. The new Release 4 uses the newly processed ISCCP HXS product as its primary input for cloud and radiance data. The ninefold increase in pixel number compared to the previous ISCCP DX allows finer gradations in cloud fraction in each grid box. It will also allow higher spatial resolutions (0.5 degree) in future releases. In addition to the input data improvements, several important algorithm improvements have been made since Release 3. These include recalculated atmospheric transmissivities and reflectivities yielding a less transmissive atmosphere. The calculations also include variable aerosol composition, allowing for the use of a detailed aerosol history from the Max Planck Institut Aerosol Climatology (MAC). Ocean albedo and snow/ice albedo are also improved from Release 3. Total solar irradiance is now variable, averaging 1361 Wm-2. Water vapor is taken from ISCCP's nnHIRS product. Results from GSW Release 4 are presented and analyzed. Early comparison to surface measurements show improved agreement.

  12. Radiation dosimetry assessment of routine CT scanning protocols used in Western Australia

    International Nuclear Information System (INIS)

    Moorin, Rachael E; Forsyth, Rene; Gibson, David J; Fox, Richard

    2013-01-01

    Technical data on local CT practice in Western Australia were collected for five major CT providers using a self-completed questionnaire. The CTDIvol DLP and effective dose for each protocol were obtained and providers were ranked according to radiation burden for each clinical scenario. The mean, median, 75th percentile and standard deviation were calculated for both effective dose and DLP for each scenario and these values were compared with published data. CT utilisation data were used to estimate the attributable radiation dose to the WA population and the potential change in population annual effective dose according to the protocol used was estimated. We found that wide variations in technique and radiation dose exist across providers for similar examinations, producing a higher radiation burden than reported internationally. As expected, the CT protocol used dramatically affects the radiation dose received, and this has a significant effect on annual population dose. This study highlights the need for recognition and understanding of both the degree of variation in radiation dose across providers and the relatively high radiation burden afforded by protocols in use in Western Australia so that necessary dialogue can be launched for practitioner consensus on appropriate diagnostic reference levels in CT scanning. (paper)

  13. A new release of the S3M code

    International Nuclear Information System (INIS)

    Pavlovic, M.; Bokor, J.; Regodic, M.; Sagatova, A.

    2015-01-01

    This paper presents a new release of the code that contains some additional routines and advanced features of displaying the results. Special attention is paid to the processing of the SRIM range file, which was not included in the previous release of the code. Examples of distributions provided by the S 3 M code for implanted ions in thyroid and iron are presented. (authors)

  14. Microcapsular imaging of malignant tumors and radiation induced release of liquid-core microcapsules for their treatment

    Energy Technology Data Exchange (ETDEWEB)

    Harada, S.; Ehara, S. [Department of Radiology, School of Medicine, Iwate Medical University, Iwate (Japan); Ishii, K. [Department of Quantum Science and Energy Engineering, School of Engineering, Tohoku University, Miyagi (Japan); Sato, T.; Enatsu, M.; Kamiya, T. [Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency, Gunma (Japan); Sera, K. [Cyclotron Center, Iwate Medical University, Iwate (Japan); Goto, S. [Nishina Memorial Cyclotron Center (NMCC), Japan Radioisotope Association, Iwate (Japan)

    2013-07-01

    Full text: Purpose: Basing on the study of PIXE and Micro PIXE camera, microcapsules of 2 types were designed: (1) CT detectable anti-αvβ3 (E[c(RGDfK)]{sub 2}, microcapsules containing P-selectin and P-selectin glycoprotein ligand-1 (PSGL-1) to observe malignant tumors via αvβ3-antigen-antibody accumulation, and (2) malignant tumors-treating microcapsules that release anticancer drug on irradiation and have a high affinity to P-selectin. To test the ability of these microcapsules for imaging malignant tumors and for treating them, we subject C3He/N mice with MM48 tumor to 2 radiotherapy sessions. Methods and Materials: For the first session, microcapsules were prepared by spraying a mixture of 4.0% alginate, 3.0% hyaluronic acid, and 1 μg E[c(RGDfK)]{sub 2}, (αvβ3 antibody) into 0.5 mmol FeCI{sub 2}, supplemented with 1 μg P-selectin. Microcapsules for the second session were produced by spraying the above-mentioned mixture with 5mg carboplatin into 0.5 mol/L FeCI{sub 2}, containing 0.1 μmol/L of PSGL-1 and the FcSv antibody against P-selectin [1]. In the first session, the microcapsules were intravenously injected, and 6 h later, the incipient metastatic foci were observed using CT. Subsequently, a 10- or 20-Gy {sup 60}Co γ-radiation dose was administered. In the second session, 1 x 10{sup 10} microcapsules were intravenously injected 1 h before P-selectin expression peaked; the microcapsules were allowed to interact with P-selectin for 1-6 h after irradiation in order to deliver sufficient microcapsules. The second session was conducted in a similar manner to the first. The releasing of P-selectin or carboplatin were imaged using micro PIXE camera. The amount of carboplatin (Pt containing anticancer drug) were quantified, using PIXE. Results. The capsule and liquid core sizes (φ) were 2.3 ± 0.92 m and 1.6 ± 0.6 m, respectively. The injected anti-αvβ3 E[c(RGDfK)]{sub 2}, microcapsules accumulated in the vascular endothelium of the incipient

  15. Routine oblique radiography of the pediatric lumbar spine: is it necessary. [Oblique radiography entails more than double the gonadal radiation dose of frontal-lateral projections

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, F.F.; Kishore, P.R.S.; Cunningham, M.E.

    1978-08-01

    A series of 86 pediatric lumbar spine abnormalities was evaluated to determine the diagnostic benefit of radiography in oblique projection as compared to frontal-lateral projections alone. In only four patients was an abnormality apparent on the oblique view which had not already been demonstrated by the frontal-lateral series; each of these represented an isolated spondylolysis. Because the diagnostic yield was low at a patient cost of more than double the gonadal radiation dose, it is recommended that oblique views be eliminated in the routine radiography of the pediatric lumbar spine.

  16. Effect of radiative transfer of heat released from combustion reaction on temperature distribution: A numerical study for a 2-D system

    International Nuclear Information System (INIS)

    Zhou Huaichun; Ai Yuhua

    2006-01-01

    Both light and heat are produced during a chemical reaction in a combustion process, but traditionally all the energy released is taken as to be transformed into the internal energy of the combustion medium. So the temperature of the medium increases, and then the thermal radiation emitted from it increases too. Chemiluminescence is generated during a chemical reaction and independent of the temperature, and has been used widely for combustion diagnostics. It was assumed in this paper that the total energy released in a combustion reaction is divided into two parts, one part is a self-absorbed heat, and the other is a directly emitted heat. The former is absorbed immediately by the products, becomes the internal energy and then increases the temperature of the products as treated in the traditional way. The latter is emitted directly as radiation into the combustion domain and should be included in the radiation transfer equation (RTE) as a part of radiation source. For a simple, 2-D, gray, emitting-absorbing, rectangular system, the numerical study showed that the temperatures in reaction zones depended on the fraction of the directly emitted energy, and the smaller the gas absorption coefficient was, the more strong the dependence appeared. Because the effect of the fraction of the directly emitted heat on the temperature distribution in the reacting zones for gas combustion is significant, it is required to conduct experimental measurements to determine the fraction of self-absorbed heat for different combustion processes

  17. Preparation of slowly released male sex hormone drug by radiation polymerization technique and its evaluation in vivo

    International Nuclear Information System (INIS)

    Liu Rueizhi; Lei Shaoqiong; Li Ximing

    1992-01-01

    The radiation polymerization technique was used for immobilization testosterone propionate into crosslinked network of poly hydroxyethyl methacrylate to prepare slowly released male sex hormone drug which is used for testicular prosthesis. The testicular prosthesis was transplanted into the scrotum of male rabbit whose testes was excised 2 months before the transplantation. Then the level of male sex hormone in serum was measured by radioimmunoassay once a week after transplantation. The results of measurement in a period of 6 months were shown that the testicular prosthesis has a stable release of male sex hormone. The testosterone level in serum of the castrated male rabbits rises markedly and finally stabilizes at the level of 429 ± 36 ng/100 ml after transplantation. Macroscopic examination of biopsies taken from the tissues around the testicular prosthesis showed that tissue compatibility was revealed well

  18. Radiation cancer, safety standards and current levels of exposure

    International Nuclear Information System (INIS)

    Mole, R.H.

    1976-01-01

    Cancer can be induced by radiation in any tissue where cancer occurs naturally. The observation that antenatal diagnostic radiography causes a small but definite increase in childhood cancer is as good evidence as could be expected in support of the scientific expectation that there would be no threshold of dose for carcinogenesis. A linear relation between radiation dose and frequency of induced cancer is a necessary assumption for a system of radiological protection but is not necessarily a reasonable basis for realistic assessments of cancer risk. Indeed there are radiobiological and epidemiological reasons to the contrary. If the linear hypothesis is accepted then at the present time in the UK the routine practice of medicine is of about 2 orders of magnitude more important in causing cancer than environmental pollution by discharge of radio-activity. The acceptability of radiation safety standards for occupational exposure may be justified by comparison of radiation cancer risks with risks from fatal accidents in the safer industries. The acceptability of the corresponding standards for members of the public seems to require more public discussion of the concept of negligible risk. Emotional reactions to uncontrolled releases of radio-activity are based at least in part on a failure to appreciate the hypothesis of linearity

  19. Synthesis and characterization of superabsorbent polymer prepared by radiation-induced graft copolymerization of acrylamide onto carboxymethyl cellulose for controlled release of agrochemicals

    Science.gov (United States)

    Hemvichian, Kasinee; Chanthawong, Auraruk; Suwanmala, Phiriyatorn

    2014-10-01

    Superabsorbent polymer (SAP) was synthesized by radiation-induced grafting of acrylamide (AM) onto carboxymethyl cellulose (CMC) in the presence of a crosslinking agent, N,N‧-methylenebisacrylamide (MBA). The effects of various parameters, such as dose, the amount of CMC, AM, MBA and ionic strength on the swelling ratio were investigated. In order to evaluate its controlled release potential, SAP was loaded with potassium nitrate (KNO3) as an agrochemical model and its potential for controlled release of KNO3 was studied. The amount of released KNO3 was analyzed by an inductively coupled plasma mass spectrometry (ICP-MS). The results from controlled release experiment agreed very well with the results from swelling experiment. The synthesized SAP was characterized by Fourier transform infrared spectroscopy (FTIR) and thermogravimetric analysis (TGA). The obtained SAP exhibited a swelling ratio of 190 g/g of dry gel.

  20. Radiation dose resulting from the releases of fly ash in the environment

    International Nuclear Information System (INIS)

    Koester, H.W.; Leenhouts, H.P.; Frissel, M.J.

    1986-06-01

    The radiological consequences from radioactivity in the emissions of coal fired power stations are evaluated for the Dutch population until the year 2030. The energy scenario for the Netherlands with the highest coal input considers an input of 55 Tg coal per year in 2030. The fly ash production is then 5.3 Tg, while 0.03 Tg fly ash will be released into the atmosphere. The radiation doses which result from the radionuclides present in the fly ash were calculated. Several pathways were considered, contribution of most of them were insignificant. However, the inhalation of fly ash may cause and H eff of 4.0 E-7 Sv.a -1 . The contribution caused by the ingestion of milk contaminated via depositions of fly ash on grass and soil may reach 0.8 E-7 Sv.a -1 . The report contains numerous calculations, references and a parameter analysis. (Auth.)

  1. Incident involving radioactive material at IAEA Safeguards Laboratory - No radioactivity released to environment

    International Nuclear Information System (INIS)

    2008-01-01

    Full text: Pressure build-up in a small sealed sample bottle in a storage safe resulted in plutonium contamination of a storage room at about 02:30 today at the IAEA's Safeguards Analytical Laboratory in Seibersdorf. All indications are that there was no release of radioactivity to the environment. Further monitoring around the laboratory will be undertaken. No one was working in the laboratory at the time. The Laboratory's safety system detected plutonium contamination in the storage room where the safe was located and in two other rooms - subsequently confirmed by a team of IAEA radiation protection experts. The Laboratory is equipped with multiple safety systems, including an air-filtering system to prevent the release of radioactivity to the environment. There will be restricted access to the affected rooms until they are decontaminated. A full investigation of the incident will be conducted. The IAEA has informed the Austrian regulatory authority. The IAEA's Laboratory in Seibersdorf is located within the complex of the Austrian Research Centers Seibersdorf (ARC), about 35 km southeast of Vienna. The laboratory routinely analyses small samples of nuclear material (uranium or plutonium) as part of the IAEA's safeguards verification work. (IAEA)

  2. Investigators find hundreds of intentional nuclear releases

    International Nuclear Information System (INIS)

    Lobsenz, G.

    1994-01-01

    Investigators with the federal Advisory Committee on Human Radiation Experiments have said that the category of intentional releases is now known to be larger, in variety and quantity, than the 13 releases identified prior to the committee's formation in January 1994 by President Clinton. The committee is now aware of hundreds of additional intentional releases. In addition to the intentional releases, the committee said it had compiled documents on 400 biomedical experiments involving radiation prior to 1975, and had at least fragmentary evidence of more than 1,000 more. The committee also discovered a top secret 1953 Defense Department policy statement on human experimentation that was based on the World War II-era Nuremberg Code. The committee said it was looking into how or whether the policy was implemented. The committee is expected to issue a final report, including recommendations on possible compensation for victims by April 1995

  3. Dilaton field released under collision of dilatonic black holes with Gauss-Bonnet term

    Energy Technology Data Exchange (ETDEWEB)

    Gwak, Bogeun [Sejong University, Department of Physics and Astronomy, Seoul (Korea, Republic of); Ro, Daeho [POSTECH, Asia Pacific Center for Theoretical Physics, Pohang, Gyeongbuk (Korea, Republic of)

    2017-08-15

    We investigate the upper limit of the gravitational radiation released upon the collision of two dilatonic black holes by analyzing the Gauss-Bonnet term. Dilatonic black holes have a dilaton hair coupled with this term. Using the laws of thermodynamics, the upper limit of the radiation is obtained, which reflected the effects of the dilaton hair. The amount of radiation released is greater than that emitted by a Schwarzschild black hole due to the contribution from the dilaton hair. In the collision, most of the dilaton hair can be released through radiation, where the energy radiated by the dilaton hair is maximized when the horizon of one black hole is minimized for a fixed second black hole. (orig.)

  4. Atmospheric Dispersion Assessment for Potential Accidental Releases at Yonggwang Nuclear Power Plants

    International Nuclear Information System (INIS)

    Na, Man Gyun; Sim, Young Rok; Jung, Chul Kee; Lee, Goung Jin; Kim, Soong Pyung; Chung, Sung Tai

    2000-01-01

    XOQ DW code is currently used to assess the atmospheric dispersion for the routine releases of radioactive gaseous effluents at Yonggwang nuclear power plants. This code was developed based on XOQDOQ code and an additional code is required to assess the atmospheric dispersion for potential accidental releases. In order to assess the atmospheric dispersion for the accidental releases, XOQAR code has been developed by using PAVAN code that is based on Reg. Guide 1.145. The terrain data of XOQ DW code inputs and the relative concentrations (X/Q) of XOQ DW code outputs are used as the inputs of the XOQAR code through the interface with XOQ DW code. By using this code, the maximum values of X/Q at exclusion area and low population zone boundaries except for sea areas were assessed as 1.33 x 10 -4 and 7.66 x 10 -6 sec/m 3 , respectively. Through the development of this code, a code system is prepared for assessing the atmospheric dispersion for the accidental releases as well as the routine releases. This developed code can be used for other domestic nuclear power plants by modifying the terrain input data

  5. Blood banking-induced alteration of red blood cell oxygen release ability.

    Science.gov (United States)

    Li, Yaojin; Xiong, Yanlian; Wang, Ruofeng; Tang, Fuzhou; Wang, Xiang

    2016-05-01

    Current blood banking procedures may not fully preserve red blood cell (RBC) function during storage, contributing to the decrease of RBC oxygen release ability. This study was undertaken to evaluate the impact of routine cold storage on RBC oxygen release ability. RBC units were collected from healthy donors and each unit was split into two parts (whole blood and suspended RBC) to exclude possible donor variability. Oxygen dissociation measurements were performed on blood units stored at 4 °C during a 5-week period. 2,3-diphosphoglycerate levels and fluorescent micrographs of erythrocyte band 3 were also analysed. P50 and oxygen release capacity decreased rapidly during the first 3 weeks, and then did not change significantly. In contrast, the kinetic properties (PO2-t curve and T*50) of oxygen release changed slowly during the first 3 weeks of storage, but then decreased significantly in the last 2 weeks. 2,3-diphosphoglycerate decreased quickly during the first 3 weeks of storage to almost undetectable levels. Band 3 aggregated significantly during the last 2 weeks of storage. RBC oxygen release ability appears to be sensitive to routine cold storage. The thermodynamic characteristics of RBC oxygen release ability changed mainly in the first 3 weeks of storage, due to the decrease of 2,3-diphosphoglycerate, whereas the kinetic characteristics of RBC oxygen release ability decreased significantly at the end of storage, probably affected by alterations of band 3.

  6. Atmospheric Radiation Measurement's Data Management Facility captures metadata and uses visualization tools to assist in routine data management.

    Science.gov (United States)

    Keck, N. N.; Macduff, M.; Martin, T.

    2017-12-01

    The Atmospheric Radiation Measurement's (ARM) Data Management Facility (DMF) plays a critical support role in processing and curating data generated by the Department of Energy's ARM Program. Data are collected near real time from hundreds of observational instruments spread out all over the globe. Data are then ingested hourly to provide time series data in NetCDF (network Common Data Format) and includes standardized metadata. Based on automated processes and a variety of user reviews the data may need to be reprocessed. Final data sets are then stored and accessed by users through the ARM Archive. Over the course of 20 years, a suite of data visualization tools have been developed to facilitate the operational processes to manage and maintain the more than 18,000 real time events, that move 1.3 TB of data each day through the various stages of the DMF's data system. This poster will present the resources and methodology used to capture metadata and the tools that assist in routine data management and discoverability.

  7. Recommended Parameter Values for GENII Modeling of Radionuclides in Routine Air and Water Releases

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Arimescu, Carmen [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Napier, Bruce A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hay, Tristan R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2012-11-01

    The GENII v2 code is used to estimate dose to individuals or populations from the release of radioactive materials into air or water. Numerous parameter values are required for input into this code. User-defined parameters cover the spectrum from chemical data, meteorological data, agricultural data, and behavioral data. This document is a summary of parameter values that reflect conditions in the United States. Reasonable regional and age-dependent data is summarized. Data availability and quality varies. The set of parameters described address scenarios for chronic air emissions or chronic releases to public waterways. Considerations for the special tritium and carbon-14 models are briefly addressed. GENIIv2.10.0 is the current software version that this document supports.

  8. Radioecology of and radiation dose from Dutch waste gypsum released into the environment

    International Nuclear Information System (INIS)

    Koster, H.W.; Weers, A.W. van; Netherlands Energy Research Foundation, Petten)

    1985-11-01

    The Dutch industries release 9 kinds of waste gypsum, 90% of the total quantity is phosphogypsum. Only waste gypsums from the phosphate industries show increased radioactivity, the strongest in phosphogypsum. All phosphogypsum, 2 Tg.a -1 , is disposed of into the Rhine at Rotterdam. This leads to an increase of radionuclides, from the U-238 chain, along the Dutch coast. The calculated increase of activity concentrations in sea food causes an increase of the individual radiation dose of maximal 150 μSv.a -1 and of the Dutch population dose of 170 manSv.a -1 . Stacking of the phosphogypsum would result in a dose increase of one order of magnitude lower. The need for environmental disposal or stacking of at least the fine and coarse fractions of the phosphogypsum, which are difficult to recycle, will remain. (Auth.)

  9. Three-dimensional, two-species magnetohydrodynamic studies of the early time behaviors of the Combined Release and Radiation Effects Satellite G2 barium release

    International Nuclear Information System (INIS)

    Xie, Lianghai; Li, Lei; Wang, Jingdong; Zhang, Yiteng

    2014-01-01

    We present a three-dimensional, two-species (Ba + and H + ) MHD model to study the early time behaviors of a barium release at about 1 R E like Combined Release and Radiation Effects Satellite G2, with emphasis placed on the three-dimensional evolution of the barium cloud and its effects on the ambient plasma environment. We find that the perturbations caused by the cloud are the combined results of the initial injection, the radial expansion, and the diamagnetic effect and propagate as fast MHD waves in the magnetosphere. In return, the transverse expansion and the cross-B motion of barium ions are constrained by the magnetic force, which lead to a field-aligned striation of ions and the decoupling of these ions from the neutrals. Our simulation shows the formation and collapse of the diamagnetic cavity in the barium cloud. The estimated time scale for the cavity evolution might be much shorter if photoionization time scale and field aligned expansion of barium ions are considered. In addition, our two species MHD simulation also finds the snowplow effect resulting from the momentum coupling between barium ions and background H + , which creates density hole and bumps in the background H + when barium ions expanding along the magnetic field lines

  10. Selected methodological aspects of routine medical supervision of radiation workers

    International Nuclear Information System (INIS)

    Schuettmann, W.

    1981-01-01

    Examinations of the blood, skin, chromosomes, eyes and lungs provide an important means for detecting biological radiation effects in occupationally exposed workers. The diagnostic value of these five methods is discussed. (author)

  11. LOW AND MEAN RADIATION DOSES IMPACT ON THE CEREBRAL TRACTS STRUCTURE OF THE CHERNOBYL ACCIDENT LIQUIDATORS IN THE REMOTE PERIOD (BASED ON ROUTINE AND DIFFUSION-TENSOR MAGNETIC RESONANCE IMAGING DATA

    Directory of Open Access Journals (Sweden)

    I. M. Levashkina

    2017-01-01

    Full Text Available To evaluate correlation between brain structural damages and radiation exposure level for the Chernobyl nuclear power plant accident liquidators, routine and diffusion tensor magnetic resonance imaging methods are efficient to visualize and evaluate those damages; it is also important to compare magnetic resonance imaging data of liquidators with results, received for people of the same age and the same stage of cerebral vascular disease (the discirculatory encephalopathy of I and II stage, but who did not participate in the Chernobyl accident liquidation and did not suffer from other liquidation factors and radiation catastrophe aftermaths. As a result, the Chernobyl accident liquidators group (49 subjects and group of control (50 subjects were examined with routine magnetic resonance imaging methods and standard protocols. In addition, the innovative method of diffusion tensor magnetic resonance imaging was applied to examine 11 cerebral tracts, bilaterally (22 tracts in both hemispheres for every subject of the research. It was for the first time when diffusion tensor magnetic resonance imaging was applied to conduct visual analysis of polymorphic brain changes for the Chernobyl accident liquidators and special research conducted to find correlation between fractional anisotropy coefficient and radiation exposure for these patients. The results of diffusion tensor magnetic resonance imaging indicated no statistically significant (p > 0,05 difference in the level of cerebral morphological changes and between average fraction anisotropy coefficient value in any cerebral tract for both sub-groups of liquidators with different level of irradiation: 28 subjects, who were exposed by low and very low radiation doses (0–100 micro-Sv, sub-group A and 21 subjects, who were exposed by mean radiation doses (100–1000 micro-Sv, sub-group B. However, comparing diffusion tensor magnetic resonance imaging results of control group and liquidators group

  12. Master schedule for CY-1983 Hanford environmental surveillance routine sampling program

    International Nuclear Information System (INIS)

    Blumer, P.J.; Sula, M.J.; Eddy, P.A.; Dirkes, R.L.

    1982-12-01

    The current schedule of data collection for the routine Hanford environmental surveillance and ground-water monitoring programs at the Hanford Site is presented. The purpose of the programs is to evaluate and report the levels of radioactive and nonradioactive pollutants in the Hanford environs. Radiological monitoring data are reported for air (particulate filter and gases/vapor), Columbia River water, sanitary water, onsite pond water, foodstuffs (whole milk, leafy vegetables, fruit, wheat/alfalfa, beef, poultry/eggs), wildlife, soil and vegetation, and direct radiation. Information is also given for on site radiation control audit surveys (roadway, railway, aerial, and waste disposal sites, and the Hanford ground-water monitoring program

  13. Determination of intake and internal radiation dose for occupationally exposed workers to iodine 131

    International Nuclear Information System (INIS)

    Kharita, M. H.; Maghrabi, M.; Sadyya, A.

    2004-12-01

    Workers who prepare and inject radioactive Iodine I 131 doses at the medical centers in Syria are potentially exposed to the radioactive intake by ingestion or inhalation during preparation or injection processes. The received amount of the radioactive intake differs according to the amount of the I 131 that released during the preparation or injection processes, and to the work conditions and the applying ways of the radiation protection principles. Because of this radioactive intake, the thyroid gland may expose to amounts of I 131 which may negatively affect the health of the workers, so it is necessary to make routine monitoring for all workers who receive an intake of more than 10% of the annual intake limit which is (2*10 6 Bq/y) for I 131 . To make this monitoring process, it is necessary to use either the thyroid gland counter in order to know the concentrated amount of the radioactivity in the gland, or the analysis of a 24 hours urine sample of the exposed workers to determine the eliminated amount of the radioactivity using gamma spectrometry, also the two processes can be applied at the same time. Since the thyroid gland counter is not available, the analysis of urine sample was done to determine the concentrated amount of the radioactivity in urine, then to estimate the radioactive intake and the internal radioactive dose. The results of applying this method dictated that some workers work in safe conditions according to the radiation protection and there is no need for them to make routine monitoring . But the other workers receive a radioactive intake of about 10% yearly of the annual intake limit and that requires a routine periodical monitoring for those workers in addition to the necessity of applying the principles of the radiation protection during the work with I 131 . These principles and systems should indicate the basic requirement of radiation protection that must be available in the laboratory that deal with I 131 either for therapy or for

  14. Radiation resistance of Candida parapsilosis

    International Nuclear Information System (INIS)

    Kristensen, H.

    1982-01-01

    The radiation resistance of 30 strains classified as Candida parapsilosis was examined. The strains originated partly from environments where ionizing radiation was used for research or routine purposes, partly from environments with no known possibility for selection of strains with unusually high radiation resistance. D-6 values between 1.5 and 2.4 Megarads were found when the cells were irradiated in the dried state, a D-6 value being the dose necessary to reduce the initial number of colony-forming units with a factor of 10 6 . The majority of D-6 values were between 1.9 and 2.1 Megarads. D-6 values for the cells irradiated in liquid media were about 2/3 of tose in the dried state. No difference in resistance was revealed depending on the origin of the strains examined. For radiation sterilization of medical products the demonstrated resistance of Candida parapsilosis might be of importance of routine use of minimum doses below 2.5 Megarads were to be accepted. (author)

  15. LOW AND MEAN RADIATION DOSES IMPACT ON THE CEREBRAL TRACTS STRUCTURE OF THE CHERNOBYL ACCIDENT LIQUIDATORS IN THE REMOTE PERIOD (BASED ON ROUTINE AND DIFFUSION-TENSOR MAGNETIC RESONANCE IMAGING DATA)

    OpenAIRE

    I. M. Levashkina; S. S. Aleksanin; S. V. Serebryakova; T. G. Gribanova

    2017-01-01

    To evaluate correlation between brain structural damages and radiation exposure level for the Chernobyl nuclear power plant accident liquidators, routine and diffusion tensor magnetic resonance imaging methods are efficient to visualize and evaluate those damages; it is also important to compare magnetic resonance imaging data of liquidators with results, received for people of the same age and the same stage of cerebral vascular disease (the discirculatory encephalopathy of I and II stage), ...

  16. Analysis of drug effects on neurotransmitter release

    International Nuclear Information System (INIS)

    Rowell, P.; Garner, A.

    1986-01-01

    The release of neurotransmitter is routinely studied in a superfusion system in which serial samples are collected and the effects of drugs or other treatments on the amount of material in the superfusate is determined. With frequent sampling interval, this procedure provides a mechanism for dynamically characterizing the release process itself. Using automated data collection in conjunction with polyexponential computer analysis, the equation which describes the release process in each experiment is determined. Analysis of the data during the nontreated phase of the experiment allows an internal control to be used for accurately assessing any changes in neurotransmitter release which may occur during a subsequent treatment phase. The use of internal controls greatly improves the signal to noise ratio and allows determinations of very low concentrations of drugs on small amounts of tissue to be made. In this presentation, the effects of 10 μM nicotine on 3 H-dopamine release in rat nucleus accumbens is described. The time course, potency and efficacy of the drug treatment is characterized using this system. Determinations of the exponential order of the release as well as the rate constants allow one to study the mechanism of the release process. A description of 3 H-dopamine release in normal as well as Ca ++ -free medium is presented

  17. External Agents' Effect on Routine Dynamics:Lack of Compliance Resulting in Routine Breakdown

    OpenAIRE

    Busse Hansen, Nicolai

    2014-01-01

    Prior investigations on organizational routines have called for re- search to enlighten our understanding of how social actors establish and main- tain of routines as well as the causes of their disruption. The present paper con- tributes to this call by conducting systematic microethnographic analyses of naturally occurring interactional routine data in the form of recordings of job interviews in an international oil contractor company. The term interactional routine is used to describe recu...

  18. Evaluation of the impact and the releases of operating nuclear facilities

    International Nuclear Information System (INIS)

    2005-01-01

    The monitoring of nuclear installations releases, the associated impacts evaluation and the radiation monitoring of the environment are of an increase interest since the last ten years. Theses two days, organized by the environment section of the SFRP (French Society of Radiation Protection), aim to discuss the following topics: the development of the methods to improve radioactive elements and toxic substances releases in the environment; the structure of the environment control and the objectives of this control; the association of the local actors to the releases monitoring and to the environment control; the perspectives of evolution in matter of nuclear facilities releases management. (A.L.B.)

  19. MCNP Version 6.2 Release Notes

    Energy Technology Data Exchange (ETDEWEB)

    Werner, Christopher John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Bull, Jeffrey S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Solomon, C. J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McKinney, Gregg Walter [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rising, Michael Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dixon, David A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Martz, Roger Lee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hughes, Henry G. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Cox, Lawrence James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Zukaitis, Anthony J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Armstrong, J. C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Forster, Robert Arthur [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Casswell, Laura [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-02-05

    Monte Carlo N-Particle or MCNP® is a general-purpose Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. This MCNP Version 6.2 follows the MCNP6.1.1 beta version and has been released in order to provide the radiation transport community with the latest feature developments and bug fixes for MCNP. Since the last release of MCNP major work has been conducted to improve the code base, add features, and provide tools to facilitate ease of use of MCNP version 6.2 as well as the analysis of results. These release notes serve as a general guide for the new/improved physics, source, data, tallies, unstructured mesh, code enhancements and tools. For more detailed information on each of the topics, please refer to the appropriate references or the user manual which can be found at http://mcnp.lanl.gov. This release of MCNP version 6.2 contains 39 new features in addition to 172 bug fixes and code enhancements. There are still some 33 known issues the user should familiarize themselves with (see Appendix).

  20. Incidents with hazardous radiation sources

    International Nuclear Information System (INIS)

    Schoenhacker, Stefan

    2016-01-01

    Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

  1. Development of a stand-alone microcomputer based DOE contractor generic radiation worker safety course

    International Nuclear Information System (INIS)

    Klos, D.B.; Gardner, P.R.

    1985-01-01

    Westinghouse Hanford Company (WHC) has developed Computer Based Training (CBT) materials for radiation and industrial safety. First released for general Fast Flux Test Facility in November, 1984. This course has now been taken by nearly 350 people. Completion times for new personnel average around eight hours. The next project undertaken was construction of a Radiation Worker Safety course generic enough for use by all contractors at the Hanford site. The design process of the Hanford site course indicated that the quantity of ''DOE common material'' may be sufficient to warrant consideration of a larger target population. Specifically, the course will be designed to run on an IBM-PC or compatible computer having 256K RAM, a standard IBM color graphics card or equivalent, a color graphics monitor, and two floppy disk drives or one hard disk. The target student population includes those who routinely work in Radiation Areas, especially crafts people. We are not targeting Health Physics personnel, except, possibly, for introductory training, nor are we directing the course toward ''casual'' or escorted workers

  2. Study of dosimetric quantities applied to patient undergoing routine chest examinations by computed tomography

    International Nuclear Information System (INIS)

    Gonzaga, Natalia Barbosa

    2012-01-01

    The radiological protection system has established a standard to protect persons against the harmful effects caused by ionizing radiation that is based on the justification, optimization and dose limitation principles. The increasing use of radiation in medicine and the related risks have stressed the discussion on patient radiation protection. The computed tomography (CT) is the diagnostic radiology technique that most contributes to patient doses and it requires optimization efforts. Diagnostic reference levels (DRL) has been established in many countries in terms of CT dosimetric quantities; in Brazil, the DRLs are still under investigation since the culture of patient protection is not very strong yet. The objective of this work was to investigate the dosimetric and protection quantities related to patients undergoing CT routine chest examinations. The ImPACT CT, CT Expo and ImpactDose softwares were used for calculations of the weight and volumetric air-kerma indexes (CW and CVOL), the air kerma - length product (P K,L ), organ equivalent dose (H T ) and the effective dose (E) for CT routine chest protocols in 19 tomographs in Belo Horizonte city. The CT Expo was selected to be validated against experimental measurements in three hospitals with thermoluminescent dosimeters and CT pencil ionization chamber in anthropomorphic and standard CT body phantoms. Experimental and calculated results indicated differences up to 97% for H T and E and acceptable agreement for C W ,C VOL and P K,L . All data from 19 tomographs showed that local DRLs for CT routine chest examinations may be chosen smaller than DRLs adopted in other countries; this would contribute to increase the radiological protection of patients. (author)

  3. Transfer parameters for routine release of HTO. Consideration of OBT

    International Nuclear Information System (INIS)

    Galeriu, D.; Paunescu, N.; Cotarlea

    1997-01-01

    Knowledge of the transfer parameters for tritium is a key requirement to assess the public dose or to establish Derived Release Limit (DRL) proper for a heavy water reactor. This report revised the transfer parameters used to assess tritium doses via the ingestion pathway. First, the procedure used in Canadian standard CSA-N288.1 to assess the DRL for tritium is revisited, clearing up some misunderstandings about the derivation of transfer parameters from air to forage and animal products. Secondly, we derive the transfer parameters applying conditions of full equilibrium to dynamic equations that describe the transfer of tritiated water in food. The new transfer parameters for tritiated water in food are more plant- and site-specific then the generic transfer parameters. The most important improvement is the introduction of organically bound tritium (OBT) production in plants or animal products. Bulk transfer parameters are introduced, which include OBT as well as HTO. Based on a standard Canadian diet, the dose increase considering OBT is almost 50 %. Recent experimental data obtained under equilibrium condition are discussed, and the revised transfer parameters for assessment purposes is demonstrated. (authors)

  4. Transfer parameters for routine release of HTO - consideration of OBT

    International Nuclear Information System (INIS)

    Galeriu, D.

    1994-06-01

    Knowledge of the transfer parameters for tritium is a key requirement to assess the public dose or to establish Derived Release Limits (DRL) appropriate for a heavy-water reactor. This report revises the transfer parameters used to assess tritium doses via the ingestion pathway. First, the procedure used in Canadian standard CSA-N288.1 to assess the DRL for tritium is revised, clearing up some misunderstandings about the derivation of transfer parameters for air to forage and animal products. Second, we rederive the transfer parameters, applying conditions of full equilibrium to dynamic equations that describe the transfer of tritiated water in food. The new transfer parameters for tritiated water in food are more plant- and site-specific than the generic transfer parameters. The most important improvement is the introduction of organically bound tritium (OBT) production in plants or animal products. Bulk transfer parameters are introduced, which include OBT as well as HTO. Based on a standard Canadian diet, the dose increase considering OBT is almost 50%. Recent experimental data obtained under equilibrium conditions are discussed, and the appropriateness of the revised transfer parameters for assessment purposes is demonstrated. (author). 26 refs., 7 tabs

  5. Transfer of Tritium in the Environment after Accidental Releases from Nuclear Facilities. Report of Working Group 7 Tritium Accidents of EMRAS II Topical Heading Approaches for Assessing Emergency Situations. Environmental Modelling for Radiation Safety (Emras II) Programme

    International Nuclear Information System (INIS)

    2014-07-01

    Environmental assessment models are used for evaluating the radiological impact of actual and potential releases of radionuclides to the environment. They are essential tools for use in the regulatory control of routine discharges to the environment and also in planning measures to be taken in the event of accidental releases. They are also used for predicting the impact of releases which may occur far into the future, for example, from underground radioactive waste repositories. It is important to verify, to the extent possible, the reliability of the predictions of such models by a comparison with measured values in the environment or with predictions of other models. The IAEA has been organizing programmes of international model testing since the 1980s. These programmes have contributed to a general improvement in models, in the transfer of data and in the capabilities of modellers in Member States. IAEA publications on this subject over the past three decades demonstrate the comprehensive nature of the programmes and record the associated advances which have been made. From 2009 to 2011, the IAEA organized a programme entitled Environmental Modelling for RAdiation Safety (EMRAS II), which concentrated on the improvement of environmental transfer models and the development of reference approaches to estimate the radiological impacts on humans, as well as on flora and fauna, arising from radionuclides in the environment. Different aspects were addressed by nine working groups covering three themes: reference approaches for human dose assessment, reference approaches for biota dose assessment and approaches for assessing emergency situations. This publication describes the work of the Tritium Accidents Working Group

  6. The embeddedness of selfish Routines

    DEFF Research Database (Denmark)

    Andersen, Poul Houman

    2001-01-01

    Routines have traditionally been seen as an organisational feature. However, like genes, routines may be carriers and initiators of organisations as well......Routines have traditionally been seen as an organisational feature. However, like genes, routines may be carriers and initiators of organisations as well...

  7. Assessment of radiological releases to the environment from a fusion reactor power plant

    International Nuclear Information System (INIS)

    Shank, K.E.; Oakes, T.W.; Easterly, C.E.

    1978-05-01

    This report summarizes the expected tritium and activation-product inventories and presents an assessment of the potential radiological releases from a fusion reactor power plant, hypothetically located at the Oak Ridge National Laboratory. Routine tritium releases and the resulting dose assessment are discussed. Uncertainties associated with the conversion of tritium gas to tritium oxide and the global tritium cycling are evaluated. The difficulties of estimating releases of activated materials and the subsequent dose commitment are reviewed

  8. Study of biological effect of radiation

    International Nuclear Information System (INIS)

    Li Guisheng

    1992-01-01

    The some progress on the study of biological effect for protract exposure to low dose rate radiation is reported, and it is indicated that the potential risk of this exposure for the human health and the importance of the routine monitoring of radiation dose for various nuclear installations. The potential exposure to the low dose rate radiation would attract people's extra attention

  9. The 2017 Release Cloudy

    Science.gov (United States)

    Ferland, G. J.; Chatzikos, M.; Guzmán, F.; Lykins, M. L.; van Hoof, P. A. M.; Williams, R. J. R.; Abel, N. P.; Badnell, N. R.; Keenan, F. P.; Porter, R. L.; Stancil, P. C.

    2017-10-01

    We describe the 2017 release of the spectral synthesis code Cloudy, summarizing the many improvements to the scope and accuracy of the physics which have been made since the previous release. Exporting the atomic data into external data files has enabled many new large datasets to be incorporated into the code. The use of the complete datasets is not realistic for most calculations, so we describe the limited subset of data used by default, which predicts significantly more lines than the previous release of Cloudy. This version is nevertheless faster than the previous release, as a result of code optimizations. We give examples of the accuracy limits using small models, and the performance requirements of large complete models. We summarize several advances in the H- and He-like iso-electronic sequences and use our complete collisional-radiative models to establish the densities where the coronal and local thermodynamic equilibrium approximations work.

  10. Evaluation of conventional and high-performance routine solar radiation measurements for improved solar resource, climatological trends, and radiative modeling

    Energy Technology Data Exchange (ETDEWEB)

    Gueymard, Christian A. [Solar Consulting Services, P.O. Box 392, Colebrook, NH 03576 (United States); Myers, Daryl R. [National Renewable Energy Laboratory, 1617 Cole Blvd., Golden, CO 80401-3305 (United States)

    2009-02-15

    The solar renewable energy community depends on radiometric measurements and instrumentation for data to design and monitor solar energy systems, and develop and validate solar radiation models. This contribution evaluates the impact of instrument uncertainties contributing to data inaccuracies and their effect on short-term and long-term measurement series, and on radiation model validation studies. For the latter part, transposition (horizontal-to-tilt) models are used as an example. Confirming previous studies, it is found that a widely used pyranometer strongly underestimates diffuse and global radiation, particularly in winter, unless appropriate corrective measures are taken. Other types of measurement problems are also discussed, such as those involved in the indirect determination of direct or diffuse irradiance, and in shadowband correction methods. The sensitivity of the predictions from transposition models to inaccuracies in input radiation data is demonstrated. Caution is therefore issued to the whole community regarding drawing detailed conclusions about solar radiation data without due attention to the data quality issues only recently identified. (author)

  11. Biological hazards of radioactivity and the biological consequences of radionuclide emissions from routine operation of nuclear power reactors

    International Nuclear Information System (INIS)

    Stendig-Lindberg, G.

    1978-01-01

    The biological hazards of radioactivity and the biological consequences of radionuclide emissions from the routine operation of nuclear power reactors are reviewed. ICRP and Scandinavian recommendations for the limitation of annual radiation doses are presented. The contribution of environmental conditions to radiation hazard is also discussed. It is concluded that a review of the justification of nuclear power is urgently needed. (H.K.)

  12. Wind field forecast for accidental release of radiative materials

    International Nuclear Information System (INIS)

    Kang Ling; Chen Jiayi; Cai Xuhui

    2003-01-01

    A meso-scale wind field forecast model was designed for emergency environmental assessment in case of accidental release of radiative materials from a nuclear power station. Actual practice of the model showed that it runs fast, has wind field prediction function, and the result given is accurate. With meteorological data collected from weather stations, and pre-treated by a wind field diagnostic model, the initial wind fields at different times were inputted as initial values and assimilation fields for the forecasting model. The model, in turn, worked out to forecast meso-scale wind field of 24 hours in a horizontal domain of 205 km x 205 km. And then, the diagnostic model was employed again with the forecasting data to obtain more detail information of disturbed wind field by local terrain in a smaller domain of 20.5 km x 20.5 km, of which the nuclear power station is at the center. Using observation data in January, April, July and October of 1996 over the area of Hangzhou Bay, wind fields in these 4 months were simulated by different assimilation time and number of the weather stations for a sensitive test. Results indicated that the method used here has increased accuracy of the forecasted wind fields. And incorporating diagnostic method with the wind field forecast model has greatly increased efficiency of the wind field forecast for the smaller domain. This model and scheme have been used in Environmental Consequence Assessment System of Nuclear Accident in Qinshan Area

  13. Codling moth control by release of radiation-sterilized moths in a pome fruit orchard and observations of other pests

    International Nuclear Information System (INIS)

    Proverbs, M.D.; Newton, J.R.; Logan, D.M.; Brinton, F.E.

    1975-01-01

    Release of radiation-sterilized male and female Laspeyresia pomonella (L.) in a 40-ha pome fruit orchard from 1969-72 in the Similkameen Valley of British Columbia reduced the wild population of this pest to a very low level without causing serious problems in control of other apple and pear pests. Percent apples injured by codling moth larvae at harvest were 0.1 in 1968 (after 3 sprays of azinphosmethyl), and 0.05, 0.02, 0.007, and 0.001 from 1969-72

  14. Evaluation of Routine Atmospheric Sounding Measurements using Unmanned Systems (ERASMUS) Science Plan

    Energy Technology Data Exchange (ETDEWEB)

    de Boer, G [University of Colorado, Boulder/CIRES; Argrow, B [University of Colorado; Bland, G [NASA - Goddard Space Flight Center - Wallops Flight Facility; Elston, J [University of Colorado, Boulder; Lawrence, D [University of Colorado; Maslanik, J [University of Colorado; Palo, S [University of Colorado; Tschudi, M [NCAR

    2015-12-01

    The use of unmanned aerial systems (UAS) is becoming increasingly popular for a variety of applications. One way in which these systems can provide revolutionary scientific information is through routine measurement of atmospheric conditions, particularly properties related to clouds, aerosols, and radiation. Improved understanding of these topics at high latitudes, in particular, has become very relevant because of observed decreases in ice and snow in polar regions.

  15. Generating Novelty Through Interdependent Routines: A Process Model of Routine Work

    NARCIS (Netherlands)

    Deken, F.; Carlile, P.R.; Berends, H.; Lauche, K.

    2016-01-01

    We investigate how multiple actors accomplish interdependent routine performances directed at novel intended outcomes and how this affects routine dynamics over time. We report findings from a longitudinal ethnographic study in an automotive company where actors developed a new business model around

  16. Release of radioisotopes and activated materials from nuclear installations and facilities

    International Nuclear Information System (INIS)

    Manfredi, P.F.; Millaud, J. E.

    2001-01-01

    This report discusses the problems of release of items from facilities and installations where radiation-based activities have been carried out. Several situations are reviewed and their release problems are discussed in detail. Particular attention is devoted to the assessment of the activity of the items to be released. A correct assessment of the activity will help the decision about the final use of the items removed from the radiation-related facility, either re-use, entering the public market, recycling, disposal and storage under different procedures. Even the final destination of the building which hosted the facility needs to be decided on the basis of an accurate assessment of the residual activity. The assessment of the activity, besides being fundamental in guaranteeing a safe approach to the procedures related to the release may result in a substantial profit. This is the case of items whose level of activity is so low that they can be put on the public market, reused or recycled for final product subject to very stringent radiation safety requirements. It will be shown that detector techniques play a fundamental role in the release process. In particular, the low-level counting techniques are fundamental in establishing whether or not the unrestrained release is feasible or not

  17. PARMELAB: a new version of PARMELA with coherent synchrotron radiation effects and a finite difference space charge routine

    International Nuclear Information System (INIS)

    Koltenbah, B.E.C.; Parazzoli, Claudio G.; Greegor, Robert B.; Dowell, David H.

    2002-01-01

    Recent interest in advanced laser light sources has stimulated development of accelerator systems of intermediate beam energy, 100-200 MeV, and high charge, 1-10 nC, for high power FEL applications and high energy, 1-2 GeV, high charge, SASE-FEL applications. The current generation of beam transport codes which were developed for high-energy, low-charge beams with low self-fields are inadequate to address this energy and charge regime, and better computational tools are required to accurately calculate self-fields. To that end, we have developed a new version of PARMELA, named PARMELA B and written in Fortran 95, which includes a coherent synchrotron radiation (CSR) routine and an improved, generalized space charge (SC) routine. An electron bunch is simulated by a collection of macro-particles, which traverses a series of beam line elements. At each time step through the calculation, the momentum of each particle is updated due to the presence of external and self-fields. The self-fields are due to CSR and SC. For the CSR calculations, the macro-particles are further combined into macro-particle-bins that follow the central trajectory of the bend. The energy change through the time step is calculated from expressions derived from the Lienard-Wiechart formulae, and from this energy change the particle's momentum is updated. For the SC calculations, we maintain the same rest-frame-electrostatic approach of the original PARMELA; however, we employ a finite difference Poisson equation solver instead of the symmetrical ring algorithm of the original code. In this way, we relax the symmetry assumptions in the original code. This method is based upon standard numerical procedures and conserves momentum to first order. The SC computational grid is adaptive and conforms to the size of the pulse as it evolves through the calculation. We provide descriptions of these two algorithms, validation comparisons with other CSR and SC methods, and a limited comparison with

  18. Characterization and consequences from CEA nuclear fuel cycle facilities effluents releases - 1995 up to 2007 period

    International Nuclear Information System (INIS)

    Ferreira, Nelson Luiz Dias; Fonseca, Lizandra Pereira de Souza

    2009-01-01

    Discharges to the environment of airborne and/or liquid radioactive effluents from the normal operation of nuclear facilities can become a potential source of radiation exposure to humans. The highest exposed members of the public are defined as the critical group. The requirements for the control and monitoring of radioactive discharges to the environment and the degree of environmental monitoring required are linked to the assessed critical group dose. The assessed dose can be compared to dose constraint, which is a fraction of the annual effective dose to members of the public, as well as the level of exemption specified by the National Commission for Nuclear Energy (CNEN). Effluents releases from the Centro Experimental Aramar (CEA) facilities are registered and described at CEA Effluent Report, semestrally sent to CNEN. Basically, that report provides information related to the type and the quantity of chemical and radioactive substances released to the environment due the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). CEA Annual Effluent Report includes assessment of the annual effective doses for members of the critical group for the CEA site. This work presents the characterization of the radioactive release source terms and a historical of the critical group annual doses from 1995 up to 2007. (author)

  19. GRAVITATIONAL RADIATION

    Directory of Open Access Journals (Sweden)

    Metin SALTIK

    1996-03-01

    Full Text Available According to classical electromagnetic theory, an accelerated charge or system of charges radiates electromagnetic waves. In a radio transmitter antenna charges are accelerated along the antenna and release electromagnetic waves, which is radiated at the velocity of light in the surrounding medium. All of the radio transmitters work on this principle today. In this study an analogy is established between the principles by which accelerated charge systems markes radiation and the accelerated mass system, and the systems cousing gravitational radiation are investigated.

  20. Ultraviolet radiation-induced interleukin 6 release in HeLa cells is mediated via membrane events in a DNA damage-independent way.

    Science.gov (United States)

    Kulms, D; Pöppelmann, B; Schwarz, T

    2000-05-19

    Evidence exists that ultraviolet radiation (UV) affects molecular targets in the nucleus or at the cell membrane. UV-induced apoptosis was found to be mediated via DNA damage and activation of death receptors, suggesting that nuclear and membrane effects are not mutually exclusive. To determine whether participation of nuclear and membrane components is also essential for other UV responses, we studied the induction of interleukin-6 (IL-6) by UV. Exposing HeLa cells to UV at 4 degrees C, which inhibits activation of surface receptors, almost completely prevented IL-6 release. Enhanced repair of UV-mediated DNA damage by addition of the DNA repair enzyme photolyase did not affect UV-induced IL-6 production, suggesting that in this case membrane events predominant over nuclear effects. UV-induced IL-6 release is mediated via NFkappaB since the NFkappaB inhibitor MG132 or transfection of cells with a super-repressor form of the NFkappaB inhibitor IkappaB reduced IL-6 release. Transfection with a dominant negative mutant of the signaling protein TRAF-2 reduced IL-6 release upon exposure to UV, indicating that UV-induced IL-6 release is mediated by activation of the tumor necrosis factor receptor-1. These data demonstrate that UV can exert biological effects mainly by affecting cell surface receptors and that this is independent of its ability to induce nuclear DNA damage.

  1. Underground Nuclear Explosions and Release of Radioactive Noble Gases

    Science.gov (United States)

    Dubasov, Yuri V.

    2010-05-01

    Over a period in 1961-1990 496 underground nuclear tests and explosions of different purpose and in different rocks were conducted in the Soviet Union at Semipalatinsk and anovaya Zemlya Test Sites. A total of 340 underground nuclear tests were conducted at the Semipalatinsk Test Site. One hundred seventy-nine explosions (52.6%) among them were classified as these of complete containment, 145 explosions (42.6%) as explosions with weak release of radioactive noble gases (RNG), 12 explosions (3.5%) as explosions with nonstandard radiation situation, and four excavation explosions with ground ejection (1.1%). Thirty-nine nuclear tests had been conducted at the Novaya Zemlya Test Site; six of them - in shafts. In 14 tests (36%) there were no RNG release. Twenty-three tests have been accompanied by RNG release into the atmosphere without sedimental contamination. Nonstandard radiation situation occurred in two tests. In incomplete containment explosions both early-time RNG release (up to ~1 h) and late-time release from 1 to 28 h after the explosion were observed. Sometimes gas release took place for several days, and it occurred either through tunnel portal or epicentral zone, depending on atmospheric air temperature.

  2. Radioactive decay data tables: a handbook of decay data for application to radiation dosimetry and radiological assessments

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1982-01-01

    Reviews compendium containing recommended decay data for approx. 500 radionuclides of interest in nuclear medicine and fusion reactor technology or of potential importance in routine or accidental releases from the nuclear fuel cycle. Primary source of the decay data presented in this handbook is the Evaluated Nuclear Structure Data File (ENSDF), developed and maintained by the US Nuclear Data Network. Topics covered include various radioactive decay processes; evaluation process and standards of ENSDF; tables and computer code MEDLIST used to produce ENSDF tables; radiation dosimetry and radiological assessments; parent-daughter activity ratios wherever the adopted decay data may contain significant uncertainties or errors due to the lack of appropriate experimental data

  3. Bedtime routines child wellbeing & development.

    Science.gov (United States)

    Kitsaras, George; Goodwin, Michaela; Allan, Julia; Kelly, Michael P; Pretty, Iain A

    2018-03-21

    Bedtime routines has shown important associations with areas associated with child wellbeing and development. Research into bedtime routines is limited with studies mainly focusing on quality of sleep. The objectives of the present study were to examine the relationship between bedtime routines and a variety of factors associated with child wellbeing and to examine possible determinants of bedtime routines. A total of 50 families with children between 3 and 5 years old took part in the study. Data on bedtime routines, parenting styles, school readiness, children's dental health, and executive function were collected. Children in families with optimal bedtime routines showed better performance in terms of executive function, specifically working memory (t (44)= - 8.51, p ≤ .001), inhibition and attention (t (48)= - 9.70, p ≤ .001) and cognitive flexibility (t (48)= - 13.1, p ≤ .001). Also, children in households with optimal bedtime routines scored higher in their readiness for school (t (48)= 6.92, p ≤ .001) and had better dental health (U = 85.5, p = .011). Parents in households with suboptimal bedtime routines showed worse performance on all measures of executive function including working memory (t (48)= - 10.47, p ≤ .001), inhibition-attention (t (48)= - 10.50, p ≤ .001) and cognitive flexibility (t (48)= - 13.6, p ≤ .001). Finally, parents with optimal bedtime routines for their children deployed a more positive parenting style in general (i.e. authoritative parenting) compared to those with suboptimal bedtime routines (t (48)= - 6.45, p ≤ .001). The results of the present study highlight the potentially important role of bedtime routines in a variety of areas associated with child wellbeing and the need for further research.

  4. Master schedule for CY-1981 Hanford environmental surveillance routine program

    International Nuclear Information System (INIS)

    Blumer, P.J.; Sula, M.J.; Eddy, P.A.

    1980-12-01

    The current schedule of data collection for the routine environmental surveillance program at the Hanford Site is provided. Questions about specific entries should be referred to the authors since modifications to the schedule are made during the year and special areas of study, usually of short duration, are not scheduled. The environmental surveillance program objectives are to evaluate the levels of radioactive and nonradioactive pollutants in the Hanford environs, as required in Manual Chapter 0513, and to monitor Hanford operations for compliance with applicable environmental criteria given in Manual Chapter 0524 and Washington State Water Quality Standards. Air quality data obtained in a separate program are also reported. The collection schedule for potable water is shown but it is not part of the routine environmental surveillance program. Schedules are presented for the following subjects: air, Columbia River, sanitary water, surface water, ground water, foodstuffs, wildlife, soil and vegetation, external radiation measurement, portable instrument surveys, and surveillance of waste disposal sites

  5. Erythrocyte 2,3-diphosphoglycerate depletion associated with hypophosphatemia detected by routine arterial blood gas analysis.

    Science.gov (United States)

    Larsen, V H; Waldau, T; Gravesen, H; Siggaard-Andersen, O

    1996-01-01

    To describe a clinical case where an extremely low erythrocyte 2,3-diphosphoglycerate concentration (2,3-DPG) was discovered by routine blood gas analysis supplemented by computer calculation of derived quantities. The finding of a low 2,3-DPG revealed a severe hypophosphatemia. Open uncontrolled study of a patient case. Intensive care observation during 41 days. A 44 year old woman with an abdominal abscess. Surgical drainage, antibiotics and parenteral nutrition. daily routine blood gas analyses with computer calculation of the hemoglobin oxygen affinity and estimation of the 2,3-DPG. An abrupt decline of 2,3-DPG was observed late in the course coincident with a pronounced hypophosphatemia. The fall in 2,3-DPG was verified by enzymatic analysis. 2,3-DPG may be estimated by computer calculation of routine blood gas data. A low 2,3-DPG which may be associated with hypophosphatemia causes an unfavorable increase in hemoglobin oxygen affinity which reduces the oxygen release to the tissues.

  6. Guidelines for the Development, Validation and Routine Control of Industrial Radiation Processes

    DEFF Research Database (Denmark)

    Safrany, A.; Miller, Arne; Kovacs, A.

    Radiation processing has become a well accepted technology on the global market, with uses ranging from the sterilization of medical devices to polymer cross-linking and curing to the irradiation of selected food items. Besides these well established uses, new radiation technology applications...... are emerging for environmental remediation and the synthesis of advanced materials and products. Quality assurance is vital for the success of these technologies and requires the development of standardized procedures as well as the harmonization of process validation and process control. It is recognized...

  7. Relations between radiation risks and radiation protection measuring techniques

    International Nuclear Information System (INIS)

    Herrmann, K.; Kraus, W.

    Relations between radiation risks and radiation protection measuring techniques are considered as components of the radiation risk. The influence of the exposure risk on type and extent of radiation protection measurements is discussed with regard to different measuring tasks. Based upon measuring results concerning the frequency of certain external and internal occupational exposures in the GDR, it has been shown that only a small fraction of the monitored persons are subjected to a high exposure risk. As a consequence the following recommendations are presented: occupationally exposed persons with small exposure risk should be monitored using only a long-term desimeter (for instance a thermoluminescence desimeter). In the case of internal exposure, the surface and air contamination levels should be controlled so strictly that routine measurements of internal contamination need not be performed

  8. Metal release from coffee machines and electric kettles.

    Science.gov (United States)

    Müller, Frederic D; Hackethal, Christin; Schmidt, Roman; Kappenstein, Oliver; Pfaff, Karla; Luch, Andreas

    2015-01-01

    The release of elemental ions from 8 coffee machines and 11 electric kettles into food simulants was investigated. Three different types of coffee machines were tested: portafilter espresso machines, pod machines and capsule machines. All machines were tested subsequently on 3 days before and on 3 days after decalcification. Decalcification of the machines was performed with agents according to procedures as specified in the respective manufacturer's manuals. The electric kettles showed only a low release of the elements analysed. For the coffee machines decreasing concentrations of elements were found from the first to the last sample taken in the course of 1 day. Metal release on consecutive days showed a decreasing trend as well. After decalcification a large increase in the amounts of elements released was encountered. In addition, the different machine types investigated clearly differed in their extent of element release. By far the highest leaching, both quantitatively and qualitatively, was found for the portafilter machines. With these products releases of Pb, Ni, Mn, Cr and Zn were in the range and beyond the release limits as proposed by the Council of Europe. Therefore, a careful rinsing routine, especially after decalcification, is recommended for these machines. The comparably lower extent of release of one particular portafilter machine demonstrates that metal release at levels above the threshold that triggers health concerns are technically avoidable.

  9. Effects of ionizing radiation and pretreatment with [D-Leu6,des-Gly10] luteinizing hormone-releasing hormone ethylamide on developing rat ovarian follicles

    International Nuclear Information System (INIS)

    Jarrell, J.; YoungLai, E.V.; McMahon, A.; Barr, R.; O'Connell, G.; Belbeck, L.

    1987-01-01

    To assess the effects of a gonadotropin-releasing hormone agonist, [D-Leu6,des-Gly10] luteinizing hormone-releasing hormone ethylamide, in ameliorating the damage caused by ionizing radiation, gonadotropin-releasing hormone agonist was administered to rats from day 22 to 37 of age in doses of 0.1, 0.4, and 1.0 microgram/day or vehicle and the rats were sacrificed on day 44 of age. There were no effects on estradiol, progesterone, luteinizing, or follicle-stimulating hormone, nor an effect on ovarian follicle numbers or development. In separate experiments, rats treated with gonadotropin-releasing hormone agonist in doses of 0.04, 0.1, 0.4, or 1.0 microgram/day were either irradiated or sham irradiated on day 30 and all groups sacrificed on day 44 of age. Irradiation produced a reduction in ovarian weight and an increase in ovarian follicular atresia. Pretreatment with the agonist prevented the reduction in ovarian weight and numbers of primordial and preantral follicles but not healthy or atretic antral follicles. Such putative radioprotection should be tested on actual reproductive performance

  10. Choice of measuring site in external personnel routine dosimetry

    International Nuclear Information System (INIS)

    Rothe, W.

    1975-01-01

    In personnel routine dosimetry the choice of a suitable measuring site is of great importance because there may be great differences between the measured doses and the equivalent doses of the whole body and of single organs, respectively. In the literature there are different points of view with regard to the measuring site particularly if diagnostic X-radiation is used and the body is partly covered with protective clothing. Likewise in most cases the conclusions regarding the most suitable measuring site drawn from measurements of dose distributions on the body surface are not in agreement. (author)

  11. Status and problem of radiation education in Thailand

    Energy Technology Data Exchange (ETDEWEB)

    Aramrattana, Manoon [Office of Atomic Energy for Peace, Vibhavadee Rangsit Road, Chatuchak, Bangkok (Thailand)

    1999-09-01

    Knowledge of radiation and its application and protection have been routinely taught, discussed and transferred to end users and the public. Limited resource and a strategic plan are identified to be the major obstacle to fully implementation of radiation education in Thailand. Current strategic planning on radiation education in Thailand will be discussed. (author)

  12. Status and problem of radiation education in Thailand

    International Nuclear Information System (INIS)

    Aramrattana, Manoon

    1999-01-01

    Knowledge of radiation and its application and protection have been routinely taught, discussed and transferred to end users and the public. Limited resource and a strategic plan are identified to be the major obstacle to fully implementation of radiation education in Thailand. Current strategic planning on radiation education in Thailand will be discussed. (author)

  13. Surviving radiation in space

    International Nuclear Information System (INIS)

    Coates, A.

    1990-01-01

    Radiation damage to communications, navigation and weather satellites is common and caused by high energy charged particles, mainly protons and electrons, from the Earth's Van Allen belts. The combined release and radiation effects satellite (CRRES), recently launched by the United States, will allow scientists to create far more realistic computer models of satellite radiation damage than has been the case to date. It is hoped that information thus received will allow satellite builders to protect these essential structures in future. The second aim of the CCRES mission is to study the effect of releasing artificially charged particles into the magnetosphere and the ionosphere. Spacecraft design engineers will benefit from the results produced by the CCRES mission. (UK)

  14. Human exposure to radiation following the release of radioactivity from a reactor accident: a quantitative assessment of the biological consequences

    International Nuclear Information System (INIS)

    Smith, H.; Stather, J.W.

    1976-11-01

    The objective of this review is to provide a biological basis upon which to assess the consequences of the exposure of a population to radioactivity released after a reactor accident. Depending upon the radiation dose, both early and late somatic damage could occur in the exposed population and hereditary effects may occur in their descendants. The development of dose-effect relationships has been based upon the limited amount of information available on humans, supplemented by data obtained from experiments on animals. (author)

  15. ANDOSE: a computer code for calculating annual doses to man from routine releases of LWR effluents for the purpose of evaluating compliance with JAEC's guide for doseobjectives

    International Nuclear Information System (INIS)

    Iijima, Toshinori; Shiraishi, Tadao

    1979-10-01

    For environmental doses from routine releases of LWRs effluents to meet the Criterion 'As Low As is Practicable (ALAP)', Japan Atomic Energy Commission (JAEC) established a series of guides, the first for 'Dose Objectives' (May 1975), the second for models and parameters for calculating the environmental doses to compare with the 'Dose Objectives' (September 1976), and the third providing onsite meteorological programs, statistics of the data obtained and atmospheric dispersion models (June 1977). JAERI has developed a computer code, designated as ANDOSE, for calculating annual releases of radioactive gaseous and liquid effluents and, then, total body doses and thyroid doses to individuals around sites on the basis of these guides. The total body doses are from radioactive noble gases as well as from radioactive materials taken with marine food. For the calculation of thyroid doses are taken into account exposure pathways via inhalation and ingestion of leafy vegetables, cow's milk and marine food. The age-specific thyroid doses are evaluated. The doses are summed up when multisource or multisite conditions need to be evaluated (Nuclear Safety Bureau's requirement). In the present report, are described source-term models, environmental transport models and dose models used in the code, of which most are provided in the guides but some are complemented by the authors, the functions of ANDOSE and the manual for users of the code. The program lists and the latter two guides mentioned above are included in the appendices. (author)

  16. Limited Releases of Krsko NPP

    International Nuclear Information System (INIS)

    Breznik, B.; Kovac, A.

    2001-01-01

    Full text: Krsko Nuclear Power Plant is about 700 MW Pressurised Water Reactor plant located in Slovenia close to the border with Croatia. The authorised limit for the radioactive releases is basically set to 50 μSv effective dose per year to the members of the public. There is also additional limitation of total activities released in a year and concentration. The poster presents the effluents of the year 2000 and evaluated dose referring to the limits and to the natural and other sources of radiation around the plant. (author)

  17. Quantification of tephritid fruit fly dispersal. Guidelines for a sterile release programme

    International Nuclear Information System (INIS)

    Baker, P.S.; Chan, A.S.T.

    1991-01-01

    The dispersal of sterile Anastrepha ludens and Ceratitis capitata was studied in a mango and coffee plantation in Chiapas, S. Mexico. Flies were released at the centre of a rectangular array of McPhail and Jackson traps. There were small though significant downwind movements in very light winds (below 1 m/s). Fly distributions were significantly correlated in the x-y plane on several days and these orientations were also related to wind direction. Released flies disappeared quickly, more than 90 % were caught within 5 days of release. Methodology for the presentation and analysis of data is discussed in relation to the needs of a practical sterile release programme. Recommendations are made for routine studies of fly dispersal

  18. Participation of the radiation hygiene laboratories to the WHO/UNEP global environmental radiation network

    International Nuclear Information System (INIS)

    Milu, C.; Gheorghe, R.

    2003-01-01

    In December 1987, a WHO-UNEP meeting held at SCPRI (Service Central de protection canter Les Rayonnements Ionisantes - Le Vesinet, France) set up the basis of the international network GERMON (Global Environmental Radiation Monitoring Network) as an extension of existing network 'Global Environment Monitoring Systems' (GEMS). The accident from Chernobyl certainly was the important nuclear event influencing this decision. The aim of the GERMON network is to initiate programmes for the routine monitoring of the environmental radioactivity and to ensure a quick interchange of credible data in case of major accidental radioactive releases, as well as the development of intervention devices in the member states running such programmes. The responsibility of the Co-ordinating Collaborating Centre (CCC) has been given to the French Service Central de Protection Centre les Rayonnements Ionisants (SCPRI). In 1994, this Service became the Office de Protection Centre les Rayonnements Ionisants (OPRI). The Ministry of Health has a national network consisting of 23 radiation hygiene laboratories; 19 of these are included in the framework of county divisions of public health , and the other 4 are compartments of the regional institutes of public health. WHO designated the Institute of Public Health from Bucharest as National Contact Centre, in charge with communicating the results obtained by the national laboratories on the indicators of environmental radioactivity, according to the established methodologies. The main indicators considered are: ambient gamma dose, radioactivity of the air, of the precipitation, and of the milk. Following the measurement and transmission protocols of the CCC, the Radiation Hygiene Laboratory from the Institute of Public Health has established a methodology to be followed by the laboratories of the national network. (authors)

  19. Utility of routine postoperative chest radiography in pediatric tracheostomy.

    Science.gov (United States)

    Genther, Dane J; Thorne, Marc C

    2010-12-01

    Routine chest radiography following pediatric tracheostomy is commonly performed in order to evaluate for air-tracking complications. Routine chest radiography affords disadvantages of radiation exposure and cost. The primary objective of this study was to determine the utility of routine postoperative chest radiography following tracheostomy in pediatric patients. Secondary objectives were to compare the rates of postoperative complications by various patient and surgeon characteristics. All infants and children 18 years of age or less (n=421) who underwent tracheostomy at a single tertiary-care medical center from January 2000 to April 2009 were included in the study. A combination of data obtained from billing and administrative systems and review of electronic medical records were recorded and compiled in a database for statistical analysis. Three air-tracking complications (2 pneumothoraces and 1 pneumomediastinum) were identified in our population of 421 pediatric patients, for an incidence of 0.71% (95% CI: 0.1-2.0%). No significant relationships were found between the incidence of air-tracking complication and surgical specialty, patient age, or type of procedure (elective, urgent/emergent). Our study identified a low rate of pneumothorax and pneumomediastinum following pediatric tracheostomy. In all three cases, the pneumothorax was suspected clinically. This finding suggests that postoperative chest radiography should be reserved for cases where there is suspicion of a complication on the basis of intraoperative findings or clinical parameters. Copyright © 2010 Elsevier Ireland Ltd. All rights reserved.

  20. The significance of routines in nursing practice.

    Science.gov (United States)

    Rytterström, Patrik; Unosson, Mitra; Arman, Maria

    2011-12-01

    The aim of this study was to illuminate the significance of routines in nursing practice. Clinical nursing is performed under the guidance of routines to varying degrees. In the nursing literature, routine is described as having both negative and positive aspects, but use of the term is inconsistent, and empirical evidence is sparse. In the research on organisational routines, a distinction is made between routine as a rule and routine as action. A qualitative design using a phenomenological-hermeneutic approach. Data collection from three focus groups focused on nurses' experience of routines. Seventeen individual interviews from a previous study focusing on caring culture were also analysed in a secondary qualitative analysis. All participants were employed as 'qualified nursing pool' nurses. Routines are experienced as pragmatic, obstructive and meaningful. The aim of the pragmatic routine was to ensure that daily working life works; this routine is practised more on the basis of rational arguments and obvious intentions. The obstructive routine had negative consequences for nursing practice and was described as nursing losing its humanity and violating the patient's integrity. The meaningful routine involved becoming one with the routine and for the nurses, it felt right and meaningful to adapt to it. Routines become meaningful when the individual action is in harmony with the cultural pattern on which the nursing work is based. Instead of letting contemporary practice passively become routine, routines can be assessed and developed using research and theoretical underpinnings as a starting point for nursing practice. Leaders have a special responsibility to develop and support meaningful routines. One approach could be to let wards examine their routines from a patient perspective on the basis of the themes of pragmatic, meaningful and obstructive routine. © 2010 Blackwell Publishing Ltd.

  1. Radiation Protection Group annual report (1997)

    International Nuclear Information System (INIS)

    Hoefert, M.

    1998-01-01

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1997. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group

  2. Radiation Protection Group annual report (1996)

    International Nuclear Information System (INIS)

    Hoefert, M.

    1997-01-01

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1996. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group

  3. Radiation Protection Group annual report (1998)

    International Nuclear Information System (INIS)

    Hoefert, M.

    1999-01-01

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1998. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group

  4. Ethical aspect in medical radiation use

    International Nuclear Information System (INIS)

    Kiefer, Juergen

    2014-01-01

    Medical radiation uses hold a specific position in radiation protection. Patients are purposely exposed to radiation while usually radiation exposure should be avoided. The radiation doses are (at least in principle) planned the risks may be estimated (again in principle). The hazards are justified by the medical benefit. Otherwise irradiation is a violation of physical integrity (article 2 Grundgesetz) that can be prosecuted. For patients no dose limits exist, the responsible physician decides on the real exposures. Justification and optimization are of predominant importance. The decision on the radiological measure, the applied technology is an ethically motivated decision besides the everyday routine.

  5. Radiation Protection Group annual report (1996)

    Energy Technology Data Exchange (ETDEWEB)

    Hoefert, M [ed.

    1997-03-25

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1996. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group.

  6. Radiation Protection Group annual report (1998)

    Energy Technology Data Exchange (ETDEWEB)

    Hoefert, M [ed.

    1999-04-15

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1998. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group.

  7. Radiation Protection Group annual report (1997)

    Energy Technology Data Exchange (ETDEWEB)

    Hoefert, M [ed.

    1998-04-10

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1997. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group.

  8. Radiation Protection Group annual report (1995)

    International Nuclear Information System (INIS)

    Hoefert, M.

    1996-01-01

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1995. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group

  9. Implementation of the Preventive Radiation Protection Act; here: Regulation governing ambient radioactivity monitoring subject to the Preventive Radiation Protection Act. Pt. 1. Measuring programme for specified normal operation monitoring (routine measuring programme). BMU circular letter dated 28.07.94 -RS II 6 - 15 603/3

    International Nuclear Information System (INIS)

    1994-01-01

    The regulation addresses the competent Federal and Land authorities responsible for implementation of the Preventive Radiation Protection Act, and the competent highest Land authorities. The regulation defines the scope of obligatory measurement of ambient radioactivity during normal operation of installations and determines the measuring techniques to be applied for this purpose. The programme determines compulsory instructions to be observed in the performance of the routine measuring programme by the competent Federal and Land authorities and thus ensures nationwide application of standard procedures

  10. Data format translation routines

    International Nuclear Information System (INIS)

    Burris, R.D.

    1981-02-01

    To enable the effective connection of several dissimilar computers into a network, modification of the data being passed from one computer to another may become necessary. This document describes a package of routines which permit the translation of data in PDP-8 formats to PDP-11 or DECsystem-10 formats or from PDP-11 format to DECsystem-10 format. Additional routines are described which permit the effective use of the translation routines in the environment of the Fusion Energy Division (FED) network and the Elmo Bumpy Torus (EBT) data base

  11. Routines and Organizational Change

    DEFF Research Database (Denmark)

    Yi, Sangyoon; Becker, Markus; Knudsen, Thorbjørn

    2014-01-01

    Routines have been perceived as a source of inertia in the process of organizational change. In this study, we suggest an overlooked, but prevalent, mechanism by which the inertial nature of routines helps, rather than hinders, organizational adaptation. Routine-level inertia plays a hidden role...... to cope with its task environment. In our nuanced perspective, inertia is not only a consequence of adaptation but also a source of adaptation. This logic is helpful to understand why reliable but apparently inertial organizations keep surviving and often exhibit outstanding performance. We conclude...

  12. User guide programmer's reference. NUDOS: A computer programme for assessing the consequences of airborne releases of radionuclides

    International Nuclear Information System (INIS)

    Grupa, J.

    1996-10-01

    NUDOS is a computer program that can be used to evaluate the consequences of airborne releases of radioactive materials. The consequences evaluated are individual dose and associated radiological risk, collective dose and the contamination of land. The code is capable of dealing with both routine and accidental releases. For accidental releases both deterministic and probabilistic calculations can be performed and the impact and effectiveness of emergency actions can be evaluated. (orig.)

  13. Routine individual monitoring of aircrew: Czech experience and results since 1998

    International Nuclear Information System (INIS)

    Spurny, F.; Ploc, O.

    2005-01-01

    Full text: International Commission on Radiological Protection (ICRP) recommended in its Publication 60 that the radiation exposure due to the cosmic component at high altitudes be taken into account when appropriate as part of occupational exposure to the radiation. Air crew members have become in such a way another group of workers for whom the exposure to ionizing radiation is one of important occupational hazard. The recommendation mentioned was incorporated to the Czech regulation already at 1997, the studies how to perform individual dosimetry of Czech companies aircrew has started immediately after. The contribution describes first the preliminary studies with the goal to elaborate optimal procedure for the aircrew routine individual dosimetry. It was decided to perform individual monitoring through the calculation based on the information on the flights realized during a period and the list of aircrew members participated in them. As a transport code CARI was chosen, since the beginning the version 6 has been used. The information on the flight schedules and the participation of aircrew in is received from the air company. In the Czech Republic, three companies are concerned with. The procedure was proposed to the Czech authorities and it received their accreditation. Routine individual dosimetry has started since 1998. It is regularly checked and innovated. Main results for the period 1998 - 2003 are as follows: both relative frequencies as well as average annual effective dosis vary with the company and with the year, without any evident general tendency; the average values of E are between 1.5 and 2 mSv, closely to the higher value; this average value is slightly higher for charter type air-companies. Further more detailed analysis will be presented, as well as future possible modifications of the procedure. (author)

  14. Quantitative assessment of radiation-induced lung changes by computerized optical densitometry of routine chest x-rays

    International Nuclear Information System (INIS)

    Bentzen, Soeren M.; Skoczylas, Jerzy Z.; Overgaard, Marie; Overgaard, Jens; Nielsen, Ole G.; Madsen, Erik Hjoellund

    1996-01-01

    REAT values, and the standard deviation was estimated at 1.35%. (d) REAT values estimated with this assay were significantly correlated with the scores of two experienced specialists, an oncologist and a radiologist (Spearman's rank correlation coefficient being 0.065, p -8 ). Conclusion: This assay quantifies radiation-induced lung injury from routine chest x-rays. Thus, it is possible to take advantage of the very large retrospective materials available in most oncological institutions. The assay has been validated in a phantom experiment and shown to be reproducible. Furthermore, it is technically easy to perform

  15. Experimental evaluation of the exposure level onboard Czech Airlines aircraft - measurements verified the routine method

    International Nuclear Information System (INIS)

    Ploc, O.; Spurny, F.; Turek, K.; Kovar, I.

    2008-01-01

    Air-crew members are exposed to ionizing radiation due to their work on board of air-crafts. The International Commission on Radiological Protection (ICRP) in 1990 recommends that exposure to cosmic radiation in the operation of jet aircraft should be recognised as occupational exposure. Czech air transport operators are therefore obliged to ensure: - Air-crew members to be well informed about the exposure level and health risks; - An analysis of complete exposure level of aircraft crew and its continuing monitoring in cases of exceeding the informative value 1 mSv; - A compliance of limit 1 mSv during pregnancy Since 1998, after receiving a proper accreditation, the Department of Radiation Dosimetry of Nuclear Physics Institute of Czech Academy of Sciences (DRD) is the competent dosimetric service realized requirements of Notice No.307 of the State Office for Nuclear Safety concerning air-crew exposure (paragraphs 87-90). The DRD has developed routine method of personal dosimetry of aircraft crew in 1998 which has been applied after receiving a proper accreditation in the same year. DRD therefore helps Czech airlines a.s. (CSA) with their legislative obligations mentioned above, and in return, once per four years, in terms of business contract, CSA allows scientific measurements performed by DRD onboard its air-crafts with the aim to verify the method of routine individual monitoring of aircraft crew exposure. (authors)

  16. Preparation of slow release anticancer drug by means of radiation technique and IT's therapeutic effect on sold tumor of mice

    International Nuclear Information System (INIS)

    Li Ximing; Shen Weiming; Liu Chengjie; Hu Xu

    1991-01-01

    In order to minimize the toxic effect of chemotherapy of malignant tumors, the authors use a method of radiation induced cast polymerization of hydrophilic monomer at low temperature for immobilization the anticancer drug, 5-Fluorouracil, into the polymer matrix. The anticancer drug-polymer composite called slow release anticancer drug was used for treatment the transplantable squamous cell carcinoma in mice 615 and the transplantable sarcoma (S180) in Kunming mice. There were marked difference between the treated group and the control group. That is the higher inhibition ratio and lower toxic effect were reported

  17. Worldwide exposures to ionizing radiation

    International Nuclear Information System (INIS)

    Bennett, B.G.

    1993-01-01

    All of mankind is exposed to ionizing radiation from natural sources, from human practices that release natural and artificial radionuclides to the environment, and from medical radiation procedures. This paper reviews the assessment in the UNSCEAR 1993 Report of the exposures of human populations worldwide to the various sources of ionizing radiation

  18. Hendee's radiation therapy physics

    CERN Document Server

    Pawlicki, Todd; Starkschall, George

    2016-01-01

    The publication of this fourth edition, more than ten years on from the publication of Radiation Therapy Physics third edition, provides a comprehensive and valuable update to the educational offerings in this field. Led by a new team of highly esteemed authors, building on Dr Hendee’s tradition, Hendee’s Radiation Therapy Physics offers a succinctly written, fully modernised update. Radiation physics has undergone many changes in the past ten years: intensity-modulated radiation therapy (IMRT) has become a routine method of radiation treatment delivery, digital imaging has replaced film-screen imaging for localization and verification, image-guided radiation therapy (IGRT) is frequently used, in many centers proton therapy has become a viable mode of radiation therapy, new approaches have been introduced to radiation therapy quality assurance and safety that focus more on process analysis rather than specific performance testing, and the explosion in patient-and machine-related data has necessitated an ...

  19. The radiation safety self-assessment program of Ontario Hydro

    International Nuclear Information System (INIS)

    Armitage, G.; Chase, W.J.

    1987-01-01

    Ontario Hydro has developed a self-assessment program to ensure that high quality in its radiation safety program is maintained. The self-assessment program has three major components: routine ongoing assessment, accident/incident investigation, and detailed assessments of particular radiation safety subsystems or of the total radiation safety program. The operation of each of these components is described

  20. Master schedule for CY-1980 Hanford Environmental Surveillance Routine Program

    International Nuclear Information System (INIS)

    Blumer, P.J.; Houston, J.R.; Eddy, P.A.

    1979-12-01

    The current schedule of data collection for the routine environmental surveillance program at the Hanford Site is presented. The enviromental surveillance program objectives are to evaluate the levels of radioactive and nonradioactive pollutants in the Hanford environs, as required in Manual Chapter 0513, and to monitor Hanford operations for compliance with applicable environmental criteria given in Manual Chapter 0524 and Washington State Water Quality Standards. Data are reported on the following topics: air; Columbia River; sanitary water; surface water; ground water; foodstuffs; wildlife; soil and vegetation; external radiation measurement; portable instrument surveys; and surveillance of waste disposal sites;

  1. Assessing the need for a routine monitoring program in three Nuclear Medicine centers in Chile

    International Nuclear Information System (INIS)

    Astudillo, R.; Hermosilla, A.; Diaz-Londono, G.; Garcia, M.

    2015-01-01

    The workers performing different activities with radionuclides in nuclear medicine centers are at potential risk of external exposure and internal contamination. The IAEA Safety Guide No. RS-G-1.2 proposed criteria for determining the need for a routine monitoring program to assess internal contamination. For this purpose, an Excel template containing the IAEA criteria was applied in three nuclear medicine centers in Chile. The results show that it is necessary to carry out a routine monitoring program for five workers who handle 131 I and three for 99m Tc. We propose to implement this template at a national level in order to improve the conditions of radiation protection in the participating centers. (authors)

  2. Intervention quality is not routinely assessed in Cochrane systematic reviews of radiation therapy interventions.

    Science.gov (United States)

    Abdul Rahim, Mohamad R; James, Melissa L; Hickey, Brigid E

    2017-10-01

    The aim of this study was to maximise the benefits from clinical trials involving technological interventions such as radiation therapy. High compliance to the quality assurance protocols is crucial. We assessed whether the quality of radiation therapy intervention was evaluated in Cochrane systematic reviews. We searched 416 published Cochrane systematic reviews and identified 67 Cochrane systematic reviews that investigated radiation therapy or radiotherapy as an intervention. For each systematic review, either quality assurance or quality control for the intervention was identified by a description of such processes in the published systematic reviews. Of the 67 Cochrane systematic reviews studied, only two mentioned quality assurance or quality control. Our findings revealed that 65 of 67 (97%) Cochrane systematic reviews of radiation therapy interventions failed to consider the quality of the intervention. We suggest that advice about the evaluation of intervention quality be added to author support materials. © 2017 The Royal Australian and New Zealand College of Radiologists.

  3. Recent advances in radiation protection instrumentation

    International Nuclear Information System (INIS)

    Babu, D.A.R.

    2012-01-01

    Radiation protection instrumentation plays very important role in radiation protection and surveillance programme. Radiation detector, which appears at the frontal end of the instrument, is an essential component of these instruments. The instrumental requirement of protection level radiation monitoring is different from conventional radiation measuring instruments. Present paper discusses the new type of nuclear radiation detectors, new protection level instruments and associated electronic modules for various applications. Occupational exposure to ionizing radiation can occur in a range of industries, such as nuclear power plants; mining and milling; medical institutions; educational and research establishments; and nuclear fuel cycle facilities. Adequate radiation protection to workers is essential for the safe and acceptable use of radioactive materials for different applications. The radiation exposures to the individual radiation workers and records of their cumulative radiation doses need to be routinely monitored and recorded

  4. Radioactive decay data tables: A handbook of decay data for application to radiation dosimetry and radiological assessments

    Science.gov (United States)

    Kocher, D. C.; Smith, J. S.

    Decay data are presented for approximately 500 radionuclides including those occurring naturally in the environment, those of potential importance in routine or accidental releases from the nuclear fuel cycle, those of current interest in nuclear medicine and fusion reactor technology, and some of those of interest to Committee 2 of the International Commission on Radiological Protection for the estimation of annual limits on intake via inhalation and ingestion for occupationally exposed individuals. Physical processes involved in radioactive decay which produce the different types of radiation observed, methods used to prepare the decay data sets for each radionuclide in the format of the computerized evaluated nuclear structure data file, the tables of radioactive decay data, and the computer code MEDLIST used to produce the tables are described. Applications of the data to problems of interest in radiation dosimetry and radiological assessments are considered as well as the calculations of the activity of a daughter radionuclide relative to the activity of its parent in a radioactive decay chain.

  5. Radiation in medicine: Origins, risks and aspirations.

    OpenAIRE

    Donya, M; Radford, M; ElGuindy, A; Firmin, D; Yacoub, MH

    2014-01-01

    The use of radiation in medicine is now pervasive and routine. From their crude beginnings 100 years ago, diagnostic radiology, nuclear medicine and radiation therapy have all evolved into advanced techniques, and are regarded as essential tools across all branches and specialties of medicine. The inherent properties of ionizing radiation provide many benefits, but can also cause potential harm. Its use within medical practice thus involves an informed judgment regarding the risk/benefit rati...

  6. Manual for medical problems of radiation protection

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The manual deals comprehensively and topically with the theoretical and practical fundamentals of radiation protection of the population considering the present knowledge in the fields of radiobiology and radiation protection medicine. The subject is covered under the following headings: (1) physics of ionizing radiations, (2) biological radiation effects, (3) the acute radiation syndrome, (4) medical treatment of the acute radiation syndrome, (5) combined radiation injuries, and (6) prophylaxis and therapy of injuries caused by fission products of nuclear explosions. The book is of interest to medical doctors, medical scientists, and students in medicine who have to acquire special knowledge in the field of radiation protection and it is of value as a reference book in daily routine

  7. Routine oblique radiography of the pediatric lumbar spine: is it necessary

    International Nuclear Information System (INIS)

    Roberts, F.F.; Kishore, P.R.S.; Cunningham, M.E.

    1978-01-01

    A series of 86 pediatric lumbar spine abnormalities was evaluated to determine the diagnostic benefit of radiography in oblique projection as compared to frontal-lateral projections alone. In only four patients was an abnormality apparent on the oblique view which had not already been demonstrated by the frontal-lateral series; each of these represented an isolated spondylolysis. Because the diagnostic yield was low at a patient cost of more than double the gonadal radiation dose, it is recommended that oblique views be eliminated in the routine radiography of the pediatric lumbar spine

  8. Effects of radiation on photographic film. A study

    International Nuclear Information System (INIS)

    Dutton, D.M.

    1971-01-01

    This study of the effects of radiation on photographic film is related to the Nevada Test Site's underground nuclear testing program, which has been active since implementation of the Limited Test Ban Treaty of 1963. Residual radioactivity, which has accidentally been released on several tests, adversely affects the photographic film used in test data acquisition. The report defines this problem in terms of radiation-caused image degradation, radiation/matter interactions, types of radiation released by accidental venting, and the photographic effects of gamma and x radiation. Techniques and experimental findings are documented that may be useful in recovering information from radiation-fogged film. Techniques discussed include processing methods, shielding, image enhancement techniques, and operational handling of potentially irradiated film. (U.S.)

  9. Increased Exposure to Rigid Routines Can Lead to Increased Challenging Behavior Following Changes to Those Routines

    Science.gov (United States)

    Bull, Leah E.; Oliver, Chris; Callaghan, Eleanor; Woodcock, Kate A.

    2015-01-01

    Several neurodevelopmental disorders are associated with preference for routine and challenging behavior following changes to routines. We examine individuals with Prader-Willi syndrome, who show elevated levels of this behavior, to better understand how previous experience of a routine can affect challenging behavior elicited by disruption to…

  10. Project Radiation protection, Annual report 1994

    International Nuclear Information System (INIS)

    Ninkovic, M.M.

    1994-12-01

    According to the action plan for the period 1991-1995, the main objective of this project during 1994 was to provide operational basis, methods and procedures for solving the radiation protection problems that might appear under routine working conditions and handling of radiation sources. The aim was also to provide special methods for action in case of accidents that could affect the employed staff and the population. Overall activity was directed to maintaining and providing personnel, instrumentation, and methods for the following special radiation protection measures: operational control of the radiation field and contamination; calibration of the radiation and dosimetry instruments-secondary dosimetry metrology laboratory; instrumentation and measuring systems for radiation protection; control of environmental transfer of radioactive material; medical radiation protection [sr

  11. Thyroid and radiation

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Shunichi; Namba, Hiroyuki; Nagataki, Shigenobu (Nagasaki Univ. (Japan). School of Medicine)

    1993-11-01

    The topic 'Thyroid and Radiation' is both an old and new area to be solved by human beings. The thyroid is an organ that is usually susceptible to exposure to ionizing radiation, both by virtue of its ability to concentrate radioiodine (internal radiation) and by routine medical examination: Chest X-ray, Dental X-ray, X-irradiation of cervical lymph nodes etc. (external radiation). Iodine-131 is widely used for the therapy of Graves' disease and thyroid cancers, of which the disadvantage is radiation-induced hypothyroidism but not complications of thyroid tumor. The thyroid gland is comparatively radioresistant, however, the data obtained from Hiroshima, Nagasaki and Marshall islands indicates a high incidence of external radiation-induced thyroid tumors as well as hypothyroidism. The different biological effects of internal and external radiation remains to be further clarified. Interestingly, recent reports demonstrate the increased number of thyroid cancer in children around Chernobyl in Belarus. In this review, we would like to introduce the effect of radiation on the thyroid gland at the molecular, cellular and tissue levels. Furthermore the clinical usefulness of iodine-131, including the safety-control for radiation exposure will be discussed. (author) 50 refs.

  12. Surgery for chronic inguinodynia following routine herniorrhaphy: beneficial effects on dysejaculation.

    Science.gov (United States)

    Verhagen, T; Loos, M J A; Scheltinga, M R M; Roumen, R M H

    2016-02-01

    Pain during sexual activities and ejaculation is reported by 3-4% of men after routine inguinal herniorrhaphy. The potential beneficial effects of surgery for chronic groin pain on dysejaculation are unknown. The objective of this study was to determine dysejaculation rates in a series of patients reporting chronic postherniorrhaphy pain and evaluate the effects of tailored neurectomy on dysejaculation. We evaluated male patients (>18 years) operated for chronic groin pain after inguinal herniorrhaphy during a 6-year time period (2004-2010). Dysejaculation was defined as a burning or searing sensation associated with ejaculation. Men reporting symptoms possibly associated with dysejaculation were sent a questionnaire investigating pain characteristics (VAS, 0-100), influence on sex life and effects of the tailored neurectomy. A Post-Herniorrhaphy Dysejaculation Score (PHDS, 0-12 points) was introduced to quantify the severity of the dysejaculation syndrome. A series of 100 males operated for chronic inguinal pain after standard herniorrhaphy were studied. Thirty-four men reported symptoms of dysejaculation prior to the tailored neurectomy. Sex life was negatively influenced in 20 of these, and 5 completely abstained from any sexual activity. Following surgery including tailored neurectomy, funicular release and/or mesh removal, VAS for dysejaculation pain was significantly reduced [n = 20, 55 (95% CI 47-63) versus 21 (95% CI 13-29), p < 0.001]. PHDS scores were also significantly attenuated [n = 20, 10 (3-12) versus 2 (0-10), p < 0.001]. Sex life normalized in two-thirds of these men (13/20). Dysejaculation in men suffering from chronic pain after routine inguinal herniorrhaphy is not uncommon. A tailored neurectomy, funicular release and/or mesh removal offer relief in the majority of these patients.

  13. Monitoring System For Improving Radiation Safety Management

    International Nuclear Information System (INIS)

    Osovizky, A.; Paran, J.; Tal, N.; Ankry, N.; Ashkenazi, B.; Tirosh, D.; Marziano, R.; Chisin, R.

    1999-01-01

    Medi SMARTS (Medical Survey Mapping Automatic Radiation Tracing System), a gamma radiation monitoring system, was installed in a nuclear medicine department. In this paper the evaluation of the system's ability to improve radiation safety management is presented. The system is based on a state of the art software that continuously collects on line radiation measurements for display, analysis and logging. Radiation is measured by GM tubes; the signal is transferred to a data processing unit and then via an RS-485 communication line to a computer. The system automatically identifies the detector type and its calibration factor, thus providing compatibility, maintainability and versatility when changing detectors. Radiation levels are displayed on the nuclear medicine department map at six locations. The system has been operating continuously for more than one year, documenting abnormal events caused by routine operation or failure incidents. In cases where abnormal working conditions were encountered, an alarm message was sent automatically to the supervisor via his tele-pager. An interesting issue observed during the system evaluation, was the inability to distinguish between high radiation levels caused by proper routine operation and those caused by safety failure incidents. The solution included examination of two parameters, radiation levels as well as their duration period. A careful analysis of the historical data, applying the appropriated combined parameters determined for each location, verified that such a system can identify abnormal events, provide alarms to warn in case of incidents and improve standard operating procedures

  14. Radiation in medicine: Origins, risks and aspirations.

    Science.gov (United States)

    Donya, Mohamed; Radford, Mark; ElGuindy, Ahmed; Firmin, David; Yacoub, Magdi H

    2014-01-01

    The use of radiation in medicine is now pervasive and routine. From their crude beginnings 100 years ago, diagnostic radiology, nuclear medicine and radiation therapy have all evolved into advanced techniques, and are regarded as essential tools across all branches and specialties of medicine. The inherent properties of ionizing radiation provide many benefits, but can also cause potential harm. Its use within medical practice thus involves an informed judgment regarding the risk/benefit ratio. This judgment requires not only medical knowledge, but also an understanding of radiation itself. This work provides a global perspective on radiation risks, exposure and mitigation strategies.

  15. The clinical characteristics of the radiation pneumonia

    International Nuclear Information System (INIS)

    Zhang Fuzheng; Wang Mingzhi; Chen Jianjiang; Wang Zhongxiang; Mao Yongjie

    2000-01-01

    Objective: To analyse the clinical characteristics of the radiation pneumonia, sum the experience and the basis of the radiation pneumonia for its prevention and treatment. Method: Twenty three cases with radiation pneumonia from 1991 to 1998 were retrospectively analysed. Its clinical manifestation, chest X-ray, thoracic CT and blood routine were evaluated. Result: The acute manifestation was fever, cough, dyspnea, and the chronic manifestation was cough and insufficiency of pulmonary function. Conclusion: The prevention of radiation pneumonia is more important, high dose cortical steroids and antibiotics were prescribed during the acute stage and the chronic radiation pneumonia is irreversible

  16. Guide for dosimetry for sterile insect release programs. 2. ed.

    International Nuclear Information System (INIS)

    2004-01-01

    This guide outlines dosimetric procedures to be followed for the radiation sterilization of live insects for use in pest management programs. The primary use of irradiated, reproductively sterile insects is in the Sterile Insect Technique, where large numbers of sterile insects are released into the field to mate with and thus control pest populations of the same species. A secondary use of sterile insects is as benign hosts for rearing insect parasitoids. The procedures outlined in this guide will help ensure that insects processed with ionizing radiation from gamma, electron, or X-ray sources receive absorbed doses within a predetermined range. Information on effective dose ranges for specific applications of insect sterilization, or on methodology for determining effective dose ranges, is not within the scope of this guide. Note: Dosimetry is only one component of a total quality control program to ensure that irradiated insects are adequately sterilized and sufficiently competitive or otherwise suitable for their intended purpose. This guide covers dosimetry in the irradiation of insects for these types of irradiators: self-contained dry-storage 137 Cs or 60 Co irradiators, large-scale gamma irradiators, and electron accelerators. Additional, detailed information on dosimetric procedures to be followed in installation qualification, operational qualification, performance qualification, and routine product processing can be found in ISO/ASTM Practices 51608 (X-ray [bremsstrahlung] facilities), 51649 (electron beam facilities), 51702 (large-scale gamma facilities), and ASTM Practice E 2116 (self-contained dry-storage gamma facilities). The absorbed dose for insect sterilization is typically within the range of 20 Gy to 600 Gy

  17. Radiation safety and protection in US dental hygiene programs

    International Nuclear Information System (INIS)

    Farman, A.G.; Hunter, N.; Grammer, S.

    1986-01-01

    A survey of radiation safety and protection measures used by programs teaching dental hygiene indicated some areas for concern. No barriers or radiation shieldings were used between operator and patient in four programs. Radiation monitoring devices were not worn by faculty operators in 16% of the programs. Fewer than half of the programs used thyroid shields for patients on a routine basis. Insufficient filtration for the kilovolt peak employed was used by 14% of the programs, and for 19% more the filtration was unknown or unspecified. Three programs used closed cones. Rectangular collimation was not used at all by 63% of the programs, and only 20% used E speed film routinely. Quality assurance for equipment maintenance and for film processing were in place at only 54% and 49% of the programs, respectively

  18. Routine chest and abdominal high-pitch CT: An alternative low dose protocol with preserved image quality

    International Nuclear Information System (INIS)

    Amacker, Nadja A.; Mader, Caecilia; Alkadhi, Hatem; Leschka, Sebastian; Frauenfelder, Thomas

    2012-01-01

    Objective: To investigate the radiation dose and image quality of the high-pitch dual source computer tomography (DSCT) for routine chest and abdominal scans. Methods: 130 consecutive patients (62 female, 68 male, median age 55 years) were included. All patients underwent 128-slice high-pitch DSCT (chest n = 99; abdomen n = 84) at a pitch of 3.2. Two observers independently rated image quality using a 4-point score (1: excellent to 4: non-diagnostic). Image noise was measured and operational radiation dose quantities were recorded. An additional group of 132 patients (chest, n = 80; abdomen n = 52) scanned with standard-pitch CT matched for age, gender, and body mass index (BMI) served as control group. Results: Interobserver agreement for image quality rating was good (k = 0.74). Subjective image quality of high-pitch CT was diagnostic in all patients (median score chest; 2, median score abdomen: 2). Image noise of high-pitch CT was comparable to standard-pitch for the chest (p = 0.32) but increased in the abdomen (p < 0.0001). For high-pitch CT radiation dose was 4.4 ± 0.9 mSv (chest) and 6.5 ± 1.2 mSv (abdomen). These values were significantly lower compared to standard-pitch CT (chest: 5.5 ± 1.2 mSv; abdomen: 11.3 ± 3.8 mSv). Conclusion: Based on the technical background high-pitch dual source CT may serve as an alternative scan mode for low radiation dose routine chest and abdominal CT.

  19. SU-E-P-10: Establishment of Local Diagnostic Reference Levels of Routine Exam in Computed Tomography

    International Nuclear Information System (INIS)

    Yeh, M; Wang, Y; Weng, H

    2015-01-01

    Introduction National diagnostic reference levels (NDRLs) can be used as a reference dose of radiological examination can provide radiation dose as the basis of patient dose optimization. Local diagnostic reference levels (LDRLs) by periodically view and check doses, more efficiency to improve the way of examination. Therefore, the important first step is establishing a diagnostic reference level. Computed Tomography in Taiwan had been built up the radiation dose limit value,in addition, many studies report shows that CT scan contributed most of the radiation dose in different medical. Therefore, this study was mainly to let everyone understand DRL’s international status. For computed tomography in our hospital to establish diagnostic reference levels. Methods and Materials: There are two clinical CT scanners (a Toshiba Aquilion and a Siemens Sensation) were performed in this study. For CT examinations the basic recommended dosimetric quantity is the Computed Tomography Dose Index (CTDI). Each exam each different body part, we collect 10 patients at least. Carried out the routine examinations, and all exposure parameters have been collected and the corresponding CTDIv and DLP values have been determined. Results: The majority of patients (75%) were between 60–70 Kg of body weight. There are 25 examinations in this study. Table 1 shows the LDRL of each CT routine examination. Conclusions: Therefore, this study would like to let everyone know DRL’s international status, but also establishment of computed tomography of the local reference levels for our hospital, and providing radiation reference, as a basis for optimizing patient dose

  20. SU-E-P-10: Establishment of Local Diagnostic Reference Levels of Routine Exam in Computed Tomography

    Energy Technology Data Exchange (ETDEWEB)

    Yeh, M; Wang, Y; Weng, H [Chiayi Chang Gung Memorial Hospital of The C.G.M.F, Puzi City, Chiayi County, Taiwan (China)

    2015-06-15

    Introduction National diagnostic reference levels (NDRLs) can be used as a reference dose of radiological examination can provide radiation dose as the basis of patient dose optimization. Local diagnostic reference levels (LDRLs) by periodically view and check doses, more efficiency to improve the way of examination. Therefore, the important first step is establishing a diagnostic reference level. Computed Tomography in Taiwan had been built up the radiation dose limit value,in addition, many studies report shows that CT scan contributed most of the radiation dose in different medical. Therefore, this study was mainly to let everyone understand DRL’s international status. For computed tomography in our hospital to establish diagnostic reference levels. Methods and Materials: There are two clinical CT scanners (a Toshiba Aquilion and a Siemens Sensation) were performed in this study. For CT examinations the basic recommended dosimetric quantity is the Computed Tomography Dose Index (CTDI). Each exam each different body part, we collect 10 patients at least. Carried out the routine examinations, and all exposure parameters have been collected and the corresponding CTDIv and DLP values have been determined. Results: The majority of patients (75%) were between 60–70 Kg of body weight. There are 25 examinations in this study. Table 1 shows the LDRL of each CT routine examination. Conclusions: Therefore, this study would like to let everyone know DRL’s international status, but also establishment of computed tomography of the local reference levels for our hospital, and providing radiation reference, as a basis for optimizing patient dose.

  1. Evaluation of Routine Atmospheric Sounding Measurements Using Unmanned Systems (ERASMUS) Field Campaign Report

    Energy Technology Data Exchange (ETDEWEB)

    de Boer, Gijs [Univ. of Colorado, Boulder, CO (United States). Cooperative Inst. for Research in Environmental Sciences (CIRES); Lawrence, Dale [Univ. of Colorado, Boulder, CO (United States); Palo, Scott [Univ. of Colorado, Boulder, CO (United States); Argrow, Brian [Univ. of Colorado, Boulder, CO (United States); LoDolce, Gabriel [Univ. of Colorado, Boulder, CO (United States); Curry, Nathan [Univ. of Colorado, Boulder, CO (United States); Weibel, Douglas [Univ. of Colorado, Boulder, CO (United States); Finnamore, W [Univ. of Colorado, Boulder, CO (United States); D' Amore, P [Univ. of Colorado, Boulder, CO (United States); Borenstein, Steven [Univ. of Colorado, Boulder, CO (United States); Nichols, Tevis [Univ. of Colorado, Boulder, CO (United States); Elston, Jack [Blackswift Technologies, Boulder, CO (United States); Ivey, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bendure, Al [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schmid, Beat [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Long, Chuck [National Oceanic and Atmospheric Administration (NOAA), Boulder, CO (United States). Earth System Research Lab.; Telg, Hagen [Univ. of Colorado, Boulder, CO (United States). Cooperative Inst. for Research in Environmental Sciences (CIRES); Gao, Rushan [National Oceanic and Atmospheric Administration (NOAA), Boulder, CO (United States). Earth System Research Lab.; Hock, T [National Center for Atmospheric Research, Boulder, CO (United States); Bland, Geoff [National Aeronautics and Space Administration (NASA), Washington, DC (United States)

    2017-03-01

    The Evaluation of Routine Atmospheric Sounding Measurements using Unmanned Systems (ERASMUS) campaign was proposed with two central goals; to obtain scientifically relevant measurements of quantities related to clouds, aerosols, and radiation, including profiles of temperature, humidity, and aerosol particles, the structure of the arctic atmosphere during transitions between clear and cloudy states, measurements that would allow us to evaluate the performance of retrievals from U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Climate Research Facility remote sensors in the Arctic atmosphere, and information on the spatial variability of heat and moisture fluxes from the arctic surface; and to demonstrate unmanned aerial system (UAS) capabilities in obtaining measurements relevant to the ARM and ASR programs, particularly for improving our understanding of Arctic clouds and aerosols.

  2. Riola release report

    Energy Technology Data Exchange (ETDEWEB)

    Woodward, E.C.

    1983-08-04

    Eleven hours after execution of the Riola Event (at 0826 PDT on 25 September 1980) in hole U2eq of the Nevada Test Site (NTS), a release of radioactivity began. When the seepage stopped at about noon the following day, up to some 3200 Ci of activity had been dispersed by light variable winds. On 26 September, examination of the geophone records showed six hours of low-level, but fairly continuous, activity before the release. Electrical measurements indicated that most cables were still intact to a depth below the stemming platform. A survey of the ground zero area showed that the seepage came through cracks between the surface conductor and the pad, through cracks in the pad, and through a crack adjacent to the pad around the mousehole (a small hole adjacent to the emplacement hole). To preclude undue radiation exposure or injury from a surprise subsidence, safety measures were instituted. Tritium seepage was suffucient to postpone site activities until a box and pipeline were emplaced to contain and remove the gas. Radiation release modeling and calculations were generally consistent with observations. Plug-hole interaction calculations showed that the alluvium near the bottom of the plug may have been overstressed and that improvements in the design of the plug-medium interface can be made. Experimental studies verified that the surface appearance of the plug core was caused by erosion, but, assuming a normal strength for the plug material, that erosion alone could not account for the disappearance of such a large portion of the stemming platform. Samples from downhole plug experiments show that the plug may have been considerably weaker than had been indicted by quality assurance (QA) samples. 19 references, 32 figures, 10 tables.

  3. Riola release report

    International Nuclear Information System (INIS)

    Woodward, E.C.

    1983-01-01

    Eleven hours after execution of the Riola Event (at 0826 PDT on 25 September 1980) in hole U2eq of the Nevada Test Site (NTS), a release of radioactivity began. When the seepage stopped at about noon the following day, up to some 3200 Ci of activity had been dispersed by light variable winds. On 26 September, examination of the geophone records showed six hours of low-level, but fairly continuous, activity before the release. Electrical measurements indicated that most cables were still intact to a depth below the stemming platform. A survey of the ground zero area showed that the seepage came through cracks between the surface conductor and the pad, through cracks in the pad, and through a crack adjacent to the pad around the mousehole (a small hole adjacent to the emplacement hole). To preclude undue radiation exposure or injury from a surprise subsidence, safety measures were instituted. Tritium seepage was suffucient to postpone site activities until a box and pipeline were emplaced to contain and remove the gas. Radiation release modeling and calculations were generally consistent with observations. Plug-hole interaction calculations showed that the alluvium near the bottom of the plug may have been overstressed and that improvements in the design of the plug-medium interface can be made. Experimental studies verified that the surface appearance of the plug core was caused by erosion, but, assuming a normal strength for the plug material, that erosion alone could not account for the disappearance of such a large portion of the stemming platform. Samples from downhole plug experiments show that the plug may have been considerably weaker than had been indicted by quality assurance (QA) samples. 19 references, 32 figures, 10 tables

  4. Use of phosphorus release batch tests for modelling an EBPR pilot plant

    DEFF Research Database (Denmark)

    Tykesson, E.; Aspegren, H.; Henze, Mogens

    2002-01-01

    The aim of this study was to evaluate how routinely performed phosphorus release tests could be used when modelling enhanced biological phosphorus removal (EBPR) using activated sludge models such as ASM2d. A pilot plant with an extensive analysis programme was used as basis for the simulations...

  5. Realism versus simplicity in the snow routine of the HBV model

    Science.gov (United States)

    Girons Lopez, Marc; Vis, Marc; Seibert, Jan

    2017-04-01

    The HBV model still enjoys great popularity, in part because of its simplicity. Depicting the hydrological processes in a catchment in a simple way reduces data requirements and minimises parameter uncertainty. However, the representation of some processes might benefit from an increased model complexity. This is, for instance, the case of snow routine in the HBV-light version of the HBV model. HBV-light uses a degree-day method with a single threshold parameter to distinguish between rain and snow and simulate snow melt. Recent research has shown that hydrological models with a more realistic representation of snow processes might be more successful in estimating runoff. In this study we explore and test different improvements to the HBV-light snow routine design by considering different threshold temperature values for rain and snow distinction as well as for the beginning of snow melt, and introducing gradual transitions instead of the current sharp threshold. The use of radiation data, which recently became available as gridded data product in Switzerland, is an additional possibility. These modifications would allow for a more realistic depiction of important hydrological processes in alpine and other snow-covered areas while preserving the characteristic simplicity of HBV. Furthermore, in this contribution we evaluate the balance between introducing more realism into the snow routine of the HBV model and keeping the number of parameters as low as possible.

  6. High School Teachers' Understanding of Blackbody Radiation

    Science.gov (United States)

    Balta, Nuri

    2018-01-01

    This study is a detailed look at the level of understanding of fundamental ideas about blackbody radiation (BBR) among physics teachers. The aim is to explore associations and ideas that teachers have regarding blackbody radiation: a concept used routinely in physics and chemistry, which is necessary to understand fundamentals of quantum physics.…

  7. PABLM, Doses from Radioactive Releases to Atmosphere and Food Chain

    International Nuclear Information System (INIS)

    Napier, B.A.; Kennedy, W.E. Jr.; Soldat, J.K.

    1983-01-01

    1 - Description of problem or function: PABLM calculates internal radiation doses to man from radionuclides in food products and external radiation doses from radionuclides in the environment. Radiation doses from radionuclides in the environment may be calculated from deposition on the soil or plants during an atmospheric or liquid release, or from exposure to residual radionuclides after the releases have ended. Radioactive decay is considered during the release, after deposition, and during holdup of food after harvest. The radiation dose models consider exposure to radionuclides deposited on the ground or crops from contaminated air or irrigation water, radionuclides in contaminated drinking water, aquatic foods raised in contaminated water, and radionuclides in bodies of water and sediments where people might fish, boat, or swim. For vegetation, the radiation dose model considers both direct deposition and uptake through roots. Doses may be calculated for either a maximum-exposed individual or for a population group. The program is designed to calculate accumulated radiation doses from the chronic ingestion of food products that contain radionuclides and doses from the external exposure to radionuclides in the environment. A first-year committed dose is calculated as well as an integrated dose for a selected number of years. 2 - Method of solution: A chain decay scheme including branching for transitions to and from isomeric states is used for radioactive decay. The equations for calculating internal radiation doses are derived from those given by the International Commission on Radio- logical Protection (ICRP) for body burdens and the maximum possible concentration (MPC) for each radionuclide. These doses are calculated as a function of radionuclide concentration in food products, ingestion rates, and a radionuclide-specific dose- commitment factor. Radiation doses from external exposure to contaminated water and soil are calculated using the basic assumption

  8. Review of radionuclides released from the nuclear fuel cycle and methods of assessing dose to man

    International Nuclear Information System (INIS)

    Bryant, P.M.

    1979-01-01

    There are two broad subject areas associated with releases of radionuclides from nuclear fuel cycle installations to the environment in which there are biological implications. One concerns interpretation of doses to man in terms of their radiological significance; the other concerns estimation of environmental transfer of radionuclides and of associated radiation doses to man. The radiation protection philosophy on which past practice regarding effluent releases of radionuclides to the environment was based is illustrated by drawing upon estimates of the associated radiation doses to man given in the 1977 report of the United Nations Scientific Committee on the Effects of Atomic Radiation. The present emphasis in radiation protection philosophy is illustrated by summarizing a review of environmental models relevant to estimation of radiation doses to population groups with reference to effluent releases of 3 H, 14 C, 85 Kr and 129 I; the author carried out the review as a contribution to a current study by an expert group set up by the Nuclear Energy Agency of OECD. Radionuclides of significance in the future may differ from those currently released to the environment because of possible developments in nuclear fuel cycles and options which may be exercised for disposal of high-level radioactive wastes, already in storage or postulated to be produced in the future. (author)

  9. 42 CFR 493.931 - Routine chemistry.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Routine chemistry. 493.931 Section 493.931 Public... Proficiency Testing Programs by Specialty and Subspecialty § 493.931 Routine chemistry. (a) Program content and frequency of challenge. To be approved for proficiency testing for routine chemistry, a program...

  10. 77 FR 28406 - Spent Fuel Transportation Risk Assessment

    Science.gov (United States)

    2012-05-14

    ... the release of some quantity of radioactive material during a severe accident. This investigation... assessment, the measure of safety was the risk of radiation doses to the public under routine and accident... assumptions has made the estimate of accident risk from the release of radioactive material in this study...

  11. Problem of routine photofluorography of the lungs of patients and medical personnel

    Energy Technology Data Exchange (ETDEWEB)

    Lehtinen, E; Pakkanen, J; Geiger, U [Zentralkrankenhaus, Tampere (Finland). Roentgendiagnostische Abteilung

    1978-02-01

    In the years 1974 and 1975 4,248 staff members of the hospital and 12,880 patients have been examined by photofluorography of the Central Hospital in Tampere. At the time of the examination no actual pulmonary or cardiac diseases were known to these patients. Among the staff two new cases of active pulmonary tuberculosis were found. Among the patients seven cases of reactivated pulmonary tuberculosis were found. Altogether there were 17 remarkable radiological results leading to treatment or follow-up examinations. A malignant pulmonary tumour was not found. The low number of positive results is not in a reasonable relation to the radiation risk; thus routine photofluorography is not indicated. Serial examinations of the staff should be continued. These examinations, however, should be made with large-size pictures, so that the radiation dose is reduced to about 20%.

  12. 3D planning and radiation oncology residents' training

    International Nuclear Information System (INIS)

    Jayaraman, Subramania

    1991-01-01

    Radiation treatments in radiation oncology clinics have been always planned to irradiate three dimensional (3D) volumes. Though the term 3D planning has come in vogue only in recent years, the essence of 3D planning had been always there. This is because the patient is a 3D subject and every treatment option adopted in a radiotherapy clinic has to be based on a 3D judgement of its acceptability. An essential aspect of training of radiation oncology residents is to help them understand the different techniques and methods used to get an acceptable 3D dose delivery. The tools of 3D planning should be introduced to the residents for their educational value. The regular use of these tools may require not only fast computers and work stations, but also a change of routine in the department. This might be difficult since the departmental routine can evolve only gradually. On the other hand, an insight about the advantages of the tools could be gained through a simple personal computer. Some examples of using the 3D planning tools through a personal computer, for educational purposes have been presented here, using clinical contexts routinely encountered. (author). 5 refs., 10 figs

  13. Environmental aspects of a tritium release from the Savannah River Plant on March 23, 1984

    International Nuclear Information System (INIS)

    Evans, A.G.; Hoel, D.D.; Kantelo, M.V.

    1985-01-01

    The environmental impact of a tritium release from the Savannah River Plant (SRP) on March 23, 1984, was assessed by using both predictive and measurement techniques. Prediction of the onsite and offsite consequences by the WIND emergency response system agreed with results determined from environmental samples. The maximum calculated radiation dose to an individual at the SRP boundary was 0.06 mrem. The maximum radiation dose to a hypothetical individual consuming milk collected at the point of highest airborne tritium concentration was calculated to be 0.17 mrem. The maximum measured (by urinalysis) dose to offsite individuals in the release trajectory was 0.02 mrem. The 0.17 mrem dose corresponds to 0.09% of the 189 mrem dose that persons who live in the vicinity of SRP receive annually from natural radiation, prorated medical radiation, and fallout. Thus the public health consequences of the release were insignificant. 11 references, 15 figures, 12 tables

  14. Canada: Living with radiation

    International Nuclear Information System (INIS)

    1995-01-01

    Canadians are exposed daily to a variety of naturally occurring radiation. Heat and light from the sun, are familiar examples. Radium and uranium are naturally occurring materials which have been found to emit radiation and so have been called radioactive. There are also various types of artificially produced forms of radiation that are employed routinely in modern living, such as radio and television waves and microwaves. X-rays, another common type of radiation, are widely used in medicine as are some man-made radioactive substances. These emit radiation just like naturally occurring radioactive materials. Surveys have shown that many people have a poor understanding of the risks associated with the activities of modern living. Exposure to ionizing radiation from radioactive materials is also considered by many persons to have a high risk, This booklet attempts to inform the readers about ionizing radiation, its uses and the risks associated with it, and to put these risks in perspective with the risks of other activities and practices. A range of topics from medical uses of radiation to emergency planning, from biological effects of radiation to nuclear power, each topic is explained to relate radiation to our everyday lives. 44 figs

  15. Canada: Living with radiation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    Canadians are exposed daily to a variety of naturally occurring radiation. Heat and light from the sun, are familiar examples. Radium and uranium are naturally occurring materials which have been found to emit radiation and so have been called radioactive. There are also various types of artificially produced forms of radiation that are employed routinely in modern living, such as radio and television waves and microwaves. X-rays, another common type of radiation, are widely used in medicine as are some man-made radioactive substances. These emit radiation just like naturally occurring radioactive materials. Surveys have shown that many people have a poor understanding of the risks associated with the activities of modern living. Exposure to ionizing radiation from radioactive materials is also considered by many persons to have a high risk, This booklet attempts to inform the readers about ionizing radiation, its uses and the risks associated with it, and to put these risks in perspective with the risks of other activities and practices. A range of topics from medical uses of radiation to emergency planning, from biological effects of radiation to nuclear power, each topic is explained to relate radiation to our everyday lives. 44 figs.

  16. Individual dose due to radioactivity accidental release from fusion reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nie, Baojie [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); University of Science and Technology of China, Hefei, Anhui, 230027 (China); Ni, Muyi, E-mail: muyi.ni@fds.org.cn [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); Wei, Shiping [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); University of Science and Technology of China, Hefei, Anhui, 230027 (China)

    2017-04-05

    Highlights: • Conservative early dose of different unit fusion radioactivity release were assessed. • Data of accident level in INES for fusion reactor were proposed. • Method of environmental restoration time after fusion accident was proposed. • The maximum possible accident level for ITER like fusion reactor is 6. • We need 34–52 years to live after the fusion hypothetical accident. - Abstract: As an important index shaping the design of fusion safety system, evaluation of public radiation consequences have risen as a hot topic on the way to develop fusion energy. In this work, the comprehensive public early dose was evaluated due to unit gram tritium (HT/HTO), activated dust, activated corrosion products (ACPs) and activated gases accidental release from ITER like fusion reactor. Meanwhile, considering that we cannot completely eliminate the occurrence likelihood of multi-failure of vacuum vessel and tokamak building, we conservatively evaluated the public radiation consequences and environment restoration after the worst hypothetical accident preliminarily. The comparison results show early dose of different unit radioactivity release under different conditions. After further performing the radiation consequences, we find it possible that the hypothetical accident for ITER like fusion reactor would result in a level 6 accident according to INES, not appear level 7 like Chernobyl or Fukushima accidents. And from the point of environment restoration, we need at least 69 years for case 1 (1 kg HTO and 1000 kg dust release) and 34–52 years for case 2 (1 kg HTO and 10kg–100 kg dust release) to wait the contaminated zone drop below the general public safety limit (1mSv per year) before it is suitable for human habitation.

  17. Electronic data processing in practical radiation protection: An evaluation of the situation in Switzerland

    International Nuclear Information System (INIS)

    Spiess, R.

    1998-01-01

    EDP tools and applications are intended to contribute reasonable, simple, safe and low-cost services in support of radiation protection activities, in order to relieve the human specialists from the routine data management work and give them time and opportunity to do the more creative work of establishing appropriate radiation protection schemes and routines in response to the needs of their working environment. This is the most common aspect and more so in those cases where the job of a radiation protection officer is a part-time job in addition to other tasks. (orig./CB) [de

  18. External radiation exposure of the public

    International Nuclear Information System (INIS)

    Mehl, J.

    1977-01-01

    Results of several ten thousand measurements on external radiation (outside buildings, in living rooms) are used for illustrating by isodose charts covering the total area of the Federal Republic of Germany the exposure of the public from external radiation originating from natural radiation of the environment. Results of calculations on external radiation exposure of the public due to releases of radioactivity in air from nuclear installations are used for illustrating by coloured isodose charts the exposure of the public in the plant site vicinity. From comparison of the exposure levels it becomes obvious that if exposure levels of several 10 mrem per year are considered to be of real concern to public health, control of natural radoactivity in the environment of man would require more attention than present and foreseeable releases of radioactivity in air from nuclear inst

  19. Incidents with hazardous radiation sources; Zwischenfaelle mit gefaehrlichen Strahlenquellen

    Energy Technology Data Exchange (ETDEWEB)

    Schoenhacker, Stefan [Bundesministerium fuer Inneres, Traiskirchen (Austria). Abt. 1/9 - Zivilschutzschule

    2016-07-01

    Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

  20. Environmental radiation monitoring

    International Nuclear Information System (INIS)

    Lachmann, Markus

    2012-01-01

    The report includes the following chapters: Development of earth and cosmic radiation - natural radioactivity. Atomic weapon tests and medicine - artificial radioactivity. A disaster and its consequences. From the air to humans; lessons learned from Chernobyl - division of work during measurements. From potatoes to baby food - the routine measuring program. Preparedness for the case of emergency - the intensive program. Three question for Martin Riepenhausen.

  1. Microfoundations of Routines and Capabilities

    DEFF Research Database (Denmark)

    Felin, Teppo; Foss, Nicolai Juul; Heimriks, Koen H.

    We discuss the microfoundations of routines and capabilities, including why a microfoundations view is needed and how it may inform work on organizational and competitive heterogeneity. Building on extant research, we identify three primary categories of micro-level components underlying routines...

  2. Modeling of radiation doses from chronic aqueous releases

    International Nuclear Information System (INIS)

    Watts, J.R.

    1976-01-01

    A general model and corresponding computer code were developed to calculate personnel dose estimates from chronic releases via aqueous pathways. Potential internal dose pathways are consumption of water, fish, crustacean, and mollusk. Dose prediction from consumption of fish, crustacean, or mollusk is based on the calculated radionuclide content of the water and applicable bioaccumulation factor. 70-year dose commitments are calculated for whole body, bone, lower large intestine of the gastrointestinal tract, and six internal organs. In addition, the code identifies the largest dose contributor and the dose percentages for each organ-radionuclide combination in the source term. The 1974 radionuclide release data from the Savannah River Plant were used to evaluate the dose models. The dose predicted from the model was compared to the dose calculated from radiometric analysis of water and fish samples. The whole body dose from water consumption was 0.45 mrem calculated from monitoring data and 0.61 mrem predicted from the model. Tritium contributed 99 percent of this dose. The whole body dose from fish consumption was 0.20 mrem calculated from monitoring data and 0.14 mrem from the model. Cesium-134,137 was the principal contributor to the 70-year whole body dose from fish consumption

  3. SUBDOSA: a computer program for calculating external doses from accidental atmospheric releases of radionuclides

    International Nuclear Information System (INIS)

    Strenge, D.L.; Watson, E.C.; Houston, J.R.

    1975-06-01

    A computer program, SUBDOSA, was developed for calculating external γ and β doses to individuals from the accidental release of radionuclides to the atmosphere. Characteristics of SUBDOSA are: doses from both γ and β radiation are calculated as a function of depth in tissue, summed and reported as skin, eye, gonadal, and total body dose; doses are calculated for releases within each of several release time intervals and nuclide inventories and atmospheric dispersion conditions are considered for each time interval; radioactive decay is considered during the release and/or transit using a chain decay scheme with branching to account for transitions to and from isomeric states; the dose from gamma radiation is calculated using a numerical integration technique to account for the finite size of the plume; and the program computes and lists the normalized air concentrations at ground level as a function of distance from the point of release. (auth)

  4. The situation of radiation curing

    International Nuclear Information System (INIS)

    Chen Weixiu

    1988-01-01

    Radiation curing is a branch of radiation processing. It has developed significantly and its annual growth rate exceeds 10% in the nineteen eighties. Several products were manufactured by radiation curing, such as magnetic media, release coating, floor tile, printing flates, optical fiber, electronics, lithography and pressure sensitive adhesives etc. The chemistry of radiation curing is often considered ahead. The safe handling of UV/EB curable material, the regulation of industial and the patent protection for development in radiation curing were introduced. The equipment and processes of this field have got progress recently

  5. Occupational radiation protection legislation in Israel

    International Nuclear Information System (INIS)

    Tadmor, J.; Schlesinger, T.; Lemesch, C.

    1980-01-01

    A committee of experts appointed by the Minister of Labour and Social Affairs has proposed a comprehensive draft regulation, concerning the legal aspects of occupational radiation protection in Israel. The first section of the proposed regulation sets forth guidelines for control in facilities where workers handle radioactive materials or radiation equipment. This includes the duties of the managers of such places to ensure adequate radiation protection and also the maximum recommended doses (whole body and individual organs) for radiation workers. The second section deals with the monitoring regulations for radiation workers who may be exposed to doses in excess of 500 mRem/y. The third section outlines the nature of the mechanical supervision required, i.e. routine and special examinations. Finally the committee also proposed six miscellaneous recommendations for radiation protection. (UK)

  6. Traceability of radiation measurements: musings of a user

    International Nuclear Information System (INIS)

    Kathren, R.L.

    1980-04-01

    Although users of radiation desire measurement traceability for a number of reasons, including legal, regulatory, contractual, and quality assurance requirements, there exists no real definition of the term in the technical literature. Definitions are proposed for both traceability and traceability to the National Bureau of Standards. The hierarchy of radiation standards is discussed and allowable uncertainties are given for each level. Areas of need with respect to radiation standards are identified, and a system of secondary radiation calibration laboratories is proposed as a means of providing quality calibrations and traceability on a routine basis

  7. Traceability of radiation measurements: musings of a user

    Energy Technology Data Exchange (ETDEWEB)

    Kathren, R.L.

    1980-04-01

    Although users of radiation desire measurement traceability for a number of reasons, including legal, regulatory, contractual, and quality assurance requirements, there exists no real definition of the term in the technical literature. Definitions are proposed for both traceability and traceability to the National Bureau of Standards. The hierarchy of radiation standards is discussed and allowable uncertainties are given for each level. Areas of need with respect to radiation standards are identified, and a system of secondary radiation calibration laboratories is proposed as a means of providing quality calibrations and traceability on a routine basis.

  8. Historical Doses from Tritiated Water and Tritiated Hydrogen Gas Released to the Atmosphere from Lawrence Livermore National Laboratory (LLNL). Part 5. Accidental Releases

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, S

    2007-08-15

    Over the course of fifty-three years, LLNL had six acute releases of tritiated hydrogen gas (HT) and one acute release of tritiated water vapor (HTO) that were too large relative to the annual releases to be included as part of the annual releases from normal operations detailed in Parts 3 and 4 of the Tritium Dose Reconstruction (TDR). Sandia National Laboratories/California (SNL/CA) had one such release of HT and one of HTO. Doses to the maximally exposed individual (MEI) for these accidents have been modeled using an equation derived from the time-dependent tritium model, UFOTRI, and parameter values based on expert judgment. All of these acute releases are described in this report. Doses that could not have been exceeded from the large HT releases of 1965 and 1970 were calculated to be 43 {micro}Sv (4.3 mrem) and 120 {micro}Sv (12 mrem) to an adult, respectively. Two published sets of dose predictions for the accidental HT release in 1970 are compared with the dose predictions of this TDR. The highest predicted dose was for an acute release of HTO in 1954. For this release, the dose that could not have been exceeded was estimated to have been 2 mSv (200 mrem), although, because of the high uncertainty about the predictions, the likely dose may have been as low as 360 {micro}Sv (36 mrem) or less. The estimated maximum exposures from the accidental releases were such that no adverse health effects would be expected. Appendix A lists all accidents and large routine puff releases that have occurred at LLNL and SNL/CA between 1953 and 2005. Appendix B describes the processes unique to tritium that must be modeled after an acute release, some of the time-dependent tritium models being used today, and the results of tests of these models.

  9. Limits for the release of uranium compounds to the environment

    International Nuclear Information System (INIS)

    Lopez, F.; Ferruz, P.; Aguayo, A.

    1987-01-01

    A conservative criteria to be be followed by a Regulatory Body, in order to provide the limits of radioactive material release in the environment, When all the parameters are not available for the optimization of radiation protection is presented. This criteria can be applied to stablishment of radioactive release limits for uranium compounds from the nuclear fuel cycle facilities. (author)

  10. Box model of radionuclide dispersion and radiation risk estimation for population in case of radioactivity release from nuclear submarine number-sign 601 dumped in the Kara Sea

    International Nuclear Information System (INIS)

    Yefimov, E.I.; Pankratov, D.V.; Ignatiev, S.V.

    1997-01-01

    When ships with nuclear reactors or nuclear materials aboard suffer shipwreck or in the case of burial or dumping of radioactive wastes, atmospheric fallout, etc., radionuclides may be released and spread in the sea, contaminating the sea water and the sea bottom. When a nuclear submarine (NS) is dumped this spread of activity may occur due to gradual core destruction by corrosion over many years. The objective of this paper is to develop a mathematical model of radionuclide dispersion and to assess the population dose and radiation risk for radionuclide release from the NS No. 601, with Pb-Bi coolant that was dumped in the Kara Sea

  11. Consuming technologies - developing routines

    DEFF Research Database (Denmark)

    Gram-Hanssen, Kirsten

    2008-01-01

    technologies and in this article these processes will be investigated from three different perspectives: an historical perspective of how new technologies have entered homes, a consumer perspective of how both houses and new technologies are purchased and finally, as the primary part of the article, a user...... perspective of how routines develop while these technologies are being used. In the conclusion these insights are discussed in relation to possible ways of influencing routines....

  12. Radioactive iodine releases from nuclear power plant, (2)

    International Nuclear Information System (INIS)

    Naritomi, Mitsuo

    1974-01-01

    Internal radiation dose through the respiratory intake of fission products is predominantly due to radioactive iodine not only at the time of reactor accidents but also in normal operation of nuclear facilities. Technological studies in this field have thus been quite active to this day. With the rapid advance of nuclear power generation in recent years, the efforts to reduce environmental release of radioactive iodine and to enhance environmental safety are all the more emphasized. Experiences in the Japan Atomic Energy Research Institute during past about six years are described concerning the radioactive iodine release to the atmosphere in 131 I production and the measures taken to reduce the release. Then, problems are expounded regarding the radioactive iodine release at the time of reactor accidents and in spent fuel reprocessing. (Mori, K.)

  13. SHAKER Version 0.0/5 Pre-release Notes

    CERN Document Server

    CERN. Geneva

    1993-01-01

    SHAKER V0.0/5 is a pre-release of a simple cocktail central rapidity phase space event generator developed for the simulation of LHC Heavy Ion events. A modified version of JETSET 7.3 (the / LUJETS / common has been enlarged to 50000 particles and the LUEDIT routine has been modified to rearrange the particle weights vectors when called with MEDIT=1) is used to manage the events. All event information is included in / LUJETS / according to Lund conventions [1].

  14. Publicly Released Prompt Radiation Spectra Suitable for Nuclear Detonation Simulations

    Science.gov (United States)

    2017-03-01

    emission. During the Hiroshima and Nagasaki bombings , the prompt radiation contributed from 40%-70% of the free-in-air dose depending on distance from...intermediate- and low-yield thermonuclear weapons for initial radiation shielding calculations No Gritzner, et al. 1976 ( EM -1, Low, Henre...DNA 4267F ( EM -1 Fission) Neutron Gritzner, et al. 1976 1.00 x 1023 Glasstone (Thermonuclear) Neutron Glasstone & Dolan 1977 1.445 x 1023 ORNL-TM

  15. Release Report for Building Debris for TA-21 Sewage Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Whicker, Jeffrey Jay [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gillis, Jessica [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-05-03

    ENV-ES finds that the materials associated with TA-21 Buildings 227 (superstructure only), and 229 (see Figure 1) meet the criteria for unrestricted release to the public for recycle or as sanitary/commercial waste. The interior and exterior of the metal shed, building 387, passed the release criteria collectively; however, results from the roof of the structure were above reference background measurements. Waste management should be consulted for waste disposition options for the roofing metal. These findings are consistent with the requirements of DOE Order 458.1 “Radiation Protection of the Public and the Environment” and LANL Policy 412 “Environmental Radiation Protection.” Sampling and data analysis, as described in this report, were sufficient to meet measurement objectives under the Multi-Agency Radiation Survey and Assessment of Materials and Equipment (MARSAME) manual (2009).

  16. Technique for comparing automatic quadrature routines

    Energy Technology Data Exchange (ETDEWEB)

    Lyness, J N; Kaganove, J J

    1976-02-01

    The present unconstrained proliferation of automatic quadrature routines is a phenomenon which is wasteful in human time and computing resources. At the root of the problem is an absence of generally acceptable standards or benchmarks for comparing or evaluating such routines. In this paper a general technique, based on the nature of the performance profile, is described which can be used for evaluation of routines.

  17. EVIDOS: Individual dosimetry in mixed neutron and photon radiation fields

    International Nuclear Information System (INIS)

    Vanhavere, F.

    2006-01-01

    The EVIDOS project (partly funded by the European Commission RTD Programme: Nuclear Energy, Euratom Framework Programme V, 1998-2002, Contract No FIKR-CT-2001-00175) aimed at improving individual monitoring in mixed neutron-photon radiation fields by evaluating the performance of routine and novel personal dosimeters for mixed radiation, and by giving guidelines for deriving sufficiently accurate values of personal dose equivalent from the readings of area survey instruments and dosimeters. The main objective of EVIDOS was to evaluate different methods for individual dosimetry in mixed neutron-photon work-places in nuclear industry. This implied a determination of the capabilities and limitations of personal dosimeters and the establishment of methods to enable sufficiently accurate values of personal dose equivalent from spectrometers, area survey instruments and routine personal dosimeters. Also novel electronic personal dosimeters were investigated. To this end spectrometric and dosimetric investigations in selected representative workplaces in nuclear industry where workers can receive significant neutron doses were performed. As part of this project, a number of tasks were executed, in particular: (1) the determination of the energy and direction distribution of the neutron fluence; (2) the derivation of the (conventionally true) values of radiation protection quantities; (3) the determination of the readings of routine and innovative personal dosimeters and of area monitors; and (4) the comparison between dosimeter readings and values of the radiation protection quantities

  18. Release process for non-real property containing residual radioactive material

    International Nuclear Information System (INIS)

    Ranek, N.L.; Chen, S.Y.; Kamboj, S.; Hensley, J.; Burns, D.; Fleming, R.; Warren, S.; Wallo, A.

    1997-01-01

    It is DOE's objective to operate its facilities and to conduct its activities so that radiation exposures to members of the public are maintained within acceptable limits and exposures to residual radioactive materials are controlled. To accomplish this, DOE has adopted Order DOE 5400.51 'Radiation Protection of the Public and the Environment', and will be promulgating IO CR Part 834 to codify and clarify the requirements of DOE 5400.5. Under both DOE 5400.5 and 10 CR Part 834, radioactively contaminated DOE property is prohibited from release unless specific actions have been completed prior to the release. This paper outlines a ten-step process that, if followed, will assist DOE Operations and contractor personnel in ensuring that the required actions established by Order DOE 5400.5 and 10 CR Part 834 have been appropriately completed prior to the release for reuse or recycle of non-real property (e.g., office furniture, computers, hand tools, machinery, vehicles and scrap metal). Following the process will assist in ensuring that radiological doses to the public from the released materials will meet applicable regulatory standards and be as low as reasonably achievable (ALARA)

  19. Automatization of the radiation control measurements

    International Nuclear Information System (INIS)

    Seki, Akio; Ogata, Harumi; Horikoshi, Yoshinori; Shirai, Kenji

    1988-01-01

    Plutonium Fuel Production Facility (PFPF) was constructed to fabricate the MOX fuels for 'MONJU' and 'JOYO' reactors and to develop the practical fuel fabricating technology. For the fuel fabrication process in this facility, centralized controlling system is being adopted for the mass production of the fuel and reduction of the radiation exposure dose. Also, the radiation control systems are suitable for the large-scale facility and the automatic-remote process of the fuel fabrication. One of the typical radiation control systems is the self moving survey system which has been developed by PNC and adopted for the automatic routine monitoring. (author)

  20. PET/CT in Radiation Therapy Planning

    DEFF Research Database (Denmark)

    Specht, Lena; Berthelsen, Anne Kiil

    2018-01-01

    Radiation therapy (RT) is an important component of the management of lymphoma patients. Most lymphomas are metabolically active and accumulate 18F-fluorodeoxyglucose (FDG). Positron emission tomography with computer tomography (PET/CT) imaging using FDG is used routinely in staging and treatment...

  1. Release mitigation spray safety systems for chemical demilitarization applications.

    Energy Technology Data Exchange (ETDEWEB)

    Leonard, Jonathan; Tezak, Matthew Stephen; Brockmann, John E.; Servantes, Brandon; Sanchez, Andres L.; Tucker, Mark David; Allen, Ashley N.; Wilson, Mollye C.; Lucero, Daniel A.; Betty, Rita G.

    2010-06-01

    Sandia National Laboratories has conducted proof-of-concept experiments demonstrating effective knockdown and neutralization of aerosolized CBW simulants using charged DF-200 decontaminant sprays. DF-200 is an aqueous decontaminant, developed by Sandia National Laboratories, and procured and fielded by the US Military. Of significance is the potential application of this fundamental technology to numerous applications including mitigation and neutralization of releases arising during chemical demilitarization operations. A release mitigation spray safety system will remove airborne contaminants from an accidental release during operations, to protect personnel and limit contamination. Sandia National Laboratories recently (November, 2008) secured funding from the US Army's Program Manager for Non-Stockpile Chemical Materials Agency (PMNSCMA) to investigate use of mitigation spray systems for chemical demilitarization applications. For non-stockpile processes, mitigation spray systems co-located with the current Explosive Destruction System (EDS) will provide security both as an operational protective measure and in the event of an accidental release. Additionally, 'tented' mitigation spray systems for native or foreign remediation and recovery operations will contain accidental releases arising from removal of underground, unstable CBW munitions. A mitigation spray system for highly controlled stockpile operations will provide defense from accidental spills or leaks during routine procedures.

  2. Development of environment radiation database management system

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Jong Gyu; Chung, Chang Hwa; Ryu, Chan Ho; Lee, Jin Yeong; Kim, Dong Hui; Lee, Hun Sun [Daeduk College, Taejon (Korea, Republic of)

    1999-03-15

    In this development, we constructed a database for efficient data processing and operating of radiation-environment related data. Se developed the source documents retrieval system and the current status printing system that supports a radiation environment dta collection, pre-processing and analysis. And, we designed and implemented the user interfaces and DB access routines based on WWW service policies on KINS Intranet. It is expected that the developed system, which organizes the information related to environmental radiation data systematically can be utilize for the accurate interpretation, analysis and evaluation.

  3. Development of environment radiation database management system

    International Nuclear Information System (INIS)

    Kang, Jong Gyu; Chung, Chang Hwa; Ryu, Chan Ho; Lee, Jin Yeong; Kim, Dong Hui; Lee, Hun Sun

    1999-03-01

    In this development, we constructed a database for efficient data processing and operating of radiation-environment related data. Se developed the source documents retrieval system and the current status printing system that supports a radiation environment dta collection, pre-processing and analysis. And, we designed and implemented the user interfaces and DB access routines based on WWW service policies on KINS Intranet. It is expected that the developed system, which organizes the information related to environmental radiation data systematically can be utilize for the accurate interpretation, analysis and evaluation

  4. Sterilization of health care products - Radiation. Part 1: Requirements for development, validation and routine control of a sterilization process for medical devices

    International Nuclear Information System (INIS)

    2006-01-01

    A sterile medical device is one that is free of viable microorganisms. International Standards, which specify requirements for validation and routine control of sterilization processes, require, when it is necessary to supply a sterile medical device, that adventitious microbiological contamination of a medical device prior to sterilization be minimized. Even so, medical devices produced under standard manufacturing conditions in accordance with the requirements for quality management systems (see, for example, ISO 13485) may, prior to sterilization, have microorganisms on them, albeit in low numbers. Such medical devices are non-sterile. The purpose of sterilization is to inactivate the microbiological contaminants and thereby transform the nonsterile medical devices into sterile ones. The kinetics of inactivation of a pure culture of microorganisms by physical and/or chemical agents used to sterilize medical devices can generally best be described by an exponential relationship between the numbers of microorganisms surviving and the extent of treatment with the sterilizing agent; inevitably this means that there is always a finite probability that a microorganism may survive regardless of the extent of treatment applied. For a given treatment, the probability of survival is determined by the number and resistance of microorganisms and by the environment in which the organisms exist during treatment. It follows that the sterility of any one medical device in a population subjected to sterilization processing cannot be guaranteed and the sterility of a processed population is defined in terms of the probability of there being a viable microorganism present on a medical device. This part of ISO 11137 describes requirements that, if met, will provide a radiation sterilization process intended to sterilize medical devices, that has appropriate microbicidal activity. Furthermore, compliance with the requirements ensures that this activity is both reliable and

  5. Clinical evaluation of the intraoral fluoride releasing system in radiation-induced xerostomic subjects. Part 2: Phase I study.

    Science.gov (United States)

    Chambers, Mark S; Mellberg, James R; Keene, Harris J; Bouwsma, Otis J; Garden, Adam S; Sipos, Tibor; Fleming, Terence J

    2006-10-01

    Radiation-induced xerostomia can result in the rapid onset and progression of dental caries in head and neck cancer patients. Topically applied fluorides have been successfully used to inhibit the formation of dental caries in this population. However, because intensive daily self-application is required, compliance is an issue. The intraoral fluoride-releasing system (IFRS) containing a sodium fluoride core is a newly developed, sustained-release, passive drug delivery system that does not require patient involvement except for periodic replacement, thus reducing the effect of patient compliance on its effectiveness in dental caries prevention. Twenty-two head and neck cancer patients from U. T. M. D. Anderson Cancer Center, with radiation-induced xerostomia, were entered into a pilot study to contrast the daily home use of a 0.4% stannous fluoride-gel-containing tray (control group) to IFRS (study group) with respect to tolerability and adherence, and to obtain information on relative caries preventive efficacy. Participants were stratified on the basis of radiation exposure and randomly assigned to treatment with either IFRS or stannous fluoride gel. Patients in both groups were fitted with two IFRS retainers and also were instructed to use a 1100-ppm fluoride conventional sodium fluoride dentifrice twice daily. The study was conducted as a single-blinded, parallel-cell trial. Pre-existing carious lesions were restored prior to the beginning of the study. The efficacy variable was determined by the mean number of new or recurrent decayed surfaces. Patients were examined for caries 4, 8, 12, 24, 36, and 48 weeks after initiation of treatment. Reports of adverse reactions were based on information volunteered by patients and that were elicited during interviews. At baseline, the resting and stimulated salivary flow rates (g/5min) were significantly greater in the control group than in the study group (pIFRS groups during the study period. The rate of new or

  6. Modulated Hawking radiation and a nonviolent channel for information release

    OpenAIRE

    Giddings, Steven B.

    2014-01-01

    Unitarization of black hole evaporation requires that quantum information escapes a black hole; an important question is to identify the mechanism or channel by which it does so. Accurate counting of black hole states via the Bekenstein–Hawking entropy would indicate this information should be encoded in radiation with average energy flux matching Hawking's. Information can be encoded with no change in net flux via fine-grained modulation of the Hawking radiation. In an approximate effective ...

  7. Environmental radiation and exposure to radiation

    International Nuclear Information System (INIS)

    1981-02-01

    Compared to 1977 the exposure to radiation of the population of the Federal Republic of Germany from both natural and artificial radiation sources has not greatly charged. The amin part of exposure to natural radiation is caused by environmental radiation and by the absorption of naturally radioactive substances into the body. Artificial exposure to radiation of the population is essentially caused by the use of ionizing rays and radioactive substances in medicine. When radioactive materials are released from nuclear facilities the exposure to radiation of the population is only very slightly increased. The real exposure to radiation of individual people can even in the worst affected places, have been at most fractions of a millirem. The exposure to radiation in the worst afected places in the area of a hard-coal power station is higher than that coming from a nuclear power station of the same capacity. The summation of all contributions to the exposure of radiation by nuclear facilities to the population led in 1978 in the Federal Republic of Germany to a genetically significant dose of clearly less than 1 millerem per year. The medium-ranged exposure to radiation by external radiation effects through professional work was in 1978 at 80 millirems. No difference to 1977. The contribution of radionuclide from the fallout coming from nuclear-weapon tests and which has been deposited in the soil, to the whole-body dose for 1978 applies the same as the genetically significant dose of the population with less than 1 millirem. (orig./HP) [de

  8. Effects of radiations on electronic components - Course IN2P3, release 6

    International Nuclear Information System (INIS)

    2007-01-01

    As many off-the-shelf electronic components are now present onboard satellites, launchers and planes, this course proposes an overview of effects radiations can have on these components, notably in space applications. A first part proposes an overview of radiative environments, and more particularly presents the space radiative environment (solar wind, solar flares, cosmic radiation, radiation belts). It also presents the atmospheric and Earth radiative environment due to cosmic radiation, the alpha radiation (origin of particles, particle flow), the radiative environment within an accelerator. The second part addresses the effects of these radiative environments on electronic components, and the associated standards and tests. It addresses cumulative effects and proposes a detailed analysis of the effects of an ionizing dose on a MOS transistor, an analysis of the effects of ionising dose rate on a bipolar NPN or PNP vertical or lateral transistor, an analysis of the effects of atomic displacements, and a discussion of structure modifications. The next part describes various single events: the Single Event Upset (SEU) and the Multiple Bit Upset (MBU) in the case of a SRAM, the SEL (Single Event Latch-up) phenomenon, the SEGR (Single Event Gate Rupture) phenomenon in the case of a Power MOSFET, and the SEB (Single Event Burnout) phenomenon in the case of a Power MOSFET

  9. Yes to early detection of cancer - no to routine mammography examinations. Parting from wishful thinking, turning to new strategies

    International Nuclear Information System (INIS)

    Dersee, T.; Dieckmann, H.; Koehnlein, W.; Kuni, H.; Lengfelder, E.; Pflugbeil, S.; Schmitz-Feuerhake, I.

    2002-01-01

    Many experts find it difficult to accept what experience has shown, namely that routine mammography examinations have lowered neither the breast cancer fatality rate nor the crude death rate. One aspect that has been neglected in propagating screenings is the high radiation sensitivity of genetically predisposed females (0.5% - 1.0%). These females should not be exposed to repeated X-rays for screening purposes. True preventive measures, which promise significant effects, include the avoidance of radiation exposure, especially during the early stages of life, and a restrictive use of oestrogen substitution therapies

  10. Yes to early detection of cancer - no to routine mammography examinations. Parting from wishful thinking, turning to new strategies

    CERN Document Server

    Dersee, T; Koehnlein, W; Kuni, H; Lengfelder, E; Pflugbeil, S; Schmitz-Feuerhake, I

    2002-01-01

    Many experts find it difficult to accept what experience has shown, namely that routine mammography examinations have lowered neither the breast cancer fatality rate nor the crude death rate. One aspect that has been neglected in propagating screenings is the high radiation sensitivity of genetically predisposed females (0.5% - 1.0%). These females should not be exposed to repeated X-rays for screening purposes. True preventive measures, which promise significant effects, include the avoidance of radiation exposure, especially during the early stages of life, and a restrictive use of oestrogen substitution therapies.

  11. Monitoring water for radioactive releases in the United States

    International Nuclear Information System (INIS)

    Porter, C.R.; Broadway, J.A.; Kahn, B.

    1990-01-01

    The major radiological environmental monitoring programs for water in the United States are described. The applications of these programs for monitoring radioactive fallout, routine discharges from nuclear facilities, and releases due to accidents at such facilities are discussed, and some examples of measurements are presented. The programs monitor rainfall, surface water, and water supplies. Samples are usually collected and analyzed on a monthly or quarterly schedule, but the frequency is increased in response to emergencies. (author)

  12. Radioactive iodine releases from nuclear power plant, (1)

    International Nuclear Information System (INIS)

    Hashimoto, Tatsuya

    1974-01-01

    Concerning the release of radioactive iodine from nuclear power plants, the guidelines and data both in Japan and abroad are briefed, including those in the United States, Tsuruga nuclear power station and working Group of the Environmental Radiation Study Committee. In case of the Tsuruga nuclear power station, the radiation dose and other data for a few years are presented. Parameters and factors proposed by the working group cover such as the dose through food intake and respiration, concentration factor, etc. (Mori, K.)

  13. ERMS - Environmental Radiation Monitoring System

    International Nuclear Information System (INIS)

    Vax, Eran; Sarusi, Benny; Sheinfeld, Mati; Levinson, Shmuel; Brandys, Irad; Sattinger, Danny; Wengrowicz, Udi; Tshuva, Avi; Tirosh, Dan

    2008-01-01

    A new Environmental Radiation Monitoring System (ERMS) has been developed in the NRCN as an extensive tool to be applied in case of nuclear malfunction or Nuclear Disposal Device (NDD) incident, as well as for routine radiation monitoring of the reactor's vicinity. The system collects real-time environmental data such as: gamma radiation, wind speed, wind direction, and temperature for monitoring purposes. The ERMS consists of a main Control Center and an array of monitoring stations. Fixed, environmental, gamma radiation monitoring stations are installed at the reactor's surroundings while portable stations can be posted rapidly along the wind direction, enhancing the spatial sampling of the radiation measurements and providing better hazard assessment at an emergency event. The presented ERMS, based on industrial standards for hardware and network protocols, is a reliable standalone system which upgrades the readiness to face a nuclear emergency event by supplying real-time, integrated meteorological and radiation data. (author)

  14. Radiation in everyday life

    International Nuclear Information System (INIS)

    Wahlstroem, B.

    1994-01-01

    The world is radioactive. Radioactive substances and radiation existed on Earth before the first man was born. Radiation reaches man from the cosmos and is also emitted from radioactive substances in the ground, in construction material, in the food and the air. All people are radioactive, too. For instance, all people have got radioactive Radium and Polonium in their skeleton, radioactive Carbon and Potassium in their muscles and radioactive noble gases and Tritium in their lungs. The radiation emitted by the body can be measured by a very sensitive radiation meter called a Whole Body Counter. This paper is a discussion of natural radioactivity and the increased exposure to radiations released by energy production and medical testing

  15. Ionizing radiation perception by insects

    International Nuclear Information System (INIS)

    Campanhola, C.

    1980-04-01

    The proof of the existence of a perception for ionizing radiation by insects was aimed at, as well as the determination of its processing mechanism. It was tried also to check if such perception induces the insects to keep away from the radiation source, proving therefore a protection against the harms caused by ionizing radiation, or else the stimulus for such behaviour is similar to that caused by light radiations. 60 Co and 241 Am were used as gamma radiation sources, the 60 Co source of 0.435mCi and the 241 Am of 99.68mCi activity. Adult insects were used with the following treatments : exposure to 60 Co and 241 Am radiation and non-exposure (control). A total of approximately 50 insects per replication was released in the central region of an opaque white wooden barrier divided into 3 sections with the same area - 60.0 cm diameter and 7.5 cm height - covered with a nylon screen. 5 replications per treatment were made and the distribution of the insects was evaluated by photographs taken at 15, 30, 45, and 60 minutes after release. Sitophilus oryzae (l., 1763) and Ephestia cautella (Walker, 1864) showed some response to 241 Am gamma radiation, i.e. negative tactism. It was concluded that ionizing radiations can be detected by insects through direct visual stimulus or by visual stimulus reslting from interaction of radiation-Cerenkov radiation - with some other occular component with a refraction index greater than water. Also, the activity of the radioactive source with regard to perception for ionizing radiation, is of relevance in comparison with the energy of the radiation emitted by same, or in other words, what really matters is the radiation dose absorbed. (Author) [pt

  16. Problems of radiation genetics. [In Russian

    Energy Technology Data Exchange (ETDEWEB)

    Dubinin, N P

    1956-01-01

    A general review is presented of recent experiments in genetics. Mutant and hereditary effects of the increase in natural radiation and that released by atomic and hydrogen tests were analyzed. Achievements and the possibilities of applying radiation in the induction of selective plant mutations are discussed.

  17. Active Movement Warm-Up Routines

    Science.gov (United States)

    Walter, Teri; Quint, Ashleigh; Fischer, Kim; Kiger, Joy

    2011-01-01

    This article presents warm-ups that are designed to physiologically and psychologically prepare students for vigorous physical activity. An active movement warm-up routine is made up of three parts: (1) active warm-up movement exercises, (2) general preparation, and (3) the energy system. These warm-up routines can be used with all grade levels…

  18. Radiation education in elementary school

    International Nuclear Information System (INIS)

    Harima, Yoshiko; Matsuda, Teruo; Ootake, Shigehiro; Ikeda, Masamichi

    1999-01-01

    Lessons to measure natural radiation have been given at the fourth elementary school of Hikari-gaoka, Nerima-ku, Tokyo, for three years. The Method of Lessons: After hearing a brief explanation about natural radiation and usage of a simple instrument of gamma ray named 'Hakaru-kun' by a lecturer (Fig. 1), every child participates to measure dose rate at several measured points within the range of school campus (Figs. 5 - 14). They calculate the average value of measured dose rate (Fig. 2) and affix tags written the average value (Fig. 3). In addition, by looking at the photographs, through the imaging plate, of radiations released from vegetables and pork, they are surprised at the fact that all the food have such activities. Finally, they watch marks of alpha particles released from the ore of samarskite in a cloud chamber. The alpha particles fly in alcohol vapor over saturated cooled with dry ice (Fig. 15). They express their impression of lesson for finding out the existence of natural radiation in their reports. (Table 1 and Fig. 4). (author)

  19. Individual radiation doses from unit releases of long lived radionuclides

    International Nuclear Information System (INIS)

    Bergstroem, U.; Nordlinder, S.

    1990-04-01

    The turn-over in a standard biosphere of radionuclides, disposed in a repository for high level waste was studied from a dose point of view. A multi-compartment model with unit releases to the biosphere was designed and solved by the BIOPATH-code. The uncertainty in the results due to the uncertainty in input parameter values were examined for all nuclides with the PRISM-system. Adults and five year old children were exposed from 10 different exposure pathways originating from activity in well and lake water. The results given as total doses per year and Bq release (conversion factors) can be used in combination with leakage rates from the geosphere for safety analysis of a repository. The conversion factors obtained (arithmetic mean values), are given. (65 refs.) (authors)

  20. Fit Between Organization Design and Organizational Routines

    Directory of Open Access Journals (Sweden)

    Constance E. Helfat

    2014-07-01

    Full Text Available Despite decades of research on both organization design and organizational routines, little research has analyzed the relationship between them. Here we propose a normative theory in which the effectiveness of organization design and redesign depends on the characteristics of routines. The analysis shows which types of organization designs may be useful as well as which design changes may or may not succeed depending on (a the specificity of routines and (b the dynamic versus static purposes of organizational routines.

  1. Arct'Alg release from hydrogel membranes

    International Nuclear Information System (INIS)

    Amaral, Renata H.; Rogero, Sizue O.; Shihomatsu, Helena M.; Lugao, Ademar B.

    2009-01-01

    The hydrogel properties make them attractive for a variety of biomedical and pharmaceutical applications, primarily in drug delivery system. Synthetic hydrogels have been studied to develop new devices for drugs or cosmetic active agents release. Arct'Alg R is an extract derived from red algae biomass which has antioxidant, anti-inflammatory and tissue regeneration stimulant properties. This extract was incorporated to poly(N-vinyl pyrrolidone) (PVP) and poly(vinyl alcohol) (PVA) hydrogel membranes obtained by gamma rays crosslinking technique. The ionizing radiation presents the advantage to occur polymerization and sterilization simultaneously in the same process. The aim of this work was the in vitro release kinetic study of Arct'Alg R from hydrogel membranes during 24 hours to verify the possibility of use in cosmetic and dermatological treatments. Results showed that about 50% and 30% of incorporated Arct'Alg R was released from PVP and PVA hydrogel membrane devices respectively. (author)

  2. Recommendations to the Technical Steering Panel regarding approach for estimating individual radiation doses resulting from releases of radionuclides to the Columbia River

    International Nuclear Information System (INIS)

    Napier, B.A.; Brothers, A.J.

    1992-07-01

    At the direction of the Technical Steering Panel (TSP) of the Hanford Environmental Dose Reconstruction (HEDR) Project, Battelle staff have reviewed and analyzed available data regarding possible historical radiation doses to individuals resulting from radionuclide releases to the Columbia River. The objective of this review was to recommend to the TSP the spatial and temporal scope and level of effort on Columbia River work to most effectively extend work performed in Phase I of the project (PNL 1991a, PNL 1991b) to meet the project objectives. A number of options were analyzed. Four stretches of the Columbia River and adjacent Pacific coastal waters were defined and investigated for four time periods. Radiation doses arising from ten potentially major exposure pathways were evaluated for each of the time/location combinations, and several alternative methods were defined for estimating the doses from each pathway. Preliminary cost estimates were also developed for implementing dose estimation activities for each of the possible combinations

  3. Quality assurance in radiation measurement

    International Nuclear Information System (INIS)

    Noriah Mod Ali

    2002-01-01

    The achievement of traceability to recognize measurement standards for ionizing radiation posses special requirements. Methods of transferring reference standard to the working situation are devised through calibration and appropriate traceability, which optimize the accuracy attainable with the method of dose determination in routine use. Appropriate procedures are developed by the SSDL-MINT to establish accurate dose measurement in wide range of radiation fields such as in medicine, agriculture and industrial application. The status of work including effort towards ISO 9000 certification of SSDL dosimetry services will be summarized. (Author)

  4. Skin dose assessment in routine personnel beta/gamma dosimetry

    International Nuclear Information System (INIS)

    Christensen, P.

    1980-01-01

    Three alternative methods are outlined by which substantial improvements of the capabilities of existing routine monitoring systems for skin dose assessment can be obtained. The introduction of a supplementary skin dosemeter may be an attractive method for systems with badges that have a capability for an additional dosemeter already built-in. The two-side reading method has limited possibilities because of reduced accuracy for mixed radiation and technical difficulties in using it for TLD systems with planchet heating. The use of a boron diffused LiF layer for skin dose assessment seems to be most attractive method since the only modification needed here is replacement of a dosemeter. However the study of this method is so far only in a preliminary stage and further investigations are needed. (U.K.)

  5. Study the Effect of Gamma Radiation on some Solid and Polymeric Materials and Its Possible Applications in Radiation Dosimetry

    International Nuclear Information System (INIS)

    El-Shawadfy, E.R.

    2015-01-01

    Dyed solid materials (films and gels) and dyed solutions dosimeters have wide-spread applications in radiation processing for installation process qualification and routine dose control for both gamma rays and electron beam irradiation. These film dosimeters have been introduced for low- and high-dose monitoring. The introduction of new types of dosimeters is due to the effort of seeking for more reliable, more stable, simpler and cheaper systems as routine dosimeters and/or label dosimeters. The main objective of this work is to study the possibility of preparing dyed solid polymeric materials (dyed films- dyed gels) and dyed solutions, and study the dosimetric studies for the prepared materials. The results obtained in this work can be summarized in the following: Section (1): Deals with the investigation of prepared three dosimetry systems based on Toludine Blue O (TBO) dye, to make them readily usable in high and low-radiation dosimetry applications (e.g. sterilization of medical products, sterilization of pharmaceutical products and polymer modification). This section is divided into three parts: Part I: This part includes the preparation and development of polymeric films for high-dose dosimetry applications, these films are based on poly (vinyl alcohol) dyed with TBO. These flexible plastic film dosimeters are bleached when exposed to gamma-ray photons (i.e. from blue to colorless) at λmax=633 nm. The radiation chemical yield (G-Value) for different concentrations of the dye as well as the dye with additive substances (chloral hydrate) was calculated. It was found that these films are highly stable for long time before and after irradiation under different storage conditions. The response of these films is not affected by humidity change in the range of relative humidity (0-56%). PVA films dyed with TBO are suitable in the dose range from 1-150 kGy. These properties suggest them to be useful for routine and dose mapping in sterilization range of radiation

  6. Evaluation of work routines in PET/CT service with and individual tool in real time

    International Nuclear Information System (INIS)

    Moreira, Maryana N.; Oliveira, Fernanda R. de; Fischer, Andreia C.F.S.; Bacelar, Alexandre

    2016-01-01

    This study used a direct monitoring system (RemoteDose) that presents the individual dose and dose rate measurements, plotted instantly, as a tool to evaluate work routines of Individuals Occupationally Exposed (IOE) of a PET/CT Service. With this evaluation was possible to identify the critical tasks performed by each work team (Pharmaceutical/Nursing/Radiology Technician team) for subsequent optimization of patient care processes. It was also possible to assess whether these tasks are properly distributed among this teams. The RemoteDose system proved to be able to assist the optimization of radiation protection of a PET/CT Service, proving to be an important ally of the Radiation Protection Supervisor in this process, since it allows the display of real-time monitoring. (author)

  7. Dosimetry for radiation processing

    International Nuclear Information System (INIS)

    McLaughlin, W.L.; Boyd, A.W.; Chadwick, K.H.; McDonald, J.C.; Miller, A.

    1989-01-01

    Radiation processing is a relatively young industry with broad applications and considerable commercial success. Dosimetry provides an independent and effective way of developing and controlling many industrial processes. In the sterilization of medical devices and in food irradiation, where the radiation treatment impacts directly on public health, the measurements of dose provide the official means of regulating and approving its use. In this respect, dosimetry provides the operator with a means of characterizing the facility, of proving that products are treated within acceptable dose limits and of controlling the routine operation. This book presents an up-to-date review of the theory, data and measurement techniques for radiation processing dosimetry in a practical and useful way. It is hoped that this book will lead to improved measurement procedures, more accurate and precise dosimetry and a greater appreciation of the necessity of dosimetry for radiation processing. (author)

  8. Reference methodologies for radioactive controlled discharges an activity within the IAEA's Program Environmental Modelling for Radiation Safety II (EMRAS II)

    International Nuclear Information System (INIS)

    Stocki, T.J.; Bergman, L.; Tellería, D.M.; Proehl, G.; Amado, V.; Curti, A.; Bonchuk, I.; Boyer, P.; Mourlon, C.; Chyly, P.; Heling, R.; Sági, L.; Kliaus, V.; Krajewski, P.; Latouche, G.; Lauria, D.C.; Newsome, L.; Smith, J.

    2011-01-01

    In January 2009, the IAEA EMRAS II (Environmental Modelling for Radiation Safety II) program was launched. The goal of the program is to develop, compare and test models for the assessment of radiological impacts to the public and the environment due to radionuclides being released or already existing in the environment; to help countries build and harmonize their capabilities; and to model the movement of radionuclides in the environment. Within EMRAS II, nine working groups are active; this paper will focus on the activities of Working Group 1: Reference Methodologies for Controlling Discharges of Routine Releases. Within this working group environmental transfer and dose assessment models are tested under different scenarios by participating countries and the results compared. This process allows each participating country to identify characteristics of their models that need to be refined. The goal of this working group is to identify reference methodologies for the assessment of exposures to the public due to routine discharges of radionuclides to the terrestrial and aquatic environments. Several different models are being applied to estimate the transfer of radionuclides in the environment for various scenarios. The first phase of the project involves a scenario of nuclear power reactor with a coastal location which routinely (continuously) discharges 60Co, 85Kr, 131I, and 137Cs to the atmosphere and 60Co, 137Cs, and 90Sr to the marine environment. In this scenario many of the parameters and characteristics of the representative group were given to the modelers and cannot be altered. Various models have been used by the different participants in this inter-comparison (PC-CREAM, CROM, IMPACT, CLRP POSEIDON, SYMBIOSE and others). This first scenario is to enable a comparison of the radionuclide transport and dose modelling. These scenarios will facilitate the development of reference methodologies for controlled discharges. (authors)

  9. Improving care coordination using organisational routines.

    Science.gov (United States)

    Prætorius, Thim

    2016-01-01

    The purpose of this paper is to systematically apply theory of organisational routines to standardised care pathways. The explanatory power of routines is used to address open questions in the care pathway literature about their coordinating and organising role, the way they change and can be replicated, the way they are influenced by the organisation and the way they influence health care professionals. Theory of routines is systematically applied to care pathways in order to develop theoretically derived propositions. Care pathways mirror routines by being recurrent, collective and embedded and specific to an organisation. In particular, care pathways resemble standard operating procedures that can give rise to recurrent collective action patterns. In all, 11 propositions related to five categories are proposed by building on these insights: care pathways and coordination, change, replication, the organisation and health care professionals. Research limitations/implications - The paper is conceptual and uses care pathways as illustrative instances of hospital routines. The propositions provide a starting point for empirical research. The analysis highlights implications that health care professionals and managers have to consider in relation to coordination, change, replication, the way the organisation influences care pathways and the way care pathways influence health care professionals. Originality/value - Theory on organisational routines offers fundamental, yet unexplored, insights into hospital processes, including in particular care coordination.

  10. Effects of release procedures on the primary stress response and post-release survival and growth of hatchery-reared spotted seatrout Cynoscion nebulosus.

    Science.gov (United States)

    Guest, T W; Rakocinski, C F; Evans, A N; Blaylock, R B

    2017-03-01

    To help explain the apparent poor post-release success of hatchery-reared (HR) spotted seatrout Cynoscion nebulosus, this study examined the effects of handling, transport and release procedures on the stress response of two age classes [48 and 80 day post-hatch (dph)] of HR C. nebulosus, as measured by cortisol concentrations and the post-release survival and growth of 48 and 80 dph HR C. nebulosus. As a proxy for stress, tissue cortisol was measured at various times during the handling, tagging (80 dph), transport, acclimation and release process. To consider the implications of the pre-release stressors, growth and survival were monitored in separate field experiments for each age class of acclimated post-transport C. nebulosus using control C. nebulosus that only experienced anaesthesia, transport, acclimation and a net release v. experimental C. nebulosus that underwent the entire routine procedure, including anaesthesia, tagging, transport, acclimation and gravity release through a pipe. For 48 dph C. nebulosus, mean cortisol varied significantly throughout handling and transport, increasing more than six-fold from controls before decreasing in mean concentration just prior to release. For 80 dph C. nebulosus, cortisol varied throughout handling, tagging and transport, first increasing more than three-fold compared with control C. nebulosus, before decreasing and rising slightly just prior to release. For 48 dph C. nebulosus within field enclosures, survival was high and similar for control and experimental groups; experimental C. nebulosus, however, were shorter, lighter and lower in condition than control C. nebulosus. For 80 dph C. nebulosus within field enclosures, fewer experimental C. nebulosus survived and those that did survive were of lower condition than C. nebulosus from the control group. Small untagged C. nebulosus may survive the release procedure better than larger C. nebulosus carrying a coded-wire tag. These findings document

  11. UNC Nuclear Industries reactor and fuels production facilities. 1984 effluent release report

    International Nuclear Information System (INIS)

    Rokkan, D.J.

    1985-01-01

    This document has been prepared to fulfill the annual reporting requirements of DOE 5484.1, ''Environmental Protection, Safety, and Health Protection Information Reporting Requirements.'' Radioanalyses performed on routine samples of liquid and airborne streams were evaluated using UNC's Environmental Release Summary computer program. All identified significant discharges from UNC facilities to the environment during CY 1984 are reported in this document

  12. 42 CFR 493.1210 - Condition: Routine chemistry.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Condition: Routine chemistry. 493.1210 Section 493....1210 Condition: Routine chemistry. If the laboratory provides services in the subspecialty of Routine chemistry, the laboratory must meet the requirements specified in §§ 493.1230 through 493.1256, § 493.1267...

  13. Derived release limits for airborne effluents at TRIGA - INR Reactor

    International Nuclear Information System (INIS)

    Toma, A.; Dulama, C.; Hirica, O.; Mihai, S.; Oprea, I.

    2008-01-01

    Beginning from fulfilling the purposes of dose limitation system recommended by ICRP, and now accepted in radiation protection, this paper presents an environmental transfer model to calculate derived release limits for airborne and gaseous radioactive effluents at TRIGA-INR, 14 MW Steady State Reactor, in function on INR-Pitesti site. The methodology consists in determination of the principal exposure pathways for different groups of population and dose calculations for each radionuclide. The characterization of radionuclides transfer to environment was made using the compartmental model. The parameter transfer concept was used to describe the distribution of radionuclides between the different compartments. Atmospheric dispersion was very carefully treated, because it is the primary mechanism of the transfer of radionuclides in the environment and it determines all exposure pathways. Calculation of the atmospheric dispersion was made using ORION-II computer code based on the Gaussian plume model which takes account of site's specific climate and relief conditions. Default values recommended by literature were used to calculate some of the parameters when specific site values were not available. After identification of all transfer parameters which characterize the most important exposure pathways, the release rate corresponding to the individual dose rate limit was calculated. This maximum release rate is the derived release limit for each radionuclide and source. In the paper, the derived release limits are calculated for noble gases, radioiodine and other airborne particulate radionuclides, which can be released on the TRIGA-INR reactor stack, and are important to radiation protection. (authors)

  14. Satellite-based constraints on explosive SO2 release from Soufrière Hills Volcano, Montserrat

    Science.gov (United States)

    Carn, Simon A.; Prata, Fred J.

    2010-09-01

    Numerous episodes of explosive degassing have punctuated the 1995-2009 eruption of Soufrière Hills volcano (SHV), Montserrat, often following major lava dome collapses. We use ultraviolet (UV) and infrared (IR) satellite measurements to quantify sulfur dioxide (SO2) released by explosive degassing, which is not captured by routine ground-based and airborne gas monitoring. We find a total explosive SO2 release of ˜0.5 Tg, which represents ˜6% of total SO2 emissions from SHV since July 1995. The majority of this SO2 (˜0.4 Tg) was vented following the most voluminous SHV dome collapses in July 2003 and May 2006. Based on our analysis, we suggest that the SO2 burden measured following explosive disruption of lava domes depends on several factors, including the instantaneous lava effusion rate, dome height above the conduit, and the vertical component of directed explosions. Space-based SO2 measurements merit inclusion in routine gas monitoring at SHV and other dome-forming volcanoes.

  15. Is radiation protection for the unborn child guaranteed by radiation protection for female workers?

    International Nuclear Information System (INIS)

    Nosske, C.; Karcher, K.

    2003-01-01

    ICRP Publication 88 recommends doses to embryo and fetus from intakes of radionuclides by the mother for various intake scenarios. Mainly by answering the question 'Is radiation protection for the unborn child guaranteed by radiation protection for female workers?' it has been assessed if the intake scenarios given in ICRP Publication 88 are adequate for radiation protection purposes. This is generally the case, but the consideration of an additional chronic intake scenario for early pregnancy would be helpful. It is demonstrated that following chronic intake by inhalation, for most radionuclides radiation protection for (female) workers is also adequate for protection of the unborn child, considered as a member of the public. However, there are a number of radionuclides for which possible intakes in routine operations should be more restricted (up to 1% of the annual limits on intake for workers in the case of nickel isotopes) to ensure radiation protection for the unborn child. (author)

  16. Bio-indicators for radiation dose assessment

    International Nuclear Information System (INIS)

    Trivedi, A.

    1990-12-01

    In nuclear facilities, such as Chalk River Laboratories, dose to the atomic radiation workers (ARWs) is assessed routinely by using physical dosimeters and bioassay procedures in accordance with regulatory recommendations. However, these procedures may be insufficient in some circumstances, e.g., in cases where the reading of the physical dosimeters is questioned, in cases of radiation accidents where the person(s) in question was not wearing a dosimeter, or in the event of a radiation emergency when an exposure above the dose limits is possible. The desirability of being able to assess radiation dose on the basis of radio-biological effects has prompted the Dosimetric Research Branch to investigate the suitability of biological devices and techniques that could be used for this purpose. Current biological dosimetry concepts suggest that there does not appear to be any bio-indicator that could reliably measure the very low doses that are routinely measured by the physical devices presently in use. Nonetheless, bio-indicators may be useful in providing valuable supplementary information in cases of unusual radiation exposures, such as when the estimated body doses are doubtful because of lack of proper physical measurements, or in cases where available results need to be confirmed for medical treatment plannings. This report evaluates the present state of biological dosimetry and, in particular, assesses the efficiency and limits of individual indicators. This has led to the recommendation of a few promising research areas that may result in the development of appropriate biological dosimeters for operational and emergency needs at Chalk River

  17. Visits to Australia by nuclear powered or armed vessels: contingency planning for the accidental release of ionizing radiation

    International Nuclear Information System (INIS)

    1989-01-01

    The report refers to the adequacy of current contingency planning by the Australian Federal and Senate authorities to deal with the accidental release of ionizating radiation from visiting nuclear powered or armed vessels in Australian waters and ports. Much of the material was obtained in response to questions put in writing by the Senate Standing Committee to the Department of Defence, ANSTO and others. In addition, the report contains relevant information from Commonwealth documents as well as the Committee findings and recommendations. Issues considered include: types of visiting nuclear powered vessels, accident likelihood and consequences, differences between naval and land-based reactors, safety records. The persons or organizations who made submissions or appeared in all public hearings are listed in the appendixes, along with all visits to Australian ports by nuclear powered warships from 1976 to 1988

  18. Risks and hazards from conventional and radiation sources

    International Nuclear Information System (INIS)

    Iyer, P.S.; Ganguly, A.K.

    1978-01-01

    Beneficial uses of radioisotopes in medicine, industry, agriculture and research are discussed. In absence of adequate safety precautions, uses of radiation may also result in harmful biological effects or genetic effects. Radiation risks and hazards are evaluated by comparing with other risks and hazards which are routinely encountered. The risk of fatality per year by various causes in U.S.A. is given. It is stated with examples and observations that some of the routine habits and necessities and minor luxuries are more risky than radiation risks. Countrywide radiation safety program in India by the Department of Atomic Energy is described in brief. Data are given to show that the risks from radiation are much lower in comparison with many conventional sources. More efficient equipment such as image intensifier is recommended to help to reduce the patient dose. It is stated that caution has to be exercised while handling the X-ray machines which may be harmful not only to patients but to doctors also. As regards, nuclear medicine, it is mentioned that though it is a fast expanding speciality in India, the number of procedures carried out in various centres is small as compared to U.S.A. and France. Some instances are given to show the consequences of the ignorance of the radiation hazards in operating machines in X-ray and gamma ray beam therapy facilities. A survey made by DRP, BARC revealed that some research laboratories lacked basic radiation protection requirements in using X-ray crystallography or analytical equipment. (B.G.W.)

  19. Review of IAEA recommendations on the principles and methodologies for limiting releases of radioactive effluents to the environment

    International Nuclear Information System (INIS)

    Ahmed, J.U.

    1988-01-01

    The limitation of radioactive releases is governed by the basic principles of radiation protection as presented in the ICRP Publication No. 26 and IAEA Safety Series No. 9. Unter its current programme on release limitation the IAEA issued Safety Series No. 77 on principles for release limitation and Safety Series No. 67 on protection against transboundary radiation exposures. A Safety Guide on global upper bounds is now nearly ready for publication, and to guide on the application of Safety Series No. 77, four documents are in various stages of completion

  20. Real-time assessment of radiation burden of the population in the vicinity of nuclear power plants during radiation accidents

    International Nuclear Information System (INIS)

    Stubna, M.

    1986-01-01

    The method is presented of real-time calculation of the radiation situation (dose equivalents) in the environs of a nuclear power plant in case of an accident involving the release of radioactive substances into the atmosphere, this for the potentially most significant exposure paths in the initial and medium stages of the accident. The method allows to take into consideration the time dependence of the rate of radioactive substance release from the nuclear power plant and to assess the development in space and time of the radiation situation in the environs of the nuclear power plant. The use of the method is illustrated by an example of the calculation of the development of the radiation situation for model accidents of a hypothetical PWR with containment. (author)

  1. Modelling isothermal fission gas release

    International Nuclear Information System (INIS)

    Uffelen, P. van

    2002-01-01

    The present paper presents a new fission gas release model consisting of two coupled modules. The first module treats the behaviour of the fission gas atoms in spherical grains with a distribution of grain sizes. This module considers single atom diffusion, trapping and fission induced re-solution of gas atoms associated with intragranular bubbles, and re-solution from the grain boundary into a few layers adjacent to the grain face. The second module considers the transport of the fission gas atoms along the grain boundaries. Four mechanisms are incorporated: diffusion controlled precipitation of gas atoms into bubbles, grain boundary bubble sweeping, re-solution of gas atoms into the adjacent grains and gas flow through open porosity when grain boundary bubbles are interconnected. The interconnection of the intergranular bubbles is affected both by the fraction of the grain face occupied by the cavities and by the balance between the bubble internal pressure and the hydrostatic pressure surrounding the bubbles. The model is under validation. In a first step, some numerical routines have been tested by means of analytic solutions. In a second step, the fission gas release model has been coupled with the FTEMP2 code of the Halden Reactor Project for the temperature distribution in the pellets. A parametric study of some steady-state irradiations and one power ramp have been simulated successfully. In particular, the Halden threshold for fission gas release and two simplified FUMEX cases have been computed and are summarised. (author)

  2. An Experimental Concept for Probing Nonlinear Physics in Radiation Belts

    Science.gov (United States)

    Crabtree, C. E.; Ganguli, G.; Tejero, E. M.; Amatucci, B.; Siefring, C. L.

    2017-12-01

    A sounding rocket experiment, Space Measurement of Rocket-Released Turbulence (SMART), can be used to probe the nonlinear response to a known stimulus injected into the radiation belt. Release of high-speed neutral barium atoms (8- 10 km/s) generated by a shaped charge explosion in the ionosphere can be used as the source of free energy to seed weak turbulence in the ionosphere. The Ba atoms are photo-ionized forming a ring velocity distribution of heavy Ba+ that is known to generate lower hybrid waves. Induced nonlinear scattering will convert the lower hybrid waves into EM whistler/magnetosonic waves. The escape of the whistlers from the ionospheric region into the radiation belts has been studied and their observable signatures quantified. The novelty of the SMART experiment is to make coordinated measurement of the cause and effect of the turbulence in space plasmas and from that to deduce the role of nonlinear scattering in the radiation belts. Sounding rocket will carry a Ba release module and an instrumented daughter section that includes vector wave magnetic and electric field sensors, Langmuir probes and energetic particle detectors. The goal of these measurements is to determine the whistler and lower hybrid wave amplitudes and spectrum in the ionospheric source region and look for precipitated particles. The Ba release may occur at 600-700 km near apogee. Ground based cameras and radio diagnostics can be used to characterize the Ba and Ba+ release. The Van Allen Probes can be used to detect the propagation of the scattering-generated whistler waves and their effects in the radiation belts. By detecting whistlers and measuring their energy density in the radiation belts the SMART mission will confirm the nonlinear generation of whistlers through scattering of lower hybrid along with other nonlinear responses of the radiation belts and their connection to weak turbulence.

  3. Routines Are the Foundation of Classroom Management

    Science.gov (United States)

    Lester, Robin Rawlings; Allanson, Patricia Bolton; Notar, Charles E.

    2017-01-01

    Classroom management is the key to learning. Routines are the foundation of classroom management. Students require structure in their lives. Routines provide that in all of their life from the time they awake until the time they go to bed. Routines in a school and in the classroom provide the environment for learning to take place. The paper is…

  4. Perspex in the verification routines for accelerator beam; El Perspex en las rutinas de verificacion del haz en un acelerador

    Energy Technology Data Exchange (ETDEWEB)

    Paredes G, L.; Genis S, R. [Instituto Nacional de Investigaciones Nucleares, Apdo. Postal 18-1027, 11801 Mexico D.F. (Mexico)

    1998-12-31

    It is analyzed the use of a perspex solid phantom, adequately referred to a water phantom, as an auxiliary alternative for the daily stability verification routines or constance of radiation beam, as an option in the case of radiotherapy installations with high charge of accelerator working and with basic dosimetry equipment. (Author)

  5. Maxine: A spreadsheet for estimating dose from chronic atmospheric radioactive releases

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, Tim [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bell, Evaleigh [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, Kenneth [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-07-24

    MAXINE is an EXCEL© spreadsheet, which is used to estimate dose to individuals for routine and accidental atmospheric releases of radioactive materials. MAXINE does not contain an atmospheric dispersion model, but rather doses are estimated using air and ground concentrations as input. Minimal input is required to run the program and site specific parameters are used when possible. Complete code description, verification of models, and user’s manual have been included.

  6. Dosimetry systems for radiation processing

    International Nuclear Information System (INIS)

    McLaughlin, W.L.; Desrosiers, M.F.

    1995-01-01

    Dosimetry serves important functions in radiation processing, where large absorbed doses and dose rates from photon and electron sources have to be measured with reasonable accuracy. Proven dosimetry systems are widely used to perform radiation measurements in development of new processes, validation, qualification and verification (quality control) of established processes and archival documentation of day-to-day and plant-to-plant processing uniformity. Proper calibration and traceability of routine dosimetry systems to standards are crucial to the success of many large-volume radiation processes. Recent innovations and advances in performance of systems that enhance radiation measurement assurance and process diagnostics include dose-mapping media (new radiochromic film and solutions), optical waveguide systems for food irradiation, solid-state devices for real-time and passive dosimetry over wide dose-rate and dose ranges, and improved analytical instruments and data acquisition. (author)

  7. Safety aspects of targets for ADTT: Activity, volatile products, residual heat release

    International Nuclear Information System (INIS)

    Gai, E.V.; Ignatyuk, A.V.; Lunev, V.P.; Shubin, Yu.N.

    1999-01-01

    Safety aspects of heavy metal liquid targets for the accelerator driven systems connected with the activity accumulation and residual energy release due to the irradiation with high energy proton beam are discussed. The results obtained for the lead-bismuth target that are under construction in IPPE now in the frame of ISTC Project No. 559 are briefly presented. The calculations and the analysis of the accumulation of the spallation reaction products, activity and energy release at various moments after the accelerator shutdown are presented. The concentrations of the reaction products, the total and partial activities, the activities of volatile products are determined. The contributions of the short-lived nuclides important for the prediction of the facility behaviour in regimes with the accelerator beam trips. The calculations and analysis of the residual energy release due to different decay type have been performed. The conclusions are as follows. The obtained results showed that long lived radioactivity accumulates mainly due to primary nuclear reactions. Secondary reactions are responsible for the production of small number of long-lived isotopes Bi-207, Po-210 and some others, being generated by radiative capture of low energy neutrons. It is possible to make a conclusion that neutrons in the energy range 20 - 800 MeV and protons with energy above 100 MeV give main contribution to the total activity generation although these parts of spectra inside the target give comparatively small contribution to the total flux. The correct consideration of short-lived nuclides contribution is the main problem in the analysis of the target behaviour in the case of short accelerator shutdowns. They make the determining contribution to the both activity and the heat release at the first moments after the accelerator shutdown, creating the intermediate links and additional channels for the long-lived nuclides accumulation chains. The strong dependence of calculated

  8. Routine sputum culture

    Science.gov (United States)

    Sputum culture ... There, it is placed in a special dish (culture). It is then watched to see if bacteria ... Elsevier; 2018:chap 36. Chernecky CC, Berger BJ. Culture, routine. In: Chernecky CC, Berger BJ, eds. Laboratory ...

  9. Predator response to releases of American shad larvae in the Susquehanna River basin

    Science.gov (United States)

    Johnson, James H.; Ringler, N.H.

    1998-01-01

    Predation on American shad (Alosa sapidissima) larvae within the first two hours of release was examined from 1989 to 1992 on 31 occasions at stocking sites in the Susquehanna River basin. Twenty-two fish species consumed shad larvae; the dominant predators were spotfin shiner (Cyprinella spiloptera), mimic shiner (Notropis volucellus) and juvenile smallmouth bass (Micropterus dolomieu). The number of shad larvae found in predator stomachs ranged from 0 to 900. Mortality of shad larvae at the stocking site was usually less than 2%. The greatest mortality (9.6%) occurred at the highest stocking level (1.5 million larvae). Highly variable predation rates and release levels of shad insufficient to achieve predator satiation hindered the ability to determine a specific type of functional response of predators. Predator numbers increased with stocking density, indicating short-term aggregation at the release site. Because of practical problems associated with releasing the large numbers of larvae that would be required to satiate predators, routine stocking at these levels is probably unreasonable. Releases of 400,000 to 700,000 larvae may reduce predation by offsetting depensatory mechanisms that operate on small releases and the effects of increased predation due to predator aggregation on large releases. Night stocking may reduce predation on larval shad at the release site.

  10. A comparison of the extended-release and standard-release formulations of tacrolimus in de novo kidney transplant recipients: a 12-month outcome study.

    Science.gov (United States)

    Fanous, Helen; Zheng, Rebecca; Campbell, Carolyn; Huang, Michael; Nash, Michelle M; Rapi, Lindita; Zaltzman, Jeffrey S; Prasad, G V Ramesh

    2013-02-01

    BACKGROUND: Limited comparative data are available on the outcomes between extended-release and standard-release tacrolimus when used de novo in kidney transplant recipients (KTRs). METHODS: We identified KTRs transplanted at our institution during 2009-10 routinely prescribed extended-release tacrolimus and compared them with those transplanted during 2008-09 prescribed standard-release tacrolimus. Graft function (eGFR by MDRD-7 equation) at 12 months post-transplant (primary outcome); new-onset diabetes and other cardiovascular risk factors, BK viremia incidence, acute rejection, and graft survival to 12 months (secondary outcomes) were compared by intent-to-treat analysis. Time-to-steady-state concentration and number of dose adjustments required to attain steady state were recorded. RESULTS: There were no important demographic differences between the extended-release (N = 106) and standard-release (N = 95) cohorts. The estimated glomerular filtration rate (eGFR) at 12 months was similar (58.8 ± 17 versus 59.2 ± 18 mL/min/1.73 m(2), P = 0.307). There was no difference in new-onset diabetes (17 versus 20%, P = 0.581), BK viremia (10 versus 7%, P = 0.450), acute rejection (7 versus 16%, P = 0.067) or graft survival (97 versus 95%, P = 0.301). Time-to-steady state was similar (9.2 ± 1.1 versus 8.1 ± 4.7 days, P = 0.490) although extended-release patients required fewer adjustments to attain steady state (1.2 ± 1.7 [0-8] versus 1.7 ± 1.5 [0-7], P = 0.030) but a similar dose (7.2 ± 2.4 [2-17] versus 7 ± 2.7 [2-16] mg/day, P = 0.697). CONCLUSION: De novo KTRs prescribed extended-release or standard-release tacrolimus demonstrate similar 12-month outcomes.

  11. Relations between radiation risks and radiation protection measuring techniques

    International Nuclear Information System (INIS)

    Herrmann, K.; Kraus, W.

    1975-10-01

    'Risk of damage' and 'exposure risk' are considered as components of the radiation risk. The influence of the 'exposure risk' on type and extent of radiation protection measurements is discussed with regard to different measuring tasks. Basing upon measuring results concerning the frequency of certain external and internal occupational exposures in the GDR, it has been shown that only a small fraction of the monitored persons are subjected to a high 'exposure risk'. As a consequence the following recommendations are given for discussion: (a) occupationally exposed persons with small 'exposure risk' should be monitored using only a long-term dosimeter (for instance a thermoluminescence dosimeter), (b) in the case of internal exposure the surface and, if necessary, air contamination should be controlled so strictly that routine measurements of internal contamination need not be performed. (author)

  12. Model description. NUDOS: A computer program for assessing the consequences of airborne releases of radionuclides

    International Nuclear Information System (INIS)

    Poley, A.D.

    1996-02-01

    NUDOS is a computer program that can be used to evaluate the consequences of airborne releases of radioactive material. The consequences which can be evaluated are individual dose and associated radiological risk, collective dose and the contamination of land. The code is capable of dealing with both continuous (routine) and accidental releases. For accidental releases both deterministic and probabilistic calculations can be performed, and the impact and effectiveness of emergency actions can be evaluated. This report contains a description of the models contained in NUDOS92 and the recommended values for the input parameters of these models. Additionally, a short overview is given of the future model improvement planned for the next NUDOS-version. (orig.)

  13. FASTPLOT, Interface Routines to MS FORTRAN Graphics Library

    International Nuclear Information System (INIS)

    1999-01-01

    1 - Description of program or function: FASTPLOT is a library of routines that can be used to interface with the Microsoft FORTRAN Graphics library (GRAPHICS.LIB). The FASTPLOT routines simplify the development of graphics applications and add capabilities such as histograms, Splines, symbols, and error bars. FASTPLOT also includes routines that can be used to create menus. 2 - Methods: FASTPLOT is a library of routines which must be linked with a user's FORTRAN programs that call any FASTPLOT routines. In addition, the user must link with the Microsoft FORTRAN Graphics library (GRAPHICS.LIB). 3 - Restrictions on the complexity of the problem: None noted

  14. Release procedures and disposal of radioactive residual substances at the Medical University Hanover (MHH)

    International Nuclear Information System (INIS)

    Scheller, F.; Behrendt, R.; Harke, H.

    2005-01-01

    The disposal of all radioactive residual packages of the MHH is regulated by the German radiation protection ordinance from 26 th July 2001; shown in appendix III, table 1, column 5: unrestricted release of solid materials and liquids. All radioactive waste packages are collected and handled by the central MHH department for radiation protection. They are sorted for type, nuclide and specific radioactivity. A few packages can directly be released as conventional waste after performing incoming measurements showing very low activity concentrations. Longer living radionuclides with specific activities above the release limits have to be delivered to the national waste disposal. For direct measurements of gamma-emitting radionuclides we use two in-situ-measuring units (ISOCS, Canberra) and a special release unit with 9 plastic scintillators in a fixed geometry (FR-9 PVT, MED Medizintechnik). Fluid beta-emitting radionuclides are measured by taking a fraction and using liquid scintillation counting (LSC). Solid beta-emitting radionuclides activity are calculated. (orig.)

  15. Radiation synovectomy in hemophilic hemarthrosis

    International Nuclear Information System (INIS)

    Wong, C.P.; Auyong, T.K.; Tong, C.M.; Luk, C.W.

    2003-01-01

    Radiation Synovectomy is an effective treatment for various kinds of arthropathies with a long history. It is a routine practice in many countries. One of the indications is hemophilic arthropathy, which is caused by repeated hemarthroses and resulting synovial hypertrophy and inflammation. The joints will subsequently be damaged and deformed, leading to significant functional disability. Synovectomy is needed to treat the hypertrophied and inflamed synovium. In this article, the procedure of radiation synovectomy will be elaborated, and a proposed working protocol for hemophilic hemarthrosis will be introduced. Moreover, efficacy (including example of cost effectiveness) of radiation synovectomy will be discussed and showed that the procedure can safely improve patients' symptoms, bleeding episodes, and can control further deterioration of the hemophilic arthropathy

  16. External Agents' Effect on Routine Dynamics

    DEFF Research Database (Denmark)

    Busse Hansen, Nicolai

    Prior investigations on organizational routines have called for re- search to enlighten our understanding of how social actors establish and main- tain of routines as well as the causes of their disruption. The present paper con- tributes to this call by conducting systematic microethnographic...... and affiliation are central to how routines are maintained but also susceptible to disruption in case of mis- management. Also the paper contributes with a more fine-tuned understanding of action in terms of them being organized in accordance with preference, which basically means that some actions are preferred...... over others. In producing an action, the relevant next action is projected. However the relevant next action is projected in a specific way and if this is not taken in to account then the routine becomes disrupted. Another core aspect is the notion of deontics that lends itself towards describing who...

  17. Analysis of tritium releases to the atmosphere by a CTR

    International Nuclear Information System (INIS)

    Renne, D.S.; Sandusky, W.F.; Dana, M.T.

    1975-08-01

    Removal by atmospheric processes of routinely and accidentally released tritium from a controlled thermonuclear reactor (CTR) was investigated. Based on previous studies, the assumed form of the tritium for this analysis was HTO or tritiated water vapor. Assuming a CTR operation in Morris, Illinois, surface water and ground-level air concentration values of tritium were computed for three space (or time) scales: local (50 Km of a plant), regional (up to 1000 Km of the plant), and global

  18. The assessment of risks from exposure to low-levels of ionizing radiation

    International Nuclear Information System (INIS)

    Gilbert, E.S.

    1992-06-01

    This report is concerned with risk assessments for human populations receiving low level radiation doses; workers routinely exposed to radiation, Japanese victims of nuclear bombs, and the general public are all considered. Topics covered include risk estimates for cancer, mortality rates, risk estimates for nuclear site workers, and dosimetry

  19. Flavor profile of radiation processed food commodities

    International Nuclear Information System (INIS)

    Chatterjee, S.; Variyar, Prasad S.; Sharma, Arun

    2006-01-01

    Full text: Flavor is one of the major quality attributes that play an important role in driving consumer choices and preferences for food. Among the several attributes that decide the flavor quality of any food, aroma and taste are the most important. While volatile constituents contribute to aroma, taste is a perception stimulated by non-volatile principles of food. Radiation processing of food has in recent years assumed increasing importance as a method for hygenization. At the doses employed for food irradiation no significant qualitative changes in the aroma constituents have been reported in most cases. An increase in perceived aroma has however been observed in several radiation processed foods. Besides volatile aroma compounds non-volatile aroma precursors are ubiquitous in plant kingdom. These compounds have been reported to exist largely as bound glycosidic conjugates and are known to undergo breakdown during processing and storage. This results in release of free aroma, thereby, modifying the flavor quality of the product. No report, however, exists on the effect of radiation processing on these bound aroma precursors. Four major class of food namely spices, oil seeds, fruits and beverages were therefore taken up for a detailed study. With respect to aroma, an enhanced breakdown of aroma precursors namely isoeugenol and 4-vinyl guaiacol glycosides and release of free aglycones was demonstrated to result in an increased aroma quality of radiation processed monsooned coffee. Breakdown of phenyl ethanol glucoside resulted in a fruitier note to pomegranate while enhanced spicy note of irradiated nutmeg arise as a result of radiolytic break down p-cymene-7-ol rutinoside precursor and release of free p-cymene-7-ol. An increased color quality of irradiated saffron was a result of the formation of free carotene aglycones namely crocetin from its glycosidic precursors while changes in perceived taste quality of radiation processed soybean could be attributed to

  20. LABCORE post release 1.0 development system project management plan

    International Nuclear Information System (INIS)

    Rich, H.S.

    1994-01-01

    The LABCORE post release 1.0 development system project management plan (SPMP) is the primary planning document governing the development of specific enhancements to the LABCORE project. The mission of the Westinghouse Hanford Company (WHC) laboratories is changing from supporting the 200 Area chemical processing plants for process control, waste management, and effluent monitoring to supporting environmental restoration and regulatory compliance commitments. The LABCORE program was implemented as the key element for meeting the commitments by upgrading the laboratories through the implementation of an Automated Data Processing improvement program in January 1994. Scope for LABCORE release 1.0 consisted of hardware and software implementation required to support a minimum number of analyses (Single-Shell Tank [SST] analysis at 222S Laboratory and Performance Evaluation samples at the Waste Sampling Characterization Facility laboratory) using manual entry of data, and to support routine laboratory functions, common to all laboratories. LABCORE post release 1.0 enhancements will expand the functionality presented to the laboratory. Post release 1.0 enhancements will also address the integration of a database for Analytical Services Program Integration, budgeting, and scheduling offices into LABCORE

  1. The Chernobyl I-131 Release: Model Validation and Assessment of the Countermeasure Effectiveness. Report of the Chernobyl 131I Release Working Group of EMRAS Theme 1

    International Nuclear Information System (INIS)

    2012-01-01

    The Chernobyl 131 I Release Working Group (IWG) which was established within the framework of the EMRAS Programme continues some of the more traditional work of previous international programmes that were aimed at increasing confidence in methods and models for the assessment of radiation exposure related to the environmental releases. There is still very little information regarding the quantitative relationship between radiation dose to the thyroid from Chernobyl and the risk of thyroid cancer. The uncertainty combined with individual estimates of radiation dose constitutes a crucial point in establishing this relationship, since, any release of radioiodine into environment creates wide range of uncertainty for internal dose assessments. The 131 I scenarios provide an excellent opportunity to compare a number of modelling approaches to a single assessment problem, in a dose reconstruction context. Nine experts in environmental modelling participated in the Plavsk Scenario dealing with areas of assessment modelling for which the capabilities are not yet well established. One could observes the remarkably improvement in models performance comparing with previous radioiodine scenarios. Predictions of the various models were within a factor of three of the observations, discrepancies between the estimates of average doses to thyroid produced by most participant not exceeded a factor of ten. The process of testing independent model calculations against independent data set also provided useful information to the originators of the test data.

  2. Criteria for radiological protection against exposure to natural radiation

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan

    2012-01-01

    Exposure of humans to natural sources of radiation has been a continuous and inevitable feature of life on earth. This exposure exceeds all due to artificial sources combined for most people. Many exposures to natural radiation sources are modified by human action. In particular, natural radionuclides are released into the environment in mineral processing and in activities such as the production of phosphate fertilizers and the use of fossil fuels. An increase of exposures to this natural radiation is caused. The relevance of exposure to natural radiation is confirmed by the fact that, for most people, the exposures to natural background radiation have been much more significant than exposures to artificial sources, with exceptions. Among these exceptions have been noted: medical exposures, accidents with release of radionuclides and some specific workplaces. In all cases, however, the natural background radiation has formed the basis on which all the others exposures are added and is a common level serving as compared to other exposures. Regulations and instructions have begun to establish in some countries to regulate natural radiation, countries like Spain, have already incorporated into its regulations on health protection against ionizing radiation the subject of natural radiation. (author) [es

  3. UVB-Stimulated TNFα Release from Human Melanocyte and Melanoma Cells Is Mediated by p38 MAPK

    Directory of Open Access Journals (Sweden)

    Visalini Muthusamy

    2013-08-01

    Full Text Available Ultraviolet (UV radiation activates cell signaling pathways in melanocytes. As a result of altered signaling pathways and UV-induced cellular damage, melanocytes can undergo oncogenesis and develop into melanomas. In this study, we investigated the effect of UV-radiation on p38 MAPK (mitogen-activated protein kinase, JNK and NFκB pathways to determine which plays a major role in stimulating TNFα secretion in human HEM (melanocytes and MM96L (melanoma cells. MM96L cells exhibited 3.5-fold higher p38 activity than HEM cells at 5 min following UVA + B radiation and 1.6-fold higher JNK activity at 15–30 min following UVB+A radiation, while NFκB was minimally activated in both cells. Irradiated HEM cells had the greatest fold of TNFα secretion (UVB: 109-fold, UVA + B: 103-fold & UVB+A: 130-fold when co-exposed to IL1α. The p38 inhibitor, SB202190, inhibited TNFα release by 93% from UVB-irradiated HEM cells. In the UVB-irradiated MM96L cells, both SB202190 and sulfasalazine (NFκB inhibitor inhibited TNFα release by 52%. Although, anisomycin was a p38 MAPK activator, it inhibited TNFα release in UV-irradiated cells. This suggests that UV-mediated TNFα release may occur via different p38 pathway intermediates compared to those stimulated by anisomycin. As such, further studies into the functional role p38 MAPK plays in regulating TNFα release in UV-irradiated melanocyte-derived cells are warranted.

  4. ISO radiation sterilization standards

    International Nuclear Information System (INIS)

    Lambert, Byron J.; Hansen, Joyce M.

    1998-01-01

    This presentation provides an overview of the current status of the ISO radiation sterilization standards. The ISO standards are voluntary standards which detail both the validation and routine control of the sterilization process. ISO 11137 was approved in 1994 and published in 1995. When reviewing the standard you will note that less than 20% of the standard is devoted to requirements and the remainder is guidance on how to comply with the requirements. Future standards developments in radiation sterilization are being focused on providing additional guidance. The guidance that is currently provided in informative annexes of ISO 11137 includes: device/packaging materials, dose setting methods, and dosimeters and dose measurement, currently, there are four Technical Reports being developed to provide additional guidance: 1. AAMI Draft TIR, 'Radiation Sterilization Material Qualification' 2. ISO TR 13409-1996, 'Sterilization of health care products - Radiation sterilization - Substantiation of 25 kGy as a sterilization dose for small or infrequent production batches' 3. ISO Draft TR, 'Sterilization of health care products - Radiation sterilization Selection of a sterilization dose for a single production batch' 4. ISO Draft TR, 'Sterilization of health care products - Radiation sterilization-Product Families, Plans for Sampling and Frequency of Dose Audits'

  5. NMR Metabolomics in Ionizing Radiation

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Jian Z.; Xiao, Xiongjie; Hu, Mary Y.

    2016-09-08

    Ionizing radiation is an invisible threat that cannot be seen, touched or smelled and exist either as particles or waves. Particle radiation can take the form of alpha, beta or neutrons, as well as high energy space particle radiation such as high energy iron, carbon and proton radiation, etc. (1) Non-particle radiation includes gamma- and x-rays. Publically, there is a growing concern about the adverse health effects due to ionizing radiation mainly because of the following facts. (a) The X-ray diagnostic images are taken routinely on patients. Even though the overall dosage from a single X-ray image such as a chest X-ray scan or a CT scan, also called X-ray computed tomography (X-ray CT), is low, repeated usage can cause serious health consequences, in particular with the possibility of developing cancer (2, 3). (b) Human space exploration has gone beyond moon and is planning to send human to the orbit of Mars by the mid-2030s. And a landing on Mars will follow.

  6. Proteomics of apheresis platelet supernatants during routine storage: Gender-related differences.

    Science.gov (United States)

    Dzieciatkowska, Monika; D'Alessandro, Angelo; Burke, Timothy A; Kelher, Marguerite R; Moore, Ernest E; Banerjee, Anirban; Silliman, Christopher C; West, Bernadette F; Hansen, Kirk C

    2015-01-01

    Proteomics has identified potential pathways involved in platelet storage lesions, which correlate with untoward effects in the recipient, including febrile non-haemolytic reactions. We hypothesize that an additional pathway involves protein mediators that accumulate in the platelet supernatants during routine storage in a donor gender-specific fashion. Apheresis platelet concentrates were collected from 5 healthy males and 5 females and routinely stored. The 14 most abundant plasma proteins were removed and the supernatant proteins from days 1 and 5 were analyzed via 1D-SDS-PAGE/nanoLC-MS/MS, before label-free quantitative proteomics analyses. Findings from a subset of 18 proteins were validated via LC-SRM analyses against stable isotope labeled standards. A total of 503 distinct proteins were detected in the platelet supernatants from the 4 sample groups: female or male donor platelets, either at storage day 1 or 5. Proteomics suggested a storage and gender-dependent impairment of blood coagulation mediators, pro-inflammatory complement components and cytokines, energy and redox metabolic enzymes. The supernatants from female donors demonstrated increased deregulation of structural proteins, extracellular matrix proteins and focal adhesion proteins, possibly indicating storage-dependent platelet activation. Routine storage of platelet concentrates induces changes in the supernatant proteome, which may have effects on the transfused patient, some of which are related to donor gender. The rationale behind this study is that protein components in platelet releasates have been increasingly observed to play a key role in adverse events and impaired homeostasis in transfused recipients. In this view, proteomics has recently emerged as a functional tool to address the issue of protein composition of platelet releasates from buffy coat-derived platelet concentrates in the blood bank. Despite early encouraging studies on buffy coat-derived platelet concentrates, platelet

  7. Routine Radiological Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    Bechtel Nevada

    1998-01-01

    The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs

  8. Experience with effluent release from the Omaha V. A. Hospital TRIGA reactor

    Energy Technology Data Exchange (ETDEWEB)

    Blotcky, A J [Veterans Administration Hospital (United States)

    1974-07-01

    The effluent release from experiments is controlled by limiting the size of each sample irradiated so that if it was accidentally completely volatized into the closed room, the radioactive concentration would not exceed the permitted limits. The possible releases of Ar-41 and N-16 from the reactor are also considered. The experimentally determined levels of radiation around the Omaha facility are shown. From the data and calculations it was concluded that the levels of effluent release from the Omaha TRIGA are very small.

  9. Experience with effluent release from the Omaha V. A. Hospital TRIGA reactor

    International Nuclear Information System (INIS)

    Blotcky, A.J.

    1974-01-01

    The effluent release from experiments is controlled by limiting the size of each sample irradiated so that if it was accidentally completely volatized into the closed room, the radioactive concentration would not exceed the permitted limits. The possible releases of Ar-41 and N-16 from the reactor are also considered. The experimentally determined levels of radiation around the Omaha facility are shown. From the data and calculations it was concluded that the levels of effluent release from the Omaha TRIGA are very small

  10. Reduction of radiation area project plan

    International Nuclear Information System (INIS)

    1979-08-01

    This plan deals with the overall reduction of outdoor surface radiation areas under Rockwell's jurisdiction. Four basic alternatives are identified which will reduce and/or stabilize radiation areas until long-term disposal decisions are made: (1) continued routine surveillance and maintenance; (2) reduction or elimination of effluent discharges; (3) improved site stabilization; and (4) site removal. The four major transport mechanisms at Hanford that are the primary forces for contamination spread are identified as wind, animal transport, concentration and dispersal by plants, and transport resulting from human activities

  11. Radiation Damage and Fission Product Release in Zirconium Nitride

    Energy Technology Data Exchange (ETDEWEB)

    Egeland, Gerald W. [New Mexico Inst. of Mining and Technology, Socorro, NM (United States)

    2005-08-29

    Zirconium nitride is a material of interest to the AFCI program due to some of its particular properties, such as its high melting point, strength and thermal conductivity. It is to be used as an inert matrix or diluent with a nuclear fuel based on transuranics. As such, it must sustain not only high temperatures, but also continuous irradiation from fission and decay products. This study addresses the issues of irradiation damage and fission product retention in zirconium nitride through an assessment of defects that are produced, how they react, and how predictions can be made as to the overall lifespan of the complete nuclear fuel package. Ion irradiation experiments are a standard method for producing radiation damage to a surface for observation. Cryogenic irradiations are performed to produce the maximum accumulation of defects, while elevated temperature irradiations may be used to allow defects to migrate and react to form clusters and loops. Cross-sectional transmission electron microscopy and grazing-incidence x-ray diffractometry were used in evaluating the effects that irradiation has on the crystal structure and microstructure of the material. Other techniques were employed to evaluate physical effects, such as nanoindentation and helium release measurements. Results of the irradiations showed that, at cryogenic temperatures, ZrN withstood over 200 displacements per atom without amorphization. No significant change to the lattice or microstructure was observed. At elevated temperatures, the large amount of damage showed mobility, but did not anneal significantly. Defect clustering was possibly observed, yet the size was too small to evaluate, and bubble formation was not observed. Defects, specifically nitrogen vacancies, affect the mechanical behavior of ZrN dramatically. Current and previous work on dislocations shows a distinct change in slip plane, which is evidence of the bonding characteristics. The stacking-fault energy changes dramatically with

  12. Radiation protection optimization using a knowledge based methodology

    International Nuclear Information System (INIS)

    Reyes-Jimenez, J.; Tsoukalas, L.H.

    1991-01-01

    This paper presents a knowledge based methodology for radiological planning and radiation protection optimization. The cost-benefit methodology described on International Commission of Radiation Protection Report No. 37 is employed within a knowledge based framework for the purpose of optimizing radiation protection and plan maintenance activities while optimizing radiation protection. 1, 2 The methodology is demonstrated through an application to a heating ventilation and air conditioning (HVAC) system. HVAC is used to reduce radioactivity concentration levels in selected contaminated multi-compartment models at nuclear power plants when higher than normal radiation levels are detected. The overall objective is to reduce personnel exposure resulting from airborne radioactivity, when routine or maintenance access is required in contaminated areas. 2 figs, 15 refs

  13. The environmental impact of radioactive releases from accidents in nuclear power reactors

    International Nuclear Information System (INIS)

    Beattie, J.R.; Griffiths, R.F.; Kaiser, G.D.; Kinchin, G.H.

    1978-01-01

    A survey of accidental releases of radioactivity from thermal and fast reactors is presented. Following a general discussion on the hazards involved, the nature of the environmental impact of radioactive releases is examined. This includes a brief review of the natural radiation background, the effect on human health of various levels of radiation and radioactivity, permissible and reference levels, and the type of hazards from both passing clouds of airbourne radioactive material and from ground deposited material. The problem of atmospheric dispersion and methods of calculations of radioactive materials in the atmosphere are examined in order for the consequences of accidental release to be analysed. National accidents and their environmental consequences are then examined. Finally there is a review of the risks to which man is always exposed because of his environment. Common and collective risks are also considered. Conclusions are reached as to the acceptibility or otherwise of the environmental impact of reactor accidents. (U.K.)

  14. Investigation of quality assurance routines of DAP-meters in Swedish hospitals; Kartlaeggning av kvalitetssaekringsrutiner foer DAP-maetare i svensk sjukvaard

    Energy Technology Data Exchange (ETDEWEB)

    Almen, Anja; Grindborg, Jan-Erik; Leitz, Wolfram

    2005-11-01

    The Swedish Radiation Protection Authority has investigated quality control of dose area product meters (DAP meters) used in x-ray diagnostics. A questionnaire was sent out to medical physics experts who are working with diagnostic radiology in Swedish hospitals. This report presents information about the routines practised and gives examples of measures to improve the quality of these practices.

  15. The sources of radiation exposure

    International Nuclear Information System (INIS)

    Bennett, B.G.

    1992-01-01

    Radiation protection of workers and of members of the public requires an assessment of the various sources of exposure, their variations in time or under specific conditions or circumstances, and the possibilities for control or limitation. The United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) has evaluated the various components of natural and man-made sources in some detail. Natural exposures form the largest component of radiation exposure of man. Variability in exposures depends on elevation, the concentrations of radionuclides in soil, food and water, the composition of building materials and the susceptibility of indoor spaces to radon build-up. Man-made sources have included exposures to fallout from atmospheric nuclear testing and discharged from nuclear fuel cycle installations in routine operations or in accidents. The other main source of radiation exposures of individuals is in medical diagnostic examinations and therapeutic treatments. (author)

  16. Methodology for assessing the radiological consequences of radioactive releases from the BPX Facility at PPPL

    International Nuclear Information System (INIS)

    McKenzie-Carter, M.A.; Lyon, R.E.; Rope, S.K.

    1991-04-01

    This report contains information to support the Environmental Assessment for the Burning Plasma Experiment (BPX) Project proposed for the Princeton Plasma Physics Laboratory (PPPL). The assumptions and methodology used to assess the impact to members of the public from operational and accidental releases of radioactive material from the proposed BPX during the operational period of the project are described. A description of the tracer release tests conducted at PPPL by NOAA is included; dispersion values from these tests are used in the dose calculations. Radiological releases, doses, and resulting health risks are calculated and summarized. The computer code AIRDOS- EPA, which is part of the computer code system CAP-88, is used to calculate the individual and population doses for routine releases; FUSCRAC3 is used to calculate doses resulting from off-normal releases where direct application of the NOAA tracer test data is not practical. Where applicable, doses are compared to regulatory limits and guideline values. 48 refs., 16 tabs

  17. Effects of atomic bomb radiations on human food

    Energy Technology Data Exchange (ETDEWEB)

    Pace, F C

    1956-01-01

    The increase in energy release of atomic weapons has increased the hazard of atomic radiation to food. Products of atomic explosions are probably similar regardless of size. Of the energy released, blast energy accounts for one-half, heat flash for one-third, initial nuclear radiation for one-twentieth, and residual radiation (potential fallout) about one-tenth. Radioactive elements may enter man by inhalation, by open wounds, or by ingestion of contaminated food. Food can become contaminated by direct fallout on unprotected food or through metabolic assimilation by plants or animals. Dust-proof containers and undamaged cans provide protection from the first hazard. Cans, etc. should be washed before opening. Other food could be cleaned and used if subsequent monitoring indicated that the fallout material had been removed.

  18. Conformal radiation therapy with or without intensity modulation in the treatment of localized prostate cancer

    International Nuclear Information System (INIS)

    Maingon, P.; Truc, G.; Bosset, M.; Peignaux, K.; Ammor, A.; Bolla, M.

    2005-01-01

    Conformal radiation therapy has now to be considered as a standard treatment of localized prostatic adenocarcinomas. Using conformational methods and intensity modulated radiation therapy requires a rigorous approach for their implementation in routine, focused on the reproducibility of the treatment, target volume definitions, dosimetry, quality control, setup positioning. In order to offer to the largest number of patients high-dose treatment, the clinicians must integrate as prognostic factors accurate definition of microscopic extension as well as the tolerance threshold of critical organs. High-dose delivery is expected to be most efficient in intermediary risks and locally advanced diseases. Intensity modulated radiation therapy is specifically dedicated to dose escalation. Perfect knowledge of classical constraints of conformal radiation therapy is required. Using such an approach in routine needs a learning curve including the physicists and a specific quality assurance program. (author)

  19. A real-time positron monitor for the estimation of stack effluent releases from PET medical cyclotron facilities

    International Nuclear Information System (INIS)

    Mukherjee, Bhaskar.

    2002-01-01

    Large activities of short-lived positron emitting radiopharmaceuticals are routinely manufactured by modern Medical Cyclotron facilities for positron emission tomography (PET) applications. During radiochemical processing, a substantial fraction of the volatile positron emitting radiopharmaceuticals are released into the atmosphere. An inexpensive, fast response positron detector using a simple positron-annihilation chamber has been developed for real-time assessment of the stack release of positron emitting effluents at the Australian National Medical Cyclotron. The positron detector was calibrated by using a 3.0 ml (1.50 MBq) aliquot of 18 FDG and interfaced to an industrial standard datalogger for the real-time acquisition of stack release data

  20. Comparison of the performance of net radiation calculation models

    DEFF Research Database (Denmark)

    Kjærsgaard, Jeppe Hvelplund; Cuenca, R.H.; Martinez-Cob, A.

    2009-01-01

    . The long-wave radiation models included a physically based model, an empirical model from the literature, and a new empirical model. Both empirical models used only solar radiation as required for meteorological input. The long-wave radiation models were used with model calibration coefficients from......Daily values of net radiation are used in many applications of crop-growth modeling and agricultural water management. Measurements of net radiation are not part of the routine measurement program at many weather stations and are commonly estimated based on other meteorological parameters. Daily...... values of net radiation were calculated using three net outgoing long-wave radiation models and compared to measured values. Four meteorological datasets representing two climate regimes, a sub-humid, high-latitude environment and a semi-arid mid-latitude environment, were used to test the models...

  1. In search for effective methods of routine formation

    Directory of Open Access Journals (Sweden)

    Kandora Marcin

    2017-05-01

    Full Text Available Organizational routines are a frequently researched phenomenon in contemporary management science. Although the available theoretical foundations of Routine Theory seem to have reached a significant degree of maturity over the last thirty years, the same could not be said about the availability of material advice for the management practice. This paper addresses this gap and proposes a framework for an effective routine shaping process. It builds on a brief analysis of available literature on routine formation, supported by case study findings. The approach proposed stresses the importance of the controlled learning process and underlines the importance of deliberate implementation, in contrast to the evolutionary and engineering views on routine emergence.

  2. Recurrent analysis of radiation protection conditions at the nuclear power station

    International Nuclear Information System (INIS)

    1986-01-01

    National Institute of Radiation Protection has cause of the Government Bill 1980/81:90 analysed following viewpoints of radiation protection: - Occupational exposes. - Dose rate trends. - Implemented and planned measures of importance from the viewpoint of radiation protection. - Releases and environmental impact. - Organisation and training in radiation protection. (authors)

  3. INDAR: a computer code for the calculation of critical group radiation exposure from routine discharges of radioactivity to seas and estuaries - description and users' guide

    International Nuclear Information System (INIS)

    Maul, P.R.; Wilmott, S.

    1988-12-01

    The computer program INDAR enables detailed estimates to be made of critical group radiation exposure arising from routine discharges of radioactivity for coastal sites where the discharge is close to the shore and the shoreline is reasonably straight, and for estuarine sites where radioactivity is rapidly mixed across the width of the estuary. Important processes which can be taken into account include the turbulence generated by the discharge, the effects of a sloping sea bed and the variation with time of the lateral dispersion coefficient. The significance of the timing of discharges can also be assessed. INDAR uses physically meaningful hydrographic parameters directly. For most sites the most important exposure pathways are seafood consumption, external exposure over estuarine sediments and beaches, and the handling of fishing gear. As well as for these primary pathways, INDAR enables direct calculations to be made for some additional exposure pathways. The secondary pathways considered are seaweed consumption, swimming, the handling of materials other than fishing gear and the inhalation of activity. (author)

  4. Radiation protection, 1975. Annual EPA review of radiation protection activities

    International Nuclear Information System (INIS)

    1976-06-01

    The EPA, under its Federal Guidance authorities, is responsible for advising the President on all matters pertaining to radiation and, through this mechanism, to provide guidance to other Federal agencies on radiation protection matters. Highlights are presented of significant radiation protection activities of all Federal agencies which were completed in 1975, or in which noteworthy progress was made during that period, and those events affecting members of the public. State or local activities are also presented where the effects of those events may be more far-reaching. At the Federal level significant strides have been made in reducing unnecessary radiation exposure through the efforts of the responsible agencies. These efforts have resulted in the promulgation of certain standards, criteria and guides. Improved control technologies in many areas make it feasible to reduce emissions at a reasonable cost to levels below current standards and guides. This report provides information on the significant activities leading to the establishment of the necessary controls for protection of public health and the environment. Radiation protection activities have been undertaken in other areas such as medical, occupational and consumer product radiation. In the context of radiation protection, ancillary activities are included in this report in order to present a comprehensive overview of the events that took place in 1975 that could have an effect on public health, either directly or indirectly. Reports of routine or continuing radiation protection operations may be found in publications of the sponsoring Federal agencies, as can more detailed information about activities reported in this document. A list of some of these reports is included

  5. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1992-06-01

    The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network is operated by the NRC in cooperation with participating states to provide continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. Ambient radiation levels result from naturally occurring radionuclides present in the soil, cosmic radiation constantly bombarding the earth from outer space, and the contribution, if any, from the monitored facilities and other man-made sources. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the first quarter of 1992. All radiation measurements are made using small, passive detectors called thermoluminescent dosimeters (TLDs), which provide a quantitative measurement of the radiation levels in the area in which they are placed. Each site is monitored by arranging approximately 40 to 50 TLD stations in two concentric rings extending to about five miles from the facility. All TLD stations are outside the site boundary of the facility

  6. IRPA Regional Congress on Radiation Protection in Central Europe

    International Nuclear Information System (INIS)

    2003-01-01

    The Congress proceedings included 93 papers. The IRPA Congress materials deals with progress the various IRPA initiatives to implement new radiation protection concepts. In accordance to this actual trends the main topics of the congress are 'Clearance levels and material release' and 'Environmental impact assessment of workplaces resp. facilities with radiation sources'. Papers and posters in all traditional radiation protection subjects (general aspects, biological effects of radiation, radiation protection in medicine, dosimetry, instrumentation, quality assurance)

  7. IRPA Regional Congress on Radiation Protection in Central Europe

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    The Congress proceedings included 93 papers. The IRPA Congress materials deals with progress the various IRPA initiatives to implement new radiation protection concepts. In accordance to this actual trends the main topics of the congress are 'Clearance levels and material release' and 'Environmental impact assessment of workplaces resp. facilities with radiation sources'. Papers and posters in all traditional radiation protection subjects (general aspects, biological effects of radiation, radiation protection in medicine, dosimetry, instrumentation, quality assurance)

  8. 40 CFR 141.621 - Routine monitoring.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Routine monitoring. 141.621 Section....621 Routine monitoring. (a) Monitoring. (1) If you submitted an IDSE report, you must begin monitoring..., you must monitor at the location(s) and dates identified in your monitoring plan in § 141.132(f...

  9. Radiation dose reduction to the male gonads during MDCT: the effectiveness of a lead shield.

    Science.gov (United States)

    Hohl, Christian; Mahnken, Andreas H; Klotz, Ernst; Das, Marco; Stargardt, Achim; Mühlenbruch, Georg; Schmidt, Thorsten; Günther, Rolf W; Wildberger, Joachim E

    2005-01-01

    Our study was designed to quantify the effect of a standard gonad shield on the testicular radiation exposure due to scatter during routine abdominopelvic MDCT. Routine abdominopelvic MDCT was performed in 34 patients with gonadal lead shielding and 32 patients without this shielding; the testes were not exposed to the direct beam during the examination. We estimated the testicular dose administered with thermoluminescent dosimetry, taking into account each patient's body weight and body mass index (BMI). With a 1-mm lead shield, the mean testicular dose was reduced from 2.40 to 0.32 mSv, a reduction of 87%. The difference was found to be statistically significant (p Shielding the male gonads reduces the testicular radiation dose during abdominopelvic MDCT significantly and can be recommended for routine use.

  10. Programmes and Systems for Source and Environmental Radiation Monitoring

    International Nuclear Information System (INIS)

    2010-01-01

    The discharge of radionuclides to the atmosphere and aquatic environments is a legitimate practice in the nuclear and other industries, hospitals and research. Where appropriate, monitoring of the discharges and of relevant environmental media is an essential regulatory requirement in order to ensure appropriate radiation protection of the public. Such monitoring provides information on the actual amounts of radioactive material discharged and the radionuclide concentrations in the environment, and is needed to demonstrate compliance with authorized limits, to assess the radiation exposure of members of the public and to provide data to aid in the optimization of radiation protection. Uncontrolled releases of radionuclides to the atmosphere and aquatic environments may occur as a result of a nuclear or radiological accident. Again, monitoring at the source of the release and of the environment is necessary. In this case, monitoring is used both to assess the radiation exposure of members of the public and to determine the actions necessary for public protection, including longer term countermeasures. Source and environmental monitoring associated with the release of radionuclides to the environment is the subject of a number of IAEA Safety Standards, particularly IAEA Safety Standard RS-G-1.8 (Environmental and Source Monitoring for Purposes of Radiation Protection). This publication is intended to complement this Safety Guide and, by so doing, replaces Safety Series No. 41 (Objectives and Design of Environmental Monitoring Programmes for Radioactive Contaminants) and Safety Series No. 46 (Monitoring of Airborne and Liquid Radioactive Releases from Nuclear Facilities to the Environment). Like Safety Standard RS-G-1.8, this Safety Report deals with monitoring at the source and in the environment associated with authorized releases of radionuclides to the environment. It also deals with the general issues of emergency monitoring during and in the aftermath of an

  11. Derived release limits (DRL's) for airborne and liquid effluents from the Chalk River Nuclear Laboratories during normal operations

    International Nuclear Information System (INIS)

    Palmer, J.F.

    1981-02-01

    Derived release limits (DRL's), based on regulatory dose limits, have been calculated for routine discharges of radioactivity in airborne and liquid effluents from the Chalk River Nuclear Laboratories. Three types of sources of airborne effluents were considered: the NRX/NRU stack, the 61 m stack connected to the 99 Mo production facility, and a roof vent typical of those installed on several buildings on the site. Sources of liquid effluents to the Ottawa River were treated as a single source from the site as a whole. Various exposure pathways to workers on the site and to members of the public outside the site boundary were considered in the calculations. The DRL's represent upper limits for routine emissions of radioactivity from the Chalk River Nuclear Laboratories to the surrounding environment. Actual releases are regulated by Administrative Levels, set lower than the DRL's, and are confirmed by monitoring. (author)

  12. The records of radiation control division, No.22 (1985)

    International Nuclear Information System (INIS)

    Fukui, Masami; Katsurayama, Kousuke; Ishida, Masahiro

    1987-03-01

    This report is a summary of activities of the radiation control division on the safety management in FY 1985. This report describes the records of the radiation control based on the activities of Indoor Radiation Control Section, Field Radiation Control Section and Personnel Radiation Control Section. External radiation doses were monitored using survey meters and film badges in the working area. Radioactive concentrations in dust and air were monitored in the radiation controlled area and at a number of locations outside the KURRI facilities. Reports of routine tasks such as the meteorological records, and the control of human exposure to radiation are described. This report also summarizes number of unscheduled tasks performed, including the replacement of the centralized monitoring board for radiation control, radiation monitors related to the extension of the spent fuel storage building, and the computer processing system of some indoor radiation monitors. Measurements of environmental radioactivity at several field locations are also presented in this report. (author)

  13. Radiomodifying effect of caffeine on mammalian cellular system using gamma radiation and proton beam radiation

    International Nuclear Information System (INIS)

    Samanth, Sneha P.; Yadav, Usha; Shirsath, K.B.; Desai, Utkarsha N.; Chaurasia, Rajesh K.; Bhat, Nagesh N.; Anjaria, K.B.; Sapra, B.K.

    2016-01-01

    Caffeine is a commonly consumed neurostimulant in the world. Reports suggest the radiomodifying effects of caffeine against low Linear Energy Transfer (LET) radiation when administered pre and post irradiation by releasing checkpoint arrest. In the present report, the radioprotective and radiosensitizing ability of caffeine (10μM - 2mM) were studied on Chinese Hamster Ovary (CRO) cell line against low as well as high LET radiation when administered pre, post and continuously during radiation. Effect of caffeine treatment on the genotoxicity induced by gamma and proton beam radiation was assessed by micronucleus assay. Effect of caffeine treatment on clonogenic survival of irradiated cells was also assessed

  14. Results of the 1993 Association of Residents in Radiation Oncology survey

    International Nuclear Information System (INIS)

    Ling, Stella M.; Flynn, Daniel F.

    1996-01-01

    In 1993, the Association of Residents in Radiation Oncology (ARRO) conducted its tenth annual survey of all residents training in radiation oncology in the United States. The characteristics of current residents are described. Factors influencing the choice of Radiation Oncology as a medical specialty, and posttraining career plans were identified. Residents raised issues on the adequacy of training, problems in work routine, and expressed concerns about board certification and recertification, and about decreased future practice opportunities

  15. Release of RANKERN 16A

    Directory of Open Access Journals (Sweden)

    Bird Adam

    2017-01-01

    Full Text Available RANKERN 16 is the latest version of the point-kernel gamma radiation transport Monte Carlo code from AMEC Foster Wheeler’s ANSWERS Software Service. RANKERN is well established in the UK shielding community for radiation shielding and dosimetry assessments. Many important developments have been made available to users in this latest release of RANKERN. The existing general 3D geometry capability has been extended to include import of CAD files in the IGES format providing efficient full CAD modelling capability without geometric approximation. Import of tetrahedral mesh and polygon surface formats has also been provided. An efficient voxel geometry type has been added suitable for representing CT data. There have been numerous input syntax enhancements and an extended actinide gamma source library. This paper describes some of the new features and compares the performance of the new geometry capabilities.

  16. Release of RANKERN 16A

    Science.gov (United States)

    Bird, Adam; Murphy, Christophe; Dobson, Geoff

    2017-09-01

    RANKERN 16 is the latest version of the point-kernel gamma radiation transport Monte Carlo code from AMEC Foster Wheeler's ANSWERS Software Service. RANKERN is well established in the UK shielding community for radiation shielding and dosimetry assessments. Many important developments have been made available to users in this latest release of RANKERN. The existing general 3D geometry capability has been extended to include import of CAD files in the IGES format providing efficient full CAD modelling capability without geometric approximation. Import of tetrahedral mesh and polygon surface formats has also been provided. An efficient voxel geometry type has been added suitable for representing CT data. There have been numerous input syntax enhancements and an extended actinide gamma source library. This paper describes some of the new features and compares the performance of the new geometry capabilities.

  17. Release of engineered nanomaterials from polymer nanocomposites: the effect of matrix degradation.

    Science.gov (United States)

    Duncan, Timothy V

    2015-01-14

    Polymer nanocomposites-polymer-based materials that incorporate filler elements possessing at least one dimension in the nanometer range-are increasingly being developed for commercial applications ranging from building infrastructure to food packaging to biomedical devices and implants. Despite a wide range of intended applications, it is also important to understand the potential for exposure to these nanofillers, which could be released during routine use or abuse of these materials so that it can be determined whether they pose a risk to human health or the environment. This article is the second of a pair that review what is known about the release of engineered nanomaterials (ENMs) from polymer nanocomposites. Two roughly separate ENM release paradigms are considered in this series: the release of ENMs via passive diffusion, desorption, and dissolution into external liquid media and the release of ENMs assisted by matrix degradation. The present article is focused primarily on the second paradigm and includes a thorough, critical review of the associated body of peer-reviewed literature on ENM release by matrix degradation mechanisms, including photodegradation, thermal decomposition, mechanical wear, and hydrolysis. These release mechanisms may be especially relevant to nanocomposites that are likely to be subjected to weathering, including construction and infrastructural materials, sporting equipment, and materials that might potentially end up in landfills. This review pays particular attention to studies that shed light on specific release mechanisms and synergistic mechanistic relationships. The review concludes with a short section on knowledge gaps and future research needs.

  18. Radiation Emergency Preparedness Tools: Psychological First Aid

    Centers for Disease Control (CDC) Podcasts

    2010-12-30

    This podcast is an overview of the Clinician Outreach and Communication Activity (COCA) Call: Practical Tools for Radiation Emergency Preparedness. A specialist working with CDC's Radiation Studies Branch describes Psychological First Aid and a newly developed multimedia training program, entitled "Psychological First Aid in Radiation Disasters.".  Created: 12/30/2010 by National Center for Environmental Health (NCEH) Radiation Studies Branch and Emergency Risk Communication Branch (ERCB)/Joint Information Center (JIC); Office of Public Health Preparedness and Response (OPHPR).   Date Released: 1/13/2011.

  19. Modeling Routinization in Games: An Information Theory Approach

    DEFF Research Database (Denmark)

    Wallner, Simon; Pichlmair, Martin; Hecher, Michael

    2015-01-01

    Routinization is the result of practicing until an action stops being a goal-directed process. This paper formulates a definition of routinization in games based on prior research in the fields of activity theory and practice theory. Routinization is analyzed using the formal model of discrete......-time, discrete-space Markov chains and information theory to measure the actual error between the dynamically trained models and the player interaction. Preliminary research supports the hypothesis that Markov chains can be effectively used to model routinization in games. A full study design is presented...

  20. Routine environmental monitoring schedule, calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Markes, B.M., Westinghouse Hanford

    1996-12-10

    This document provides the Environmental Restorations Contractor (ERC) and the Project Hanford Management Contractor.(PHMC) a schedule in accordance with the WHC-CM-7-5, Environmental Compliance` and BHI- EE-02, Environmental Requirements, of monitoring and sampling routines for the Near-Field Monitoring (NFM) program during calendar year (CY) 1997. Every attempt will be made to consistently follow this schedule; any deviation from this schedule will be documented by an internal memorandum (DSI) explaining the reason for the deviation. The DSI will be issued by the scheduled performing organization and directed to Near-Field Monitoring. The survey frequencies for particular sites are determined by the technical judgment of Near- Field Monitoring and may depend on the site history, radiological status, use, and general conditions. Additional surveys may be requested at irregular frequencies if conditions warrant. All radioactive wastes sites are scheduled to be surveyed at least annually. Any newly discovered wastes sites not documented by this schedule will be included in the revised schedule for CY 1998. The outside perimeter road surveys of 200 East and West Area and the rail survey from the 300 Area to Columbia Center will be performed in the year 2000 per agreement with Department of Energy. Richland Field Office. This schedule does not discuss staffing needs, nor does it list the monitoring equipment to be used in completing specific routines. Personnel performing routines to meet this schedule shall communicate any need for assistance in completing these routines to Radiological Control management and Near-Field Monitoring. After each routine survey is completed, a copy of the survey record, maps, and data sheets will be forwarded to Near-Field Monitoring. These routine surveys will not be considered complete until this documentation is received. At the end of each month, the ERC and PHMC radiological control organizations shall forward a copy of the Routine

  1. Erratum to "Clinical evaluation of the intraoral fluoride releasing system in radiation-induced xerostomic subjects. Part 2: Phase I study".

    Science.gov (United States)

    Chambers, Mark S; Fleming, Terence J; Toth, Béla B; Lemon, James C; Craven, Timothy E; Bouwsma, Otis J; Garden, Adam S; Espeland, Mark A; Keene, Harris J; Martin, Jack W; Sipos, Tibor

    2007-01-01

    Radiation-induced xerostomia can result in the rapid onset and progression of dental caries in head and neck cancer patients. Topically applied fluorides have been successfully used to inhibit the formation of dental caries in this population. However, because intensive daily self-application is required, compliance is an issue. The intraoral fluoride-releasing system (IFRS) containing a sodium fluoride core is a newly developed, sustained-release, passive drug delivery system that does not require patient involvement except for periodic replacement, thus reducing the effect of patient compliance on its effectiveness in dental caries prevention. Twenty-two head and neck cancer patients from U. T. M. D. Anderson Cancer Center, with radiation-induced xerostomia, were entered into a pilot study to contrast the daily home use of a 0.4% stannous fluoride-gel-containing tray (control group) to IFRS (study group) with respect to tolerability and adherence, and to obtain information on relative caries preventive efficacy. Participants were stratified on the basis of radiation exposure and randomly assigned to treatment with either IFRS or stannous fluoride gel. Patients in both groups were fitted with two IFRS retainers and also were instructed to use a 1100-ppm fluoride conventional sodium fluoride dentifrice twice daily. The study was conducted as a single-blinded, parallel-cell trial. Pre-existing carious lesions were restored prior to the beginning of the study. The efficacy variable was determined by the mean number of new or recurrent decayed surfaces. Patients were examined for caries 4, 8, 12, 24, 36, and 48 weeks after initiation of treatment. Reports of adverse reactions were based on information volunteered by patients and that were elicited during interviews. At baseline, the resting and stimulated salivary flow rates (g/5min) were significantly greater in the control group than in the study group (pIFRS groups during the study period. The rate of new or

  2. A study of 60 patients with percutaneous trigger finger releases: clinical and ultrasonographic findings.

    Science.gov (United States)

    Gulabi, D; Cecen, G S; Bekler, H I; Saglam, F; Tanju, N

    2014-09-01

    We present the clinical results and ultrasonographic findings of 61 trigger digits treated with percutaneous A1 pulley release. An endoscopic carpal tunnel knife was used for the release in the outpatient department. The mean follow-up period was 3.5 months. A total of 55 digits (90%) had complete relief of their triggering postoperatively. Six digits (10%) had Grade 2 triggering clinically in the early postoperative period.The complications included six cases of insufficient release (10%), scar sensitivity in one patient, short-term hypoaesthesia in three digits (5%), and flexor tendon laceration noted on postoperative ultrasonography in eight digits (13%). No neurovascular damage was noted on the postoperative ultrasonography. Ultrasonograpy provides information about tendon laceration and changes in thickness of the pulleys and confirm A1 pulley release after surgery, but it does not alter clinical decision-making. We believe that pre- and postoperative ultrasonograpy does not need to be included as a routine examination. © The Author(s) 2014.

  3. Potential radiation doses from 1994 Hanford Operations

    Energy Technology Data Exchange (ETDEWEB)

    Soldat, J.K.; Antonio, E.J.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the potential radiation doses to the public from releases originating at the Hanford Site. Members of the public are potentially exposed to low-levels of radiation from these effluents through a variety of pathways. The potential radiation doses to the public were calculated for the hypothetical MEI and for the general public residing within 80 km (50 mi) of the Hanford Site.

  4. Potential radiation doses from 1994 Hanford Operations

    International Nuclear Information System (INIS)

    Soldat, J.K.; Antonio, E.J.

    1995-01-01

    This section of the 1994 Hanford Site Environmental Report summarizes the potential radiation doses to the public from releases originating at the Hanford Site. Members of the public are potentially exposed to low-levels of radiation from these effluents through a variety of pathways. The potential radiation doses to the public were calculated for the hypothetical MEI and for the general public residing within 80 km (50 mi) of the Hanford Site

  5. Radiation signatures from a locally energized flaring loop

    Science.gov (United States)

    Emslie, A. G.; Vlahos, L.

    1980-01-01

    The radiation signatures from a locally energized solar flare loop based on the physical properties of the energy release mechanisms were consistent with hard X-ray, microwave, and EUV observations for plausible source parameters. It was found that a suprathermal tail of high energy electrons is produced by the primary energy release, and that the number of energetic charged particles ejected into the interplanetary medium in the model is consistent with observations. The radiation signature model predicts that the intrinsic polarization of the hard X-ray burst should increase over the photon energy range of 20 to 100 keV.

  6. Radiation stability of methionine-35S and selenomethionine-75Se

    International Nuclear Information System (INIS)

    Galateanu, I.; Lungu, V.V.; Viorel, D.

    1976-01-01

    The radiation stability of methionine- 35 S and selenomethionine 75 Se was investigated using the methods of thin-layer chromatography, gas chromatography and ESR. Radiation decomposition of methionine- 35 S mainly consists in an oxidation process and in the release of volatile products. The ESR-spectra of irradiated DL-methionine indicated a strong localization of the unpaired electrons on sulfur atoms. Radiation damage to selenomethionine- 75 Se as a function of radiation dose proved an increased stability of this compound and its radiation decomposition consists in the formation of oxidized products and by direct rupture of the selenium bounds accompanied by the formation of volatile compounds like CH 3 SEH and SeH 2 . The self-radiolysis of the aqueous solution of selenomethionine- 75 Se during its storage in air leads, however, to a lower decomposition rate which consists in the release of inorganic selenium and in an oxidation process. (author)

  7. Detection of irradiated cheese and exotic fruits by a simple routine control method

    International Nuclear Information System (INIS)

    Spiegelberg, A.; Schulzki, G.; Helle, N.; Boegl, K.W.; Schreiber, G.A.

    1993-01-01

    The results demonstrate very clearly that Florisil chromatography is a suitable routine method to detect irradiation treatment in Camembert, mango seeds and avocado flesh. Inspite of excluding 1-14:1 as marker for irradiation treatment on account of fat attendant flavour compounds in fruits, an unequivocal revelation of irradiated samples was possible because the most important radiation-induced hydrocarbons 1,7-26:2 and 8-14:1 (arising from oleic acid) could be clearly detected in both fruits. In addition, high amounts of 1-16:1 from stearic acid are present in irradiated mango and 6,9-17:2 from linoleic acid in avocado. (orig.)

  8. Radionuclide releases to the Columbia River from Hanford Operations, 1944--1971

    International Nuclear Information System (INIS)

    Heeb, C.M.; Bates, D.J.

    1994-05-01

    The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. One source of radionuclide releases to the Columbia River was from production reactor operations. This report provides a quantitative estimate of the amount of radioactivity released each month (1944--1971) to the Columbia River from eleven radionuclides as well as from gross beta activity

  9. Melatonin as Protection Against Radiation Injury

    DEFF Research Database (Denmark)

    Zetner, D.; Andersen, L. P H; Rosenberg, J.

    2016-01-01

    Introduction: Radiation is widely used in the treatment of various cancers and in radiological imaging procedures. Ionizing radiation causes adverse effects, leading to decreased quality of life in patients, by releasing free radicals that cause oxidative stress and tissue damage. The sleep......-hormone melatonin is a free radical scavenger, and induces several anti-oxidative enzymes. This review investigates the scientific literature on the protective effects of melatonin against exposure to ionizing radiation, and discusses the clinical potential of melatonin as prophylactic treatment against ionizing...... and protected against radiation enteritis. These protective effects were only documented when melatonin was administered prior to exposure to ionizing radiation. Discussion: This review documents that melatonin effectively protects animals against injury to healthy tissues from ionizing radiation. However...

  10. Iodine 131 therapy patients: radiation dose to staff

    International Nuclear Information System (INIS)

    Castronovo, F.P. Jr.; Beh, R.A.; Veilleux, N.M.

    1986-01-01

    Metastasis to the skeletal system from follicular thyroid carcinoma may be treated with an oral dose of 131 I-NaI. Radiation exposures to hospital personnel attending these patients were calculated as a function of administered dose, distance from the patient and time after administration. Routine or emergency patient handling tasks would not exceed occupational radiation protection guidelines for up to 30 min immediately after administration. The emergency handling of several patients presents the potential for exceeding these guidelines. (author)

  11. Improving care coordination using organisational routines

    DEFF Research Database (Denmark)

    Prætorius, Thim

    2016-01-01

    Purpose – The purpose of this paper is to systematically apply theory of organisational routines to standardised care pathways. The explanatory power of routines is used to address open questions in the care pathway literature about their coordinating and organising role, the way they change......: care pathways and coordination, change, replication, the organisation and health care professionals. Research limitations/implications – The paper is conceptual and uses care pathways as illustrative instances of hospital routines. The propositions provide a starting point for empirical research....... Practical implications – The analysis highlights implications that health care professionals and managers have to consider in relation to coordination, change, replication, the way the organisation influences care pathways and the way care pathways influence health care professionals. Originality...

  12. Air concentration and ground deposition following radioactive airborne releases

    International Nuclear Information System (INIS)

    Brofferio, C.; Cagnetti, P.; Ferrara, V.

    1985-01-01

    The fundamental aim of this report is to provide the mathematical and physical operational basis for the evaluation of air concentration and ground deposition, following radioactive airborne releases from a nuclear power plant, both during normal operations and in accidental conditions. As far as accidental releases are concerned, the basical assumptions on meteorological and diffusive situation are considered from a safety point of view: namely those pessimistic but realistically representative situation are taken into account which lead to maximum air concentration and ground deposition values, even if characterized by low recurrence probability. Those elements are the inputs for many environmental transfer models of maximum consequence evaluations up to man. As far as routine releases are concerned, it is shown, together with the usual models based on long term averaged meteorological conditions, also models studied to estimate atmospheric diffusion and deposition in low wind situations and in fog conditions, being those latter very frequent in the Po valley. Finally, the main operations and modalities of collecting and elaborating meteorological data for for radioprotection evaluations are also shown. It is to be pointed out that the methods and the models developed and considered in this work are of a more general validity, and can be also used for applications concerning non-radioactive releases, as it is the case when dealing with conventional power plants

  13. Industrialization drive of radiation processing for economic growth in China

    International Nuclear Information System (INIS)

    Lu Yanxiao

    1996-12-01

    The transfer of research and development achievements of radiation processing to routine industrial applications in China is reviewed. While making a brief survey of historical background, the paper indicates the different roles that various domestic organizations played in the industrialization drive of radiation processing. Among them the Government's role is the most important one. In accordance with recent growth of the number of industrial radiation facilities (e.g. cobalt-60 irradiators and electron beam accelerators) and current application of radiation processing in main fields in different parts of the country, it can be said that a new radiation processing industry is shaping up in its developing stage to satisfy the growing requirements for economic booming in China. (16 refs.)

  14. Current Practice Patterns Surrounding Fertility Concerns in Stage I Seminoma Patients: Survey of United States Radiation Oncologists.

    Science.gov (United States)

    Post, Carl M; Jain, Aditya; Degnin, Catherine; Chen, Yiyi; Craycraft, Mike; Hung, Arthur Y; Jaboin, Jerry J; Thomas, Charles R; Mitin, Timur

    2018-01-16

    Patients with testicular seminoma may face fertility issues because of their underlying disease as well as treatments they undergo. The current patterns of practice among U.S. radiation oncologists aimed at assessing and preserving fertility in patients with Stage I seminoma are unknown. We surveyed practicing U.S. radiation oncologists via an Institutional Review Board-approved online questionnaire. Respondents' characteristics and perceived patient infertility rates were analyzed for association with treatment recommendations. We received 353 responses, of whom one quarter (23%) consider themselves experts. A vast majority (84%) recommend observation as a default strategy. Fifty-two percent routinely advise fertility assessment for patients before observation or chemotherapy, and 74% routinely do so before adjuvant radiation therapy (RT). Forty-one percent and 43% believe that 10% and 30% of patients are infertile following orchiectomy, respectively. Thirty-seven percent and 22% believe infertility rates following para-aortic RT to be 30% and 50%, respectively. Eighty percent routinely use clamshell scrotal shielding. Responders with higher perceived infertility rates are more likely to recommend fertility assessment/sperm banking (Fisher's exact p < 0.0001). Responders who routinely advised fertility assessment were more likely to use clamshell shielding (Cochran-Armitage trend test p = 0.0007). Clamshell use was positively correlated with higher perceived infertility rates following para-aortic RT (Spearman's correlation coefficient = 0.006). Despite a clear knowledge of fertility issues in men diagnosed with seminoma, there is no universal adoption of fertility assessment among U.S. radiation oncologists.

  15. GEWEX Surface Radiation Budget (SRB)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The NASA/GEWEX Surface Radiation Budget (SRB) Release-3.0 data sets contains global 3-hourly, daily, monthly/3-hourly, and monthly averages of surface and top-of...

  16. An update on standards for radiation in the environment and associated estimates of risk

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1989-01-01

    This presentation reviews current and proposed standards, recommendations, and guidances for limiting routine radiation exposures of the public, and estimates the risk corresponding to standards, recommendations, and guidances. These estimates provide a common basis for comparing different criteria for limiting public exposures to radiation, as well as hazardous chemicals

  17. Radiation exposure of pediatric patients and physicians during cardiac catheterization and balloon pulmonary valvuloplasty.

    Science.gov (United States)

    Wu, J R; Huang, T Y; Wu, D K; Hsu, P C; Weng, P S

    1991-07-15

    Thermoluminescent dosimeters were applied to various areas of 61 pediatric patients and physicians to measure radiation doses during routine cardiac catheterization and during 4 cases of balloon pulmonary valvuloplasty. Radiation doses were measured during chest roentgenography, fluoroscopy and cineangiography. Average skin dose to the chest was 121 microGy during chest x-ray, 5,182 microGy during catheterization and 641 mGy during valvuloplasty. For the eyes, thyroid and gonads of the patients, the exposure during routine catheterization was equal to 0.4, 6 and 0.2 chest x-rays, respectively. Radiation dose of the operator was 3 microGy for the eyes and 6 miCroGy in the thyroid. About 56% of the operator's dose could be reduced by thyroid shields, and 80% by lead aprons. The assistant received only 1 microGy outside the thyroid shield. Therefore, we have concluded that the patients' dose during routine catheterization is largely based on our experimental results, but the dose is acceptable based on the risk factor analysis. The skin dose to the right lateral chest of the patient during valvuloplasty is extremely high, perhaps as high as the equivalent of 1,000 chest x-rays. Besides the clinical benefits of valvuloplasty, the long-term radiation-related hazards to the patient should be carefully monitored.

  18. Radiation exposure of pediatric patients and physicians during cardiac catheterization and balloon pulmonary valvuloplasty

    International Nuclear Information System (INIS)

    Wu, J.R.; Huang, T.Y.; Wu, D.K.; Hsu, P.C.; Weng, P.S.

    1991-01-01

    Thermoluminescent dosimeters were applied to various areas of 61 pediatric patients and physicians to measure radiation doses during routine cardiac catheterization and during 4 cases of balloon pulmonary valvuloplasty. Radiation doses were measured during chest roentgenography, fluoroscopy and cineangiography. Average skin dose to the chest was 121 microGy during chest x-ray, 5,182 microGy during catheterization and 641 mGy during valvuloplasty. For the eyes, thyroid and gonads of the patients, the exposure during routine catheterization was equal to 0.4, 6 and 0.2 chest x-rays, respectively. Radiation dose of the operator was 3 microGy for the eyes and 6 miCroGy in the thyroid. About 56% of the operator's dose could be reduced by thyroid shields, and 80% by lead aprons. The assistant received only 1 microGy outside the thyroid shield. Therefore, the authors have concluded that the patients dose during routine catheterization is largely based on our experimental results, but the dose is acceptable based on the risk factor analysis. The skin dose to the right lateral chest of the patient during valvuloplasty is extremely high, perhaps as high as the equivalent of 1,000 chest x-rays. Besides the clinical benefits of valvuloplasty, the long-term radiation-related hazards to the patient should be carefully monitored

  19. Radiation exposure by radio-iodine release of the planned nuclear power plant Wyhl

    Energy Technology Data Exchange (ETDEWEB)

    Bleck-Neuhaus, J

    1981-01-01

    The radioecology of iodine-131 in the off-air of a nuclear power plant is subject to investigation of the critical exposure pathway air - pasture ground - cow - milk. According to the findings on the factors influencing the radiation exposure of man presented in scientific publication we have to deviate today from static equilibrium models. Such models can no longer satisfy at the present state of the art. The viewing of the short-term time behaviour of the radioecological parameter that is imperative with iodine-131 shows that the conventional calculation, chiefly with mean values of many years, does not satisfy the requirements to replace the calculation of the radiation exposure at the most unfavourable points of exposure demanded by the Radiation Protection Ordinance. This report proves that in a number of possible events under normal operating conditions the radiation exposure is far more important and the limiting dose rates are unmistakably exceeded. If favourable conditions coincide it can in fact be expected that the radiation exposure by radio iodine remains below the limiting close rate.

  20. [The controversy of routine articulator mounting in orthodontics].

    Science.gov (United States)

    Wang, Li; Han, Xianglong; Bai, Ding

    2013-06-01

    Articulators have been widely used by clinicians of dentistry. But routine articulator mounting is still controversial in orthodontics. Orthodontists oriented by gnathology approve routine articulator mounting while nongnathologic orthodontists disapprove it. This article reviews the thoughts of orthodontist that they agree or disagree with routine articulator mounting based on the considerations of biting, temporomandibular disorder (TMD), periodontitis, and so on.

  1. Extra holiday because of ionising radiation not necessary

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    The 'regulations for special measures to protect employees working with X-rays and radium radiation' of 21st November 1947, which included a statutory six-week holiday period annually, has now been superceded by 'regulations on special protective measures for work with ionising radiation', issued by the Directorate for Work Inspection on 31st March 1978, effective from 1st May 1978. In addition to removing the requirement for six weeks annual holiday for radiation personnel, routine medical surveillance is only required every third year instead of annually. A number of other changes are mentioned. The basis for these changes is that continuous personnel dosimetry and better knowledge of the effects of ionising radiation allows any necessary measures to be taken on the basis of these. (JIW)

  2. A robust estimate of the number and characteristics of persons released from prison in Australia.

    Science.gov (United States)

    Avery, Alex; Kinner, Stuart A

    2015-08-01

    To estimate the number and characteristics of adults released from prison in Australia. We calculated ratios, stratified by age, sex and Indigenous status, by comparing the number of persons released from prison in New South Wales (NSW), with the number in NSW prisons on 30 June of the corresponding year. These stratified ratios were applied to Australia-wide prison data to estimate the number and characteristics of persons released annually. We estimated that in 2013, 38,576 persons were released from prison in Australia - 25.3% more than the daily prison population. Young people, Indigenous people and women were over-represented among those released. We estimated that 3.69 Indigenous women aged 18-24 were released annually for each equivalent person in prison; and 2.75 non-Indigenous women aged 18-24 were released annually for each equivalent person in prison. The annual 'flow' through Australia's prisons is well in excess of the daily number, but information on those moving through prison systems is not yet publicly available. The characteristics of those released from prison differ meaningfully from those of people in prison. Routine, national reporting of prison separations is critical to informing upscaling and targeting of Throughcare services for this profoundly vulnerable population. © 2015 Public Health Association of Australia.

  3. Thyroid dysfunction after radiation therapy to the neck

    International Nuclear Information System (INIS)

    Soejima, Toshinori; Hirota, Saeko; Obayashi, Kayoko; Takada, Yoshiki; Kimura, Shuji; Yoshida, Shoji.

    1993-01-01

    The effects of radiation on the thyroid were investigated in 102 patients treated by radiation therapy to the neck. All patients had radiation ports which included the thyroid gland. Serum thyroid stimulating hormone (TSH) levels were elevated in 41 cases and the cumulative elevation rate was 52.1% in 5 years. The high frequency of elevated serum TSH levels observed in patients whose thyroid glands were included within the radiation fields (74.1%) was statistically significant compared to those whose thyroid glands were only partially included (23.4%). Among the patients whose entire thyroid glands were included within the radiation field, combination with chemotherapy increased the frequency of elevated serum TSH levels, but the increase was not statistically significant. Among 36 laryngeal cancer patients treated by only radiation therapy through a portal encompassing part of the thyroid, 4 (14%) were found to have elevated serum TSH levels. We advocate routine monitoring of thyroid functions after radiation therapy to the neck. (author)

  4. Radiation protection and communication. Sociology and communication impact in radiation protection

    International Nuclear Information System (INIS)

    Berne, G.; Bicheron, G.; Franco, P.

    2000-01-01

    Communication about nuclear energy was the subject of this conference. Different examples of communications are detailed in fields as different as impact of iodine 131 release in waste waters or public information about radiation protection, the north Cotentin radioecology group or what information to give to the patients in nuclear medicine. (N.C.)

  5. Instrument evaluation no. 33. Automess Szintomat 6134 radiation survey meter

    International Nuclear Information System (INIS)

    McClure, D.R.

    1986-04-01

    The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to be carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the appropriate Recommendations of the International Electrotechnical Commission. The radiations in the tests are, in general, selected from the range of reference radiations for instrument calibration being drawn up by the International Standards Organisation. Normally, each report deals with the capabilities and limitations of one model of instrument and no direct comparison with other instruments intended for similar purposes is made, since the significance of particular performance characteristics largely depends on the radiations and environmental conditions in which the instrument is to be used. The results quoted here have all been obtained from tests on instruments in routine production, with the appropriate measurements being made by the NRPB. This instrument evaluation report deals with the Automess Szintomat 6134 Radiation Survey Meter

  6. Iron release from ferritin and lipid peroxidation by radiolytically generated reducing radicals

    International Nuclear Information System (INIS)

    Reif, D.W.; Schubert, J.; Aust, S.D.

    1988-01-01

    Iron is involved in the formation of oxidants capable of damaging membranes, protein, and DNA. Using 137 Cs gamma radiation, we investigated the release of iron from ferritin and concomitant lipid peroxidation by radiolytically generated reducing radicals, superoxide and the carbon dioxide anion radical. Both radicals released iron from ferritin with similar efficiencies and iron mobilization from ferritin required an iron chelator. Radiolytically generated superoxide anion resulted in peroxidation of phospholipid liposomes as measured by malondialdehyde formation only when ferritin was included as an iron source and the released iron was found to be chelated by the phospholipid liposomes

  7. Efficiency of lead aprons in blocking radiation − how protective are they?

    Directory of Open Access Journals (Sweden)

    Seung-Jae Hyun

    2016-05-01

    Interpretation: The 0.5 mm lead aprons blocked just over one third of the radiation scattered towards the surgeon. Use of robotic-guidance in a minimally invasive approach provided for a reduction of 62.5% of the overall radiation the surgeon was exposed to during open conventional approach. We conclude that reduced radiation use (e.g. by using robotic guidance is a more effective strategy for minimizing exposure to radiation than reliance on protection by lead aprons, and recommend utilization of practices and technologies that reduce the surgical team’s routine exposure to X-rays.

  8. Radiation sterilization of tissue allografts: Requirements for validation and routine control. A code of practice

    International Nuclear Information System (INIS)

    2007-12-01

    These recommendations for the radiation sterilization of tissue allografts adopt the principles that the International Organization for Standardization (ISO) applies to the radiation sterilization of health care products. The approach has been adapted to take into account the special features associated with human tissues and the features that distinguish them from industrially produced sterile health care products. The approach as described here is not applicable if viral contamination is identified. Thus it is emphasized that the human donors of the tissues must be medically and serologically screened. To further support this screening it is recommended that autopsy reports be reviewed if available. This adaptation of established ISO methods can thus only be applied to sterilization of tissue allografts if the radiation sterilization described here is the terminal stage of a careful, detailed, documented sequence of procedures involving: donor selection; tissue retrieval; tissue banking general procedures; specific processing procedures; labelling; and distribution. The methods proposed here for the establishment of a sterilization dose are based on statistical approaches used for the sterilization of health care products and modified appropriately for the low numbers of tissue allograft samples typically available. This code of practice will be useful to tissue banking staff, surgeons using tissues for transplantation, regulators who oversee the safety of transplantation and radiation sterilization procedures, members of tissue banking associations, health service personnel in hospitals in which tissue transplantations are performed and inter-governmental organizations involved in transplantation issues, for example the World Health Organization. This publication was discussed extensively at an international meeting in Wrexham in the United Kingdom and was approved by the Technical Advisory Committee of the relevant IAEA project, which included the Chairpersons

  9. Present status and expected progress in radiation processing dosimetry

    DEFF Research Database (Denmark)

    Kovács, A.; Miller, A.

    2004-01-01

    The paper describes the present status of radiation processing dosimetry including the methods used most widely in gamma- and electron processing as well as the new methods under development or introduction. The recent trends with respect to calibrationof routine dosimetry systems as well...

  10. Herwig++ 2.6 release note

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, K.; Gieseke, S.; Roehr, C. [Karlsruher Institut fuer Technologie, Karlsruhe (DE). Inst. fuer Theoretische Physik] (and others)

    2012-05-15

    A new release of the Monte Carlo event generator Herwig++ (version 2.6) is now available. This version comes with a number of improvements including: a new structure for the implementation of next-to-leading order matrix elements; an improved treatment of wide-angle gluon radiation; new hard-coded next-to-leading order matrix elements for deep inelastic scattering and weak vector boson fusion; additional models of physics beyond the StandardModel, including the production of colour sextet particles; a statistical colour reconnection model; automated energy scaling of underlying-event tunes.

  11. Herwig++ 2.6 release note

    International Nuclear Information System (INIS)

    Arnold, K.; Gieseke, S.; Roehr, C.

    2012-05-01

    A new release of the Monte Carlo event generator Herwig++ (version 2.6) is now available. This version comes with a number of improvements including: a new structure for the implementation of next-to-leading order matrix elements; an improved treatment of wide-angle gluon radiation; new hard-coded next-to-leading order matrix elements for deep inelastic scattering and weak vector boson fusion; additional models of physics beyond the StandardModel, including the production of colour sextet particles; a statistical colour reconnection model; automated energy scaling of underlying-event tunes.

  12. The Endogenous Origins of Experience, Routines and Organizational Capabilities

    DEFF Research Database (Denmark)

    Foss, Nicolai Juul; Felin, Teppo

    2011-01-01

    In this paper we discuss the origins and emergence of organizational routines and capabilities. We first argue that there are theoretical and endogeneity-related concerns associated with the key antecedents and mechanisms specified by the extant routines and capabilities literature. Specifically,...... or rationalist, choice-based approach can provide a more fruitful (though preliminary) foundation for understanding organizational behavior and capabilities.......In this paper we discuss the origins and emergence of organizational routines and capabilities. We first argue that there are theoretical and endogeneity-related concerns associated with the key antecedents and mechanisms specified by the extant routines and capabilities literature. Specifically......, we explicate the behaviorist and empiricist foundations of the organizational routines and capabilities literature and the extant emphasis placed on experience, repetition, and observation as the key antecedents and mechanisms of routines and capabilities. Based on this discussion we highlight...

  13. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1983

    International Nuclear Information System (INIS)

    Patzer, R.G.; Black, S.C.; Grossman, R.F.; Smith, D.D.

    1984-07-01

    This report covers the routine radiation monitoring activities conducted by the Environmental Monitoring Systems Laboratory-Las Vegas in areas which may be affected by nuclear testing programs of the Department of Energy. This monitoring is conducted to document compliance with standards, to identify trends in environmental radiation, and to provide such information to the public. It summarizes these activities for calendar year 1983. No radioactivity attributable to NTS activities was detectable offsite by the monitoring networks. Using recorded wind data and Pasquill stability categories, atmospheric dispersion calculations based on reported radionuclide releases yield an estimated dose of 5 x 10 -5 man-rem to the population within 80 km of the Nevada Test Site during 1983. World-wide fallout of Kr-85, Sr-90, Cs-137, and Pu-239 detected by the monitoring networks would cause maximum exposure to an individual of less than 0.2 mrem per year. Plutonium and krypton in air were similar to 1982 levels while cesium and strontium in other samples were near the detection limits. An occasional net exposure to offsite residents has been detected by the TLD network. On investigation, the cause of such net exposures has been due to personal habits or occupational activities, not to NTS activities. 29 references, 35 figures, 30 tables

  14. Intelligent biomembranes and biochips by radiation

    International Nuclear Information System (INIS)

    Nakayama, H.; Sutani, K.; Sakata, S.; Kita, Y.; Kaetsu, I.; Uchida, K.; Matsubara, Y.

    2002-01-01

    Complete text of publication follows. The authors have studied stimuli-responsive polyelectrolyte and polyampholyte hydrogels. Thermo-responsive copolymer hydrogels also have been studied. Recently, the authors have applied those hydrogels to radiation curable intelligent coatings for the gating of drug release channel. One way of this application is the coating on a drug including membrane to initiate and stop the drug release by on-off switching of stimulations. Some practical intelligent biomembranes such as glucose responsive insulin release membrane, glucose responsive nicotine release membrane and temperature responsive perfume release membrane were investigated and proved the function. On the other hand, the stimuli-responsive coating was applied to the porous biochip to cover the multi-drug reservoirs in the chip and computer programmed drug release from the biochip was investigated. Some results of primary studies proved the possibility of techniques for the application to biochip systems such as multi-signals responsive multi-drug release systems

  15. Radiation exposure by man-modified materials containing natural radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Becker, D.E. [Technical Inspection Agency of Bavaria, Munich (Germany); Eder, E. [Government of Bavaria, Ministry for State Development and Environmental Affairs Development, Munich (Germany); Reichelt, A. [Technical Inspection Agency of Bavaria, Munich (Germany)

    1992-07-01

    More than one hundred materials, containing natural radioactive nuclides, are being investigated due to radiation exposure to people. This paper deals with thoriated gas mantles and shows that the radiation exposure by inhalation of radionuclides released while burning and exchange is not negligible. (author)

  16. Studies on the role of central histamine in the acquisition of a radiation-induced conditioned taste aversion

    International Nuclear Information System (INIS)

    Rabin, B.M.; Hunt, W.A.; Lee, J.

    1982-01-01

    The experiments described in this report were designed to test two hypotheses about how exposure to low-level radiation can affect the behavior of an organism: first, tht radiation effects on behavior are mediated by a radiation-induced release of histamine; and second, that this radiation-induced histamine release can exert relatively direct effects on the central nervous system. The results of the first experiment showed that microinjection of histamine directly into the fourth ventricle of rats produced a taste aversion to a novel sucrose solution. Pretreating rats with intraventricular H 1 or H 2 blockers was not effective in preventing the acquisition of the radiation-induced aversion, although the H 1 blocker did prevent the acquisition of a histamine-induced taste aversion. It also was not possible to establish a cross-tolerance between centrally administered histamine and radiation. The results are interpreted as not supporting the hypothesis that a radiation-induced release of central histamine mediates the acquisition of a conditioned taste aversion following exposure to low-level radiation

  17. Environmental radiation monitoring; Ueberwachung der Umweltradioaktivitaet

    Energy Technology Data Exchange (ETDEWEB)

    Lachmann, Markus

    2012-07-01

    The report includes the following chapters: Development of earth and cosmic radiation - natural radioactivity. Atomic weapon tests and medicine - artificial radioactivity. A disaster and its consequences. From the air to humans; lessons learned from Chernobyl - division of work during measurements. From potatoes to baby food - the routine measuring program. Preparedness for the case of emergency - the intensive program. Three question for Martin Riepenhausen.

  18. Plastic scintillation dosimetry for radiation therapy: minimizing capture of Cerenkov radiation noise

    International Nuclear Information System (INIS)

    Beddar, A Sam; Suchowerska, Natalka; Law, Susan H

    2004-01-01

    Over the last decade, there has been an increased interest in scintillation dosimetry using small water-equivalent plastic scintillators, because of their favourable characteristics when compared with other more commonly used detector systems. Although plastic scintillators have been shown to have many desirable dosimetric properties, as yet there is no successful commercial detector system of this type available for routine clinical use in radiation oncology. The main factor preventing this new technology from realizing its full potential in commercial applications is the maximization of signal coupling efficiency and the minimization of noise capture. A principal constituent of noise is Cerenkov radiation. This study reports the calculated capture of Cerenkov radiation by an optical fibre in the special case where the radiation is generated by a relativistic particle on the fibre axis and the fibre axis is parallel to the Cerenkov cone. The fraction of radiation captured is calculated as a function of the fibre core refractive index and the refractive index difference between the core and the cladding of the fibre for relativistic particles. This is then used to deduce the relative intensity captured for a range of fibre core refractive indices and fibre core-cladding refractive index differences. It is shown that the core refractive index has little effect on the amount of radiation captured compared to the refractive index difference. The implications of this result for the design of radiation therapy plastic scintillation dosimeters are considered

  19. Determination of potential radiation exposure via terrestrial food chains by the release of radioactive material from nuclear facilities

    International Nuclear Information System (INIS)

    Handge, P.; Meurin, G.

    1978-01-01

    The radiation exposure level caused by consumption of vegetable and animal products in the environment of nuclear power plants is determined to a large extent by the release of 90 Sr, 134 Cs, and 137 Cs. For long-lived nuclides, especially 90 Sr, transfer from the soil into vegetation makes the essential contribution to plant contamination after several years of power plant operation. The relevant transfer coefficients for the different plant species vary, depending on the soil properties, between 0.02 and 6.0 [pCi/kg fresh weigth of vegetation : pCi/kg dry weight of soil] for Sr and between 1.10 -3 and 0.2 [pCi/kg fresh weight of vegetation : pCi/kg dry weight of soil] for Cs. The sensitivity analysis shows that already a variation of the transfer coefficients for Sr from 0.5 up to 2.5 [pCi/kg fresh weight of vegetation : pCi/kg dry weight of soil] and for Cs from 3.10 -2 up to 2.10 -1 cause variations in the level of radiation exposure for individual exposure pathways by factors fo 2 to 4. Correspondingly higher values are to be expected by still larger transfer of Sr and Cs from the ground to vegetation. For transfer coefficients >- 2.5 [pCi/kg fresh weight of vegetation : pCi/kg dry weight of soil], however, removal of radioactive substances from the ground by the plants must not remain without consideration any longer. (orig./HP) [de

  20. ITS Version 3.0: Powerful, user-friendly software for radiation modelling

    International Nuclear Information System (INIS)

    Kensek, R.P.; Halbleib, J.A.; Valdez, G.D.

    1993-01-01

    ITS (the Integrated Tiger Series) is a powerful, but user-friendly, software package permitting state-of-the-art modelling of electron and/or photon radiation effects. The programs provide Monte Carlo solution of linear time-independent coupled electron/photon radiation transport problems, with or without the presence of macroscopic electric and magnetic fields. The ITS system combines operational simplicity and physical accuracy in order to provide experimentalist and theorists alike with a method for the routine but rigorous solution of sophisticated radiation transport problems

  1. Completion of decommissioning: Monitoring for site release and license termination

    International Nuclear Information System (INIS)

    Boing, L.E.

    1997-01-01

    To request termination of a license upon completion of dismantling or decommissioning activities, documenting any residual radioactivity to show that the levels are environmentally acceptable will be necessary. When the regulators approve the decommissioning plan, they establish what the release criteria for the decommissioned site will be at the time of the site release and license termination. The criteria are numeric guidelines for direct radiation in soils and on surfaces. If the regulatory body finds that the measured on-site values are below the guidelines, the site will be acceptable for unrestricted release (no radiological controls or future use). If areas are found above those values, more decontamination or cleanup of these areas may be required unless the regulatory body grants an exemption

  2. The institutionalization of a routine

    DEFF Research Database (Denmark)

    Nickelsen, Niels Christian

    2008-01-01

    -which has before largely been treated in overview by institutionalism-plays an important role in the making of a routine. In my empirical study, I demonstrate that the concept and practice of the valve changes, and that it is identified in a number of ways, as it passes through the testing phase...... of production. I argue that the negotiation of these changes during test production is the fulcrum in the routinization of the production procedure. It is through these identity shifts that the valve is both reified, and rendered producible and applicable in the customer world....

  3. Electrochemical examination of ability of dsDNA/PAM composites for storing and releasing of doxorubicin.

    Science.gov (United States)

    Zabost, Ewelina; Liwinska, Wioletta; Karbarz, Marcin; Kurek, Eliza; Lyp, Marek; Donten, Mikolaj; Stojek, Zbigniew

    2016-06-01

    Composites consisting of ss- and ds-DNA strands and polyacrylamide (PAM) hydrogel have been synthesized. DNA was entrapped non-covalently. The obtained DNA biomaterial exhibited a strong increase in guanine and adenine anodic currents when temperature reached the physiological level. This increase was related to the unique oligonucleotide structural changes in the composite. The structural alterations in the PAM lattices were employed for the release of the drug accumulated in the composite. Doxorubicin (Dox) was selected as the drug; it was accumulated by intercalation to dsDNA and was slowly released from the dsDNA/PAM system by using a minor temperature increase (up to 40÷45 °C) as it is routinely done in hyperthermia. The applied release temperature was either constant or oscillating. The binding strength, the rate of Dox release and the properties of the composite were examined using voltammetry, SEM and ICP-MS. Copyright © 2015 Elsevier B.V. All rights reserved.

  4. Radiation problems expected for the German spallation neutron source

    International Nuclear Information System (INIS)

    Goebel, K.

    1981-01-01

    The German project for the construction of a Spallation Neutron Source with high proton beam power (5.5 MW) will have to cope with a number of radiation problems. The present report describes these problems and proposes solutions for keeping exposures for the staff and release of activity and radiation into the environment as low as reasonably achievable. It is shown that the strict requirements of the German radiation protection regulations can be met. The main problem will be the exposure of maintenance personnel to remanent gamma radiation, as is the case at existing proton accelerators. Closed ventilation and cooling systems will reduce the release of (mainly short-lived) activity to acceptable levels. Shielding requirements for different sections are discussed, and it is demonstrated by calculations and extrapolations from experiments that fence-post doses well below 150 mrem/y can be obtained at distances of the order of 100 metres from the principal source points. The radiation protection system proposed for the Spallation Neutron Source is discussed, in particular the needs for monitor systems and a central radiation protection data base and alarm system. (orig.)

  5. Safety and clinical efficacy of some radiation-sterilized medical products and pharmaceuticals

    International Nuclear Information System (INIS)

    Kulkarni, R.D.; Gopal, N.G.S.

    1975-01-01

    Medical products and pharmaceuticals must conform to certain minimum physico-chemical microbiological and biological requirements. The biological requirements comprise principally testing for toxicity, safety, and pyrogens. Besides the above-mentioned criteria, there are two other important characteristics, viz. clinical efficacy and tolerance in animal and/or human beings. These latter requirements, expected from the final product released for general human use, are not carried out routinely. In the present-day pharmaceutical and medical technology, numerous mew products are appearing, many of them requiring radiation sterilization as they are not stable towards the other conventional methods of sterilization. While the post-irradiation physicochemical changes in a product may not be significant, the bio-availability or biological activity of the product may be affected to a more significant extent. Some evidence of this has recently been reported. Hence, it is desirable to carry out studies on safety as well as clinical efficacy on irradiated products. This paper describes some studies on plastic-based medical products, a pharmaceutical raw material, a typical infusion fluid such as normal saline, antibiotics and their ointments. (author)

  6. Publicly Released Prompt Radiation Spectra Suitable for Nuclear Detonation Simulations, Revision 1

    Science.gov (United States)

    2017-12-01

    dominates the photon emission. During the Hiroshima and Nagasaki bombings , the prompt radiation contributed from 40% to 70% of the free-in-air dose...spectra for high-, intermediate- and low-yield thermonuclear weapons for initial radiation shielding calculations No Gritzner, et al. 1976 ( EM -1...Glasstone (Fission) Neutron Glasstone & Dolan 1977 7.760 x 1022 Terrell Neutron Glasstone & Dolan 1977 7.760 x 1022 DNA 4267F ( EM -1 Fission

  7. Radiation risks revisited

    International Nuclear Information System (INIS)

    Ackland, L.

    1993-01-01

    The Stewart team's findings are based on previously restricted Hanford data that the U.S. Dept. of Energy began releasing in 1990 to settle a lawsuit filed by the Three Mile Island Public Health Fund. The records include those of the 7,342 workers who died before 1987 and were employed at the plant between 1944 and 1978. These workers were among more than 35,000 men and women whose radiation doses were measured by film-badge monitoring during this period. According to contemporary radiation standards, these recorded exposures were safe. But Stewart and Kneale, using a new technique to more effectively isolate occupational doses from other causes of cancer, have calculated that approximately 3 percent of the 1,732 cancer deaths in the group resulted from work-place radiation exposure

  8. Determining cutoff distances for assessing risks from transportation accident radiation releases

    International Nuclear Information System (INIS)

    Sandquist, G.M.; Slaughter, D.M.; Kimura, C.Y.; Brumburgh, G.

    1995-01-01

    The transportation of radioactive materials throughout the United States and the world is a ubiquitous and sometimes controversial activity. Almost universally, these transportation activities have been performed without major incident, and the safety record for transportation of radioactive material is outstanding compared with the transportation of other hazardous materials. Nevertheless, concerns still exist regarding adequate regulation of radioactive material transportation and accurate assessment of the health risks associated with accidents. These concerns are addressed through certification by the cognizant regulatory authority over the transportation container or the performance of a transportation risk assessment. In a transportation risk assessment, accident situations are examined, frequencies are estimated, and consequences resulting from the accident are analyzed and evaluated for acceptance. A universal question with any transportation risk assessment that examines the radiological consequences from release accidents is, At what distance may the dispersion analysis be terminated? This paper examines cutoff distances and their consequences for assessing health risks from radiological transportation releases

  9. ORGANIZATIONAL ROUTINES IN RUSSIAN COMPANIES: REVIEW OF PRACTICES

    Directory of Open Access Journals (Sweden)

    Olga Valieva

    2014-10-01

    Full Text Available Results of the first stage of the researches conducted in 2012-2013 are presented in article. Researches are connected with studying of transformational processes intra corporate of managemetn practices in the Russian companies and their subsequent institutionalization. Preliminary results showed that in the companies there is a standard set of organizational routines which part are information, and administrative routines, routines of the power of the founder, genetic, institutional and development routines. During research statistically significant connection between types of organizational structures, the sizes of the organization, information processing and administrative practices is established. It is revealed as change of approaches to management of the organization can affect a corruption component.

  10. Radiation safety - an IAEA perspective

    International Nuclear Information System (INIS)

    Persson, L.

    1993-01-01

    The activities of the IAEA relating to radiation safety cover: The preparation of International Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources - it is expected that the new Basic Safety Standards will be adopted by the sponsoring organizations in 1994. The radiological consequences of the Chernobyl accident: the thyroid cancer controversy - the hypothesis that must be tested is whether the reported increased incidence of thyroid cancer due to exposure to radioactive iodine released in the Chernobyl accident, and there are several questions that must be answered before a firm conclusion can be reached. Emergency Response Services (ERS): In March 1993, at the request of Viet Nam, which invoked the Energency Assistance Convention, a medical team organized by the IAEA went to Hanoi and assisted in arranging for an overexposed person to be transferred from Viet Nam to Paris for specialized medical treatment. In April 1993, the ERS was used to inform Member States of the consequences of an explosion at the Tomsk 7 fuel reprocessing plant in Siberia, Russia, which caused a radiation leak. Reassessing the long range transport of radioactive material through the environment: Data from the Chernobyl accident have been used for model validation in the Atmospheric Transport Model Evaluation Study (ATMES). A follow-up programme, the European Tracer Experiment (ETEX) with experimental studies of long range atmospheric movements over Europe has been established in order to increase knowledge and prediction capability. As part of the programme, a non-toxic atmospheric tracer will be released under suitable conditions in 1994. The Radiation Protection Advisory Teams Service (RAPAT): In many of the developing countries visited, the lack of an adequate infrastructure for radiation protection is the main obstacle to improved radiation protection. Strengthening radiation and nuclear safety infrastructures in successor states of the USSR: The

  11. Emerging radiation protection

    International Nuclear Information System (INIS)

    Allard, D.J.

    1993-01-01

    In recent years, a number of radiation protection issues have emerged into the public forum. The perceived high risks associated with radiation exposure, and disproportionate media attention to such issues, have contributed to heightened concerns by the public and the individual occupationally exposed worker. This paper examines the new and controversial radiation risk estimates of the National Research Council's BEIR V committee, which are based on the most current atomic-bomb survivor data and a revised dosimetry model. These risk estimates are somewhat higher than past values, and may eventually impact the legal framework in the United States through the regulations of the EPA, NRC, DOE, OSHA, and other agencies that set radiation exposure standards. Additionally, present regulations and standards are often based upon differing levels of acceptable risk, which have led to conflicting exposure and effluent release criteria. Further, due to inherent boundaries in legal authority, many potentially significant sources of radiation exposure to the public remain unregulated Radiation exposure scenarios such as medical x-ray, radon, and other technology enhanced sources have no legal limits. These issues and others are examined and analyzed with respect to regulatory policy

  12. Cellular Studies with UVA Radiation: A Role for Iron (invited paper)

    International Nuclear Information System (INIS)

    Tyrrell, R.M.; Pourzand, C.A.; Brown, J.; Hejmadi, V.; Kvam, V.; Ryter, S.; Watkin, R.D.

    2000-01-01

    The UVA (320-380 nm) component of sunlight or sunbeds acts as an oxidising carcinogen and has been clearly implicated in skin cancer. Since UVA radiation interacts with cells by generating active oxygen species, the damaging effects of this radiation will be exacerbated by the presence of catalytically reactive iron in cells. It has now been shown by two independent techniques (dequenching of metal-quenched calcein fluorescence in cells and changes in the binding activity of the iron responsive protein IRPI) that UVA radiation causes an immediate release of 'free' iron in human skin fibroblasts via the proteolysis of ferritin (Ft). Within minutes of exposure to a range of doses of UVA at natural exposure levels, the binding activity of IRP-1, as well as Ft levels, decrease in a dose-dependent manner. It is proposed that the oxidative damage to lysosomes that leads to Ft degradation and the consequent release of potentially harmful 'free' iron to the cytosol might be a major factor in UVA-induced damage to the skin. UVA radiation also breaks down heme-containing proteins in the microsomal membrane to release free heme as an additional photosensitising component. This will provide another source of enhanced free iron in skin cells since constitutive heme oxygenase 2 (in keratinocytes) and UVA-inducible heme oxygenase-1 (in fibroblasts) are likely to break down any free heme to biliverdin and release iron and carbon monoxide in the process. It is postulated that, in skin fibroblasts, this free heme release and the enhanced free iron pools will lead to an adaptive response involving heme oxygenase (with a maximum about 10 h) and ferritin (in 24-48 h) that will scavenge the heme and iron released by subsequent oxidising (UVA) treatments. (author)

  13. Mobile environmental radiation monitoring station

    International Nuclear Information System (INIS)

    Assido, H.; Shemesh, Y.; Mazor, T.; Tal, N.; Barak, D.

    1997-01-01

    A mobile environmental radiation monitoring station has been developed and established for the Israeli Ministry of Environment. The radiation monitoring station is ready for immediate placing in any required location, or can be operated from a vehicle. The station collects data Tom the detector and transfers it via cellular communication network to a Computerized Control Center for data storage, processing, and display . The mobile station is fully controlled from the. Routinely, the mobile station responses to the data request accumulated since the last communication session. In case of fault or alarm condition in the mobile station, a local claim is activated and immediately initiates communication with the via cellular communication network. (authors)

  14. Dynamic evaluation of environmental impact due to tritium accidental release from the fusion reactor

    International Nuclear Information System (INIS)

    Nie, Baojie; Ni, Muyi; Jiang, Jieqiong; Wu, Yican

    2015-01-01

    As one of the key safety issues of fusion reactors, tritium environmental impact of fusion accidents has attracted great attention. In this work, the dynamic tritium concentrations in the air and human body were evaluated on the time scale based on accidental release scenarios under the extreme environmental conditions. The radiation dose through various exposure pathways was assessed to find out the potential relationships among them. Based on this work, the limits of HT and HTO release amount for arbitrary accidents were proposed for the fusion reactor according to dose limit of ITER. The dynamic results aim to give practical guidance for establishment of fusion emergency standard and design of fusion tritium system. - Highlights: • Dynamic tritium concentration in the air and human body evaluated on the time scale. • Different intake forms and relevant radiation dose assessed to find out the potential relationships. • HT and HTO release amount limits for arbitrary accidents proposed for the fusion reactor according to dose limit

  15. 42 CFR 493.1267 - Standard: Routine chemistry.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Routine chemistry. 493.1267 Section 493.1267 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES... Systems § 493.1267 Standard: Routine chemistry. For blood gas analyses, the laboratory must perform the...

  16. NRC TLD Direct Radiation Monitoring Network. Volume 5, No. 2. Progress report, April-June 1985

    International Nuclear Information System (INIS)

    Jang, J.; Kramaric, M.; Cohen, L.

    1985-09-01

    The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network provides continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the second quarter of 1985. A complete listing of the site facilities monitored is included

  17. PEG modulated release of etanidazole from implantable PLGA/PDLA discs.

    Science.gov (United States)

    Wang, Fangjing; Lee, Timothy; Wang, Chi-Hwa

    2002-09-01

    In this work, etanidazole (one type of hypoxic radiosensitizer) is encapsulated into spray dried poly(D),L-lactide-co-glycolide) (PLGA) microspheres and then compressed into discs for controlled release applications. Etanidazole is characterized by intracellular glutathione depletion and glutathione transferases inhibition, thereby enhancing sensitivity to radiation. It is also cytotoxic to tumor cells and can chemosensitize some alkylating agents by activating their tumor cell killing capabilities. We observed the release characteristics of etanidazole in the dosage forms of microspheres and discs, subjected to different preparation conditions. The release characteristics, morphology changes, particle size, and encapsulation efficiency of microspheres are also investigated. The release rate of etanidazole from implantable discs (13 mm in diameter, 1 mm in thickness, fabricated by a press) is much lower than microspheres due to the reduced specific surface. After the initial burst of 1% release for the first day, the cumulative release within the first week is less than 2% until a secondary burst of release (caused by polymer degradation) occurs after one month. Some key preparation conditions such as drug loadings, disc thickness and diameter, and compression pressure can affect the initial burst of etanidazole from the discs. However, none of them can significantly make the release more uniform. In contrast, the incorporation of polyethylene glycol (PEG) can greatly enhance the release rate of discs and also reduces the secondary burst effect, thereby achieving a sustained release for about 2 months.

  18. Radionuclide releases to the atmosphere from Hanford Operations, 1944--1972. Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Heeb, C.M.

    1994-05-01

    The purpose of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. The first step in determining dose is to estimate the amount and timing of radionuclide releases to air and water. This report provides the air release information.

  19. Effect of simulated rainfall and weathering on release of preservative elements from CCA treated wood

    Science.gov (United States)

    Stan Lebow; R. Sam Williams; Patricia Lebow

    2003-01-01

    The release of arsenic from wood pressure-treated with chromated copper arsenate (CCA) can be decreased by application of wood finishes, but little is known about the types of finishes that are best suited for this purpose. This study evaluated the effects of finish water repellent content and ultraviolet (UV) radiation on the release of arsenic, copper, and chromium...

  20. Breaking the Waves: Routines and Rituals in Entrepreneurship Education

    Science.gov (United States)

    Neergaard, Helle; Christensen, Dorthe Refslund

    2017-01-01

    Learning is related to the environment created for the learning experience. This environment is often highly routinized and involves a certain social structure, but in entrepreneurship education, such routinization and structure may actually counteract the learning goals. This article investigates how classroom routines and rituals impact on…

  1. Preliminary analysis of public dose from CFETR gaseous tritium release

    Energy Technology Data Exchange (ETDEWEB)

    Nie, Baojie [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031 (China); University of Science and Technology of China, Hefei, Anhui 230027 (China); Ni, Muyi, E-mail: muyi.ni@fds.org.cn [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031 (China); Lian, Chao; Jiang, Jieqiong [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031 (China)

    2015-02-15

    Highlights: • Present the amounts and limit dose of tritium release to the environment for CFETR. • Perform a preliminary simulation of radiation dose for gaseous tritium release. • Key parameters about soil types, wind speed, stability class, effective release height and age were sensitivity analyzed. • Tritium release amount is recalculated consistently with dose limit in Chinese regulation for CFETR. - Abstract: To demonstrate tritium self-sufficiency and other engineering issues, the scientific conception of Chinese Fusion Engineering Test Reactor (CFETR) has been proposed in China parallel with ITER and before DEMO reactor. Tritium environmental safety for CFETR is an important issue and must be evaluated because of the huge amounts of tritium cycling in reactor. In this work, different tritium release scenarios of CFETR and dose limit regulations in China are introduced. And the public dose is preliminarily analyzed under normal and accidental events. Furthermore, after finishing the sensitivity analysis of key input parameters, the public dose is reevaluated based on extreme parameters. Finally, tritium release amount is recalculated consistently with the dose limit in Chinese regulation for CFETR, which would provide a reference for tritium system design of CFETR.

  2. Cost-benefit analysis in optimising the radiological protection of the public: a provisional framework

    International Nuclear Information System (INIS)

    1981-07-01

    The advice given is concerned solely with the application of a quantitative framework to the optimisation of protection of members of the public, exposed as a result of routine releases of radionuclides to the environment or emissions of radiation in normal operating conditions. (author)

  3. Simulated atmospheric disperison of radioactive material released in an urban area

    International Nuclear Information System (INIS)

    Akins, R.E.; Church, H.W.; Tierney, M.S.

    1977-01-01

    A combination of Gaussian plume and particle-in-cell techniques is used to simulate the atmospheric transport and dispersion of a puff release of radioactive material. The release is caused by an accident that is assumed to occur during the shipment of the radioactive material through central New York City. The simulation provides estimates of volumetric and surface concentrations of the dispersed material that are used to predict radiation doses incurred by the City's population in the event of an accidental release. In the simulation, the release point is arbitrary and the material is assumed to be either a gas or fine particles. The Gaussian plume model follows cloud concentrations from the release time until times when transport over distances up to 500 m has been achieved. The released cloud may stabilize at street level or above the mean buildings height; at a street intersection or in the middle of the block. The possibility of the formation of multiple clouds, owing to circumstances of wind flow direction and street geometry, is allowed

  4. LAPACK users` guide: Release 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, E.; Bai, Z.; Bischof, C.; Demmel, J.; Dongarra, J.; Du Croz, J.; Greenbaum, A.; Hammarling, S.; McKenney, A.; Ostrouchov, S.; Sorensen, D.

    1992-01-31

    LAPACK is a transportable library of Fortran 77 subroutines for solving the most common problems in numerical linear algebra: systems of linear equations, linear least squares problems, eigenvalue problems and singular value problems. LAPACK is designed to supersede LINPACK and EISPACK, principally by restructuring the software to achieve much greater efficiency on vector processors, high-performance ``superscalar`` workstations, and shared-memory multi-processors. LAPACK also adds extra functionality, uses some new or improved algorithms, and integrates the two sets of algorithms into a unified package. The LAPACK Users` Guide gives an informal introduction to the design of the algorithms and software, summarizes the contents of the package, describes conventions used in the software and documentation, and includes complete specifications for calling the routines. This edition of the Users` guide describes Release 1.0 of LAPACK.

  5. An estimation of whole body doses due to routine operation of the first Philippine Research Reactor (PRR-1)

    International Nuclear Information System (INIS)

    Palattao, M.V.B.; Azanon, E.M.; Paz, L.R. de la

    1989-01-01

    Atmospheric dispersion calculation of the routine releases of the Triga-converted Philippine Research Reactor (PRR-1) was carried out using the computer model developed by the United States Nuclear Regulatory Commission (USNRC). It calculates average relative effluent concentration (X/Q) and average relative deposition values (D/Q) for twenty-two (22) specific distances up to 80 km from the area of concern for each sixteen compass directions. This model is based on the theory that material released to the atmosphere will be normally distributed (Gaussiah) about the plume center-line. Surface meteorological data based on a five-year monitoring period at the PAGASA Science Garden station proximate to the site were utilized in the assessment. From the result of X/Q values, annual whole body in mSv y -1 with impact to 41 Ar was evaluated. (Auth.). 9 refs.; 8 tabs.; 6 figs

  6. Monitoring the Radiation Damage of the ATLAS Pixel Detector

    CERN Document Server

    Cooke, M; The ATLAS collaboration

    2012-01-01

    The Pixel Detector is the innermost charged particle tracking component employed by the ATLAS experiment at the CERN Large Hadron Collider (LHC). The instantaneous luminosity delivered by the LHC, now routinely in excess of 5x10^{33} cm^{-2} s^{-1}, results in a rapidly increasing accumulated radiation dose to the detector. Methods based on the sensor depletion properties and leakage current are used to monitor the evolution of the radiation damage, and results from the 2011 run are presented.

  7. Monitoring the radiation damage of the ATLAS pixel detector

    International Nuclear Information System (INIS)

    Cooke, M.

    2013-01-01

    The pixel detector is the innermost charged particle tracking component employed by the ATLAS experiment at the CERN Large Hadron Collider (LHC). The instantaneous luminosity delivered by the LHC, now routinely in excess of 5×10 33 cm −2 s −1 , results in a rapidly increasing accumulated radiation dose to the detector. Methods based on the sensor depletion properties and leakage current are used to monitor the evolution of the radiation damage, and results from the 2011 run are presented

  8. 42 CFR 493.841 - Standard; Routine chemistry.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Standard; Routine chemistry. 493.841 Section 493.841 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES... These Tests § 493.841 Standard; Routine chemistry. (a) Failure to attain a score of at least 80 percent...

  9. Elevated UV-B radiation increased the decomposition of Cinnamomum camphora and Cyclobalanopsis glauca leaf litter in subtropical China

    Energy Technology Data Exchange (ETDEWEB)

    Song, Xinzhang Z.; Zhang, Huiling L.; Jiang, Hong; Yu, Shuquan Q. [Zhejiang Agriculture and Forestry Univ., Lin' an (China). The Nurturing Station for the State Key Lab. of Subtropical Silviculture; Zhejiang Agriculture and Forestry Univ., Lin' an (China). Zhejiang Provincial Key Lab. of Carbon Cycling and Carbon Sequestration in Forest Ecosystems; Chang, Scott X. [Alberta Univ., Edmonton (Canada). Dept. of Renewable Resources; Peng, Changhui H. [Quebec Univ., Montreal (Canada). Inst. of Environment Sciences

    2012-03-15

    Ultraviolet-B (UV-B) radiation reaching the earth's surface has been increasing due to ozone depletion and can profoundly influence litter decomposition and nutrient cycling in terrestrial ecosystems. The role of UV-B radiation in litter decomposition in humid environments is poorly understood; we thus investigated the effect of UV-B radiation on litter decomposition and nitrogen (N) release in a humid subtropical ecosystem in China. We conducted a field-based experiment using the litterbag method to study litter decomposition and N release under ambient and elevated (31% above ambient) UV-B radiation, using the leaf litter of two common tree species, Cinnamomum camphora and Cyclobalanopsis glauca, native to subtropical China. Elevated UV-B radiation significantly increased the decomposition rate of C. camphora and C. glauca leaf litter by 16.7% and 27.8%, respectively, and increased the N release from the decomposing litter of C. glauca but not C. camphora. Elevated UV-B radiation significantly accelerated the decomposition of litter of two native tree species and the N release from the decomposition litter of C. glauca in humid subtropical China, which has implications for soil carbon flux and forest productivity. (orig.)

  10. Order no 206 concerning medical surveillance of work with ionizing radiation

    International Nuclear Information System (INIS)

    1990-03-01

    This Order implements Council Directive 80/836/Euratom on radiation protection as amended by Directive 84/467/Euratom. It entered into force on 4 April 1990, replacing the Decree of 29 February 1972. It prescribes in particular that persons required to perform work exposing them to ionizing radiation must first undergo a medical examination to determine their fitness for this work. They must also be subject to routine surveillance [fr

  11. Atmospheric dilution factors for radioactive releases from Inshas research reactor, Egypt

    International Nuclear Information System (INIS)

    Abdel Aal, M.M.; Aly, A.I.M.; Tawfik, F.S.

    1994-01-01

    In the frame of assessing the suitability of Inshas site for constructing a new research reactor 20 MW, the meteorological condition are analyzed to determine the most affected population sectors. The atmospheric stability classes are estimated by a developed computer program in which the meteorological data for one year are used as input data. The results indicate that stability class F (moderately stable) is predominant one. The dilution factor is calculated using the computer code XOQDOQ for meteorological evaluation of routine effluent releases at nuclear power stations, which implements regulatory Guide 1.111 for both normal and desert conditions and for ground and elevated releases. The concentration isopleths are plotted and the most affected sector is the southern one with higher values for desert condition than the corresponding normal condition at same distance from the source. 4 fig., 3 tab

  12. Generic assessment of radiation exposures to workers in a portable smelter and to the surrounding population

    International Nuclear Information System (INIS)

    Randolph, M.L.; Watson, A.P.; O'Donnell, F.R.

    1978-10-01

    A scenario for operation of a proposed portable smelter has been developed by National Lead Company of Ohio to recycle radioactively contaminated ferrous scrap arising from modifications at nuclear facilities of the Department of Energy. The current generic study complements that work by developing tables of radiation dose conversion factors for estimation of external whole-body doses and 50-year whole-body internal dose commitments to routine workers in the smelter and to the public within 50 miles of the smelter. Applications of the tables to specific cases require site-specific source terms consisting of amounts of radionuclides present in scrap metal, separation efficiency for radionuclides, concentration of contaminated airborne particulates, ingested amount of contaminated material, and amount of metal released through the stack. Equations relating doses to tabular values and these source terms are developed, and hypothetical sample calculations are given. Assumptions, approximations, and limitations of the methods are discussed as well as nonroutine operations and nonradioactive hazards

  13. Environmental contamination from a ground-level release of fission products

    International Nuclear Information System (INIS)

    Stupka, R.C.; Kephart, G.S.; Rittmann, P.D.

    1986-08-01

    On January 11, 1985, a ground-level release of fission products, primarily 90 Sr, occurred at the Hanford Site in southeastern Washington State. The release was detected during routine surveys and the majority of the contamination was confined to the immediate area where the release occurred. Response to the incident was complicated by a strong inversion that resulted in a buildup of 222 Rn daughter products on environmental air samples and outdoor surfaces. The cause of the release appears to have been the operation of a transfer jet that inadvertently pressurized an unblanked line leading to the 241-C-151 Diversion Box. A buildup of pressure inside the diversion box forced contaminated air through gaps in the diversion box cover blocks resulting in an unmonitored, short duration release to the environment. The source term was estimated using data obtained from environmental air samplers. The ground deposition speed was calculated using the integrated exposure (air samples) and surface contamination levels obtained from recently fallen snow. The total release was estimated to be 1.4 Ci 90 Sr and 0.02 Ci 137 Cs. Based on this source term, the maximum 50-yr dose commitment to onsite pesonnel was 50 mrem whole body and 600 mrem bone. No detectable internal deposition occurred during the incident and corrective action which followed; this was probably due to several factors: (1) prompt detection of the release; (2) localized contamination control; (3) excellent personnel protection practices; and (4) the protection offered by building ventilation systems. The theoretical maximum offsite individual would receive a potential 1-yr dose commitment of 0.01 mrem whole body and 0.2 mrem bone from this incident. The potential 50-yr dose commitment would be 0.13 mrem whole body and 2.0 mrem bone. In actuality, neither onsite or offsite individuals would be expected to receive even these small dose commitments

  14. Releases of radioactivity from uranium mills and effluent treatment costs

    International Nuclear Information System (INIS)

    Witherspoon, J.P.; Sears, M.B.; Blanco, R.E.

    1977-01-01

    Airborne releases of radioactive materials from uranium milling to the environment consist of ore dust, yellowcake dust, tailings dust, and radon gas while the mill is active. After a mill has ceased operations, tailings may be stabilized to minimize or prevent airborne releases of radioactive particulates. However, radon gas will continue to be released in amounts inversely proportional to the degree of stabilization treatment (and expense). Liquid waste disposal is by evaporation and natural seepage to the ground beneath the tailings impoundment area. The release of radioactive materials (and potential radiation exposures) determines the majority of costs associated with minimizing the environmental impact of uranium milling. Radwaste treatments to reduce estimated radiation doses to individuals to 3 to 5% of those received with current milling practices are equivalent to $0.66 per pounds of U 3 O 8 and 0.032 mill per kWhr of electricity. This cost would cover a high efficiency reverse jet bag filter and high energy venturi scrubbers for dusts, neutralization of liquids, and an asphalt-lined tailings basin with a clay core dam to reduce seepage. In addition, this increased cost would cover stabilization of tailings, after mill closure, with a 1-in. asphalt membrane topped by 2 ft of earth and 0.5 ft of crushed rock to provide protection against future leaching and wind erosion. The cost of reducing the radiological hazards associated with uranium milling to this degree would contribute about 0.4% to the current total cost of nuclear power

  15. Personnel radiation monitoring by thermoluminescence dosimetry (2000-2001)

    International Nuclear Information System (INIS)

    Mi-Cho-Cho, Daw; Hla-Hla-Win, Daw; Thin-Thin-Kraing

    2001-01-01

    Thermoluminescence dosimetry service was introduced in 1991. Personnel who exposed directly or indirectly to radiation is monitored by thermoluminescent dosimeter. TL materials used for thermoluminescent dosimeter are in the form of thin disc. Personnel whole-body and extremity doses are measured by thermoluminescence dosimetry. The Harshaw Model 4500 TLD reader and Vinten 654E TLD reader are used for TLD evaluation. At present about 600 radiation workers are provided with TLD for routine monitoring. It was found that most personnel had received within permissible dose recommended by the International Commission on Radiological Protection (ICRP). (author)

  16. EPR-dosimetry for radiation processing of food

    International Nuclear Information System (INIS)

    Peimel-Stuglik, Z.; Fabisiak, S.

    2002-01-01

    The usefulness of two, easy accessible alanine-polymer dosimeters to low (D ≤ 10 kGy) ionizing radiation dose measurements, were investigated. In both cases (ALANPOL from IChTJ and foil dosemeters from Gamma Service, Radeberg, Germany) the results were positive. EPR-alanine method based on the described dosimeters meets the requirements to use it in radiation processing of food. Thin foil dosemeters from Gamma Service are recommended mainly for dose distribution measurements. ALANPOL - for routine use. The advantage of ALANPOL is lower price, higher sensitivity and high resistance to unfavourable environmental conditions, including water. (author)

  17. Radiation resistance of pyrocarbon-boned fuel and absorbing elements for HTGR

    International Nuclear Information System (INIS)

    Gurin, V.A.; Konotop, Yu.F.; Odejchuk, N.P.; Shirochenkov, S.D.; Yakovlev, V.K.; Aksenov, N.A.; Kuprienko, V.A.; Lebedev, I.G.; Samsonov, B.V.

    1990-01-01

    In choosing the reactor type, problems of nuclear and radiation safety are outstanding. The analysis of the design and experiments show that HTGR type reactors helium cooled satisfy all the safety requirements. It has been planned in the Soviet Union to construct two HTGR plants, VGR-50 and VG-400. Later it was decided to construct an experimental plant with a low power high temperature reactor (VGM). Spherical uranium-graphite fuel elements with coated fuel particles are supposed to be used in HTGR core. A unique technology for producing spherical pyrocarbon-bound fuel and absorbing elements of monolithic type has been developed. Extended tests were done to to investigate fuel elements behaviour: radiation resistance of coated fuel particles with different types of fuel; influence of the coated fuel particles design on gaseous fission products release; influence of non-sphericity on coated fuel particle performance; dependence of gaseous fission products release from fuel elements on the thickness of fuel-free cans; confining role of pyrocarbon as a factor capable of diminishing the rate of fission products release; radiation resistance of spherical fuel elements during burnup; radiation resistance of spherical absorbing elements to fast neutron fluence and boron burnup

  18. Ionization radiation in sterilization of the tissue transplants

    International Nuclear Information System (INIS)

    Uhrynowska-Tyszkiewicz, I.; Kaminski, A.

    2007-01-01

    Established in 1963, the Central Tissue Bank in Warsaw is a multi-tissue bank located in the Department of Transplantology of the Medical University in Warsaw. Allografts such as bone, cartilage, tendons, ligaments, sclera, skin and amnion are preserved mainly by deep-freezing and/or lyophilization and subsequently radiation-sterilized with a dose of 35 kGy with gamma rays in a 60 Co source (at the Institute of Applied Radiation Chemistry in Lodz) or with electron beam 10 MeV accelerator (at the Institute of Nuclear Chemistry and Technology in Warsaw). This is the oldest working tissue bank in the world, which for almost 40 years now has routinely used ionizing radiation for sterilization of tissue allografts

  19. TLD DRD dose discrepancy: role of beta radiation fields

    International Nuclear Information System (INIS)

    Munish Kumar; Pradhan, S.M.; Bihari, R.R.; Bakshi, A.K.; Chougaonkar, M.P.; Babu, D.A.R.; Gupta, Anil

    2014-01-01

    Ionization chamber based direct reading/pocket dosimeters (DRDs), are used along with the legal dosimeters (thermoluminescent dosimeters-TLDs) for day to day monitoring and control of radiation doses received by radiation workers. The DRDs are routinely used along with the passive dosimeters (TLDs) in nuclear industry at different radiation installations where radiation levels could vary significantly and the possibility of receiving doses beyond investigation levels by radiation workers is not ruled out. Recently, recommendations for dealing with discrepancies between personal dosimeter systems used in parallel were issued by ISO. The present study was performed to measure the response of ionization chamber based pocket dosimeters to various beta sources having energy (E max ) ranging from 0.224 MeV-3.54 MeV. It is expected that the above study will be useful in resolving the disparity between TLD and DRD doses at those radiation installations where radiation workers are likely to be exposed simultaneously from photons and beta particles

  20. Updated on effluents releases of the CEA nuclear fuel cycle facilities - 1995 to 2010 period

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Nelson Luiz Dias [Centro Tecnologico da Marinha em Sao Paulo (CTMSP) Sao Paulo, SP (Brazil)

    2011-07-01

    The environmental impact assessment of the Centro Experimental Aramar (CEA) facilities has been presented in a former work, based on the measured effluent releases data, for the period from 1995 to 2007. This work shows the update up to 2010. The effluents releases to the environment result from the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). Basically, this work presents the radioactive release source terms, as described at the CEA Effluent Report sent to the National Commission for Nuclear Energy (CNEN) each semester, and a historical assessment of the critical group annual doses from 1995 up to 2010. The assessed doses are compared to the maximum dose constraint as well as to the exemption level specified by CNEN. (author)

  1. Concept and approaches used in assessing individual and collective doses from releases of radioactive effluents

    International Nuclear Information System (INIS)

    1988-06-01

    To guide on the applications of the principles for limiting radioactive releases contained in Safety Series 77, the Agency is in the process of preparing a number of safety guides. The first one is this present document which deals with the principal aspects of the methods for the assessment of the individual and collective dose. It aims at giving a general guidance to those responsible for establishing programmes for the determination of individual doses as well as collective doses in connection with licensing a site for a nuclear installation. The document is concerned with the principles applied for calculating individual and collective doses from routine releases of radionuclides to the atmosphere and hydrosphere but not releases directly to the geosphere, as in waste management. These areas will be covered by other Agency publications. 75 refs, figs and tabs

  2. Updated on effluents releases of the CEA nuclear fuel cycle facilities - 1995 to 2010 period

    International Nuclear Information System (INIS)

    Ferreira, Nelson Luiz Dias

    2011-01-01

    The environmental impact assessment of the Centro Experimental Aramar (CEA) facilities has been presented in a former work, based on the measured effluent releases data, for the period from 1995 to 2007. This work shows the update up to 2010. The effluents releases to the environment result from the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). Basically, this work presents the radioactive release source terms, as described at the CEA Effluent Report sent to the National Commission for Nuclear Energy (CNEN) each semester, and a historical assessment of the critical group annual doses from 1995 up to 2010. The assessed doses are compared to the maximum dose constraint as well as to the exemption level specified by CNEN. (author)

  3. A Patient Friendly Corifollitropin Alfa Protocol without Routine Pituitary Suppression in Normal Responders.

    Science.gov (United States)

    Wang, Huai-Ling; Lai, Hsing-Hua; Chuang, Tzu-Hsuan; Shih, Yu-Wei; Huang, Shih-Chieh; Lee, Meng-Ju; Chen, Shee-Uan

    2016-01-01

    The release of corifollitropin alfa simplifies daily injections of short-acting recombinant follicular stimulating hormone (rFSH), and its widely-used protocol involves short-acting gonadotropins supplements and a fixed GnRH antagonist regimen, largely based on follicle size. In this study, the feasibility of corifollitropin alfa without routine pituitary suppression was evaluated. A total of 288 patients were stimulated by corifollitropin alfa on cycle day 3 following with routine serum hormone monitoring and follicle scanning every other day after 5 days of initial stimulation, and a GnRH antagonist (0.25 mg) was only used prophylactically when the luteinizing hormone (LH) was ≧ 6 IU/L (over half of the definitive LH surge). The incidence of premature LH surge (≧ 10 IU/L) was 2.4% (7/288) before the timely injection of a single GnRH antagonist, and the elevated LH level was dropped down from 11.9 IU/L to 2.2 IU/L after the suppression. Two hundred fifty-one patients did not need any antagonist (87.2% [251/288]) throughout the whole stimulation. No adverse effects were observed regarding oocyte competency (fertilization rate: 78%; blastocyst formation rate: 64%). The live birth rate per OPU cycle after the first cryotransfer was 56.3% (161/286), and the cumulative live birth rate per OPU cycle after cyrotransfers was 69.6% (199/286). Of patients who did and did not receive GnRH antagonist during stimulation, no significant difference existed in the cumulative live birth rates (78.4% vs. 68.3%, p = 0.25). The results demonstrated that the routine GnRH antagonist administration is not required in the corifollitropin-alfa cycles using a flexible and hormone-depended antagonist regimen, while the clinical outcome is not compromised. This finding reveals that the use of a GnRH antagonist only occasionally may be needed.

  4. A Patient Friendly Corifollitropin Alfa Protocol without Routine Pituitary Suppression in Normal Responders.

    Directory of Open Access Journals (Sweden)

    Huai-Ling Wang

    Full Text Available The release of corifollitropin alfa simplifies daily injections of short-acting recombinant follicular stimulating hormone (rFSH, and its widely-used protocol involves short-acting gonadotropins supplements and a fixed GnRH antagonist regimen, largely based on follicle size. In this study, the feasibility of corifollitropin alfa without routine pituitary suppression was evaluated. A total of 288 patients were stimulated by corifollitropin alfa on cycle day 3 following with routine serum hormone monitoring and follicle scanning every other day after 5 days of initial stimulation, and a GnRH antagonist (0.25 mg was only used prophylactically when the luteinizing hormone (LH was ≧ 6 IU/L (over half of the definitive LH surge. The incidence of premature LH surge (≧ 10 IU/L was 2.4% (7/288 before the timely injection of a single GnRH antagonist, and the elevated LH level was dropped down from 11.9 IU/L to 2.2 IU/L after the suppression. Two hundred fifty-one patients did not need any antagonist (87.2% [251/288] throughout the whole stimulation. No adverse effects were observed regarding oocyte competency (fertilization rate: 78%; blastocyst formation rate: 64%. The live birth rate per OPU cycle after the first cryotransfer was 56.3% (161/286, and the cumulative live birth rate per OPU cycle after cyrotransfers was 69.6% (199/286. Of patients who did and did not receive GnRH antagonist during stimulation, no significant difference existed in the cumulative live birth rates (78.4% vs. 68.3%, p = 0.25. The results demonstrated that the routine GnRH antagonist administration is not required in the corifollitropin-alfa cycles using a flexible and hormone-depended antagonist regimen, while the clinical outcome is not compromised. This finding reveals that the use of a GnRH antagonist only occasionally may be needed.

  5. Q-PYTHIA: a medium-modified implementation of final state radiation

    Science.gov (United States)

    Armesto, Néstor; Cunqueiro, Leticia; Salgado, Carlos A.

    2009-10-01

    We present a Monte Carlo implementation, within PYTHIA, of medium-induced gluon radiation in the final state branching process. Medium effects are introduced through an additive term in the splitting functions computed in the multiple-soft scattering approximation. The observable effects of this modification are studied for different quantities as fragmentation functions and the hump-backed plateau, and transverse momentum and angular distributions. The anticipated increase of intra-jet multiplicities, energy loss of the leading particle and jet broadening are observed as well as modifications of naive expectations based solely on analytical calculations. This shows the adequacy of a Monte Carlo simulator for jet analyses. Effects of hadronization are found to wash out medium effects in the soft region, while the main features remain. To show the performance of the implementation and the feasibility of our approach in realistic experimental situations we provide some examples: fragmentation functions, nuclear suppression factors, jet shapes and jet multiplicities. The package containing the modified routines is available for public use. This code, which is not an official PYTHIA release, is called Q-PYTHIA. We also include a short manual to perform the simulations of jet quenching.

  6. Caffeine-mediated release of alpha-radiation-induced G2 arrest increases the yield of chromosome aberrations

    International Nuclear Information System (INIS)

    Luecke-Huhle, C.; Hieber, L.; Wegner, R.D.

    1983-01-01

    Severe and partly irreversible G2 arrest caused by americium-241 alpha-particles in Chinese hamster V79 cells acted as a competing process to the yield of detectable aberrant mitoses at metaphase. With increasing dose of alpha-radiation an increasing fraction of cells was irreversibly arrested in G2 with the consequence of interphase death before the first post-irradiation mitosis. This irreversible G2 arrest (demonstrated by flow cytofluorometry and mitotic indices) could be overcome by adding caffeine 8 hours after irradiation, the time point of maximum G2 arrest (80-90 per cent of all cells). Within 3.5 hours the number of aberrant mitoses increased by this treatment from 54 to 96 per cent and from 65 to 99.9 per cent for doses of 1.75 and 4.38 Gy of alpha-particles, respectively. The aberration frequency per mitotic cell, scored as chromatid and isochromatid breaks, rings, interchanges and dicentrics increased by a factor of about 3 after releasing G2 arrested cells. The frequency distribution of aberrations per cell revealed that, after 4.38 Gy, 58 per cent of the formerly G2-arrested cells had more than five aberrations per cell compared to only 8 per cent without the interaction of caffeine. (author)

  7. The care of radiation casualties. 6. rev. ed.

    International Nuclear Information System (INIS)

    Carpaij, W.J.M.; Keverling Buisman, A.S.

    1981-01-01

    All routine procedures taken by the Occupational Health Service of the Health Protection Department of ECN in case of a personal contamination with radioactive materials and/or overexposure with ionising radiation are described in detail. The appendices contain information concerning limits of intake and all forms and registration-charts used in these procedures

  8. Feasibility of dual-energy computed tomography in radiation therapy planning

    Science.gov (United States)

    Sheen, Heesoon; Shin, Han-Back; Cho, Sungkoo; Cho, Junsang; Han, Youngyih

    2017-12-01

    In this study, the noise level, effective atomic number ( Z eff), accuracy of the computed tomography (CT) number, and the CT number to the relative electron density EDconversion curve were estimated for virtual monochromatic energy and polychromatic energy. These values were compared to the theoretically predicted values to investigate the feasibility of the use of dual-energy CT in routine radiation therapy planning. The accuracies of the parameters were within the range of acceptability. These results can serve as a stepping stone toward the routine use of dual-energy CT in radiotherapy planning.

  9. Assessment of consequences from airborne releases of radioactive material

    International Nuclear Information System (INIS)

    McGrath, P.E.; Blond, R.M.

    1976-01-01

    Over the past several years, the manner in which assessments have been made of the consequences of large airborne releases of radioactive material has not changed much conceptually. The models to describe the atmospheric dispersion of the radioactive material have generally been time-invariant, i.e., the meteorological conditions (thermal stability, wind speed, and precipitation) are invariant during release and the subsequent period of radiation exposure of the population to the airborne material. The frequency distribution of the meteorological conditions are determined by analyzing several years of weather data from the appropriate geographical location. In reality, weather is continuously changing over short time periods (hours) following the release. It is to be expected that the changing meteorological conditions would have important effects on the potential consequences of the release. A time-dependent atmospheric dispersion model was developed and implemented in the Reactor Safety Study. This paper provides a description of the model and the nature of the results generated. Emphasis is given to an explanation of how, and why, these results differ from those estimated with time-invariant models

  10. Dosimetry systems for radiation processing in Japan

    International Nuclear Information System (INIS)

    Tamura, Naoyuki

    1995-01-01

    The present situation of dosimetry systems for radiation processing industry in Japan is reviewed. For gamma-rays irradiation the parallel-plate ionization chamber in TRCRE, JAERI has been placed as a reference standard dosimeter for processing-level dose. Various solid and liquid chemical dosimeters are used as routine dosimeters for gamma processing industries. Alanine dosimeters is used for the irradiation purpose which needs precise dosimetry. For electron-beam irradiation the electron current density meter and the total absorption calorimeter of TRCRE are used for the calibration of routine dosimeters. Plastic film dosimeters, such as cellulose triacetate and radiochromic dye are used as routine dosimeters for electron processing industries. When the official traceability systems for processing-level dosimetry now under investigation is completed, the ionization chamber of TRCRE is expected to have a role of the primary standard dosimeter and the specified alanine dosimeter will be nominated for the secondary or reference standard dosimeter. (author)

  11. Advanced Computational Methods for Thermal Radiative Heat Transfer

    Energy Technology Data Exchange (ETDEWEB)

    Tencer, John; Carlberg, Kevin Thomas; Larsen, Marvin E.; Hogan, Roy E.,

    2016-10-01

    Participating media radiation (PMR) in weapon safety calculations for abnormal thermal environments are too costly to do routinely. This cost may be s ubstantially reduced by applying reduced order modeling (ROM) techniques. The application of ROM to PMR is a new and unique approach for this class of problems. This approach was investigated by the authors and shown to provide significant reductions in the computational expense associated with typical PMR simulations. Once this technology is migrated into production heat transfer analysis codes this capability will enable the routine use of PMR heat transfer in higher - fidelity simulations of weapon resp onse in fire environments.

  12. Environmental radiation protection standards

    International Nuclear Information System (INIS)

    Richings, L.D.G.; Morley, F.; Kelley, G.N.

    1978-04-01

    The principles involved in the setting of radiological protection standards are reviewed, and the differences in procedures used by various countries in implementing them are outlined. Standards are taken here to mean the specific numerical limits relating to radiation doses to people or to amounts of radioactive material released into the environment. (author)

  13. Results for SEAFP-subtask A 10: Assessments of individual and collective doses to the public for routine and accidental releases of tritium and activation products

    International Nuclear Information System (INIS)

    Raskob, W.

    1995-04-01

    Dose calculations have been performed for accidental releases of tritium and activation products. Unit releases of 1 GBq per nuclide have been investigated for 31 fusion relevant nuclides. Additionally, unit releases of 1g of tritium and several activated materials have been studied. Under normal operation conditions, dose calculations have been performed for real source terms of tritium and activated materials. The individual dose values at the fence of the site (1 km) as well as the collective dose to the public (from 1 km to 100 km) have been obtained. As site specific parameters are still missing, different so called ''worst case'' release conditions have been applied. To have a first guess of the influence of the release duration on the dose to the Most Exposed Individual (MEI) in the vicinity of a reactor, different release durations, ranging from 1 hour up to 168 hours have been investigated, too. Finally, dose calculations have been performed for mobilisation source terms which take account of deposition and retention in the plant. This has been done for several RPM and APM source terms. The dose values of these final source terms seem to be less than every criteria to start emergency actions, however, some problems e.g. the behaviour of tritium in the plant, remain unsolved. (orig.)

  14. Micronuclei Frequencies in Lymphocytes of Nuclear Malaysia Radiation Workers

    International Nuclear Information System (INIS)

    Mohd Rodzi Ali; Aisyah Mohd Yusof; Rahimah Abdul Rahim; Juliana Mahamat Napiah; Yahaya Talib; Shafii Khamis

    2016-01-01

    The objective of the study is to investigate the frequency of cell aberration in lymphocytes of the Nuklear Malaysia radiation workers. A total of 58 blood samples were collected from the radiation workers during their routine medical examination. The donor age range is between 23 to 58 years, 31 male and 27 female. Blood samples were cultured according to the standard protocol recommended by the International Atomic Energy Agency. The mean micronuclei (MN) is 23.5 ± 0.9 MN/ 1000 binucleate, with the median value of 24 MN/ 1000 binucleate. The lowest number of MN was 9, and the highest was 43. There is no correlation between the number of MN in blood and yearly cumulative dose for radiation workers. The results indicate the MN expression due to small radiation exposure is almost negligible in Nuclear Malaysia radiation workers. (author)

  15. Evaluation of quality of polaprezinc suppositories and their clinical effect on radiation proctitis

    International Nuclear Information System (INIS)

    Shikata, Toshiyuki; Nakamura, Takeshi; Hikasa, Shinichi; Hamaguchi, Tsuneo; Doi, Hiroshi; Kamikonya, Norihiko; Kadobayashi, Muneo; Kimura, Takeshi

    2010-01-01

    Polaprezinc (PZ) suppositories have been used for radiation proctitis in our hospital. In this study, we established methods to evaluate the quality of hospital-prepared PZ suppositories and investigated their stability. As PZ is dissociated at an acidic pH but not at a medium pH, the release of PZ from the suppository was carried out using chelatometric titration in weakly acidic buffer solutions (pH 3, pH 4, and pH 5). As the release of PZ from the suppository was fastest in the buffer solution at pH 3, we used this pH for the release test for PZ. Conducting this test in the stability investigation showed that the amount of PZ released from the suppository after 84 days was the same as that immediately after manufacture. We also examined the clinical efficacy of the PZ suppository in 5 patients with radiation proctitis, finding that efficacy was satisfactory in 3 patients. These results indicated that the PZ suppository is a good treatment for radiation proctitis. (author)

  16. Dosimetry of natural and man-made alpha emitters in plankton

    International Nuclear Information System (INIS)

    Paschoa, A.S.; Baptista, G.B.; Wrenn, M.E.; Eisenbrid, M.

    1980-11-01

    Comparison between the natural and man-made alpha radiation dose rates to plankton can be important for predicting the potential long-term effects on aquatic biota resulting from the routine or accidental radioactive releases from the nuclear fuel cycle. A contribution is made here towards the goal of comparing natural with man-made alpha radiation dose rates to plankton using the same method of calculation in both cases. (Author) [pt

  17. Induction of micronuclei by X radiation and various chemical agents in red blood cells of Pleurodeles waltl. Uptake, release and excretion of one of them: benzo(a)pyrene

    International Nuclear Information System (INIS)

    Grinfeld, S.

    1983-11-01

    The first part of the study is concerned with the effects of X radiation and of various substances dissolved in the breeding water (carbaryl, N-nitrosocarbaryl, benzo(a)pyrene, formol, cafeine, colchicine...) on the formation of micronuclei in red blood cells of Pleurodele larvae. The curves of the dose-effect relationships and of the kinetics of micronuclei formation are established for X radiation and benzo(a)pyrene. In the second part, a scintigraphic study concerning benzo(a)pyrene uptake, release and excretion by larvae, is presented. This study enables the dose-effect curve and the kinetics of micronuclei formation for this substance, to be interpreted. This study must allow the development of a cytogenetic test for the detection of radiomimetic substances in aqueous medium. Pleurodele is proposed as a new animal for the study of genetic toxicology [fr

  18. Radiation biology of mosquitoes

    Directory of Open Access Journals (Sweden)

    Knols Bart GJ

    2009-11-01

    Full Text Available Abstract There is currently renewed interest in assessing the feasibility of the sterile insect technique (SIT to control African malaria vectors in designated areas. The SIT relies on the sterilization of males before mass release, with sterilization currently being achieved through the use of ionizing radiation. This paper reviews previous work on radiation sterilization of Anopheles mosquitoes. In general, the pupal stage was irradiated due to ease of handling compared to the adult stage. The dose-response curve between the induced sterility and log (dose was shown to be sigmoid, and there was a marked species difference in radiation sensitivity. Mating competitiveness studies have generally been performed under laboratory conditions. The competitiveness of males irradiated at high doses was relatively poor, but with increasing ratios of sterile males, egg hatch could be lowered effectively. Males irradiated as pupae had a lower competitiveness compared to males irradiated as adults, but the use of partially-sterilizing doses has not been studied extensively. Methods to reduce somatic damage during the irradiation process as well as the use of other agents or techniques to induce sterility are discussed. It is concluded that the optimal radiation dose chosen for insects that are to be released during an SIT programme should ensure a balance between induced sterility of males and their field competitiveness, with competitiveness being determined under (semi- field conditions. Self-contained 60Co research irradiators remain the most practical irradiators but these are likely to be replaced in the future by a new generation of high output X ray irradiators.

  19. The care of radiation casualities. 6. rev. ed.

    International Nuclear Information System (INIS)

    Carpaij, W.J.M.; Keverling Buisman, A.S.

    1981-01-01

    This manual describes in detail all routine procedures taken by the Occupational Health Service of the Health Protection Department of ECN in case of a personal contamination with radioactive materials and/or overexposure with ionising radiation. The appendices contain information concerning limits of intake and all forms and registration-charts used in these procedures. (orig.)

  20. MARSAME Radiological Release Report for Archaeological Artifacts Excavated from Area L

    Energy Technology Data Exchange (ETDEWEB)

    Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Whicker, Jeffrey Jay [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gillis, Jessica Mcdonnel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-06-03

    In 1991 Los Alamos National Laboratory’s (LANL’s) cultural resources team excavated archaeological site LA 4618 located at Technical Area 54, within Material Disposal Area L (MDA L). MDA L received non-radioactive chemical waste from the early 1960s until 1985. Further development of the MDA required excavation of several cultural sites under National Historic Preservation Act requirements; artifacts from these sites have been subsequently stored at LANL. The LANL cultural resources group would now like to release these artifacts to the Museum of Indian Arts and Culture in Santa Fe for curation. The history of disposal at Area L suggests that the artifact pool is unlikely to be chemically contaminated and LANL staff washed each artifact at least once following excavation. Thus, it is unlikely that the artifacts present a chemical hazard. LANL’s Environmental Stewardship group (EPC-ES) has evaluated the radiological survey results for the Area L artifact pool and found that the items described in this report meet the criteria for unrestricted radiological release under Department of Energy (DOE) Order 458.1 Radiation Protection of the Public and the Environment and are candidates for release without restriction from LANL control. This conclusion is based on the known history of MDA L and on radiation survey data.