Severe accident management at nuclear power plants - emergency preparedness and response actions

International Nuclear Information System (INIS)

Pawar, S.K.; Krishnamurthy, P.R.

2015-01-01

This paper describes the current level of emergency planning and preparedness and also improvement in the emergency management programme over the years including lessons learned from Fukushima accident, hazard analysis and categorization of nuclear facilities into hazard category for establishing the emergency preparedness class, classification of emergencies based on the Emergency Action Levels (EAL), development of EAL’s for PHWR, Generic Criteria in terms of projected dose for initiating protective actions (precautionary urgent protective actions, urgent protective actions, early protective actions), operational intervention levels (OIL), Emergency planning zones and distances, protection strategy and reference levels, use of residual dose for establishing reference levels for optimization of protection strategy, criteria for termination of emergency, transition of emergency exposure situation to existing exposure situation or planned exposure situation, criteria for medical managements of exposed persons and guidance for controlling the dose of emergency workers. This paper also highlights the EALs for typical PHWR type reactors for all types of emergencies (plant, site and offsite), transition from emergency operating procedures (EOP) to accident management guidelines (AMG) to emergency response actions and proposed implementation of guidelines

Commercial sugar, an alternative dosemeter for the dose determination in radiological emergency conditions

International Nuclear Information System (INIS)

Urena N, F.; Galindo, S.

1997-01-01

It was carried out the dosimetric evaluation of commercial sugar, with the purpose to determine the feasibility to be able to use this type of substance as a dosimetric material in cases to present some radiological emergency cases. The studied parameters using the Electron Paramagnetic Resonance (EPR) technique were: pre-doses signal or depth signal, dose-response stability, reproducibility, reliability and signal clearing decreasing. (Author)

Estimating Derived Response Levels at the Savannah River Site for Use with Emergency Response Models

International Nuclear Information System (INIS)

Simpkins, A.A.

2002-01-01

Emergency response computer models at the Savannah River Site (SRS) are coupled with real-time meteorological data to estimate dose to individuals downwind of accidental radioactive releases. Currently, these models estimate doses for inhalation and shine pathways, but do not consider dose due to ingestion of contaminated food products. The Food and Drug Administration (FDA) has developed derived intervention levels (DIL) which refer to the radionuclide-specific concentration in food present throughout the relevant period of time, with no intervention, that could lead to an individual receiving a radiation dose equal to the protective action guide. In the event of an emergency, concentrations in various food types are compared with these levels to make interdictions decisions. Prior to monitoring results being available, concentrations in the environmental media (i.e. soil), called derived response levels (DRLs), can be estimated from the DILs and directly compared with computer output to provide preliminary guidance as to whether intervention is necessary. Site-specific derived response levels (DRLs) are developed for ingestion pathways pertinent to SRS: milk, meat, fish, grain, produce, and beverage. This provides decision-makers with an additional tool for use immediately following an accident prior to the acquisition of food monitoring data

Modernisation of Radiation Monitoring Room as a Part of Slovenian Emergency Response Centre

International Nuclear Information System (INIS)

Sarvari, A.; Mitic, D.

2003-01-01

In the year 2002 the Slovenian Nuclear Safety Administration (SNSA) moved to the new premises therefore it had to rearrange some of its rooms for the emergency situation. SNSA does not operate with a dedicated Emergency Response Centre (ERC), instead of it the SNSA has to rearrange the existing rooms in case of an emergency. Modernisation of the equipment, with the help of government of the United Kingdom of Great Britain and Northern Ireland, for the emergency situation was carried out, especially in the monitoring room. The radiation monitoring system, which is placed in the monitoring room, continuously collects, processes and archives the incoming data of exposure to radiation and meteorological parameters on the Slovenian territory (A model national emergency response plan for radiological accidents, IAEA, Vienna, 1993. IAEA-TECDOC-718). In the emergency situation the monitoring room transforms into the room for the Dose Assessment Group (DAG), which is part of ERC (IAEA emergency response network, IAEA, Vienna, 2000, EPR-ERNET (2000)). The modernisation of monitoring room and within the DAG room with new equipment and its purpose is described in this article. Modernisation of the monitoring room and the room for DAG showed to be inevitably needed. Modernisation of the monitoring room has brought the SNSA a sophisticated and reliable system of controlling the external exposure to radiation on the Slovenian territory. The equipment, especially the equipment for the use in the emergency situation, brought novelties for the Dose Assessment Group. The group has now better and easier control of radiation situation in case of an accident. In overall this modernisation has put the Slovenian Nuclear Safety Administration a step forward in having a dedicated Emergency Response Centre, since it does not need to rearrange the room for the Dose Assessment Group. (author)

Introducing PCTRAN as an evaluation tool for nuclear power plant emergency responses

International Nuclear Information System (INIS)

Cheng, Yi-Hsiang; Shih, Chunkuan; Chiang, Show-Chyuan; Weng, Tung-Li

2012-01-01

Highlights: ► PCTRAN is integrated with an atmospheric dispersion algorithm. ► The improved PCTRAN acts as an accident/incident simulator and a data exchange system. ► The software helps the responsible organizations decide the rescue and protective actions. ► The evaluation results show the nuclear power plant accident and its off-site dose consequences. ► The software can be used for nuclear power plant emergency responses. - Abstract: Protecting the public from radiation exposure is important if a nuclear power plant (NPP) accident occurs. Deciding appropriate protective actions in a timely and effective manner can be fulfilled by using an effective accident evaluation tool. In our earlier work, we have integrated PCTRAN (Personal Computer Transient Analyzer) with the off-site dose calculation model. In this study, we introduce PCTRAN as an evaluation tool for nuclear power plant emergency responses. If abnormal conditions in the plant are monitored or observed, the plant staffs can distinguish accident/incident initiation events. Thus, the responsible personnel can immediately operate PCTRAN and set up those accident/incident initiation events to simulate the nuclear power plant transient or accident in conjunction with off-site dose distributions. The evaluation results consequently help the responsible organizations decide the rescue and protective actions. In this study, we explain and demonstrate the capabilities of PCTRAN for nuclear emergency responses, through applying it to simulate the postulated nuclear power plant accident scenarios.

ANS-8.23: Criticality accident emergency planning and response

International Nuclear Information System (INIS)

Pruvost, N.L.

1991-01-01

A study group has been formed under the auspices of ANS-8 to examine the need for a standard on nuclear criticality accident emergency planning and response. This standard would be ANS-8.23. ANSI/ANS-8.19-1984, Administrative Practices for Nuclear Criticality Safety, provides some guidance on the subject in Section 10 titled -- Planned Response to Nuclear Criticality Accidents. However, the study group has formed a consensus that Section 10 is inadequate in that technical guidance in addition to administrative guidance is needed. The group believes that a new standard which specifically addresses emergency planning and response to a perceived criticality accident is needed. Plans for underway to request the study group be designated a writing group to create a draft of such a new standard. The proposed standard will divide responsibility between management and technical staff. Generally, management will be charged with providing the necessary elements of emergency planning such as a criticality detection and alarm system, training, safe evacuation routes and assembly areas, a system for timely accountability of personnel, and an effective emergency response organization. The technical staff, on the other hand, will be made responsible for establishing specific items such as safe and clearly posted evacuation evacuation routes and dose criteria for personnel assembly areas. The key to the question of responsibilities is that management must provide the resources for the technical staff to establish the elements of an emergency response effort

SPEEDI: system for prediction of environmental emergency dose information

International Nuclear Information System (INIS)

Chino, Masamichi; Ishikawa, Hirohiko; Kai, Michiaki

1984-03-01

In this report a computer code system for prediction of environmental emergency dose information , i.e., SPEEDI for short, is presented. In case of an accidental release of radioactive materials from a nuclear plant, it is very important for an emergency planning to predict the concentration and dose caused by the materials. The SPEEDI code system has been developed for this purpose and it has features to predict by calculation the released nuclides, wind fields, concentrations and dose based on release information, actual weather and topographical data. (author)

Optimization of in-vivo monitoring program for radiation emergency response

Energy Technology Data Exchange (ETDEWEB)

Ha, Wi Ho; Kim, Jong Kyung [Dept. of Nuclear Engineering, Hanyang University, Seoul (Korea, Republic of)

2016-12-15

In case of radiation emergencies, internal exposure monitoring for the members of public will be required to confirm internal contamination of each individual. In-vivo monitoring technique using portable gamma spectrometer can be easily applied for internal exposure monitoring in the vicinity of the on-site area. In this study, minimum detectable doses (MDDs) for '1'3'4Cs, {sup 137}Cs, and {sup 131}I were calculated adjusting minimum detectable activities (MDAs) from 50 to 1,000 Bq to find out the optimal in-vivo counting condition. DCAL software was used to derive retention fraction of Cs and I isotopes in the whole body and thyroid, respectively. A minimum detectable level was determined to set committed effective dose of 0.1 mSv for emergency response. We found that MDDs at each MDA increased along with the elapsed time. 1,000 Bq for {sup 134}Cs and {sup 137}Cs, and 100 Bq for {sup 131}I were suggested as optimal MDAs to provide in-vivo monitoring service in case of radiation emergencies. In-vivo monitoring program for emergency response should be designed to achieve the optimal MDA suggested from the present work. We expect that a reduction of counting time compared with routine monitoring program can achieve the high throughput system in case of radiation emergencies.

Establishing a mobile automatic monitoring station for emergency response

International Nuclear Information System (INIS)

Fang, Hsin-Fa

2008-01-01

Full text: A radiological/nuclear emergency event may cause environmental contamination. The emergency response works always need to plan an environmental survey programme incorporating the assessment results to see what is happening. The places where are assessed to have the highest radioactive contamination/radiation dose will catch more concern and need continuous monitoring. It will cause unnecessary dangers and dose to command that personnel conduct surveying in such places when the radiological/nuclear accident become more severe. A mobile automatic monitoring station has been established for emergency response by INER (Institute of Nuclear Energy Research) to solve the problem practically. The monitoring station involves a HPIC to monitor radiation dose, an anemometer to monitor wind speed and direction, a GPS to get position data, a GPRS/3G communication module to send monitoring and positioning data to the monitoring centre where can show the monitoring result directly on a map shown on the computer. These instruments are integrated in a trailer easy to be towed to the place need to be monitored. The electric power of the station is supplied by s a solar power energy system. It can supply the station working at least 10 days without extra electric power supply designed based on the expected time length of a nuclear power plant event. The HPIC is very sensitive and stable that can discriminate a 10 nSv/hr increasing of dose rate with the monitoring time period every ten seconds. Where the radiological dispersion device events happened is not predictable, it is difficult to get suitable wind monitoring data to assess the result of radiological dispersion device events. The anemometer added on the station can provide the real time wind monitoring data to help assessment works. (author)

Radiation-induced damage analysed by luminescence methods in retrospective dosimetry and emergency response.

Science.gov (United States)

Woda, Clemens; Bassinet, Céline; Trompier, François; Bortolin, Emanuela; Della Monaca, Sara; Fattibene, Paola

2009-01-01

The increasing risk of a mass casualty scenario following a large scale radiological accident or attack necessitates the development of appropriate dosimetric tools for emergency response. Luminescence dosimetry has been reliably applied for dose reconstruction in contaminated settlements for several decades and recent research into new materials carried close to the human body opens the possibility of estimating individual doses for accident and emergency dosimetry using the same technique. This paper reviews the luminescence research into materials useful for accident dosimetry and applications in retrospective dosimetry. The properties of the materials are critically discussed with regard to the requirements for population triage. It is concluded that electronic components found within portable electronic devices, such as e.g. mobile phones, are at present the most promising material to function as a fortuitous dosimeter in an emergency response.

Dose-Response Calculator for ArcGIS

Science.gov (United States)

Hanser, Steven E.; Aldridge, Cameron L.; Leu, Matthias; Nielsen, Scott E.

2011-01-01

The Dose-Response Calculator for ArcGIS is a tool that extends the Environmental Systems Research Institute (ESRI) ArcGIS 10 Desktop application to aid with the visualization of relationships between two raster GIS datasets. A dose-response curve is a line graph commonly used in medical research to examine the effects of different dosage rates of a drug or chemical (for example, carcinogen) on an outcome of interest (for example, cell mutations) (Russell and others, 1982). Dose-response curves have recently been used in ecological studies to examine the influence of an explanatory dose variable (for example, percentage of habitat cover, distance to disturbance) on a predicted response (for example, survival, probability of occurrence, abundance) (Aldridge and others, 2008). These dose curves have been created by calculating the predicted response value from a statistical model at different levels of the explanatory dose variable while holding values of other explanatory variables constant. Curves (plots) developed using the Dose-Response Calculator overcome the need to hold variables constant by using values extracted from the predicted response surface of a spatially explicit statistical model fit in a GIS, which include the variation of all explanatory variables, to visualize the univariate response to the dose variable. Application of the Dose-Response Calculator can be extended beyond the assessment of statistical model predictions and may be used to visualize the relationship between any two raster GIS datasets (see example in tool instructions). This tool generates tabular data for use in further exploration of dose-response relationships and a graph of the dose-response curve.

Experimental data and dose-response models

International Nuclear Information System (INIS)

Ullrich, R.L.

1985-01-01

Dose-response relationships for radiation carcinogenesis have been of interest to biologists, modelers, and statisticians for many years. Despite his interest there are few instances in which there are sufficient experimental data to allow the fitting of various dose-response models. In those experimental systems for which data are available the dose-response curves for tumor induction for the various systems cannot be described by a single model. Dose-response models which have been observed following acute exposures to gamma rays include threshold, quadratic, and linear models. Data on sex, age, and environmental influences of dose suggest a strong role of host factors on the dose response. With decreasing dose rate the effectiveness of gamma ray irradiation tends to decrease in essentially every instance. In those cases in which the high dose rate dose response could be described by a quadratic model, the effect of dose rate is consistent with predictions based on radiation effects on the induction of initial events. Whether the underlying reasons for the observed dose-rate effect is a result of effects on the induction of initial events or is due to effects on the subsequent steps in the carcinogenic process is unknown. Information on the dose response for tumor induction for high LET (linear energy transfer) radiations such as neutrons is even more limited. The observed dose and dose rate data for tumor induction following neutron exposure are complex and do not appear to be consistent with predictions based on models for the induction of initial events

Dose-response curves from incomplete data

International Nuclear Information System (INIS)

Groer, P.G.

1978-01-01

Frequently many different responses occur in populations (animal or human) exposed to ionizing radiation. To obtain a dose-response curve, the exposed population is first divided into sub-groups whose members received the same radiation dose. To estimate the response, the fraction of subjects in each sub-group that showed the particular response of interest is determined. These fractions are plotted against dose to give the dose-response curve. This procedure of plotting the fractions versus the radiation dose is not the correct way to estimate the time distribution for a particular response at the different dose levels. Other observed responses competed for the individuals in the exposed population and therefore prevented manifestation of the complete information on the response-time distribution for one specific response. Such data are called incomplete in the statistical literature. A procedure is described which uses the by now classical Kaplan-Meier estimator, to establish dose-response curves from incomplete data under the assumption that the different observed responses are statistically independent. It is demonstrated that there is insufficient information in the observed survival functions to estimate the time distribution for one particular response if the assumption of independence is dropped. In addition, it is not possible to determine from the data (i.e. type of response and when it occurred) whether or not the different response-time distributions are independent. However, it is possible to give sharp bounds between which the response has to lie. This implies that for incomplete data, only a 'dose-response band' can be established if independence of the competing responses cannot be assumed. Examples are given using actual data to illustrate the estimation procedures

The Fukushima Daiichi Accident. Technical Volume 3/5. Emergency Preparedness and Response

International Nuclear Information System (INIS)

2015-08-01

This volume describes the key events and response actions from the onset of the accident at the Fukushima Daiichi nuclear power plant (NPP), operated by the Tokyo Electric Power Company (TEPCO), on 11 March 2011. It also describes the national emergency preparedness and response (EPR) system in place in Japan and the international EPR framework prior to the accident. It is divided into five sections. Section 3.1 describes the initial actions taken by Japan in response to the accident, involving: identification of the accident, notification of off-site authorities and activation of the response; mitigatory actions taken on-site; and initial off-site response. Section 3.2 describes the protective measures taken for personnel in response to the natural disaster, protection of emergency workers, medical management of emergency workers and the voluntary involvement of members of the public in the emergency response. Section 3.3 describes the protective actions and other response actions taken by Japan to protect the public. It addresses urgent and early protective actions; the use of a dose projection model, the System for Prediction of Environmental Emergency Dose Information (SPEEDI), as a basis for decisions on protective actions during the accident; environmental monitoring; provision of information to the public and international community; and issues related to international trade and waste management. Section 3.4 describes the transition from the emergency phase to the recovery phase. It also addresses the national analysis of the accident and the emergency response. Section 3.5 describes the response by the IAEA, other international organizations within the Inter- Agency Committee on Radiological and Nuclear Emergencies (IACRNE), the actions of IAEA Member States with regard to protective actions recommended to their nationals in Japan and the provision of international assistance. A summary, observations and lessons conclude each section. There are three

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of radiation protection. The publication also proposes a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default oils for deposition, individual monitoring and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables at the scene of a nuclear or radiological emergency

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Russian Ed.)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of radiation protection. The publication also proposes a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default oils for deposition, individual monitoring and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables at the scene of a nuclear or radiological emergency.

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-11-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of principles of radiation protection. The publication also provides a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default OILs for deposition, individual contamination and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables on the scene of a radiological emergency.

Emergency Doses (ED) - Revision 3: A calculator code for environmental dose computations

International Nuclear Information System (INIS)

Rittmann, P.D.

1990-12-01

The calculator program ED (Emergency Doses) was developed from several HP-41CV calculator programs documented in the report Seven Health Physics Calculator Programs for the HP-41CV, RHO-HS-ST-5P (Rittman 1984). The program was developed to enable estimates of offsite impacts more rapidly and reliably than was possible with the software available for emergency response at that time. The ED - Revision 3, documented in this report, revises the inhalation dose model to match that of ICRP 30, and adds the simple estimates for air concentration downwind from a chemical release. In addition, the method for calculating the Pasquill dispersion parameters was revised to match the GENII code within the limitations of a hand-held calculator (e.g., plume rise and building wake effects are not included). The summary report generator for printed output, which had been present in the code from the original version, was eliminated in Revision 3 to make room for the dispersion model, the chemical release portion, and the methods of looping back to an input menu until there is no further no change. This program runs on the Hewlett-Packard programmable calculators known as the HP-41CV and the HP-41CX. The documentation for ED - Revision 3 includes a guide for users, sample problems, detailed verification tests and results, model descriptions, code description (with program listing), and independent peer review. This software is intended to be used by individuals with some training in the use of air transport models. There are some user inputs that require intelligent application of the model to the actual conditions of the accident. The results calculated using ED - Revision 3 are only correct to the extent allowed by the mathematical models. 9 refs., 36 tabs

The Student Volunteer Army: a 'repeat emergent' emergency response organisation.

Science.gov (United States)

Carlton, Sally; Mills, Colleen E

2017-10-01

This paper seeks to contribute to understanding of the factors associated with an effective emergent emergency response organisation and to provide new insights into this understudied area. It examines, through an analysis of a range of textual resources, the emergence and re-emergence of the Student Volunteer Army (SVA) during the devastating earthquakes in Canterbury, New Zealand, in 2010-11. This evaluation is conducted in relation to the four key features of an effective emergency response organisation: adaptability; direction; leadership; and communication. In addition, the paper aims to further understanding of 'emergency entrepreneurship' and thus of the values and strategies that underpin social entrepreneur organisations in times of normalcy. The paper concludes that the unique position of the SVA as a 'repeat emergent' emergency response organisation enabled it to innovate continually and to improve repeatedly its systems, relationships, and image, such that it exhibited features common to emergent and established emergency response organisations. © 2017 The Author(s). Disasters © Overseas Development Institute, 2017.

SAVANNAH RIVER SITE CAPABILITIES FOR CONDUCTING INGESTION PATHWAY CONSEQUENCE ASSESSMENTS FOR EMERGENCY RESPONSE

Energy Technology Data Exchange (ETDEWEB)

Hunter, C

2007-12-11

Potential airborne releases of radioactivity from facilities operated for the U. S. Department of Energy at the Savannah River Site could pose significant consequences to the public through the ingestion pathway. The Savannah River National Laboratory has developed a suite of technologies needed to conduct assessments of ingestion dose during emergency response, enabling emergency manager at SRS to develop initial protective action recommendation for state agencies early in the response and to make informed decisions on activation of additional Federal assets that would be needed to support long-term monitoring and assessment activities.

Updated tool for nuclear criticality accident emergency response

International Nuclear Information System (INIS)

Broadhead, B.L.; Hopper, C.M.

1995-01-01

Some 20 yr ago a hand-held slide rule was developed at the Oak Ridge Y-12 Plant to aid in the response to several postulated nuclear criticality accidents. These assumed accidents involved highly enriched uranium in either a bare metal or a uranyl nitrate system. The slide rule consisted of a sliding scale based on the total fission yield and four corresponding dose indicators: (1) a prompt radiation dose relationship as a function of distance; (2) a delayed fission product gamma dose rate relationship as a function of time and distance; (3) the total dose relationship with time and distance; and (4) the I-min integrated dose relationship with time and distance. The original slide rule was generated assuming very simplistic numerical procedures such as the inverse-square relationship of dose with distance and the Way-Wigner relationship to express the time dependence of the dose. The simple prescriptions were tied to actual dose measurements from similar systems to yield a meaningful, yet simple approach to emergency planning and response needs. This paper describes the application of an advanced procedure to the updating of the original slide rule for five critical systems. These five systems include (a) an unreflected sphere of 93.2 wt% enriched uranium metal, (b) an unreflected sphere of 93.2 wt% enriched uranyl nitrate solution with a H/ 235 U ratio of 500, (c) an unreflected sphere of damp 93.2 wt% enriched uranium oxide with a H/ 235 U ratio of 10, (d) an unreflected sphere of 4.95 wt% enriched uranyl fluoride solution having a H/ 235 U ratio of 410, and (e) an unreflected sphere of damp 5 wt% enriched uranium dioxide having a H/ 235 U ratio of 200

Repair and dose-response at low doses

International Nuclear Information System (INIS)

Totter, J.R.; Weinberg, A.M.

1977-04-01

The DNA of each individual is subject to formation of some 2-4 x 10 14 ion pairs during the first 30 years of life from background radiation. If a single hit is sufficient to cause cancer, as is implicit in the linear, no-threshold theories, it is unclear why all individuals do not succumb to cancer, unless repair mechanisms operate to remove the damage. We describe a simple model in which the exposed population displays a distribution of repair thresholds. The dose-response at low dose is shown to depend on the shape of the threshold distribution at low thresholds. If the probability of zero threshold is zero, the response at low dose is quadratic. The model is used to resolve a longstanding discrepancy between observed incidence of leukemia at Nagasaki and the predictions of the usual linear hypothesis

Dose-response-a challenge for allelopathy?

Science.gov (United States)

Belz, Regina G; Hurle, Karl; Duke, Stephen O

2005-04-01

The response of an organism to a chemical depends, among other things, on the dose. Nonlinear dose-response relationships occur across a broad range of research fields, and are a well established tool to describe the basic mechanisms of phytotoxicity. The responses of plants to allelochemicals as biosynthesized phytotoxins, relate as well to nonlinearity and, thus, allelopathic effects can be adequately quantified by nonlinear mathematical modeling. The current paper applies the concept of nonlinearity to assorted aspects of allelopathy within several bioassays and reveals their analysis by nonlinear regression models. Procedures for a valid comparison of effective doses between different allelopathic interactions are presented for both, inhibitory and stimulatory effects. The dose-response applications measure and compare the responses produced by pure allelochemicals [scopoletin (7-hydroxy-6-methoxy-2H-1-benzopyran-2-one); DIBOA (2,4-dihydroxy-2H-1,4-benzoxaxin-3(4H)-one); BOA (benzoxazolin-2(3H)-one); MBOA (6-methoxy-benzoxazolin-2(3H)-one)], involved in allelopathy of grain crops, to demonstrate how some general principles of dose responses also relate to allelopathy. Hereupon, dose-response applications with living donor plants demonstrate the validity of these principles for density-dependent phytotoxicity of allelochemicals produced and released by living plants (Avena sativa L., Secale cereale L., Triticum L. spp.), and reveal the use of such experiments for initial considerations about basic principles of allelopathy. Results confirm that nonlinearity applies to allelopathy, and the study of allelopathic effects in dose-response experiments allows for new and challenging insights into allelopathic interactions.

Oligodendroglial response to ionizing radiation: Dose and dose-rate response

International Nuclear Information System (INIS)

Levy, R.P.

1991-01-01

An in vitro system using neuroglia from neonatal rat brain was developed to examining the morphologic, immunocytochemical and biochemical response of oligodendroglia to ionizing radiation. Following acute γ-radiation at day-in-culture (DIC) 8, oligodendrocyte counts at DIC 14 were 55% to 65% of control values after 2 Gy, and 29% to 36% after 5 Gy. Counts increased to near-normal levels at DIC 21 in the 2 Gy group and to 75% of normal in the 5 Gy group. Myelin basic protein levels (MBP) at DIC 14 were 60% of control values after 2 Gy, and 40% after 5 Gy. At DIC 21, MBP after 2 Gy was 45% greater than that observed at DIC 14, but MBP, as a fraction of age-matched control values, dropped from 60% to 50%. Following 5 Gy, absolute MBP changed little between DIC 14 and DIC 21, but decreased from 40% to 25% of control cultures. It was concluded that oligodendrocytes in irradiated cultures had significantly lower functional capacity than did unirradiated controls. The response to split-dose irradiation indicated that nearly all sublethal damage in the oligodendrocyte population (and its precursors) was repaired within 3 h to 4 h. At DIC 14, the group irradiated in a single fraction had significantly lower oligodendrocyte counts than any group given split doses; all irradiated cultures had marked depression of MBP synthesis, but to significant differences referable to time interval between doses. At DIC 21, cultures irradiated at intervals of 0 h to 2 h had similar oligodendrocyte counts to one another, but these counts were significantly lower than in cultures irradiated at intervals of 4 h to 6 h; MBP levels remained depressed at DIC 21 for all irradiated cultures. The oligodendrocyte response to dose rate (0.03 to 1.97 Gy/min) was evaluated at DIC 14 and DIC 21. Exposure at 0.03 Gy/min suppressed oligodendrocyte counts at DIC 21 less than did higher dose rates in 5-Gy irradiated cultures

Doses of emergency exposure to the USSR Navy personnel

International Nuclear Information System (INIS)

Skaletskiy, Yuriy

2013-01-01

Radiological consequences of the Soviet Navy accidents are significant and the number of acute radiation syndrome (ARS) cases is comparable to the number of ARS cases to Chernobyl catastrophe witness and clean-up workers in 1986. Results of a careful clinical-epidemiological examination of the personnel overexposed in the Navy accidents not only have value of radiobiology and radiation medicine specialists but can become a basis for the evaluation of the effectiveness of social protection strategy for the Chernobyl catastrophe clean-up workers. The officially registered exposure doses to persons affected by the Navy radiation accidents in some cases differ from the actual ones due to the imperfections of radiation monitoring facilities at the time of accidents. There was a tendency of clinical overstatement of the exposure doses resulting in diagnosis of 1st degree of ARS to persons who received external doses lower than 0.75. In some cases even 0.2 Gy was overstated as ARS severity for 2nd, 3rd, and 4th degrees. Exposure doses to the affected by the Navy accidents and their ARS severity degrees were evaluated with rather good accuracy. The use of modern method and approaches to the retrospective dose assessment allows more accurate evaluation of the submarine personnel exposure doses as well as verification of every ARS case, thus creating a necessary dosimetric basis for the organization of a correct radiation epidemiological investigation for persons of this contingent. Regretfully, tragic experience of nuclear power plants operation at the Navy vessels was not subject to analysis of specialists in order to improve nuclear safety, radiation protection, and emergency response organization in order to nuclear energy use in the USSR. (N.T.)

Dose Response Model of Biological Reaction to Low Dose Rate Gamma Radiation

International Nuclear Information System (INIS)

Magae, J.; Furikawa, C.; Hoshi, Y.; Kawakami, Y.; Ogata, H.

2004-01-01

It is necessary to use reproducible and stable indicators to evaluate biological responses to long term irradiation at low dose-rate. They should be simple and quantitative enough to produce the results statistically accurate, because we have to analyze the subtle changes of biological responses around background level at low dose. For these purposes we chose micronucleus formation of U2OS, a human osteosarcoma cell line, as indicators of biological responses. Cells were exposed to gamma ray in irradiation rom bearing 50,000 Ci 60Co. After irradiation, they were cultured for 24 h in the presence of cytochalasin B to block cytokinesis, and cytoplasm and nucleus were stained with DAPI and prospidium iodide, respectively. the number of binuclear cells bearing micronuclei was counted under a fluorescence microscope. Dose rate in the irradiation room was measured with PLD. Dose response of PLD is linear between 1 mGy to 10 Gy, and standard deviation of triplicate count was several percent of mean value. We fitted statistically dose response curves to the data, and they were plotted on the coordinate of linearly scale response and dose. The results followed to the straight line passing through the origin of the coordinate axes between 0.1-5 Gy, and dose and does rate effectiveness factor (DDREF) was less than 2 when cells were irradiated for 1-10 min. Difference of the percent binuclear cells bearing micronucleus between irradiated cells and control cells was not statistically significant at the dose above 0.1 Gy when 5,000 binuclear cells were analyzed. In contrast, dose response curves never followed LNT, when cells were irradiated for 7 to 124 days. Difference of the percent binuclear cells bearing micronucleus between irradiated cells and control cells was not statistically significant at the dose below 6 Gy, when cells were continuously irradiated for 124 days. These results suggest that dose response curve of biological reaction is remarkably affected by exposure

A computerized assessment and response system for radiological emergency at Diablo Canyon Nuclear Power Plant

International Nuclear Information System (INIS)

Shih, C.C.; Thuillier, R.H.

1984-01-01

The U.S. Nuclear Regulatory Commission requires that nuclear power plants provide for rapid assessment and response in the event of a radiological emergency. At the Diablo Canyon Nuclear Power Plant, Pacific Gas and Electric Company uses a system of linked central minicomputer, satellite desktop computers and microprocessors to provide decision makers with timely and pertinent information in emergency situations. The system provides for data acquisition and microprocessing at meteorological and radiological monitoring sites. Current estimates or projections of offsite dose commitment are made in real-time by a dispersion/dose calculation model. Computerized dissemination of data and calculational results to decision makers at the government and utility levels is also available. The basic system in use is a commercially available Emergency Assessment and Response System (EARS). This generic system has been modified in-house to meet requirements specific to emergency situations at the plant. Distinctive features of the modification program includes: a highly professional man-machine interaction; consideration of site-specific factors; simulation of environmental radiology for development of drill scenarios; and concise, pertinent reports as input to decision making

Dose-response relationships for carcinogens: a review

International Nuclear Information System (INIS)

Zeise, L.; Wilson, R.; Crouch, E.A.C.

1987-01-01

The authors review the experimental evidence for various shapes of dose-response relationships for carcinogens and summarize those experiments that give the most information on relatively low doses. A brief review of some models is given to illustrate the shapes of dose-response curve expected from them. Their major interest is in the use of dose-response relationships to estimate risks to humans at low doses, and so they pay special attention to experimentally observed and theoretically expected nonlinearities. There are few experimental examples of nonlinear dose-response relations in humans, but this may simply be due to the limitations in the data. The several examples in rodents, even though for high dose data, suggest that nonlinearity is common. In some cases such nonlinearities may be rationalized on the basis of the pharmacokinetics of the test compound or its metabolites

Dose-response relationship in clinical oncology

International Nuclear Information System (INIS)

Gehan, E.A.

1984-01-01

The relationship of dose (and dose rate) to response and toxicity in clinical oncology is reviewed. The concepts expressed by some authors in dose-response studies in animal and human systems are reviewed briefly. Dose rate and tactics of conducting clinical studies are reviewed for both radiotherapy and various types of chemotherapeutic treatment. Examples are given from clinical studies in Hodgkin's disease, acute leukemia, and breast cancer that may prove useful in planning future clinical studies

AEROS: a real-time emergency response system for atmospheric releases of toxic material

International Nuclear Information System (INIS)

Nasstrom, J.S.; Greenly, G.D.

1986-01-01

The Atmospheric Release Advisory Capability (ARAC) at the Lawrence Livermore National Laboratory has developed a sophisticated computer-based real-time emergency response system for radiotoxic releases into the atmosphere. The ARAC Emergency Response Operating System (AEROS) has a centralized computer facility linked to remote site computers, meteorological towers, and meteorological data sources. The system supports certain fixed sites, but has the ability to respond to accidents at arbitrary locations. Product quality and response time are optimized by using complex three-dimensional dispersion models; extensive on-line data bases; automated data processing; and an efficient user interface, employing graphical computer displays and computer-displayed forms. Upon notification, the system automatically initiates a response to an emergency and proceeds through preliminary calculations, automatically processing accident information, meteorological data, and model parameters. The model calculations incorporate mass-consistent three-dimensional wind fields, terrain effects, and particle-in-cell diffusion. Model products are color images of dose or deposition contours overlaid on a base map

Touch screen man machine interfere for emergency dose calculations

International Nuclear Information System (INIS)

Woodard, K.; Abrams, M.

1987-01-01

Emergency dose calculation systems generally use a keyboard to provide the interface between the user and the computer. This interface is preferred by users who work daily with computers; however, for many plant personnel who are not continuously involved with computer operations, the use of a keyboard can be cumbersome and time consuming. This is particularly true when the user is under pressure during a drill or an actual emergency. Experience in many applications of Pickard, Lowe and Garrick's PLG's Meteorological Information and Dose Assessment System (MIDAS) has shown that user friendliness is a key ingredient toward achieving acceptance of computerized systems. Hardware to support to touch screen interface is now available and has been implemented in MIDAS. Recent experience has demonstrated that selection times for dose calculations are reduced, data entry errors have been minimized, and confusion over appropriate entries has been avoided due to the built-in logic. A 10-yr search for an acceptable keyboard replacement has ended

Transport accident emergency response plan

International Nuclear Information System (INIS)

Vallette-Fontaine, M.; Frantz, P.

1998-01-01

To comply with the IAEA recommendations for the implementation of an Emergency Response Plan as described in Safety Series 87, Transnucleaire, a company deeply involved in the road and rail transports of the fuel cycle, masters means of Emergency Response in the event of a transport accident. This paper aims at analyzing the solutions adopted for the implementation of an Emergency Response Plan and the development of a technical support and adapted means for the recovery of heavy packagings. (authors)

Emergency response workers workshop

International Nuclear Information System (INIS)

Agapeev, S.A.; Glukhikh, E.N.; Tyurin, R.L.

2012-01-01

A training workshop entitled Current issues and potential improvements in Rosatom Corporation emergency prevention and response system was held in May-June, 2012. The workshop combined theoretical training with full-scale practical exercise that demonstrated the existing innovative capabilities for radiation reconnaissance, diving equipment and robotics, aircraft, emergency response and rescue hardware and machinery. This paper describes the activities carried out during the workshop [ru

Generic procedures for medical response during a nuclear or radiological emergency. Emergency preparedness and response

International Nuclear Information System (INIS)

2005-04-01

The aim of this publication is to serve as a practical resource for planning the medical response to a nuclear or radiological emergency. It fulfils in part functions assigned to the IAEA under Article 5.a(ii) of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), namely, to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. Effective medical response is a necessary component of the overall response to nuclear or radiological (radiation) emergencies. In general, the medical response may represent a difficult challenge for the authorities due to the complexity of the situation, often requiring specialized expertise, and special organizational arrangements and materials. To be effective, adequate planning and preparedness are needed. This manual, if implemented, should help to contribute to coherent international response. The manual provides the practical tools and generic procedures for use by emergency medical personnel during an emergency situation. It also provides guidance to be used at the stage of preparedness for development of medical response capabilities. The manual also addresses mass casualty emergencies resulting from malicious acts involving radioactive material. This part was supported by the Nuclear Security Fund. The manual was developed based on a number of assumptions about national and local capabilities. Therefore, it must be reviewed and revised as part of the planning process to match the potential accidents, threats, local conditions and other unique characteristics of the facility where it may be used

Dose-projection considerations for emergency conditions at nuclear power plants

International Nuclear Information System (INIS)

Stoetzel, G.A.; Ramsdell, J.V.; Poeton, R.W.; Powell, D.C.; Desrosiers, A.E.

1983-05-01

The purpose of this report is to review the problems and issues associated with making environmental radiation-dose projections during emergencies at nuclear power plants. The review is divided into three areas: source-term development, characterization of atmospheric dispersion and selection of appropriate dispersion models, and development of dosimetry calculations for determining thyroid dose and whole-body dose for ground-level and elevated releases. A discussion of uncertainties associated with these areas is also provided

Dose-projection considerations for emergency conditions at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Stoetzel, G.A.; Ramsdell, J.V.; Poeton, R.W.; Powell, D.C.; Desrosiers, A.E.

1983-05-01

The purpose of this report is to review the problems and issues associated with making environmental radiation-dose projections during emergencies at nuclear power plants. The review is divided into three areas: source-term development, characterization of atmospheric dispersion and selection of appropriate dispersion models, and development of dosimetry calculations for determining thyroid dose and whole-body dose for ground-level and elevated releases. A discussion of uncertainties associated with these areas is also provided.

Biological responses to low dose rate gamma radiation

International Nuclear Information System (INIS)

Magae, Junji; Ogata, Hiromitsu

2003-01-01

Linear non-threshold (LNT) theory is a basic theory for radioprotection. While LNT dose not consider irradiation time or dose-rate, biological responses to radiation are complex processes dependent on irradiation time as well as total dose. Moreover, experimental and epidemiological studies that can evaluate LNT at low dose/low dose-rate are not sufficiently accumulated. Here we analyzed quantitative relationship among dose, dose-rate and irradiation time using chromosomal breakage and proliferation inhibition of human cells as indicators of biological responses. We also acquired quantitative data at low doses that can evaluate adaptability of LNT with statistically sufficient accuracy. Our results demonstrate that biological responses at low dose-rate are remarkably affected by exposure time, and they are dependent on dose-rate rather than total dose in long-term irradiation. We also found that change of biological responses at low dose was not linearly correlated to dose. These results suggest that it is necessary for us to create a new model which sufficiently includes dose-rate effect and correctly fits of actual experimental and epidemiological results to evaluate risk of radiation at low dose/low dose-rate. (author)

IAEA emergency response network ERNET. Emergency preparedness and response. Date effective: 1 December 2002

International Nuclear Information System (INIS)

2003-04-01

The Parties to the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency have undertaken to co-operate among themselves and with the IAEA in facilitating the prompt provision of assistance in the event of a nuclear accident or radiological emergency, and in minimizing the consequences and in protecting life, property and the environment from the effects of any radioactive releases. As part of the IAEA strategy for supporting such co-operation, the Secretariat of the IAEA is establishing a global Emergency Response Network (ERNET) of teams suitably qualified to respond rapidly, on a regional basis, to nuclear accidents or radiological emergencies. This manual sets out the criteria and requirements to be met by ERNET teams. It is intended for use by institutions in Member States in developing, applying and maintaining their emergency response capabilities and in implementing quality assurance programmes within the context of ERNET. The manual is worded on the assumption that a State Competent Authority designated as the body responsible for reacting to nuclear accidents or radiological emergencies which occur outside the jurisdiction of that State will be the State Contact Point for receiving requests for assistance from the IAEA under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency

IAEA emergency response network ERNET. Emergency preparedness and response. Date effective: 1 December 2000

International Nuclear Information System (INIS)

2000-12-01

The Parties to the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency have undertaken to co-operate among themselves and with the IAEA in facilitating the prompt provision of assistance in the event of a nuclear accident or radiological emergency, and in minimizing the consequences and in protecting life, property and the environment from the effects of any radioactive releases. As part of the IAEA strategy for supporting such co-operation, the Secretariat of the IAEA is establishing a global Emergency Response Network (ERNET) of teams suitably qualified to respond rapidly, on a regional basis, to nuclear accidents or radiological emergencies. This manual sets out the criteria and requirements to be met by ERNET teams. It is intended for use by institutions in Member States in developing, applying and maintaining their emergency response capabilities and in implementing quality assurance programmes within the context of ERNET. The manual is worded on the assumption that a State Competent Authority designated as the body responsible for reacting to nuclear accidents or radiological emergencies which occur outside the jurisdiction of that State will be the State Contact Point for receiving requests for assistance from the IAEA under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency

Emergency planning and response preparedness in Slovenia

International Nuclear Information System (INIS)

Martincic, R.; Frlin-Lubi, A.; Usenicnik, B.

2000-01-01

Disasters do occur and so do nuclear or radiological accidents. Experience has shown that advance emergency response preparedness is essential in order to mitigate the consequences of an accident. In Slovenia, the Civil Protection Organization is the responsible authority for emergency preparedness and response to any kind of disasters. The Krko Nuclear Power Plant is the only nuclear power plant in Slovenia. To date the plant has operated safely and no serious incidents have been recorded. Slovenia nevertheless, maintains a high level of emergency preparedness, which is reflected in the area of prevention and safety and in the area of emergency response preparedness. The emergency management system for nuclear emergencies is incorporated into an overall preparedness and response system. The paper presents an overview of nuclear or radiological emergency response preparedness in Slovenia and its harmonization with the international guidelines. (author)

Development of regional atmospheric dynamic and air pollution models for nuclear emergency response system WSPEEDI

International Nuclear Information System (INIS)

Furuno, Akiko; Yamazawa, Hiromi; Lee, Soon-Hwan; Tsujita, Yuichi; Takemiya, Hiroshi; Chino, Masamichi

2000-01-01

WSPEEDI (Worldwide version of System for Prediction of Environmental Emergency Dose Information) is a computer-based emergency response system to predict long-range atmospheric dispersion of radionuclides discharged into the atmosphere due to a nuclear accident. WSPEEDI has been applied to several international exercises and real events. Through such experiences, the new version of WSPEEDI aims to employ a combination of an atmospheric dynamic model and a particle random walk model for more accurate predictions. This paper describes these models, improvement of prediction and computational techniques for quick responses. (author)

Lessons Learned from the Response to Radiation Emergencies (1945-2010)

International Nuclear Information System (INIS)

2012-01-01

occurred, most notably, the Windscale fire in 1957, the Three Mile Island accident in 1979, the Chernobyl accident in 1986, the Sarov accident in 1997 and the Tokaimura accident in 1999. Radiological emergencies have occurred throughout the world, and when invited by the country concerned, the IAEA has undertaken comprehensive reviews of the events, the purpose of which is to compile information about the causes of the accidents, the subsequent emergency response including medical management, dose reconstruction, public communication, etc., so that any lessons can be shared with national authorities and regulatory organizations, emergency planners and a broad range of specialists, including physicists, technicians and medical specialists, and persons responsible for radiation protection. It is appropriate to analyze the findings of these and other reports on the response to radiation emergencies in order to consolidate these lessons.

Lessons Learned from the Response to Radiation Emergencies (1945-2010)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-08-15

occurred, most notably, the Windscale fire in 1957, the Three Mile Island accident in 1979, the Chernobyl accident in 1986, the Sarov accident in 1997 and the Tokaimura accident in 1999. Radiological emergencies have occurred throughout the world, and when invited by the country concerned, the IAEA has undertaken comprehensive reviews of the events, the purpose of which is to compile information about the causes of the accidents, the subsequent emergency response including medical management, dose reconstruction, public communication, etc., so that any lessons can be shared with national authorities and regulatory organizations, emergency planners and a broad range of specialists, including physicists, technicians and medical specialists, and persons responsible for radiation protection. It is appropriate to analyze the findings of these and other reports on the response to radiation emergencies in order to consolidate these lessons.

Equivalent dose determination in foraminifera: analytical description of the CO2--signal dose-response curve

International Nuclear Information System (INIS)

Hoffmann, D.; Woda, C.; Mangini, A.

2003-01-01

The dose-response of the CO 2 - signal (g=2.0006) in foraminifera with ages between 19 and 300 ka is investigated. The sum of two exponential saturation functions is an adequate function to describe the dose-response curve up to an additional dose of 8000 Gy. It yields excellent dating results but requires an artificial doses of at least 5000 Gy. For small additional doses of about 500 Gy the single exponential saturation function can be used to calculate a reliable equivalent dose D E , although it does not describ the dose-response for higher doses. The CO 2 - -signal dose-response indicates that the signal has two components of which one is less stable than the other

Application of Robotic System for Emergency Response in NPP

International Nuclear Information System (INIS)

Jeong, Kyung Min; Seo, Yong Chil; Shin, Ho Chul; Lee, Sung Uk; Cho, Jae Wan; Choi, Young Soo; Kim, Chang Hoi; Kim, Seung Ho

2010-01-01

Increasing energy demand and concerns over climate change make increasing use of nuclear power plant in worldwide. Even though the probability of accident is greatly reduced, safety is the highest priority issue in the nuclear energy industry. Applying highly reliable and conservative 'defense in depth' concepts with the design and construction of NPP, there are very little possibilities with which accidents are occur and radioactive materials are released to environments in NPP. But NPP have prepared with the emergency response procedures and conduct exercises for post-accident circumstance according to the procedures. The application of robots for emergency response task for post-accident in nuclear facilities is not a new concept. Robots have been sent to recover the damaged reactor at Chernobyl where human workers could receive a lifetime dose of radiation in minutes. Based on NRC's TMI-2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. The first robot was lowered into the basement through a hatch and human operators monitoring in a control room drove it through mud, water and debris, capturing the initial post-accident images of the reactor's basement. It was used for several years equipped with various tools allowing it to scour surfaces, scoop samples and vacuum sludge. A second version carried a core sampler to determine the intensity and depth of the radiation that had permeated into the walls. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extendable to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and obtaining remote

Application of Robotic System for Emergency Response in NPP

Energy Technology Data Exchange (ETDEWEB)

Jeong, Kyung Min; Seo, Yong Chil; Shin, Ho Chul; Lee, Sung Uk; Cho, Jae Wan; Choi, Young Soo; Kim, Chang Hoi; Kim, Seung Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-10-15

Increasing energy demand and concerns over climate change make increasing use of nuclear power plant in worldwide. Even though the probability of accident is greatly reduced, safety is the highest priority issue in the nuclear energy industry. Applying highly reliable and conservative 'defense in depth' concepts with the design and construction of NPP, there are very little possibilities with which accidents are occur and radioactive materials are released to environments in NPP. But NPP have prepared with the emergency response procedures and conduct exercises for post-accident circumstance according to the procedures. The application of robots for emergency response task for post-accident in nuclear facilities is not a new concept. Robots have been sent to recover the damaged reactor at Chernobyl where human workers could receive a lifetime dose of radiation in minutes. Based on NRC's TMI-2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. The first robot was lowered into the basement through a hatch and human operators monitoring in a control room drove it through mud, water and debris, capturing the initial post-accident images of the reactor's basement. It was used for several years equipped with various tools allowing it to scour surfaces, scoop samples and vacuum sludge. A second version carried a core sampler to determine the intensity and depth of the radiation that had permeated into the walls. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extendable to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and

Epidemiological methods for assessing dose-response and dose-effect relationships

DEFF Research Database (Denmark)

Kjellström, Tord; Grandjean, Philippe

2007-01-01

Selected Molecular Mechanisms of Metal Toxicity and Carcinogenicity General Considerations of Dose-Effect and Dose-Response Relationships Interactions in Metal Toxicology Epidemiological Methods for Assessing Dose-Response and Dose-Effect Relationships Essential Metals: Assessing Risks from Deficiency......Description Handbook of the Toxicology of Metals is the standard reference work for physicians, toxicologists and engineers in the field of environmental and occupational health. This new edition is a comprehensive review of the effects on biological systems from metallic elements...... access to a broad range of basic toxicological data and also gives a general introduction to the toxicology of metallic compounds. Audience Toxicologists, physicians, and engineers in the fields of environmental and occupational health as well as libraries in these disciplines. Will also be a useful...

Dose-response relationship with radiotherapy: an evidence?

International Nuclear Information System (INIS)

Chauvet, B.; Rauglaudre, G. de; Mineur, L.; Alfonsi, M.; Reboul, F.

2003-01-01

The dose-response relationship is a fundamental basis of radiobiology. Despite many clinical data, difficulties remain to demonstrate a relation between dose and local control: relative role of treatment associated with radiation therapy (surgery, chemotherapy, hormonal therapy), tumor heterogeneity, few prospective randomized studies, uncertainty of local control assessment. Three different situations are discussed: tumors with high local control probabilities for which dose effect is demonstrated by randomized studies (breast cancer) or sound retrospective data (soft tissues sarcomas), tumors with intermediate local control probabilities for which dose effect seems to be important according to retrospective studies and ongoing or published phase III trials (prostate cancer), tumors with low local control probabilities for which dose effect appears to be modest beyond standard doses, and inferior to the benefit of concurrent chemotherapy (lung and oesophageal cancer). For head and neck tumors, the dose-response relationship has been explored through hyperfractionation and accelerated radiation therapy and a dose effect has been demonstrated but must be compared to the benefit of concurrent chemotherapy. Last but not least, the development of conformal radiotherapy allow the exploration of the dose response relationship for tumors such as hepatocellular carcinomas traditionally excluded from the field of conventional radiation therapy. In conclusion, the dose-response relationship remains a sound basis of radiation therapy for many tumors and is a parameter to take into account for further randomized studies. (author)

Assessment of internal doses in emergency situations

Energy Technology Data Exchange (ETDEWEB)

Rahola, T.; Muikku, M. [Radiation and Nuclear Safety Authority - STUK (Finland); Falk, R.; Johansson, J. [Swedish Radiation Protection Authority - SSI (Sweden); Liland, A.; Thorshaug, S. [NRPA (Norway)

2006-04-15

The need for assessing internal radiation doses in emergency situations was demonstrated after accidents in Brazil, Ukraine and other countries. Lately more and more concern has been expressed regarding malevolent use of radiation and radioactive materials. The scenarios for such use are more difficult to predict than for nuclear power plant or weapons accidents. Much of the results of the work done in the IRADES project can be adopted for use in various accidental situations involving radionuclides that are not addressed in this report. If an emergency situation occurs in only one or a few of the Nordic countries, experts from the other countries could be called upon to assist in monitoring. A big advantage is then our common platform. In the Nordic countries much work has been put down on quality assurance of measurements and on training of dose assessment calculations. Attention to this was addressed at the internal dosimetry course in October 2005. Nordic emergency preparedness exercises have so far not included training of direct measurements of people in the early phase of an emergency. The aim of the IRADES project was to improve the preparedness especially for thyroid measurements. The modest financial support did not enable the participants to make big efforts but certainly acted as a much appreciated reminder of the importance of being prepared also to handle situations with malevolent use of radioactive materials. It was left to each country to decide to which extent to improve the practical skills. There is still a need for detailed national implementation plans. Measurement strategies need to be developed in each country separately taking into account national regulations, local circumstances and resources. End users of the IRADES report are the radiation protection authorities. (au)

Assessment of internal doses in emergency situations

International Nuclear Information System (INIS)

Rahola, T.; Muikku, M.; Falk, R.; Johansson, J.; Liland, A.; Thorshaug, S.

2006-04-01

The need for assessing internal radiation doses in emergency situations was demonstrated after accidents in Brazil, Ukraine and other countries. Lately more and more concern has been expressed regarding malevolent use of radiation and radioactive materials. The scenarios for such use are more difficult to predict than for nuclear power plant or weapons accidents. Much of the results of the work done in the IRADES project can be adopted for use in various accidental situations involving radionuclides that are not addressed in this report. If an emergency situation occurs in only one or a few of the Nordic countries, experts from the other countries could be called upon to assist in monitoring. A big advantage is then our common platform. In the Nordic countries much work has been put down on quality assurance of measurements and on training of dose assessment calculations. Attention to this was addressed at the internal dosimetry course in October 2005. Nordic emergency preparedness exercises have so far not included training of direct measurements of people in the early phase of an emergency. The aim of the IRADES project was to improve the preparedness especially for thyroid measurements. The modest financial support did not enable the participants to make big efforts but certainly acted as a much appreciated reminder of the importance of being prepared also to handle situations with malevolent use of radioactive materials. It was left to each country to decide to which extent to improve the practical skills. There is still a need for detailed national implementation plans. Measurement strategies need to be developed in each country separately taking into account national regulations, local circumstances and resources. End users of the IRADES report are the radiation protection authorities. (au)

Radiological emergency: Malaysian preparedness and response

International Nuclear Information System (INIS)

Yusof, M. A. W.; Ali, H. M.

2011-01-01

Planning and preparation in advance for radiological emergencies can help to minimise potential public health and environmental threats if and when an actual emergency occurs. During the planning process, emergency response organisations think through how they would respond to each type of incident and the resources that will be needed. In Malaysia, planning, preparation for and response to radiological emergencies involve many parties. In the event of a radiological emergency and if it is considered a disaster, the National Security Council, the Atomic Energy Licensing Board and the Malaysian Nuclear Agency (Nuclear Malaysia) will work together with other federal agencies, state and local governments, first responders and international organisations to monitor the situation, contain the release, and clean up the contaminated site. Throughout the response, these agencies use their protective action guidelines. This paper discusses Malaysian preparedness for, and response to, any potential radiological emergency. (authors)

The Brazilian emergency response system

International Nuclear Information System (INIS)

Santos, Raul dos

1997-01-01

With the objective of improving the response actions to potential or real emergency situations generated by radiological or nuclear accidents, the Brazilian National Nuclear Energy Commission (CNEN) installed an integrated response system on a 24 hours basis. All the natiowide notifications on events that may start an emergency situation are converged to this system. Established since July 1990, this system has received around 300 notifications in which 5% were classified as potential emergency situation. (author)

Differences in activity concentrations and doses between domestic and commercial food production in England and Wales. Implications for nuclear emergency response

International Nuclear Information System (INIS)

Prosser, S.; Brown, J.; Smith, J.

1999-10-01

In the event of an accidental release of radionuclides into the environment, MAFF has a statutory responsibility to ensure that a wholesome and safe food supply is maintained to the population of England. MAFF also provides scientific advice on contamination of food by radioactivity to the Welsh Assembly and the Scottish Executive. This responsibility will apply whatever the source of radioactive contamination. Where foods are produced domestically by individuals, i.e. in private gardens and allotments, MAFF has no statutory powers to prevent their harvest or consumption. MAFF must therefore rely solely upon the provision of appropriate advice to protect those domestic producers potentially at risk. Advice which has been issued to such individuals and households during past nuclear emergency exercises has been based on assessments carried out for commercially produced foods. Under contract to MAFF, NRPB has undertaken a desk-top study to review the adequacy of the current MAFF emergency procedures for protecting consumers of foods produced domestically. In particular, the study has examined the validity of basing advice for domestic consumers on commercial food production and consumption, rather than by explicitly considering the domestic situation. As part of the study, reviews have been carried out of the level and types of domestic food production and consumption in the UK. In addition, comparisons have been made between agricultural practices in commercial and domestic situations. The data from these reviews have subsequently been used to compare the doses received by individuals from consuming contaminated foods from commercial and domestic sources. The study has concluded that, in general, the current MAFF emergency procedures for protecting the domestic consumer are adequate. In the event of an accident occurring some factors may need more consideration, however. These include differences in growing periods and harvesting dates between commercial and

Medical Preparedness and Response for a Nuclear or Radiological Emergency. Training Materials

International Nuclear Information System (INIS)

2014-01-01

Syndrome (Local Radiation Injury); • Cytogenetic Dose Assessments; • Psychological Effects of Radiation Emergencies; • Psychosocial Aspects in Radiation Emergencies • Use of Detection Equipment; • Communication with the Public; • International Emergency Preparedness and Response Framework; • Medical Management On-site and at Pre-hospital Levels; • Hospital Preparedness and Management of Persons Accidentally Exposed to Ionizing Radiation; • Iodine Thyroid Blocking and Other Response Actions; • Lessons Learned from Past Nuclear and Radiological Emergencies. The information is presented in the form of lectures and supplementary materials for drills and tabletop exercises, including a sample triage tag and victim cards. In addition, the CD-ROM contains information on frequently asked questions and suggested answers, a basic and an advanced pre-test, a review test and pocket guides for medical responders at pre-hospital and hospital levels

Initial operations in local nuclear emergency response headquarter

International Nuclear Information System (INIS)

2012-06-01

As a result of the Fukushima nuclear accident due to the Great East Japan Earthquake and the tsunami that occurred thereafter, local nuclear emergency response headquarters (local headquarters) was set up at off-site center (OFC). However, several obstacles such as the collapse of means of communication resulting from severed communication lines, food and fuel shortage resulting from stagnant physical distribution, and increasing radiation dose around the center significantly restricted originally intended operation of local headquarters. In such severe situation, the personnel gathered at the OFC from the government, local public bodies and electric companies from March 11 to 15 acted without sufficient food, sleep or rest and did all they could against successively occurring unexpected challenges by using limited means of communication. However, issues requiring further consideration were activities of each functional group, location of OFC and the functions of equipment, machines and materials and reflecting the consideration results into future protective measures and revision of the manual for nuclear emergency response were greatly important. This report described investigated results on initial operations in local headquarters such as situation of activities conducted by local headquarters and operations at functional groups. (T. Tanaka)

Radiological emergency response - a functional approach

International Nuclear Information System (INIS)

Chowdhury, P.

1998-01-01

The state of Louisiana's radiological emergency response programme is based on the federal guidance 'Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants' (NUREG-0654, FEMA-REP-1 Rev. 1). Over the past 14 years, the planning and implementation of response capabilities became more organized and efficient; the training programme has strengthened considerably; co-ordination with all participating agencies has assumed a more co-operative role, and as a result, a fairly well integrated response planning has evolved. Recently, a more 'functional' approach is being adopted to maximize the programme's efficiency not only for nuclear power plant emergency response, but radiological emergency response as a whole. First, several broad-based 'components' are identified; clusters of 'nodes' are generated for each component; these 'nodes' may be divided into 'sub-nodes' which will contain some 'attributes'; 'relational bonds' among the 'attributes' will exist. When executed, the process begins and continues with the 'nodes' assuming a functional and dynamic role based on the nature and characteristics of the 'attributes'. The typical response based on stand-alone elements is thus eliminated, the overlapping of functions is avoided, and a well structured and efficient organization is produced, that is essential for today's complex nature of emergency response. (author)

Quantitative analysis of biological responses to low dose-rate γ-radiation, including dose, irradiation time, and dose-rate

International Nuclear Information System (INIS)

Magae, J.; Furukawa, C.; Kawakami, Y.; Hoshi, Y.; Ogata, H.

2003-01-01

Full text: Because biological responses to radiation are complex processes dependent on irradiation time as well as total dose, it is necessary to include dose, dose-rate and irradiation time simultaneously to predict the risk of low dose-rate irradiation. In this study, we analyzed quantitative relationship among dose, irradiation time and dose-rate, using chromosomal breakage and proliferation inhibition of human cells. For evaluation of chromosome breakage we assessed micronuclei induced by radiation. U2OS cells, a human osteosarcoma cell line, were exposed to gamma-ray in irradiation room bearing 50,000 Ci 60 Co. After the irradiation, they were cultured for 24 h in the presence of cytochalasin B to block cytokinesis, cytoplasm and nucleus were stained with DAPI and propidium iodide, and the number of binuclear cells bearing micronuclei was determined by fluorescent microscopy. For proliferation inhibition, cells were cultured for 48 h after the irradiation and [3H] thymidine was pulsed for 4 h before harvesting. Dose-rate in the irradiation room was measured with photoluminescence dosimeter. While irradiation time less than 24 h did not affect dose-response curves for both biological responses, they were remarkably attenuated as exposure time increased to more than 7 days. These biological responses were dependent on dose-rate rather than dose when cells were irradiated for 30 days. Moreover, percentage of micronucleus-forming cells cultured continuously for more than 60 days at the constant dose-rate, was gradually decreased in spite of the total dose accumulation. These results suggest that biological responses at low dose-rate, are remarkably affected by exposure time, that they are dependent on dose-rate rather than total dose in the case of long-term irradiation, and that cells are getting resistant to radiation after the continuous irradiation for 2 months. It is necessary to include effect of irradiation time and dose-rate sufficiently to evaluate risk

ANSI/ANS-8.23-1997: nuclear criticality accident emergency planning and response

International Nuclear Information System (INIS)

Baker, J.S.

2004-01-01

for improvements to increase the usefulness of this standard are being solicited. The Working Group currently has ten members and is drafting a revision of ANSI/ANS-8.23. The focus of this effort is to include additional technical guidance on the following topics: (1) Recommendations for radiation monitoring instruments that may be used during an emergency response to a criticality accident; (2) Recommended resources for a criticality safety specialist during an emergency response to a criticality accident; (3) An example showing how to construct an emergency exercise for a fissile material processing facility. This includes: (a) Estimating the fission source term based on a credible accident scenario; (b) Estimating doses to nearby personnel; (c) Estimating doses to rescuers; (d) A discussion of evacuation and rescue considerations; (e) A review of dosimetry and medical response issues; and (f) Recommendations for the conduct of drills and exercises. This additional guidance will be contained in appendices to the revised standard. In addition, the revised standard will include a reference to an extensive bibliography of resources for emergency planning. The first revision of ANSI/ANS-8.23 should be provided to ANS-8 for ballot by the fall of 2004.

ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

International Nuclear Information System (INIS)

Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

2009-01-01

Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

International Nuclear Information System (INIS)

Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

2008-01-01

Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

48 CFR 452.236-77 - Emergency Response.

Science.gov (United States)

2010-10-01

... contracts: Emergency Response (NOV 1996) (a) Contractor's Responsibility for Fire Fighting. (1) The... emergency work (anticipated to be restricted to fire fighting). An equitable adjustment for the temporary... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Emergency Response. 452...

Mathematical model for evaluation of dose-rate effect on biological responses to low dose γ-radiation

International Nuclear Information System (INIS)

Ogata, H.; Kawakami, Y.; Magae, J.

2003-01-01

Full text: To evaluate quantitative dose-response relationship on the biological response to radiation, it is necessary to consider a model including cumulative dose, dose-rate and irradiation time. In this study, we measured micronucleus formation and [ 3 H] thymidine uptake in human cells as indices of biological response to gamma radiation, and analyzed mathematically and statistically the data for quantitative evaluation of radiation risk at low dose/low dose-rate. Effective dose (ED x ) was mathematically estimated by fitting a general function of logistic model to the dose-response relationship. Assuming that biological response depends on not only cumulative dose but also dose-rate and irradiation time, a multiple logistic function was applied to express the relationship of the three variables. Moreover, to estimate the effect of radiation at very low dose, we proposed a modified exponential model. From the results of fitting curves to the inhibition of [ 3 H] thymidine uptake and micronucleus formation, it was obvious that ED 50 in proportion of inhibition of [ 3 H] thymidine uptake increased with longer irradiation time. As for the micronuclei, ED 30 also increased with longer irradiation times. These results suggest that the biological response depends on not only total dose but also irradiation time. The estimated response surface using the three variables showed that the biological response declined sharply when the dose-rate was less than 0.01 Gy/h. These results suggest that the response does not depend on total cumulative dose at very low dose-rates. Further, to investigate the effect of dose-rate within a wider range, we analyzed the relationship between ED x and dose-rate. Fitted curves indicated that ED x increased sharply when dose-rate was less than 10 -2 Gy/h. The increase of ED x signifies the decline of the response or the risk and suggests that the risk approaches to 0 at infinitely low dose-rate

Land Transport Emergency Response Technology Report

International Nuclear Information System (INIS)

DOTSON, LORI J.; PIERCE, JIM D.

2003-01-01

Sandia National Laboratories was tasked by the Japan Nuclear Cycle Development Institute (JNC) to provide assistance in developing an emergency response plan for radioactive material transportation activities. Those tasks included compiling radioactive materials (RAM) transportation accident data FR-om the open literature and databases, investigating emergency response plans for radioactive materials transport in the United States, and developing specific recommendations for the JNC' nuclear material transport emergency response plan, based on information gathered during the first two tasks. These recommendations include developing a RAM database, a public transparency Internet website, an emergency response inFR-astructure designed specifically for transportation needs, and a clear set of directives to provide authority in the case of transportation accidents or incidents involving RAM

MONTEC, an interactive fortran program to simulate radiation dose and dose-rate responses of populations

International Nuclear Information System (INIS)

Perry, K.A.; Szekely, J.G.

1983-09-01

The computer program MONTEC was written to simulate the distribution of responses in a population whose members are exposed to multiple radiation doses at variable dose rates. These doses and dose rates are randomly selected from lognormal distributions. The individual radiation responses are calculated from three equations, which include dose and dose-rate terms. Other response-dose/rate relationships or distributions can be incorporated by the user as the need arises. The purpose of this documentation is to provide a complete operating manual for the program. This version is written in FORTRAN-10 for the DEC system PDP-10

Using principles from emergency management to improve emergency response plans for research animals.

Science.gov (United States)

Vogelweid, Catherine M

2013-10-01

Animal research regulatory agencies have issued updated requirements for emergency response planning by regulated research institutions. A thorough emergency response plan is an essential component of an institution's animal care and use program, but developing an effective plan can be a daunting task. The author provides basic information drawn from the field of emergency management about best practices for developing emergency response plans. Planners should use the basic principles of emergency management to develop a common-sense approach to managing emergencies in their facilities.

Radiation Dose-Response Relationships and Risk Assessment

International Nuclear Information System (INIS)

Strom, Daniel J.

2005-01-01

The notion of a dose-response relationship was probably invented shortly after the discovery of poisons, the invention of alcoholic beverages, and the bringing of fire into a confined space in the forgotten depths of ancient prehistory. The amount of poison or medicine ingested can easily be observed to affect the behavior, health, or sickness outcome. Threshold effects, such as death, could be easily understood for intoxicants, medicine, and poisons. As Paracelsus (1493-1541), the 'father' of modern toxicology said, 'It is the dose that makes the poison.' Perhaps less obvious is the fact that implicit in such dose-response relationships is also the notion of dose rate. Usually, the dose is administered fairly acutely, in a single injection, pill, or swallow; a few puffs on a pipe; or a meal of eating or drinking. The same amount of intoxicants, medicine, or poisons administered over a week or month might have little or no observable effect. Thus, before the discovery of ionizing radiation in the late 19th century, toxicology ('the science of poisons') and pharmacology had deeply ingrained notions of dose-response relationships. This chapter demonstrates that the notion of a dose-response relationship for ionizing radiation is hopelessly simplistic from a scientific standpoint. While useful from a policy or regulatory standpoint, dose-response relationships cannot possibly convey enough information to describe the problem from a quantitative view of radiation biology, nor can they address societal values. Three sections of this chapter address the concepts, observations, and theories that contribute to the scientific input to the practice of managing risks from exposure to ionizing radiation. The presentation begins with irradiation regimes, followed by responses to high and low doses of ionizing radiation, and a discussion of how all of this can inform radiation risk management. The knowledge that is really needed for prediction of individual risk is presented

Hormesis: from marginalization to mainstream A case for hormesis as the default dose-response model in risk assessment

International Nuclear Information System (INIS)

Calabrese, Edward J.

2004-01-01

The paper provides an account of how the hormetic dose response has emerged in recent years as a serious dose-response model in toxicology and risk assessment after decades of extreme marginalization. In addition to providing the toxicological basis of this dose-response revival, the paper reexamines the concept of a default dose model in toxicology and risk assessment and makes the argument that the hormetic model satisfies criteria (e.g., generalizability, frequency, application to risk assessment endpoints, false positive/negative potential, requirements for hazard assessment, reliability of estimating risks, capacity for validation of risk estimates, public health implications of risk estimates) for such a default model better than its chief competitors, the threshold and linear at low dose models. The selection of the hormetic model as the default model in risk assessment for noncarcinogens and specifically for carcinogens would have a profound impact on the practice of risk assessment and its societal implications

Southern states radiological emergency response laws and regulations

International Nuclear Information System (INIS)

1990-06-01

The purpose of this report is to provide a summary of the emergency response laws and regulations in place in the various states within the southern region for use by legislators, emergency response planners, the general public and all persons concerned about the existing legal framework for emergency response. SSEB expects to periodically update the report as necessary. Radiation protection regulations without emergency response provisions are not included in the summary. The radiological emergency response laws and regulations of the Southern States Energy Compact member states are in some cases disparate. Several states have very specific laws on radiological emergency response while in others, the statutory law mentions only emergency response to ''natural disasters.'' Some states have adopted extensive regulations on the topic, others have none. For this reason, any general overview must necessarily discuss laws and regulations in general terms. State-by-state breakdowns are given for specific states

Nuclear accident/radiological emergency assistance plan. NAREAP - edition 2000. Emergency preparedness and response

International Nuclear Information System (INIS)

2000-01-01

The purpose of the Nuclear Accident/Radiological Emergency Assistance Plan (NAREAP) is to describe the framework for systematic, integrated, co-ordinated, and effective preparedness and response for a nuclear accident or radiological emergency involving facilities or practices that may give rise to a threat to health, the environment or property. The purpose of the NAREAP is: to define the emergency response objectives of the Agency's staff in a nuclear accident or a radiological emergency; to assign responsibilities for performing the tasks and authorities for making the decisions that comprise the Agency staff's response to a nuclear accident or radiological emergency; to guide the Agency managers who must ensure that all necessary tasks are given the necessary support in discharging the Agency staff responsibilities and fulfilling its obligations in response to an emergency; to ensure that the development and maintenance of detailed and coherent response procedures are well founded; to act as a point of reference for individual Agency staff members on their responsibilities (as an individual or a team member) throughout a response; to identify interrelationships with other international intergovernmental Organizations; and to serve as a training aid to maintain readiness of personnel. The NAREAP refers to the arrangements of the International Atomic Energy Agency and of the United Nations Security and Safety Section at the Vienna International Centre (UNSSS-VIC) that may be necessary for the IAEA to respond to a nuclear accident or radiological emergency, as defined in the Early Notification and Assistance Conventions. It covers response arrangements for any situation that may have actual, potential or perceived radiological consequences and that could require a response from the IAEA, as well as the arrangements for developing, maintaining and exercising preparedness. The implementing procedures themselves are not included in the NAREAP, but they are required

Basic data of emergency response centre

International Nuclear Information System (INIS)

Jenieek, O.

1995-01-01

Emergency Response Centre (ERC) of Czech Republic is a highly specialized institution belonging to Nuclear Safety State Administration (SONS), which assures its activities both organizationally and technically. Main function of the ERC in the case of nuclear emergency is to fulfil the needs of SONS, Governmental Committee for Nuclear Emergencies in ER (GCNE ER) and the regional organs of State Authorities concerning the emergency planning and preparedness, evaluation of nuclear emergency consequences, including the emergency management and response. In the case of major failure or accident on NPP, the ERC carries out the performance analysis and review of a given NPP. It also monitors the dosimetric situation and transfers the recommendation to GCNE ER, Regional Emergency Management Committees and to NPP

Dose-response characteristics of an amorphous silicon EPID

International Nuclear Information System (INIS)

Winkler, Peter; Hefner, Alfred; Georg, Dietmar

2005-01-01

Electronic portal imaging devices (EPIDs) were originally developed for the purpose of patient setup verification. Nowadays, they are increasingly used as dosimeters (e.g., for IMRT verification and linac-specific QA). A prerequisite for any clinical dosimetric application is a detailed understanding of the detector's dose-response behavior. The aim of this study is to investigate the dosimetric properties of an amorphous silicon EPID (Elekta IVIEWGT) with respect to three photon beam qualities: 6, 10, and 25 MV. The EPID showed an excellent temporal stability on short term as well as on long term scales. The stability throughout the day was strongly influenced by warming up, which took several hours and affected EPID response by 2.5%. Ghosting effects increased the sensitivity of the EPID. They became more pronounced with decreasing time intervals between two exposures as well as with increasing dose. Due to ghosting, changes in pixel sensitivity amounted up to 16% (locally) for the 25 MV photon beam. It was observed that the response characteristics of our EPID depended on dose as well as on dose rate. Doubling the dose rate increased the EPID sensitivity by 1.5%. This behavior was successfully attributed to a dose per frame effect, i.e., a nonlinear relationship between the EPID signal and the dose which was delivered to the panel between two successive readouts. The sensitivity was found to vary up to 10% in the range of 1 to 1000 monitor units. This variation was governed by two independent effects. For low doses, the EPID signal was reduced due to the linac's changing dose rate during startup. Furthermore, the detector reading was influenced by intrabeam variations of EPID sensitivity, namely, an increase of detector response during uniform exposure. For the beam qualities which were used, the response characteristics of the EPID did not depend on energy. Differences in relative dose-response curves resulted from energy dependent temporal output

Environmental and emergency response capabilities of Los Alamos Scientific Laboratory's radiological air sampling program

International Nuclear Information System (INIS)

Gunderson, T.C.

1980-05-01

Environmental and emergency response radiological air sampling capabilities of the Environmental Surveillance Group at Los Alamos Scientific Laboratory are described. The air sampling program provides a supplementary check on the adequacy of containment and effluent controls, determines compliance with applicable protection guides and standards, and assesses potential environmental impacts on site environs. It also allows evaluation of potential individual and total population doses from airborne radionuclides that may be inhaled or serve as a source of external radiation. The environmental program is sufficient in scope to detect fluctuations and long-term trends in atmospheric levels of radioactivity originating onsite. The emergency response capabilities are designed to respond to both onsite unplanned releases and atmospheric nuclear tests

Adaptive workflow simulation of emergency response

NARCIS (Netherlands)

Bruinsma, Guido Wybe Jan

2010-01-01

Recent incidents and major training exercises in and outside the Netherlands have persistently shown that not having or not sharing information during emergency response are major sources of emergency response inefficiency and error, and affect incident mitigation outcomes through workflow planning

Radiation emergency response in Illinois, Alabama, and Texas

International Nuclear Information System (INIS)

Larsen, D.K.; Chester, R.O.

1978-03-01

The objective of this study was to examine state radiation emergency response and to locate any areas of emergency planning in need of improvement. This report briefly presents a summary of laws and defining documents governing radiation emergency response, describes the existing and projected need for such response, and presents the authors' analyses of the evolution of state response plans and their application to radiation incidents. Three states' programs are discussed in detail: Illinois, Alabama, and Texas. These states were selected because they have quite different emergency-response programs. Therefore, these state programs provide a wide variety of approaches to state radiation emergency response

Emergency planning and response - role nad responsibilities of the regulatory body

International Nuclear Information System (INIS)

Nizamska, M.

1999-01-01

The development of a emergency plan and organisation of adequate emergency preparedness in case of radiological accident in NPP cannot be effective without the appropriate preparatory work. In most countries, also in Republic of Bulgaria, several organisations are identified to have a potential role to play in a radiological emergency. For these reason is very important to have a national organisation, with a mandate to organise, inspect and co-ordinate the possibility of ministries and institution to react in case of radiological emergency, i.e. to quarantine the possibility for implementation of adequate counter measure for protection of the population and environment in case of radiological emergency in NPP. For the purposes of the emergency planning and response the NPP operator, ministries and the institutions developed an Emergency plan - NPP Emergency Plan and National Emergency Plan. The development of the emergency plans will be impossible without the good co-operation of the organisations which have a responsibilities in a radiological emergency. Once emergency plans are adopted, each individual organisation, also the NPP operator, must ensure that in can carry out its role effectively in accordance with the emergency plan and can develop the appropriate organisation for action and implementation of protection counter measures. For testing the emergency plans a regular exercise must be organised. Periodic reviews of the plan and modifications, based on actual events and exercise experience must be performed. The main aim of these report is to present the Bulgarian emergency planning organisation and response by explaining the national emergency panning and response legislation, implementation of IAEA recommendations and exercise experience

Statistical and low dose response

International Nuclear Information System (INIS)

Thorson, M.R.; Endres, G.W.R.

1981-01-01

The low dose response and the lower limit of detection of the Hanford dosimeter depend upon may factors, including the energy of the radiation, whether the exposure is to be a single radiation or mixed fields, annealing cycles, environmental factors, and how well various batches of TLD materials are matched in the system. A careful statistical study and sensitivity analysis were performed to determine how these factors influence the response of the dosimeter system. Estimates have been included in this study of the standard deviation of calculated dose for various mixed field exposures from 0 to 1000 mrem

A unique manual method for emergency offsite dose calculations

International Nuclear Information System (INIS)

Wildner, T.E.; Carson, B.H.; Shank, K.E.

1987-01-01

This paper describes a manual method developed for performance of emergency offsite dose calculations for PP and L's Susquehanna Steam Electric Station. The method is based on a three-part carbonless form. The front page guides the user through selection of the appropriate accident case and inclusion of meteorological and effluent data data. By circling the applicable accident descriptors, the user circles the dose factors on pages 2 and 3 which are then simply multiplied to yield the whole body and thyroid dose rates at the plant boundary, two, five, and ten miles. The process used to generate the worksheet is discussed, including the method used to incorporate the observed terrain effects on airflow patterns caused by the Susquehanna River Valley topography

Update of the Nuclear Criticality Slide Rule for the Emergency Response to a Nuclear Criticality Accident

Science.gov (United States)

Duluc, Matthieu; Bardelay, Aurélie; Celik, Cihangir; Heinrichs, Dave; Hopper, Calvin; Jones, Richard; Kim, Soon; Miller, Thomas; Troisne, Marc; Wilson, Chris

2017-09-01

AWE (UK), IRSN (France), LLNL (USA) and ORNL (USA) began a long term collaboration effort in 2015 to update the nuclear criticality Slide Rule for the emergency response to a nuclear criticality accident. This document, published almost 20 years ago, gives order of magnitude estimates of key parameters, such as number of fissions and doses (neutron and gamma), useful for emergency response teams and public authorities. This paper will present, firstly the motivation and the long term objectives for this update, then the overview of the initial configurations for updated calculations and preliminary results obtained with modern 3D codes.

Update of the Nuclear Criticality Slide Rule for the Emergency Response to a Nuclear Criticality Accident

Directory of Open Access Journals (Sweden)

Duluc Matthieu

2017-01-01

Full Text Available AWE (UK, IRSN (France, LLNL (USA and ORNL (USA began a long term collaboration effort in 2015 to update the nuclear criticality Slide Rule for the emergency response to a nuclear criticality accident. This document, published almost 20 years ago, gives order of magnitude estimates of key parameters, such as number of fissions and doses (neutron and gamma, useful for emergency response teams and public authorities. This paper will present, firstly the motivation and the long term objectives for this update, then the overview of the initial configurations for updated calculations and preliminary results obtained with modern 3D codes.

Single toxin dose-response models revisited

Energy Technology Data Exchange (ETDEWEB)

Demidenko, Eugene, E-mail: eugened@dartmouth.edu [Department of Biomedical Data Science, Geisel School of Medicine at Dartmouth, Hanover, NH03756 (United States); Glaholt, SP, E-mail: sglaholt@indiana.edu [Indiana University, School of Public & Environmental Affairs, Bloomington, IN47405 (United States); Department of Biological Sciences, Dartmouth College, Hanover, NH03755 (United States); Kyker-Snowman, E, E-mail: ek2002@wildcats.unh.edu [Department of Natural Resources and the Environment, University of New Hampshire, Durham, NH03824 (United States); Shaw, JR, E-mail: joeshaw@indiana.edu [Indiana University, School of Public & Environmental Affairs, Bloomington, IN47405 (United States); Chen, CY, E-mail: Celia.Y.Chen@dartmouth.edu [Department of Biological Sciences, Dartmouth College, Hanover, NH03755 (United States)

2017-01-01

The goal of this paper is to offer a rigorous analysis of the sigmoid shape single toxin dose-response relationship. The toxin efficacy function is introduced and four special points, including maximum toxin efficacy and inflection points, on the dose-response curve are defined. The special points define three phases of the toxin effect on mortality: (1) toxin concentrations smaller than the first inflection point or (2) larger then the second inflection point imply low mortality rate, and (3) concentrations between the first and the second inflection points imply high mortality rate. Probabilistic interpretation and mathematical analysis for each of the four models, Hill, logit, probit, and Weibull is provided. Two general model extensions are introduced: (1) the multi-target hit model that accounts for the existence of several vital receptors affected by the toxin, and (2) model with a nonzero mortality at zero concentration to account for natural mortality. Special attention is given to statistical estimation in the framework of the generalized linear model with the binomial dependent variable as the mortality count in each experiment, contrary to the widespread nonlinear regression treating the mortality rate as continuous variable. The models are illustrated using standard EPA Daphnia acute (48 h) toxicity tests with mortality as a function of NiCl or CuSO{sub 4} toxin. - Highlights: • The paper offers a rigorous study of a sigmoid dose-response relationship. • The concentration with highest mortality rate is rigorously defined. • A table with four special points for five morality curves is presented. • Two new sigmoid dose-response models have been introduced. • The generalized linear model is advocated for estimation of sigmoid dose-response relationship.

Development of a health and safety manual for emergency response operations

International Nuclear Information System (INIS)

Riland, C.A.; Junio, S.S.

2000-01-01

The Federal Radiological Monitoring and Assessment Center (FRMAC) Health and Safety Manual, which has been under development by a multi-agency group, is nearing completion and publication. The manual applies to offsite monitoring during a radiological accident or incident. Though written for multi-agency offsite monitoring activities (FRMAC), the manual is generic in nature and should be readily adaptable for other emergency response operations. Health and safety issues for emergency response situations often differ from those of normal operations. Examples of these differences and methodologies to address these issues are discussed. Challenges in manual development, including lack of regulatory and guidance documentation, are also discussed. One overriding principle in the Health and Safety Manual development is the overall reduction of risk, not just dose. The manual is broken into several chapters, which include Overview of Responsibities, Health Physics, Industrial Hygiene and Safey, Medical, and Environmental Compliance and Records. Included is a series of appendices, which presents additional information on forms and plans for default scenarios

Southern states radiological emergency response laws and regulations

International Nuclear Information System (INIS)

1989-07-01

The purpose of this report is to provide a summary of the emergency response laws and regulations in place in the various states within the southern region for use by legislators, emergency response planners, the general public and all persons concerned about the existing legal framework for emergency response. SSEB expects to periodically update the report as necessary. Radiation protection regulations without emergency response provisions are not included in the summary

The TransPetro emergency response system

Energy Technology Data Exchange (ETDEWEB)

Filho, A.T.F.; Cardoso, V.F.; Carbone, R.; Berardinelli, R.P. [Petrobras-TransPetro, Rio de Janeiro (Brazil); Carvalho, M.T.M.; Casanova, M.A. [Pontificia Univ. Catolica, Rio de Janeiro (Brazil). Dept. de Informatica, TeCGraf

2004-07-01

Petrobras-TransPetro developed the TransPetro Emergency Response System in response to emergency situations at large oil pipelines or at terminal facilities located in sea or river harbour areas. The standard of excellence includes full compliance with environmental regulations set by the federal government. A distributed workflow management software called InfoPAE forms the basis of the system in which actions are defined, along with geographic and conventional data. The first prototype of InfoPAE was installed in 1999. Currently it is operational in nearly 80 installations. The basic concepts and functionality of the TransPetro Emergency Response System were outlined in this paper with reference to the mitigative actions that are based on an evaluation of the organization of the emergency teams; the communication procedures; characterization of the installations; definition of accidental scenarios; environmental sensitivity maps; simulation of oil spill trajectories and dispersion behaviour; geographical data of the area surrounding the installations; and, other conventional data related to the installations, including available equipment. The emergency response team can take action as soon as an accident is detected. The action plan involves characterizing several scenarios and delegating mitigative actions to specific sub-teams, each with access to geographic data on the region where the emergency occurred. 13 refs., 3 figs.

ARAC: a computer-based emergency dose-assessment service

International Nuclear Information System (INIS)

Sullivan, T.J.

1990-01-01

Over the past 15 years, the Lawrence Livermore National Laboratory's Atmospheric Release Advisory Capability (ARAC) has developed and evolved a computer-based, real-time, radiological-dose-assessment service for the United States Departments of Energy and Defense. This service is built on the integrated components of real-time computer-acquired meteorological data, extensive computer databases, numerical atmospheric-dispersion models, graphical displays, and operational-assessment-staff expertise. The focus of ARAC is the off-site problem where regional meteorology and topography are dominant influences on transport and dispersion. Through application to numerous radiological accidents/releases on scales from small accidental ventings to the Chernobyl reactor disaster, ARAC has developed methods to provide emergency dose assessments from the local to the hemispheric scale. As the power of computers has evolved inversely with respect to cost and size, ARAC has expanded its service and reduced the response time from hours to minutes for an accident within the United States. Concurrently the quality of the assessments has improved as more advanced models have been developed and incorporated into the ARAC system. Over the past six years, the number of directly connected facilities has increased from 6 to 73. All major U.S. Federal agencies now have access to ARAC via the Department of Energy. This assures a level of consistency as well as experience. ARAC maintains its real-time skills by participation in approximately 150 exercises per year; ARAC also continuously validates its modeling systems by application to all available tracer experiments and data sets

Hazardous Materials Management and Emergency Response (HAMMER)

Data.gov (United States)

Federal Laboratory Consortium — The Volpentest Hazardous Materials Management and Emergency Response (HAMMER) Federal Training Center is a safety and emergency response training center that offers...

Dose/dose-rate responses of shrimp larvae to UV-B radiation

International Nuclear Information System (INIS)

Damkaer, D.M.

1981-01-01

Previous work indicated dose-rate thresholds in the effects of UV-B on the near-surface larvae of three shrimp species. Additional observations suggest that the total dose response varies with dose-rate. Below 0.002 Wm -2 sub([DNA]) irradiance no significant effect is noted in activity, development, or survival. Beyond that dose-rate threshold, shrimp larvae are significantly affected if the total dose exceeds about 85 Jm -2 sub([DNA]). Predictions cannot be made without both the dose-rate and the dose. These dose/dose-rate thresholds are compared to four-year mean dose/dose-rate solar UV-B irradiances at the experimental site, measured at the surface and calculated for 1 m depth. The probability that the shrimp larvae would receive lethal irradiance is low for the first half of the season of surface occurrence, even with a 44% increase in damaging UV radiation. (orig.)

Dose/dose-rate responses of shrimp larvae to UV-B radiation

Energy Technology Data Exchange (ETDEWEB)

Damkaer, D.M.; Dey, D.B.; Heron, G.A.

1981-01-01

Previous work indicated dose-rate thresholds in the effects of UV-B on the near-surface larvae of three shrimp species. Additional observations suggest that the total dose response varies with dose-rate. Below 0.002 Wm/sup -2/sub((DNA)) irradiance no significant effect is noted in activity, development, or survival. Beyond that dose-rate threshold, shrimp larvae are significantly affected if the total dose exceeds about 85 Jm/sup -2/sub((DNA)). Predictions cannot be made without both the dose-rate and the dose. These dose/dose-rate thresholds are compared to four-year mean dose/dose-rate solar UV-B irradiances at the experimental site, measured at the surface and calculated for 1 m depth. The probability that the shrimp larvae would receive lethal irradiance is low for the first half of the season of surface occurrence, even with a 44% increase in damaging UV radiation.

Radiological emergency response planning in Pennsylvania

International Nuclear Information System (INIS)

Henderson, O.K.

1981-01-01

The most important aspect of emergency preparedness is to recognize and accept the fact that there exists a potential for a problem or a condition and that it requires some attention. Emergency plans should be sufficiently flexible so as to accommodate the emergency situation as it unfolds. Of the several emergency responses that may be taken following a nuclear power plant accident evacuation evokes the greatest attention and discussion as to whether it is truly a feasible option. Movements of people confined to mass care facilities or on life support systems involve special requirements. The Three Mile Island accident has been the most studied nuclear incident in the history of the nuclear power reactor industry. The findings of these reports will have a major influence on nuclear power issues as they are addressed in the future. The question remains as to whether the political leadership will be willing to provide the resources required by the emergency plan. Future safety and emergency response to nuclear accidents depend upon Government and industry acting responsibly and not merely responding to regulations. The Three Mile Island accident has had some beneficial side effects for the emergency management community. It has: increased the level of awareness and importance of emergency planning; served as a catalyst for the sharing of experiences and information; encouraged standardization of procedures; and emphasized the need for identifying and assigning responsibilities. The Emergency Management Organization in responding to a disaster situation does not enjoy the luxury of time. It needs to act decisively and correctly. It does not often get a second chance. Governments, at all levels, and the nuclear power industry have been put on notice as a result of Three Mile Island. The future of nuclear energy may well hang in the balance, based upon the public's perception of the adequacy of preparedness and safety measures being taken. (author)

A Tactical Emergency Response Management System (Terms ...

African Journals Online (AJOL)

2013-03-01

Mar 1, 2013 ... information is a result of collaboration between accident response personnel. ... Tactical Emergency Response Management System (TERMS) which unifies all these different ... purpose of handling crisis and emergency.

Emergency Response Resources guide for nuclear power plant emergencies

International Nuclear Information System (INIS)

1992-07-01

On August 28 and September 18, 1990, the States of Louisiana and Mississippi, Gulf States Utilities, five local parishes, six Federal agencies, and the American Nuclear Insurers participated in a post-emergency TABLETOP exercise in Baton Rouge, Louisiana. One of the products developed from that experience was this guide for understanding the responsibilities and obtaining resources for specific needs from the various participants, particularly from those organizations within the Federal Government. This first revision of that guide broadens the focus of the original document. Also, new information defines the major Federal response facilities. This guide should assist State and local government organizations with identifying and obtaining those resources for the post-emergency response when their resources have been exhausted

Lessons Learned from the Response to Radiation Emergencies (1945-2010) (French Edition)

International Nuclear Information System (INIS)

2014-01-01

occurred, most notably, the Windscale fire in 1957, the Three Mile Island accident in 1979, the Chernobyl accident in 1986, the Sarov accident in 1997 and the Tokaimura accident in 1999. Radiological emergencies have occurred throughout the world, and when invited by the country concerned, the IAEA has undertaken comprehensive reviews of the events, the purpose of which is to compile information about the causes of the accidents, the subsequent emergency response including medical management, dose reconstruction, public communication, etc., so that any lessons can be shared with national authorities and regulatory organizations, emergency planners and a broad range of specialists, including physicists, technicians and medical specialists, and persons responsible for radiation protection. It is appropriate to analyze the findings of these and other reports on the response to radiation emergencies in order to consolidate these lessons

Lessons Learned from the Response to Radiation Emergencies (1945-2010) (Spanish Edition)

International Nuclear Information System (INIS)

2014-01-01

occurred, most notably, the Windscale fire in 1957, the Three Mile Island accident in 1979, the Chernobyl accident in 1986, the Sarov accident in 1997 and the Tokaimura accident in 1999. Radiological emergencies have occurred throughout the world, and when invited by the country concerned, the IAEA has undertaken comprehensive reviews of the events, the purpose of which is to compile information about the causes of the accidents, the subsequent emergency response including medical management, dose reconstruction, public communication, etc., so that any lessons can be shared with national authorities and regulatory organizations, emergency planners and a broad range of specialists, including physicists, technicians and medical specialists, and persons responsible for radiation protection. It is appropriate to analyze the findings of these and other reports on the response to radiation emergencies in order to consolidate these lessons

Lessons Learned from the Response to Radiation Emergencies (1945-2010) (Arabic Edition)

International Nuclear Information System (INIS)

2014-01-01

occurred, most notably, the Windscale fire in 1957, the Three Mile Island accident in 1979, the Chernobyl accident in 1986, the Sarov accident in 1997 and the Tokaimura accident in 1999. Radiological emergencies have occurred throughout the world, and when invited by the country concerned, the IAEA has undertaken comprehensive reviews of the events, the purpose of which is to compile information about the causes of the accidents, the subsequent emergency response including medical management, dose reconstruction, public communication, etc., so that any lessons can be shared with national authorities and regulatory organizations, emergency planners and a broad range of specialists, including physicists, technicians and medical specialists, and persons responsible for radiation protection. It is appropriate to analyze the findings of these and other reports on the response to radiation emergencies in order to consolidate these lessons.

Lessons Learned from the Response to Radiation Emergencies (1945-2010) (Russian Edition)

International Nuclear Information System (INIS)

2013-01-01

occurred, most notably, the Windscale fire in 1957, the Three Mile Island accident in 1979, the Chernobyl accident in 1986, the Sarov accident in 1997 and the Tokaimura accident in 1999. Radiological emergencies have occurred throughout the world, and when invited by the country concerned, the IAEA has undertaken comprehensive reviews of the events, the purpose of which is to compile information about the causes of the accidents, the subsequent emergency response including medical management, dose reconstruction, public communication, etc., so that any lessons can be shared with national authorities and regulatory organizations, emergency planners and a broad range of specialists, including physicists, technicians and medical specialists, and persons responsible for radiation protection. It is appropriate to analyze the findings of these and other reports on the response to radiation emergencies in order to consolidate these lessons.

Confidence bounds for nonlinear dose-response relationships

DEFF Research Database (Denmark)

Baayen, C; Hougaard, P

2015-01-01

An important aim of drug trials is to characterize the dose-response relationship of a new compound. Such a relationship can often be described by a parametric (nonlinear) function that is monotone in dose. If such a model is fitted, it is useful to know the uncertainty of the fitted curve...... intervals for the dose-response curve. These confidence bounds have better coverage than Wald intervals and are more precise and generally faster than bootstrap methods. Moreover, if monotonicity is assumed, the profile likelihood approach takes this automatically into account. The approach is illustrated...

Dose response relationship in local radiotherapy for hepatocellular carcinoma

International Nuclear Information System (INIS)

Park, Hee Chul; Seong, Jin Sil; Han, Kwang Hyub; Chon, Chae Yoon; Moon, Young Myoung; Song, Jae Seok; Suh, Chang Ok

2001-01-01

In this study, it was investigated whether dose response relation existed or not in local radiotherapy for primary hepatocellular carcinoma. From January 1992 to March 2000, 158 patients were included in present study. Exclusion criteria included the presence of extrahepatic metastasis, liver cirrhosis of Child's class C, tumors occupying more than two thirds of the entire liver, and performance status on the ECOG scale of more than 3. Radiotherapy was given to the field including tumor with generous margin using 6, 10-MV X-ray. Mean tumor dose was 48.2±7.9 Gy in daily 1.8 Gy fractions. Tumor response was based on diagnostic radiologic examinations such as CT scan, MR imaging, hepatic artery angiography at 4-8 weeks following completion of treatment. Statistical analysis was done to investigate the existence of dose response relationship of local radiotherapy when it was applied to the treatment of primary hepatocellular carcinoma. An objective response was observed in 106 of 158 patients, giving a response rate of 67. 1%. Statistical analysis revealed that total dose was the most significant factor in relation to tumor response when local radiotherapy was applied to the treatment of primary hepatocellular carcinoma. Only 29.2% showed objective response in patients treated with dose less than 40 Gy, while 68.6% and 77.1 % showed major response in patients with 40-50 Gy and more than 50 Gy, respectively. Child-Pugh classification was significant factor in the development of ascites, overt radiation induced liver disease and gastroenteritis. Radiation dose was an important factor for development of radiation induced gastroduodenal ulcer. Present study showed the existence of dose response relationship in local radiotherapy for primary hepatocellular carcinoma. Only radiotherapy dose was a significant factor to predict the objective response. Further study is required to predict the maximal tolerance dose in consideration of liver function and non-irradiated liver

Reevaluation of nasal swab method for dose estimation at nuclear emergency accident

International Nuclear Information System (INIS)

Yamada, Yuji; Fukutsu, Kumiko; Kurihara, Osamu; Akashi, Makoto

2008-01-01

ICRP Publication 66 human respiratory tract model has been used extensively over in exposure dose assessment. It is well known that respiratory deposition efficiency of inhaled aerosol and its deposition region strongly depend on the particle size. In most of exposure accidents, however, nobody knows a size of inhaled aerosol. And thus two default aerosol sizes of 5μ in AMAD for the workers and 1μ in AMAD for the public are given as being representative in the ICRP model, but both sizes are not linked directly to the maximum dose. In this study, the most hazardous size to our health effects and how to estimate an intake activity was discussed from a viewpoint of emergency medicine. In exposure accident of alpha emitter such as Pu-239, lung monitor and bioassay measurements are not the best methods for rapid estimation with high sensitivity, so that an applicability of nasal swab method has been investigated. A computer software, LUDEP, was used in the calculation of respiratory deposition. It showed that the effective dose per unit intake activity strongly depended on the inhaled aerosol size. In case of Pu-239 dioxide aerosols, it was confirmed that the maximum of dose conversion factor was observed around 0.01μ. It means that this 0.01μ is the most hazardous size at exposure accident of Pu-239. From analysis of the relationship between AI and ET l deposition, it was found that the dose conversion factor from the activity deposited in ET l region also was affected by the aerosol size. The usage of the ICRP's default size in nasal swab method might cause obvious underestimation of the intake activity. Dose estimation based on nasal swab method is possible from safety side at nuclear emergency, and the availability in quantity should be reevaluated for emergency medicine considering of chelating agent administration. (author)

Radiological Emergency Response Data

Data.gov (United States)

U.S. Environmental Protection Agency — Quality Data Asset includes all current and historical emergency radiological response event and incident of national significance data and surveillance, monitoring,...

Simulation analysis of the use of emergency resources during the emergency response to a major fire

NARCIS (Netherlands)

Zhou, Jianfeng; Reniers, G.L.L.M.E.

2016-01-01

During an emergency response to an accident or disaster, emergency response actions often need to use various emergency resources. The use of resources plays an important role in the successful implementation of emergency response, but there may be conflicts in the use of resources for emergency

Manual for first responders to a radiological emergency. Emergency preparedness and response

International Nuclear Information System (INIS)

2008-01-01

Under Article 5.a(ii) of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. As stated in IAEA Safety Standards Series No. GS-R-2 'Preparedness and Response for a Nuclear or Radiological Emergency', which establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, 'first responders shall take all practicable and appropriate actions to minimize the consequences of a nuclear or radiological emergency'. The IAEA General Conference, in resolution GC(49)/RES/9, continues to encourage Member States 'to adopt the relevant Agency standards, procedures and practical tools' and underlines 'the need for first responders to have appropriate training for dealing with ionizing radiation during nuclear and radiological emergencies'. This publication is intended to assist in meeting these requirements and to fulfil Article 5 of the Assistance Convention. Its aim is to provide practical guidance for those who will respond during the first few hours to a radiological emergency (referred to here as 'first responders') and for national officials who would support this early response. It provides guidance in the form of action guides, instructions, and supporting data that can be easily applied by a State to build a basic capability to respond to a radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This report, published as part of the IAEA Emergency Preparedness and Response Series, replaces and builds on IAEA-TECDOC-1162 in the area of early response and first responders' actions. It takes account of the

Emergency response to mass casualty incidents in Lebanon.

Science.gov (United States)

El Sayed, Mazen J

2013-08-01

The emergency response to mass casualty incidents in Lebanon lacks uniformity. Three recent large-scale incidents have challenged the existing emergency response process and have raised the need to improve and develop incident management for better resilience in times of crisis. We describe some simple emergency management principles that are currently applied in the United States. These principles can be easily adopted by Lebanon and other developing countries to standardize and improve their emergency response systems using existing infrastructure.

Towards accurate emergency response behavior

International Nuclear Information System (INIS)

Sargent, T.O.

1981-01-01

Nuclear reactor operator emergency response behavior has persisted as a training problem through lack of information. The industry needs an accurate definition of operator behavior in adverse stress conditions, and training methods which will produce the desired behavior. Newly assembled information from fifty years of research into human behavior in both high and low stress provides a more accurate definition of appropriate operator response, and supports training methods which will produce the needed control room behavior. The research indicates that operator response in emergencies is divided into two modes, conditioned behavior and knowledge based behavior. Methods which assure accurate conditioned behavior, and provide for the recovery of knowledge based behavior, are described in detail

OEM Emergency Response Information

Data.gov (United States)

U.S. Environmental Protection Agency — The Office of Emergency Management retains records of all incident responses in which it participates. This data asset includes three major sources of information:...

The influence of dose fractionation and dose rate on normal tissue responses

International Nuclear Information System (INIS)

Barendsen, G.W.

1982-01-01

An analysis of responses of a variety of normal tissues in animals to fractionated irradiations has been made with the aim of developing a formalism for the prediction of tolerance doses as a function of the dose per fraction and the overall treatment time. An important feature of the formalism is that it is directly based on radiological insights and therefore provides a logical concept to account for the diversity of tissue responses. (Auth.)

Emergency response to radiological occurrences in the centre of isotopes in Cuba

International Nuclear Information System (INIS)

Amador, Zayda H.; Perez, Saul; Torres, Mirta B.; Ayra, Fernando E.

2008-01-01

It is internationally recognized that establishment and implementation emergency provisions are key issues for an effective response. This paper aims to summarize the experiences in responding to radiological events in the Centre of Isotopes (CENTIS), the biggest radioactive facility in Cuba. Specific potential accident scenarios are assessed by identifying maximum radioactive inventories, operational procedures, room dimensions and ventilation system parameters. Additionally, transport accidents are analyzed since CENTIS is also the main carrier of radioactive materials in Cuba. A range of events is considered from highly improbable events of larger consequence to more frequent events of small radiological impact. The maximum radionuclide release events are identified. A review of the radiological occurrences from 1997 to 2007 is conducted, using the Cuban's regulatory classification system. The details of these occurrences have been entered into the Radiological Event Database (RED). Spills of 131 I in controlled zone are mainly registered. It has been not reported any incident in about two thousand road shipments carried out. Results show a good agreement between hypothesized occurrences and those registered. There were obtained the maximum values of exposures for workers and first responders as follows: 2.23mSv (effective dose (E)), 0.7mSv (committed effective dose) and 50.49mSv (equivalent dose to hands). The biggest contribution to E took place during opening a radioactive package with 14.8GBq of 90 Sr in controlled zone. Suitable sets of individual protective means and monitoring equipment have been guaranteed. The programmes of training and full-scale exercises are fulfilled. Finally, it is concluded that findings from operational experience and preparedness infrastructure have contributed to CENTIS' emergency response capabilities. (author)

Post-emergency response resources guide

International Nuclear Information System (INIS)

1991-07-01

On August 28 and September 18, 1990, the States of Louisiana and Mississippi, Gulf States Utilities, five local parishes, six Federal agencies, and the American Nuclear Insurers participated in a post-emergency TABLETOP exercise in Baton Rouge, Louisiana. One of the products developed from that experience is this guide for understanding the responsibilities and obtaining resources for specific needs from the various participants, particularly those organizations within the federal government. This guide should assist state and local government organizations with identifying and obtaining those resources for the post-emergency response when theirs have been exhausted

TESS-based dose-response using pediatric clonidine exposures.

Science.gov (United States)

Benson, Blaine E; Spyker, Daniel A; Troutman, William G; Watson, William A

2006-06-01

The toxic and lethal doses of clonidine in children are unclear. This study was designed to determine whether data from the American Association of Poison Control Centers Toxic Exposure Surveillance System (TESS) could be utilized to determine a dose-response relationship for pediatric clonidine exposure. 3,458 single-substance clonidine exposures in children TESS from January 2000 through December 2003 were examined. Dose ingested, age, and medical outcome were available for 1550 cases. Respiratory arrest cases (n = 8) were classified as the most severe of the medical outcome categories (Arrest, Major, Moderate, Mild, and No effect). Exposures reported as a "taste or lick" (n = 51) were included as a dose of 1/10 of the dosage form involved. Dose ranged from 0.4 to 1980 (median 13) microg/kg. Weight was imputed based on a quadratic estimate of weight for age. Dose certainty was coded as exact (26% of cases) or not exact (74%). Medical outcome (response) was examined via logistic regression using SAS JMP (release 5.1). The logistic model describing medical outcome (P TESS data can provide the basis for a statistically sound description of dose-response for pediatric clonidine poisoning exposures.

Dose-response meta-analysis of differences in means

Directory of Open Access Journals (Sweden)

Alessio Crippa

2016-08-01

Full Text Available Abstract Background Meta-analytical methods are frequently used to combine dose-response findings expressed in terms of relative risks. However, no methodology has been established when results are summarized in terms of differences in means of quantitative outcomes. Methods We proposed a two-stage approach. A flexible dose-response model is estimated within each study (first stage taking into account the covariance of the data points (mean differences, standardized mean differences. Parameters describing the study-specific curves are then combined using a multivariate random-effects model (second stage to address heterogeneity across studies. Results The method is fairly general and can accommodate a variety of parametric functions. Compared to traditional non-linear models (e.g. E max, logistic, spline models do not assume any pre-specified dose-response curve. Spline models allow inclusion of studies with a small number of dose levels, and almost any shape, even non monotonic ones, can be estimated using only two parameters. We illustrated the method using dose-response data arising from five clinical trials on an antipsychotic drug, aripiprazole, and improvement in symptoms in shizoaffective patients. Using the Positive and Negative Syndrome Scale (PANSS, pooled results indicated a non-linear association with the maximum change in mean PANSS score equal to 10.40 (95 % confidence interval 7.48, 13.30 observed for 19.32 mg/day of aripiprazole. No substantial change in PANSS score was observed above this value. An estimated dose of 10.43 mg/day was found to produce 80 % of the maximum predicted response. Conclusion The described approach should be adopted to combine correlated differences in means of quantitative outcomes arising from multiple studies. Sensitivity analysis can be a useful tool to assess the robustness of the overall dose-response curve to different modelling strategies. A user-friendly R package has been developed to facilitate

A Generalized QMRA Beta-Poisson Dose-Response Model.

Science.gov (United States)

Xie, Gang; Roiko, Anne; Stratton, Helen; Lemckert, Charles; Dunn, Peter K; Mengersen, Kerrie

2016-10-01

Quantitative microbial risk assessment (QMRA) is widely accepted for characterizing the microbial risks associated with food, water, and wastewater. Single-hit dose-response models are the most commonly used dose-response models in QMRA. Denoting PI(d) as the probability of infection at a given mean dose d, a three-parameter generalized QMRA beta-Poisson dose-response model, PI(d|α,β,r*), is proposed in which the minimum number of organisms required for causing infection, K min , is not fixed, but a random variable following a geometric distribution with parameter 0Poisson model, PI(d|α,β), is a special case of the generalized model with K min = 1 (which implies r*=1). The generalized beta-Poisson model is based on a conceptual model with greater detail in the dose-response mechanism. Since a maximum likelihood solution is not easily available, a likelihood-free approximate Bayesian computation (ABC) algorithm is employed for parameter estimation. By fitting the generalized model to four experimental data sets from the literature, this study reveals that the posterior median r* estimates produced fall short of meeting the required condition of r* = 1 for single-hit assumption. However, three out of four data sets fitted by the generalized models could not achieve an improvement in goodness of fit. These combined results imply that, at least in some cases, a single-hit assumption for characterizing the dose-response process may not be appropriate, but that the more complex models may be difficult to support especially if the sample size is small. The three-parameter generalized model provides a possibility to investigate the mechanism of a dose-response process in greater detail than is possible under a single-hit model. © 2016 Society for Risk Analysis.

Maximum likelihood estimation for cytogenetic dose-response curves

International Nuclear Information System (INIS)

Frome, E.L.; DuFrain, R.J.

1986-01-01

In vitro dose-response curves are used to describe the relation between chromosome aberrations and radiation dose for human lymphocytes. The lymphocytes are exposed to low-LET radiation, and the resulting dicentric chromosome aberrations follow the Poisson distribution. The expected yield depends on both the magnitude and the temporal distribution of the dose. A general dose-response model that describes this relation has been presented by Kellerer and Rossi (1972, Current Topics on Radiation Research Quarterly 8, 85-158; 1978, Radiation Research 75, 471-488) using the theory of dual radiation action. Two special cases of practical interest are split-dose and continuous exposure experiments, and the resulting dose-time-response models are intrinsically nonlinear in the parameters. A general-purpose maximum likelihood estimation procedure is described, and estimation for the nonlinear models is illustrated with numerical examples from both experimental designs. Poisson regression analysis is used for estimation, hypothesis testing, and regression diagnostics. Results are discussed in the context of exposure assessment procedures for both acute and chronic human radiation exposure

Emergency response planning in Pennsylvania

International Nuclear Information System (INIS)

Reilly, M.A.

1988-01-01

In the decade since the accident at Three Mile Island, emergency planning for response to these events has undergone a significant change in Pennsylvania, as elsewhere. Changes respond to federal guidance and to state agency initiatives. The most singular change is the practice of implementing a protective action throughout the entire emergency planning zone (EPZ). Due to Pennsylvania agency experiences during the accident, the decision was made soon after to develop a staff of nuclear engineers, each giving special day-to-day attention to a specific nuclear power station in the state. Changes in communications capabilities are significant, these being dedicated phone lines between the Commonwealth and each power station, and the reorientation of the Department of Environmental Resources radio network to accommodate direction of field monitoring teams from Harrisburg. Changes that are being or will be implemented in the near future include assessing the emergency response data system for electronic delivery of plant parameter data form facilities during accidents, increased participation in exercises, emergency medical planning, and training, the inclusion of all 67 counties in Pennsylvania in an ingestion EPZ, and the gradual severance of dependence on land-line emergency communication systems

New Nuclear Emergency Prognosis system in Korea

Science.gov (United States)

Lee, Hyun-Ha; Jeong, Seung-Young; Park, Sang-Hyun; Lee, Kwan-Hee

2016-04-01

This paper reviews the status of assessment and prognosis system for nuclear emergency response in Korea, especially atmospheric dispersion model. The Korea Institute of Nuclear Safety (KINS) performs the regulation and radiological emergency preparedness of the nuclear facilities and radiation utilizations. Also, KINS has set up the "Radiological Emergency Technical Advisory Plan" and the associated procedures such as an emergency response manual in consideration of the IAEA Safety Standards GS-R-2, GS-G-2.0, and GS-G-2.1. The Radiological Emergency Technical Advisory Center (RETAC) organized in an emergency situation provides the technical advice on radiological emergency response. The "Atomic Computerized Technical Advisory System for nuclear emergency" (AtomCARE) has been developed to implement assessment and prognosis by RETAC. KINS developed Accident Dose Assessment and Monitoring (ADAMO) system in 2015 to reflect the lessons learned from Fukushima accident. It incorporates (1) the dose assessment on the entire Korean peninsula, Asia region, and global region, (2) multi-units accident assessment (3) applying new methodology of dose rate assessment and the source term estimation with inverse modeling, (4) dose assessment and monitoring with the environmental measurements result. The ADAMO is the renovated version of current FADAS of AtomCARE. The ADAMO increases the accuracy of the radioactive material dispersion with applying the LDAPS(Local Data Assimilation Prediction System, Spatial resolution: 1.5 km) and RDAPS(Regional Data Assimilation Prediction System, Spatial resolution: 12km) of weather prediction data, and performing the data assimilation of automatic weather system (AWS) data from Korea Meteorological Administration (KMA) and data from the weather observation tower at NPP site. The prediction model of the radiological material dispersion is based on the set of the Lagrangian Particle model and Lagrangian Puff model. The dose estimation methodology

An emergency response plan for transportation

International Nuclear Information System (INIS)

Fontaine, M.V.; Guerel, E.

2000-01-01

Transnucleaire is involved in road and rail transport of nuclear fuel cycle materials. To comply with IAEA recommendations, Transnucleaire has to master methods of emergency response in the event of a transport accident. Considering the utmost severe situations, Transnucleaire has studied several cases and focused especially on an accident involving a heavy cask. In France, the sub-prefect of each department is in charge of the organisation of the emergency teams. The sub-prefect may request Transnucleaire to supply experts, organisation, equipment and technical support. The Transnucleaire Emergency Response Plan covers all possible scenarios of land transport accidents and relies on: (i) an organisation ready for emergency situations, (ii) equipment dedicated to intervention, and (iii) training of its own experts and specialised companies. (author)

Mahalanobis distance and variable selection to optimize dose response

International Nuclear Information System (INIS)

Moore, D.H. II; Bennett, D.E.; Wyrobek, A.J.; Kranzler, D.

1979-01-01

A battery of statistical techniques are combined to improve detection of low-level dose response. First, Mahalanobis distances are used to classify objects as normal or abnormal. Then the proportion classified abnormal is regressed on dose. Finally, a subset of regressor variables is selected which maximizes the slope of the dose response line. Use of the techniques is illustrated by application to mouse sperm damaged by low doses of x-rays

Off-site response for radiological emergencies

International Nuclear Information System (INIS)

Eldridge, J.S.; Oakes, T.W.; Hubbard, H.M.; Hibbitts, H.W.

1982-01-01

Environmental radiological surveillance under emergency conditions at off-site locations is one of the advisory functions provided by DOE within the ORO jurisdiction. The Department of Environmental Management of ORNL has been requested to provide sampling and analytical assistance at such emergency response activities. We have assembled and identified specific individuals and equipment to provide a rapid response force to perform field measurements for environmental radioactivity releases as a consequence of nuclear accidents. Survey teams for sample collection and field measurements are provided along with analytical assistance to operate the radioactivity measuring equipment in the DOE emergency van

Assessing Emergency Preparedness and Response Capacity Using Community Assessment for Public Health Emergency Response Methodology: Portsmouth, Virginia, 2013.

Science.gov (United States)

Kurkjian, Katie M; Winz, Michelle; Yang, Jun; Corvese, Kate; Colón, Ana; Levine, Seth J; Mullen, Jessica; Ruth, Donna; Anson-Dwamena, Rexford; Bayleyegn, Tesfaye; Chang, David S

2016-04-01

For the past decade, emergency preparedness campaigns have encouraged households to meet preparedness metrics, such as having a household evacuation plan and emergency supplies of food, water, and medication. To estimate current household preparedness levels and to enhance disaster response planning, the Virginia Department of Health with remote technical assistance from the Centers for Disease Control and Prevention conducted a community health assessment in 2013 in Portsmouth, Virginia. Using the Community Assessment for Public Health Emergency Response (CASPER) methodology with 2-stage cluster sampling, we randomly selected 210 households for in-person interviews. Households were questioned about emergency planning and supplies, information sources during emergencies, and chronic health conditions. Interview teams completed 180 interviews (86%). Interviews revealed that 70% of households had an emergency evacuation plan, 67% had a 3-day supply of water for each member, and 77% had a first aid kit. Most households (65%) reported that the television was the primary source of information during an emergency. Heart disease (54%) and obesity (40%) were the most frequently reported chronic conditions. The Virginia Department of Health identified important gaps in local household preparedness. Data from the assessment have been used to inform community health partners, enhance disaster response planning, set community health priorities, and influence Portsmouth's Community Health Improvement Plan.

Dose calculations for severe LWR accident scenarios

International Nuclear Information System (INIS)

Margulies, T.S.; Martin, J.A. Jr.

1984-05-01

This report presents a set of precalculated doses based on a set of postulated accident releases and intended for use in emergency planning and emergency response. Doses were calculated for the PWR (Pressurized Water Reactor) accident categories of the Reactor Safety Study (WASH-1400) using the CRAC (Calculations of Reactor Accident Consequences) code. Whole body and thyroid doses are presented for a selected set of weather cases. For each weather case these calculations were performed for various times and distances including three different dose pathways - cloud (plume) shine, ground shine and inhalation. During an emergency this information can be useful since it is immediately available for projecting offsite radiological doses based on reactor accident sequence information in the absence of plant measurements of emission rates (source terms). It can be used for emergency drill scenario development as well

Dose-response relationships and risk estimates for the induction of cancer due to low doses of low-LET radiation

International Nuclear Information System (INIS)

Elaguppillai, V.

1981-01-01

Risk estimates for radiation-induced cancer at low doses can be obtained only by extrapolation from the known effects at high doses and high dose rates, using a suitable dose-response model. The applicability of three different models, linear, sublinear and supralinear, are discussed in this paper. Several experimental studies tend to favour a sublinear dose-response model (linear-quadratic model) for low-LET radiation. However, human epidemiological studies do not exclude any of the dose-response relationships. The risk estimates based on linear and linear quadratic dose-response models are compared and it is concluded that, for low-LET radiation, the linear dose-response model would probably over-estimate the actual risk of cancer by a factor of two or more. (author)

The Dose Response Relationship for Radiation Carcinogenesis

Science.gov (United States)

Hall, Eric

2008-03-01

Recent surveys show that the collective population radiation dose from medical procedures in the U.S. has increased by 750% in the past two decades. It would be impossible to imagine the practice of medicine today without diagnostic and therapeutic radiology, but nevertheless the widespread and rapidly increasing use of a modality which is a known human carcinogen is a cause for concern. To assess the magnitude of the problem it is necessary to establish the shape of the dose response relationship for radiation carcinogenesis. Information on radiation carcinogenesis comes from the A-bomb survivors, from occupationally exposed individuals and from radiotherapy patients. The A-bomb survivor data indicates a linear relationship between dose and the risk of solid cancers up to a dose of about 2.5 Sv. The lowest dose at which there is a significant excess cancer risk is debatable, but it would appear to be between 40 and 100 mSv. Data from the occupation exposure of nuclear workers shows an excess cancer risk at an average dose of 19.4 mSv. At the other end of the dose scale, data on second cancers in radiotherapy patients indicates that cancer risk does not continue to rise as a linear function of dose, but tends towards a plateau of 40 to 60 Gy, delivered in a fractionated regime. These data can be used to estimate the impact of diagnostic radiology at the low dose end of the dose response relationship, and the impact of new radiotherapy modalities at the high end of the dose response relationship. In the case of diagnostic radiology about 90% of the collective population dose comes from procedures (principally CT scans) which involve doses at which there is credible evidence of an excess cancer incidence. While the risk to the individual is small and justified in a symptomatic patient, the same is not true of some screening procedures is asymptomatic individuals, and in any case the huge number of procedures must add up to a potential public health problem. In the

Emergency response training with the BNL plant analyzer

International Nuclear Information System (INIS)

Cheng, H.S.; Guppy, J.G.; Mallen, A.N.; Wulff, W.

1987-01-01

Presented is the experience in the use of the BNL Plant Analyzer for NRC emergency response training to simulated accidents in a BWR. The unique features of the BNL Plant Analyzer that are important for the emergency response training are summarized. A closed-loop simulation of all the key systems of a power plant in question was found essential to the realism of the emergency drills conducted at NRC. The faster than real-time simulation speeds afforded by the BNL Plant Analyzer have demonstrated its usefulness for the timely conduct of the emergency response training

SICOEM: emergency response data system

International Nuclear Information System (INIS)

Martin, A.; Villota, C.; Francia, L.

1993-01-01

The main characteristics of the SICOEM emergency response system are: -direct electronic redundant transmission of certain operational parameters and plant status informations from the plant process computer to a computer at the Regulatory Body site, - the system will be used in emergency situations, -SICOEM is not considered as a safety class system. 1 fig

SICOEM: emergency response data system

Energy Technology Data Exchange (ETDEWEB)

Martin, A.; Villota, C.; Francia, L. (UNESA, Madrid (Spain))

1993-01-01

The main characteristics of the SICOEM emergency response system are: -direct electronic redundant transmission of certain operational parameters and plant status informations from the plant process computer to a computer at the Regulatory Body site, - the system will be used in emergency situations, -SICOEM is not considered as a safety class system. 1 fig.

TESS-based dose-response using pediatric clonidine exposures

International Nuclear Information System (INIS)

Benson, Blaine E.; Spyker, Daniel A.; Troutman, William G.; Watson, William A.

2006-01-01

Objective: The toxic and lethal doses of clonidine in children are unclear. This study was designed to determine whether data from the American Association of Poison Control Centers Toxic Exposure Surveillance System (TESS) could be utilized to determine a dose-response relationship for pediatric clonidine exposure. Methods: 3458 single-substance clonidine exposures in children <6 years of age reported to TESS from January 2000 through December 2003 were examined. Dose ingested, age, and medical outcome were available for 1550 cases. Respiratory arrest cases (n = 8) were classified as the most severe of the medical outcome categories (Arrest, Major, Moderate, Mild, and No effect). Exposures reported as a 'taste or lick' (n = 51) were included as a dose of 1/10 of the dosage form involved. Dose ranged from 0.4 to 1980 (median 13) μg/kg. Weight was imputed based on a quadratic estimate of weight for age. Dose certainty was coded as exact (26% of cases) or not exact (74%). Medical outcome (response) was examined via logistic regression using SAS JMP (release 5.1). Results: The logistic model describing medical outcome (P < 0.0001) included Log dose/kg (P 0.0000) and Certainty (P = 0.045). Conclusion: TESS data can provide the basis for a statistically sound description of dose-response for pediatric clonidine poisoning exposures

Studies on adaptive response of lymphocyte transformation induced by low-dose irradiation

International Nuclear Information System (INIS)

Du Zeji; Su Liaoyuan; Tian Hailin; Zou Huawei

1995-10-01

Human peripheral blood lymphocytes stimulated by mitogen in vitro for 24 h were exposed to low-dose γ-ray irradiation (0.5∼4.0 cGy, adaptive dose). They showed an adaptive response to the inhibition of 3 H-TdR incorporation by subsequent higher acute doses of γ-ray (challenge dose). At the interval of 24 h between adaptive dose and challenge dose, the strongest adaptive response induced by low-dose irradiation was found. It is also found that the response induced by 1.0 cGy of adaptive dose was more obvious than that by other doses and that 3.0 Gy of challenge dose produced the strongest adaptive response. As the challenge doses increased, the adaptive response reduced. (2 figs., 2 tabs.)

Southern states radiological emergency response laws and regulations

International Nuclear Information System (INIS)

1989-02-01

The radiological emergency response laws and regulations of the Southern States Energy Compact member states are in some cases disparate. Several states have very specific laws on radiological emergency response while in others, the statutory law mentions only emergency response to ''natural disasters.'' Some states have adopted extensive regulations on the topic; others have none. For this reason, any general overview must necessarily discuss laws and regulations in general terms

Status and developing of nuclear emergency response techniques in China

International Nuclear Information System (INIS)

Jiangang, Zhang; Bing, Zhao; Rongyao, Tang; Xiaoxiao, Xu

2008-01-01

Full text: Nuclear Emergency preparedness and response in China is consistent with international basic principle of nuclear safety and emergency response. Nuclear emergency response techniques in China developed with nuclear power from 1980s. The status of nuclear emergency techniques in China are: 1) China have plentiful experiences and abilities in the fields of nuclear facility emergency planning and preparedness, nuclear accident consequence assessment, emergency monitoring, and emergency advisory; 2) Emergency assistance ability in China has a foundation, however it cannot satisfy national requirement; 3) Emergency planning and preparedness is not based on hazard assessment; 4) Remote monitoring and robot techniques in not adaptable to the requirements of nuclear emergency response; 5) A consistent emergency assessment system is lack in China. In this paper, it is analyzed what is the developing focal points of nuclear emergency response techniques in China, and it is proposed that the main points are: a) To develop the research of emergency preparedness on the base of hazard analysis; b) To improve remote monitoring and robot ability during nuclear emergency; c) To develop the response technique research with anti-terrorism. (author)

Scaling-up Support for Emergency Response Organizations

NARCIS (Netherlands)

Oomes, A.H.J.; Neef, R.M.

2005-01-01

We present the design of an information system that supports the process of scaling-up of emergency response organizations. This process is vital for effective emergency response but tends to go awry in practice. Our proposed system consists of multiple distributed agents that are capable of

Dose-response relationship in local radiotherapy for hepatocellular carcinoma

International Nuclear Information System (INIS)

Park, Hee Chul; Seong, Jinsil; Han, Kwang Hyub; Chon, Chae Yoon; Moon, Young Myoung; Suh, Chang Ok

2002-01-01

Purpose: Dose escalation using three-dimensional conformal radiotherapy (3D-CRT) is based on the hypothesis that increasing the dose can enhance tumor control. This study aimed to determine whether a dose-response relationship exists in local radiotherapy for primary hepatocellular carcinoma (HCC). Methods and Materials: One hundred fifty-eight patients were enrolled in the present study between January 1992 and March 2000. The exclusion criteria included the presence of an extrahepatic metastasis, liver cirrhosis of Child class C, tumors occupying more than two-thirds of the entire liver, and a performance status on the Eastern Cooperative Oncology Group scale of more than 3. Radiotherapy was given to the field, including the tumor, with generous margin using 6- or 10-MV X-rays. The mean radiation dose was 48.2 ± 7.9 Gy in daily 1.8-Gy fractions. The tumor response was assessed based on diagnostic radiologic examinations, including a computed tomography scan, magnetic resonance imaging, and hepatic artery angiography 4-8 weeks after the completion of treatment. Liver toxicity and gastrointestinal complications were evaluated. Results: An objective response was observed in 106 of 158 (67.1%) patients. Statistical analysis revealed that the total dose was the most significant factor associated with the tumor response. The response rates in patients treated with doses 50 Gy were 29.2%, 68.6%, and 77.1%, respectively. Survivals at 1 and 2 years after radiotherapy were 41.8% and 19.9%, respectively, with a median survival time of 10 months. The rate of liver toxicity according to the doses 50 Gy was 4.2%, 5.9%, and 8.4%, respectively, and the rate of gastrointestinal complications was 4.2%, 9.9%, and 13.2%, respectively. Conclusions: The present study showed the existence of a dose-response relationship in local radiotherapy for primary HCC. Only the radiation dose was a significant factor for predicting an objective response. The results of this study showed that 3D

Tumor and normal tissue responses to fractioned non-uniform dose delivery

Energy Technology Data Exchange (ETDEWEB)

Kaellman, P; Aegren, A; Brahme, A [Karolinska Inst., Stockholm (Sweden). Dept. of Radiation Physics

1996-08-01

The volume dependence of the radiation response of a tumor is straight forward to quantify because it depends primarily on the eradication of all its clonogenic cells. A tumor therefore has a parallel organization as any surviving clonogen in principle can repopulate the tumor. The difficulty with the response of the tumor is instead to know the density and sensitivity distribution of the most resistant clonogenic cells. The increase in the 50% tumor control dose and the decrease in the maximum normalized slope of the dose response relation, {gamma}, in presence of small compartments of resistant tumor cells have therefore been quantified to describe their influence on the dose response relation. Injury to normal tissue is a much more complex and gradual process. It depends on earlier effects induced long before depletion of the differentiated and clonogenic cells that in addition may have a complex structural and functional organization. The volume dependence of the dose response relation of normal tissues is therefore described here by the relative seriality, s, of the infrastructure of the organ. The model can also be generalized to describe the response of heterogeneous tissues to non uniform dose distributions. The new model is compared with clinical and experimental data on normal tissue response, and shows good agreement both with regard to the shape of dose response relation and the volume dependence of the isoeffect dose. The response of tumors and normal tissues are quantified for arbitrary dose fractionations using the linear quadratic cell survival parameters {alpha} and {beta}. The parameters of the dose response relation are derived both for a constant dose per fraction and a constant number of dose fractions, thus in the latter case accounting also for non uniform dose delivery. (author). 26 refs, 4 figs.

Some Qualitative Requirements for Testing of Nuclear Emergency Response Robots

International Nuclear Information System (INIS)

Eom, Heungseop; Cho, Jai Wan; Choi, Youngsoo; Jeong, Kyungmin

2014-01-01

Korea Atomic Energy Research Institute (KAERI) is carrying out the project 'Development of Core Technology for Remote Response in Nuclear Emergency Situation', and as a part of the project, we are studying the reliability and performance requirements of nuclear emergency response robots. In this paper, we described some qualitative requirements for testing of nuclear emergency response robots which are different to general emergency response robots. We briefly introduced test requirements of general emergency response robots and described some qualitative aspects of test requirements for nuclear emergency response robots. When considering an immature field-robot technology and variety of nuclear emergency situations, it seems hard to establish quantitative test requirements of these robots at this time. However, based on studies of nuclear severe accidents and the experience of Fukushima NPP accident, we can expect some test requirements including quantitative ones for nuclear emergency response robots

Radiological Emergency Response Health and Safety Manual

Energy Technology Data Exchange (ETDEWEB)

D. R. Bowman

2001-05-01

This manual was created to provide health and safety (H&S) guidance for emergency response operations. The manual is organized in sections that define each aspect of H and S Management for emergency responses. The sections are as follows: Responsibilities; Health Physics; Industrial Hygiene; Safety; Environmental Compliance; Medical; and Record Maintenance. Each section gives guidance on the types of training expected for managers and responders, safety processes and procedures to be followed when performing work, and what is expected of managers and participants. Also included are generic forms that will be used to facilitate or document activities during an emergency response. These ensure consistency in creating useful real-time and archival records and help to prevent the loss or omission of information.

Science in Emergency Response at CDC: Structure and Functions.

Science.gov (United States)

Iskander, John; Rose, Dale A; Ghiya, Neelam D

2017-09-01

Recent high-profile activations of the US Centers for Disease Control and Prevention (CDC) Emergency Operations Center (EOC) include responses to the West African Ebola and Zika virus epidemics. Within the EOC, emergency responses are organized according to the Incident Management System, which provides a standardized structure and chain of command, regardless of whether the EOC activation occurs in response to an outbreak, natural disaster, or other type of public health emergency. By embedding key scientific roles, such as the associate director for science, and functions within a Scientific Response Section, the current CDC emergency response structure ensures that both urgent and important science issues receive needed attention. Key functions during emergency responses include internal coordination of scientific work, data management, information dissemination, and scientific publication. We describe a case example involving the ongoing Zika virus response that demonstrates how the scientific response structure can be used to rapidly produce high-quality science needed to answer urgent public health questions and guide policy. Within the context of emergency response, longer-term priorities at CDC include both streamlining administrative requirements and funding mechanisms for scientific research.

Radiation Emergency Planning in Petroleum Industry

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.; El-Naggar, M.A.; Abdel-Fattah, A.T.; Gomaa, A.M.

2001-01-01

Similar to all industrial activities utilizing radiation sources, or dealing with radioactive materials in its operations, petroleum industry requires the organization of a Radiation Emergency Plan. This plan should be based on a comprehensive and subtle understanding of the extensive multidisciplinary operations involved in petroleum processing and the dangers that threaten human health, environment and property; both from ordinary emergency situations common to petroleum industry activities and also from radiation emergency events. Radiation emergencies include radiological source accidents involving occurrence of high dose exposures. Radioactive contamination or spill are also major problems that may cause low dose exposures and environmental radioactive contamination. The simultaneous occurrence of other industrial emergency events such as fires or structural collapses will add to the seriousness of the emergency situation. The essential aspects of Radiation Emergency Planning include notification, assessment of situation, foresight, definition of roles and responsibilities including health safety and environmental concepts. An important contribution to the Emergency Planning is the proper intelligent medical response. Another essential parameter is the training of personnel that will undertake the responsibility of executing the emergency procedures according to the various emergency situations. The main features of the radiation Emergency Plan in Petroleum industry is presented in the text

Radioactive materials transportation emergency response plan

International Nuclear Information System (INIS)

Karmali, N.

1987-05-01

Ontario Hydro transports radioactive material between its nuclear facilities, Atomic Energy of Canada Limited at Chalk River Laboratories and Radiochemical Company in Kanata, on a regular basis. Ontario Hydro also occasionally transports to Whiteshell Laboratories, Hydro-Quebec and New Brunswick Electric Power Commission. Although there are stringent packaging and procedural requirements for these shipments, Ontario Hydro has developed a Radioactive Materials Transportation Emergency Response Plan in the event that there is an accident. The Transportation Emergency Response plan is based on six concepts: 1) the Province id divided into three response areas with each station (Pickering, Darlington, Bruce) having identified response areas; 2) response is activated via a toll-free number. A shift supervisor at Pickering will answer the call, determine the hazards involved from the central shipment log and provide on-line advice to the emergency worker. At the same time he will notify the nearest Ontario Hydro area office to provide initial corporate response, and will request the nearest nuclear station to provide response assistance; 3) all stations have capability in terms of trained personnel and equipment to respond to an accident; 4) all Ontario Hydro shipments are logged with Pickering NGS. Present capability is based on computerized logging with the computer located in the shift office at Pickering to allow quick access to information on the shipment; 5) there is a three tier structure for emergency public information. The local Area Manager is the first Ontario Hydro person at the scene of the accident. The responding facility technical spokesperson is the second line of Corporate presence and the Ontario Hydro Corporate spokesperson is notified in case the accident is a media event; and 6) Ontario Hydro will respond to non-Hydro shipments of radioactive materials in terms of providing assistance, guidance and capability. However, the shipper is responsible

Establishment and verification of dose-response curve of chromosomal aberrations after exposure to very high dose γ-ray

International Nuclear Information System (INIS)

Chen Ying; Luo Yisheng; Cao Zhenshan; Liu Xiulin

2006-01-01

To estimate accurately biological dose of the victims exposed to high dose, the dose-response curves of chromosome aberration induced by 6-22 Gy 60 Co γ-ray were established. Human peripheral blood in vitro was irradiated, then lymphocytes were concentrated, cultured 52h, 68h and 72h and harvested. The frequencies of dicentrics (multi-centrics) and rings were counted and compared between different culture times. The dose-response curves and equations were established, as well as verified with high dose exposure accidents. The experiment showed that the culture time should be prolonged properly after high dose exposure, and no significant differences were observed between 52-72h culture. The dose-response curve of 6-22 Gy fitted to linear-square model Y=-2.269 + 0.776D - 7.868 x 10 -3 D 2 and is reliable through verification of the accident dose estimations. In this study, the dose-response curve and equation of chromosome dic + r after 6-22 Gy high dose irradiation were established firstly, and exact dose estimation can be achieved according to it. (authors)

System for prediction of environmental emergency dose information

International Nuclear Information System (INIS)

Moriuchi, Shigeru

1989-01-01

According to the national research program revised by the Japan Nuclear Safety Commission after the TMI-2 reactor accident JAERI started the development of a computer code system for the real-time prediction of environmental consequences following a nuclear reactor accident, and in 1985 the basic development of the System for Prediction of Environmental Emergency Dose Information SPEEDI was completed. The system consists of three-dimensional models of wind field calculation (WIND04), dispersion calculation (PRWDA) and internal and external dose calculation (CIDE), and is designed to speedily predict radioactive concentration in the air, the ground deposition and radiation doses of upto 100 km range by simulation calculation when the radioactive materials are accidentally released from a reactor. At Chernobyl accident the calculational domain of SPEEDI were extended tentatively upto 2000 km, and simulation calculations of the movement of radioactive cloud were executed, and the estimation of the amounts of released radioactivities were made using calculated results and observed data. The calculated distribution and the movement of plume well agreed with the distribution patterns evaluated from observation data, and the estimated source term agreed approximately with data reported from USSR and other countries. (author)

Cytogenetics dosimetry: dose-response curve for low doses of X-ray

International Nuclear Information System (INIS)

Lara, Virginia E. Noval; Pineda Bolivar, William R.; Riano, Victor M. Pabon; Ureana, Cecilia Crane

2013-01-01

The purpose of this study was to conduct a preliminary study for the standardization in the future, the dose-response curve for low doses of X-rays, through the analysis of in vitro cultures of peripheral blood samples of 3 men and 3 women occupationally not exposed to artificial sources of ionizing radiation, age 18-40 years, where possible nonsmokers

Remifentanil dose for laryngeal mask airway insertion with a single standard dose of propofol during emergency airway management in elderly patients.

Science.gov (United States)

Ryu, Junghee; Oh, Ah Young; Baek, Ji-Seok; Kim, Jin-Hee; Park, Sang-Heon; Noh, Jae-Mun

2014-04-01

This study determined the dose of remifentanil to use during insertion of a Classic™ laryngeal mask airway (LMA, The Laryngeal Mask Co., Nicosia, Cyprus) in elderly patients during emergency airway management when combined with a single dose of propofol. Patients aged 65-80 years were enrolled. Anesthesia was induced with propofol 1 mg/kg, and then a blinded dose of remifentanil was infused over 30 s after confirming the patient's loss of consciousness. The dose of remifentanil was determined using Dixon's up-and-down method, starting at 0.5 µg/kg (a step size of 0.1 µg/kg). Insertion of the LMA was attempted 60 s after loss of consciousness. In total, 23 patients were recruited and the mean age ± standard deviation was 72 ± 3 years. The effective dose for successful LMA insertion in 50% of the patients (ED50) was 0.20 ± 0.05 µg/kg. No patient needed more than 0.3 µg/kg. Remifentanil 0.20 ± 0.05 µg/kg with propofol 1 mg/kg resulted in excellent LMA insertion in 50% of elderly patients without significant hemodynamic changes during emergency airway management.

Emergency response and radiation monitoring systems in Russian regions

International Nuclear Information System (INIS)

Arutyunyan, R.; Osipiyants, I.; Kiselev, V.; Ogar, K; Gavrilov, S.

2008-01-01

Full text: Preparedness of the emergency response system to elimination of radiation incidents and accidents is one of the most important elements of ensuring safe operation of nuclear power facilities. Routine activities on prevention of emergency situations along with adequate, efficient and opportune response actions are the key factors reducing the risks of adverse effects on population and environment. Both high engineering level and multiformity of the nuclear branch facilities make special demands on establishment of response system activities to eventual emergency situations. First and foremost, while resolving sophisticated engineering and scientific problems emerging during the emergency response process, one needs a powerful scientific and technical support system.The emergency response system established in the past decade in Russian nuclear branch provides a high efficiency of response activities due to the use of scientific and engineering potential and experience of the involved institutions. In Russia the responsibility for population protection is imposed on regional authority. So regional emergence response system should include up-to-date tools of radiation monitoring and infrastructure. That's why new activities on development of radiation monitoring and emergency response system were started in the regions of Russia. The main directions of these activities are: 1) Modernization of the existing and setting-up new facility and territorial automatic radiation monitoring systems, including mobile radiation surveillance kits; 2) Establishment of the Regional Crisis Centres and Crisis Centres of nuclear and radiation hazardous facilities; 3) Setting up communication systems for transfer, acquisition, processing, storage and presentation of data for participants of emergency response at the facility, regional and federal levels; 4) Development of software and hardware systems for expert support of decision-making on protection of personnel, population

Emergency Response to Radioactive Material Transport Accidents

International Nuclear Information System (INIS)

EL-shinawy, R.M.K.

2009-01-01

Although transport regulations issued by IAEA is providing a high degree of safety during transport opertions,transport accidents involving packages containing radioactive material have occurred and will occur at any time. Whenever a transport accident involving radioactive material accurs, and many will pose no radiation safety problems, emergency respnose actioms are meeded to ensure that radiation safety is maintained. In case of transport accident that result in a significant relesae of radioactive material , loss of shielding or loss of criticality control , that consequences should be controlled or mitigated by proper emergency response actions safety guide, Emergency Response Plamming and Prepardness for transport accidents involving radioactive material, was published by IAEA. This guide reflected all requirememts of IAEA, regulations for safe transport of radioactive material this guide provide guidance to the publicauthorites and other interested organziation who are responsible for establishing such emergency arrangements

Hanford Emergency Response Plan

International Nuclear Information System (INIS)

Wagoner, J.D.

1994-04-01

The Hanford Emergency Response Plan for the US Department of Energy (DOE), Richland Operations Office (RL), incorporates into one document an overview of the emergency management program for the Hanford Site. The program has been developed in accordance with DOE orders, and state and federal regulations to protect worker and public health and safety and the environment in the event of an emergency at or affecting the Hanford Site. This plan provides a description of how the Hanford Site will implement the provisions of DOE 5500 series and other applicable Orders in terms of overall policies and concept of operations. It should be used as the basis, along with DOE Orders, for the development of specific contractor and RL implementing procedures

Hanford Emergency Response Plan

Energy Technology Data Exchange (ETDEWEB)

Wagoner, J.D.

1994-04-01

The Hanford Emergency Response Plan for the US Department of Energy (DOE), Richland Operations Office (RL), incorporates into one document an overview of the emergency management program for the Hanford Site. The program has been developed in accordance with DOE orders, and state and federal regulations to protect worker and public health and safety and the environment in the event of an emergency at or affecting the Hanford Site. This plan provides a description of how the Hanford Site will implement the provisions of DOE 5500 series and other applicable Orders in terms of overall policies and concept of operations. It should be used as the basis, along with DOE Orders, for the development of specific contractor and RL implementing procedures.

IEA Response System for Oil Supply Emergencies

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-12-15

Emergency response to oil supply disruptions has remained a core mission of the International Energy Agency since its founding in 1974. This information pamphlet explains the decisionmaking process leading to an IEA collective action, the measures available -- focusing on stockdraw -- and finally, the historical background of major oil supply disruptions and the IEA response to them. It also demonstrates the continuing need for emergency preparedness, including the growing importance of engaging key transition and emerging economies in dialogue about energy security.

IEA Response System for Oil Supply Emergencies

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-15

Emergency response to oil supply disruptions has remained a core mission of the International Energy Agency since its founding in 1974. This information pamphlet explains the decisionmaking process leading to an IEA collective action, the measures available -- focusing on stockdraw -- and finally, the historical background of major oil supply disruptions and the IEA response to them. It also demonstrates the continuing need for emergency preparedness, including the growing importance of engaging key transition and emerging economies in dialogue about energy security.

Dose-response relationship for breast cancer induction at radiotherapy dose

Directory of Open Access Journals (Sweden)

Gruber Günther

2011-06-01

Full Text Available Abstract Purpose Cancer induction after radiation therapy is known as a severe side effect. It is therefore of interest to predict the probability of second cancer appearance for the patient to be treated including breast cancer. Materials and methods In this work a dose-response relationship for breast cancer is derived based on (i the analysis of breast cancer induction after Hodgkin's disease, (ii a cancer risk model developed for high doses including fractionation based on the linear quadratic model, and (iii the reconstruction of treatment plans for Hodgkin's patients treated with radiotherapy, (iv the breast cancer induction of the A-bomb survivor data. Results The fitted model parameters for an α/β = 3 Gy were α = 0.067Gy-1 and R = 0.62. The risk for breast cancer is according to this model for small doses consistent with the finding of the A-bomb survivors, has a maximum at doses of around 20 Gy and drops off only slightly at larger doses. The predicted EAR for breast cancer after radiotherapy of Hodgkin's disease is 11.7/10000PY which can be compared to the findings of several epidemiological studies where EAR for breast cancer varies between 10.5 and 29.4/10000PY. The model was used to predict the impact of the reduction of radiation volume on breast cancer risk. It was estimated that mantle field irradiation is associated with a 3.2-fold increased risk compared with mediastinal irradiation alone, which is in agreement with a published value of 2.7. It was also shown that the modelled age dependency of breast cancer risk is in satisfying agreement with published data. Conclusions The dose-response relationship obtained in this report can be used for the prediction of radiation induced secondary breast cancer of radiotherapy patients.

Emergency response plan for accidents in Saudi Arabia

International Nuclear Information System (INIS)

Al-Solaiman, K.M.; Al-Arfaj, A.M.; Farouk, M.A.

2000-01-01

This paper presents a brief description of the general emergency plan for accidents involving radioactive materials in the Kingdom of Saudi Arabia. Uses of radioactive materials and radiation sources and their associated potential accident are specified. Most general accident scenarios of various levels have been determined. Protective measures have been specified to reduce individual and collective doses arising during accident situations. Intervention levels for temporary exposure situations, as established in the IAEA's basic safety standards for protection against ionising radiation and for the safety of radiation sources, are adopted as national intervention levels. General procedures for implementation of the response plan, including notification and radiological monitoring instrumentation and equipment, are described and radiation monitoring teams are nominated. Training programs for the different parties which may be called upon to respond are studied and will be started. (author)

Nuclear emergency planning and response in the Netherlands: Experiences obtained from large scale exercises

International Nuclear Information System (INIS)

Smetsers, R.C.G.M.; Pruppers, M.J.M.; Sonderen, J.F. van

2000-01-01

In 1986 the Chernobyl accident led the Dutch Government to a reconsideration of their possibilities for managing nuclear emergencies. It was decided to improve both the national emergency management organization and the infrastructure for collecting and presenting technical information. The first improvement resulted in the National Plan for Nuclear Emergency Planning and Response (EPR) and the second in a series of technical facilities for the assessment of radiation doses. Since 1990, following the implementation of the EPR and most of the technical facilities, several emergency exercises have taken place to test the effectiveness of organization and infrastructure. Special emphasis has been given to the early phase of the simulated accidents. This paper summarises the experiences obtained from these exercises. Major obstacles appear to be: (1) keeping all participants properly informed during the process, (2) the difference in working attitude of technical experts and decision-makers, (3) premature orders for countermeasures and (4) the (too) large number of people involved in the decision-making process. From these experiences requirements for instruments can be deduced. Such instruments include predictive models, to be used for dose assessment in the early phase of an accident which, apart from being fast, should yield uncomplicated results suitable for decision-makers. Refinements of models, such as taking into account the specific nature of the (urban) environment, are not needed until the recovery phase of a nuclear accident. (author)

Chinese experience on medical response to radiation emergencies

International Nuclear Information System (INIS)

Liu, Ying; Qin, Bin; Lei, Cuiping; Chen, Huifang; Han, Yuhong

2008-01-01

Full text: Chinese Center for Medical Response to Radiation Emergency (CCMRRE) was established in 1992, based on the National Institute for Radiological Protection, China CDC (NIRP, China CDC). CCMRRE is a liaison of WHO/REMPAN and functions as a national and professional institute for medical preparedness and response to emergencies involving radioactive material. CCMRRE participates in drafting National Medical Assistant Program for Radiation Emergency and relevant technical documents, develops preventive measures and technique means of medical preparedness and response to radiation emergency. CCMRRE is responsible for medical response to radiological or nuclear accident on national level. CCMRRE holds training courses, organizes drills and provides technical support to local medical organizations in practicing medical preparedness and response to radiation emergency. CCMRRE collects, analyzes and exchanges information on medical response to radiological and nuclear emergency and establishes relevant database. CCMRRE also guides and participates in radiation pollution monitoring on accident sites. In the past ten years, we accumulate much knowledge and experience on medical response to radiation emergencies. In this context, we will discuss Xinzhou Accident, which took place in 1992 and involved in three deaths, and Ha'erbin Accident that took place in 2005 and involved one death. A father and two brothers in Xinzhou Accident died of over-exposed to 60 Co source and misdiagnosis and improper treatment, which indicates that most general practitioners are uncertain about the health consequences of exposure to ionizing radiation and the medical management of exposed patients. When Ha'erbin Accident happened in 2005, the local hospital gave the right diagnosis and treatment based on the clinic symptoms and signs, which prevent more people suffering from over-expose to 192 Ir source. The distinct changes comes from the education and training to primary doctors related

First Response to Medical Emergency

International Nuclear Information System (INIS)

Manisah Saedon; Sarimah Mahat; Muhamad Nurfalah Karoji; Hasnul Nizam Osman

2015-01-01

Accident or medical emergencies, both minor and critical, occurs each day and can happen in any workplace. In any medical emergencies, time is a critical factor because the first person to arrive at the scene of an accident has a key role in the rescue of a victim. With the knowledge of some common medical procedures and emergency actions, this first responder can make a positive contribution to the welfare of the accident victim. In some cases, this contribution can make difference between life and death. Improper response to medical emergencies by an untrained person can result in worsen injuries or death. Therefore, first aids training are necessary to provide the information. (author)

Oil supply security: the emergency response potential of IEA countries

International Nuclear Information System (INIS)

1995-01-01

This work deals with the oil supply security and more particularly with the emergency response potential of International Energy Agency (IEA) countries. The first part describes the changing pattern of IEA emergency response requirements. It begins with the experience from the past, then gives the energy outlook to 2010 and ends with the emergency response policy issues for the future. The second part is an overview on the IEA emergency response potential which includes the organisation, the emergency reserves, the demand restraint and the other response mechanisms. The third part gives the response potential of individual IEA countries. The last part deals with IEA emergency response in practice and more particularly with the gulf crisis of 1990-1991. It includes the initial problems raised by the gulf crisis, the adjustment and preparation and the onset of military action with the IEA response.(O.L.). 7 figs., 85 tabs

Understanding Public Responses to Emerging Technologies

NARCIS (Netherlands)

Macnaghten, Philip; Davies, S.R.; Kearnes, Matthew

2015-01-01

Previous studies aimed at understanding public responses to emerging technologies have given limited attention to the social and cultural processes through which public concerns emerge. When probed, these have tended to be explained either in cognitive social psychological terms, typically in the

The Key Events Dose-Response Framework: a cross-disciplinary mode-of-action based approach to examining dose-response and thresholds.

Science.gov (United States)

Julien, Elizabeth; Boobis, Alan R; Olin, Stephen S

2009-09-01

The ILSI Research Foundation convened a cross-disciplinary working group to examine current approaches for assessing dose-response and identifying safe levels of intake or exposure for four categories of bioactive agents-food allergens, nutrients, pathogenic microorganisms, and environmental chemicals. This effort generated a common analytical framework-the Key Events Dose-Response Framework (KEDRF)-for systematically examining key events that occur between the initial dose of a bioactive agent and the effect of concern. Individual key events are considered with regard to factors that influence the dose-response relationship and factors that underlie variability in that relationship. This approach illuminates the connection between the processes occurring at the level of fundamental biology and the outcomes observed at the individual and population levels. Thus, it promotes an evidence-based approach for using mechanistic data to reduce reliance on default assumptions, to quantify variability, and to better characterize biological thresholds. This paper provides an overview of the KEDRF and introduces a series of four companion papers that illustrate initial application of the approach to a range of bioactive agents.

Skull base chordomas: analysis of dose-response characteristics

International Nuclear Information System (INIS)

Niemierko, Andrzej; Terahara, Atsuro; Goitein, Michael

1997-01-01

Objective: To extract dose-response characteristics from dose-volume histograms and corresponding actuarial survival statistics for 115 patients with skull base chordomas. Materials and Methods: We analyzed data for 115 patients with skull base chordoma treated with combined photon and proton conformal radiotherapy to doses in the range 66.6Gy - 79.2Gy. Data set for each patient included gender, histology, age, tumor volume, prescribed dose, overall treatment time, time to recurrence or time to last observation, target dose-volume histogram, and several dosimetric parameters (minimum/mean/median/maximum target dose, percent of the target volume receiving the prescribed dose, dose to 90% of the target volume, and the Equivalent Uniform Dose (EUD). Data were analyzed using the Kaplan-Meier survivor function estimate, the proportional hazards (Cox) model, and parametric modeling of the actuarial probability of recurrence. Parameters of dose-response characteristics were obtained using the maximum likelihood method. Results: Local failure developed in 42 (36%) of patients, with actuarial local control rates at 5 years of 59.2%. The proportional hazards model revealed significant dependence of gender on the probability of recurrence, with female patients having significantly poorer prognosis (hazard ratio of 2.3 with the p value of 0.008). The Wilcoxon and the log-rank tests of the corresponding Kaplan-Meier recurrence-free survival curves confirmed statistical significance of this effect. The Cox model with stratification by gender showed significance of tumor volume (p=0.01), the minimum target dose (p=0.02), and the EUD (p=0.02). Other parameters were not significant at the α level of significance of 0.05, including the prescribed dose (p=0.21). Parametric analysis using a combined model of tumor control probability (to account for non-uniformity of target dose distribution) and the Weibull failure time model (to account for censoring) allowed us to estimate

Dose-response analysis using R

DEFF Research Database (Denmark)

Ritz, Christian; Baty, Florent; Streibig, Jens Carl

2015-01-01

Dose-response analysis can be carried out using multi-purpose commercial statistical software, but except for a few special cases the analysis easily becomes cumbersome as relevant, non-standard output requires manual programming. The extension package drc for the statistical environment R provides...

Communication with the Public in a Nuclear or Radiological Emergency. Emergency Preparedness and Response

International Nuclear Information System (INIS)

2012-05-01

The aim of this publication is to provide practical guidance for public information officers on the preparation for and response to a nuclear or radiological emergency, and to fulfil in part functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), as well as meeting requirements stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, and in IAEA Safety Standards No. GS-R-2, Preparedness and Response for a Nuclear or Radiological Emergency. Under Article 5(a)(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. IAEA Safety Standards Series No. GS-R-2 establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, and specifies that 'All practicable steps shall be taken to provide the public with useful, timely, truthful, consistent and appropriate information throughout a nuclear or radiological emergency' in the response phase. It also requires 'responding to incorrect information and rumours; and responding to requests for information from the public and from the news and information media'. This publication provides guidance in the form of action guides and information sheets that can be easily applied by a State to build a basic capability to respond to a nuclear or radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This publication is published as part of the IAEA's Emergency Preparedness and Response series and complements the Manual for First Responders to a Radiological Emergency in the parts related to the tasks of public information officers. It takes

Dose assessment of the patient and the helper in emergency head computed tomography

International Nuclear Information System (INIS)

Chang, Rong-Chou; Yu, Cheng-Ching; Hsu, Fang-Yuh; Chen, Tou-Rong; Hsu, Shih-Ming; Tyan, Yeu-Sheng

2011-01-01

Computed Tomography (CT) becomes more and more important and is frequently used in modern diagnostic techniques. CT offers an effective diagnosis on lesion and pathology; however, it also delivers a radiation dose to patients. Besides, in some special emergency cases, the patient may require someone to help him in the examination room to perform the head CT, due to the patient lost intellectual and operational capacity. This study evaluated the delivered radiation dose and the risk of radiation-induced cancer for the patient and for the helper after carrying out the emergent head CT examination. A Rando phantom with thermoluminescent dosimeter (TLD) chips inside relevant organs was used to simulate the patient during head CT examination. An effective dose of 2.06 ± 0.16 mSv and 1.46 ± 0.07 mSv without and with wearing the lead apron were found respectively, considering ICRP 60 recommendation. ICRP 103 recommendations the readings would have been 1.29 ± 0.15 mSv and 0.71 ± 0.04 mSv. The effective dose determined from the dose-length product (DLP) method (2.19 mSv) was similar to the value (2.06 ± 0.16 mSv) estimated by TLD method considering the ICRP 60 recommendation (without lead apron). Assuming a 5% total risk for fatal cancer per Sv in the general population, risk of radiation-induced cancer for patients were 1.03 × 10 −2 % (without lead apron) and 7.80 × 10 −3 % (with lead apron) for ICRP 60, and were 6.45 × 10 −3 % (without lead apron) and 3.55 × 10 −3 % (with lead apron) for ICRP 103. The dose received by the helper was assessed by wearing a personal badge. The helper during emergent head CT examination may receive a personal dose equivalent (H p (10)) of 19.36 ± 5.89 μSv and 138.81 ± 101.28 μSv with and without lead apron, respectively, at distance of 0.3–1 m from the center of CT scanner. Based on the observed dose reduction of a factor of 7.17 we recommend that helpers wear lead apron in the CT examination room.

Disaster Monitoring and Emergency Response Services in China

Science.gov (United States)

Wu, J.; Han, X.; Zhou, Y.; Yue, P.; Wang, X.; Lu, J.; Jiang, W.; Li, J.; Tang, H.; Wang, F.; Li, X.; Fan, J.

2018-04-01

The Disaster Monitoring and Emergency Response Service(DIMERS) project was kicked off in 2017 in China, with the purpose to improve timely responsive service of the institutions involved in the management of natural disasters and man-made emergency situations with the timely and high-quality products derived from Space-based, Air-based and the in-situ Earth observation. The project team brought together a group of top universities and research institutions in the field of Earth observations as well as the operational institute in typical disaster services at national level. The project will bridge the scientific research and the response services of massive catastrophe in order to improve the emergency response capability of China and provide scientific and technological support for the implementation of the national emergency response strategy. In response to the call for proposal of "Earth Observation and Navigation" of 2017 National Key R&D Program of China, Professor Wu Jianjun, the deputy chairman of Faculty of Geographical Science of Beijing Normal University, submitted the Disaster Monitoring and Emergency Response Service (DIMERS) project, jointly with the experts and scholars from Institute of Remote Sensing and Digital Earth, Chinese Academy of Sciences, Wuhan University, China Institute of Earthquake Forecasting of China Earthquake Administration and China Institute of Water Resources and Hydropower Science. After two round evaluations, the proposal was funded by Ministry of Science and Technology of China.

RADIOIODINE TREATMENT OF GRAVES’ DISEASE – DOSE/RESPONSE ANALYSIS

Directory of Open Access Journals (Sweden)

Jitka Čepková

2014-01-01

Full Text Available The clinical outcome of 153 Graves’ disease patients treated with a wide dose range of radioactive iodine-131 (RAI was analyzed retrospectively. Six to nine months after the first dose of RAI 60 patients (39% were hypothyroid (or rather thyroxine-substituted and 26 (17% were euthyroid, while 67 patients (44% did not respond properly: in 32 (21% their antithyroid drug (ATD dose could be reduced but not withdrawn (partial response and 35 (23% remained hyperthyroid or the same dose of ATD was necessary (no response. The outcome did not correspond significantly to the administered activity of RAI (medians 259, 259, 222, and 259 MBq for hypothyroid, euthyroid, partial, and no response subgroups, respectively, or the activity retained in the gland at 24 h (medians 127, 105, 143, and 152 MBq. The effect was, however, clearly, and in a stepwise pattern, dependent on initial thyroid volume (17, 26, 33 and 35 ml, P  6 MBq/g, cure rate 80% and lower (≤ 6 MBq/g, cure rate 46% doses gave highly significant difference (P < 0.001. With our dosing range we found a dose-dependent clinical outcome that suggests an optimum delivered dose near 6.5 MBq/g, resulting in successful treatment of ca 80% patients.

Dose escalation with 3-D CRT in prostate cancer: five year dose responses and optimal treatment

International Nuclear Information System (INIS)

Hanks, Gerald; Hanlon, Alexandra; Pinover, Wayne; Hunt, Margie; Movsas, Benjamin; Schultheiss, Timothy

1997-01-01

Purpose: To report 5 yr dose responses in prostate cancer patients treated with 3D-CRT and describe optimal treatment based on dose response. Methods: Dose escalation was studied in 233 consecutive patients treated with 3D-CRT between 3/89 and 10/92. All surviving patients have >32 mo follow-up, the median follow-up is 55 mo. Estimated logistic cumulative distribution functions (logit response models) fit to 5 yr actuarial bNED outcome are reported for 3 dose groups in each of 3 pretreatment PSA groupings (10-19.9 ng/ml and 20+ ng/ml); no dose response is observed for patients with pretreatment PSA <10 ng/ml. Logit response models fit to 5 yr actuarial late morbidity rates (grade 2 GI, grade 2 GU, grade 3,4 GI) are also reported for 4 dose groups. Patients are treated with CT planned 4-field conformal technique where the PTV encompasses the CTV by 1.0 cm in all directions including the anterior rectal wall margin. Patients are followed at 6 mo intervals with PSA and DRE, and bNED failure is defined as PSA ≥1.5 ng/ml and rising on two consecutive measures. The Fox Chase modification of the LENT morbidity scale is used for GI morbidity including any blood transfusion and/or more than 2 coagulations as a grade 3 event. GU morbidity follows the RTOG scale. Results: The logit response models based on 5 yr bNED results have slopes of 27% and 18% for pretreatment PSA grouping 10-19.9 ng/ml and 20+ ng/ml, respectively. The 50% bNED response is observed at 71 Gy and 80 Gy respectively, while the 80% bNED response is observed at 76 Gy for the 10-19.9 ng/ml group and estimated at 88 Gy for the 20+ ng/ml group. Logit dose response models for grade 2 GI and grade 2 GU morbidity show markedly different slopes, 23% versus 4%, respectively. The slope for grade 3,4 GI is 12%. The dose response model indicates grade 3,4 GI complication rates at 5 yrs are 8% at 76 Gy and 12% at 80 Gy. Conclusion: Based on 5 yr results, we can draw some conclusions about appropriate dose from these

Population variability in biological adaptive responses to DNA damage and the shapes of carcinogen dose-response curves

International Nuclear Information System (INIS)

Conolly, Rory B.; Gaylor, David W.; Lutz, Werner K.

2005-01-01

Carcinogen dose-response curves for both ionizing radiation and chemicals are typically assumed to be linear at environmentally relevant doses. This assumption is used to ensure protection of the public health in the absence of relevant dose-response data. A theoretical justification for the assumption has been provided by the argument that low dose linearity is expected when an exogenous agent adds to an ongoing endogenous process. Here, we use computational modeling to evaluate (1) how two biological adaptive processes, induction of DNA repair and cell cycle checkpoint control, may affect the shapes of dose-response curves for DNA-damaging carcinogens and (2) how the resulting dose-response behaviors may vary within a population. Each model incorporating an adaptive process was capable of generating not only monotonic dose-responses but also nonmonotonic (J-shaped) and threshold responses. Monte Carlo analysis suggested that all these dose-response behaviors could coexist within a population, as the spectrum of qualitative differences arose from quantitative changes in parameter values. While this analysis is largely theoretical, it suggests that (a) accurate prediction of the qualitative form of the dose-response requires a quantitative understanding of the mechanism (b) significant uncertainty is associated with human health risk prediction in the absence of such quantitative understanding and (c) a stronger experimental and regulatory focus on biological mechanisms and interindividual variability would allow flexibility in regulatory treatment of environmental carcinogens without compromising human health

Radiological emergency response - a functional approach

International Nuclear Information System (INIS)

Chowdhury, Prosanta

1997-01-01

The radiological emergency response program in the State of Louisiana is discussed. The improved approach intends to maximize the efficiency for both nuclear power plant and radiological emergency response as a whole. Several broad-based components are identified: cluster of 'nodes' are generated for each component; these 'nodes' may be divided into 'sub-nodes' which will contain some 'attributes'; 'relational bonds' among the 'attributes' will exist. When executed, the process begins and continues with the 'nodes' assuming a functional and dynamic role based on the nature and characteristics of the 'attributes'. The typical response based on stand-alone elements is eliminated; overlapping of functions is avoided, and is produced a well-structure and efficient organization

Numerical models and their role in emergency response: a perspective on dispersion modeling for emergency preparedness

International Nuclear Information System (INIS)

Greenly, G.D.; Dickerson, M.H.

1983-03-01

Numerical models on several levels of complexity should be available to the emergency response planner. They are a basic tool but must be used in conjunction with both measurements and experience. When these tools are used in a complimentary fashion they greatly enhance the capability of the consequence manager to respond in an emergency situation. Because each accident or incident develops it's own characteristics and requirements the system must be capable of a flexible response. Interaction and feedback between model results from a suite of models and measurements (including airborne measurements) serve the emergency response planner's spectrum of needs, ranging from planning exercises and emergency precalculations to a real-time emergency response

Dose-response relationships for environmentally mediated infectious disease transmission models.

Directory of Open Access Journals (Sweden)

Andrew F Brouwer

2017-04-01

Full Text Available Environmentally mediated infectious disease transmission models provide a mechanistic approach to examining environmental interventions for outbreaks, such as water treatment or surface decontamination. The shift from the classical SIR framework to one incorporating the environment requires codifying the relationship between exposure to environmental pathogens and infection, i.e. the dose-response relationship. Much of the work characterizing the functional forms of dose-response relationships has used statistical fit to experimental data. However, there has been little research examining the consequences of the choice of functional form in the context of transmission dynamics. To this end, we identify four properties of dose-response functions that should be considered when selecting a functional form: low-dose linearity, scalability, concavity, and whether it is a single-hit model. We find that i middle- and high-dose data do not constrain the low-dose response, and different dose-response forms that are equally plausible given the data can lead to significant differences in simulated outbreak dynamics; ii the choice of how to aggregate continuous exposure into discrete doses can impact the modeled force of infection; iii low-dose linear, concave functions allow the basic reproduction number to control global dynamics; and iv identifiability analysis offers a way to manage multiple sources of uncertainty and leverage environmental monitoring to make inference about infectivity. By applying an environmentally mediated infectious disease model to the 1993 Milwaukee Cryptosporidium outbreak, we demonstrate that environmental monitoring allows for inference regarding the infectivity of the pathogen and thus improves our ability to identify outbreak characteristics such as pathogen strain.

Aquatic emergency response model at the Savannah River Plant

International Nuclear Information System (INIS)

Hayes, D.W.

1987-01-01

The Savannah River Plant emergency response plans include a stream/river emergency response model to predict travel times, maximum concentrations, and concentration distributions as a function of time at selected downstream/river locations from each of the major SRP installations. The menu driven model can be operated from any of the terminals that are linked to the real-time computer monitoring system for emergency response

Some hybrid models applicable to dose-response relationships

International Nuclear Information System (INIS)

Kumazawa, Shigeru

1992-01-01

A new type of models of dose-response relationships has been studied as an initial stage to explore a reliable extrapolation of the relationships decided by high dose data to the range of low dose covered by radiation protection. The approach is to use a 'hybrid scale' of linear and logarithmic scales; the first model is that the normalized surviving fraction (ρ S > 0) in a hybrid scale decreases linearly with dose in a linear scale, and the second is that the induction in a log scale increases linearly with the normalized dose (τ D > 0) in a hybrid scale. The hybrid scale may reflect an overall effectiveness of a complex system against adverse events caused by various agents. Some data of leukemia in the atomic bomb survivors and of rodent experiments were used to show the applicability of hybrid scale models. The results proved that proposed models fit these data not less than the popular linear-quadratic models, providing the possible interpretation of shapes of dose-response curves, e.g. shouldered survival curves varied by recovery time. (author)

Method for developing arrangements for response to a nuclear or radiological emergency. Updating IAEA-TECDOC-953. Emergency preparedness and response. Publication date: October 2003

International Nuclear Information System (INIS)

2003-09-01

In 1997 the IAEA compiled, consolidated and organized existing information, and published the TECDOC-953 'Method for Development of Emergency Response Preparedness for Nuclear or Radiological Accidents'. Subsequently this publication was used extensively by the IAEA for training and for evaluation of emergency response programmes. In November 1999 a technical committee meeting (TCM) with representatives of over 20 States reviewed and provided feedback on IAEA-TECDOC-953. In March 2002, the IAEA's Board of Governors approved a Safety Requirements publication, 'Preparedness and Response for a Nuclear or Radiological Emergency', jointly sponsored by seven international organizations, which establishes the requirements for an adequate level of preparedness and response for a nuclear or radiological emergency in any State. The IAEA General Conference in resolution GC(46)/RES/9 encouraged Member States to implement, if necessary, instruments for improving their own preparedness and response capabilities for nuclear and radiological incidents and accidents, including their arrangements for responding to acts involving the malicious use of nuclear or radioactive material and to threats of such acts, and has further encouraged them to implement the Safety Requirements for Preparedness and Response to a Nuclear or Radiological Emergency. The obligations, responsibilities and requirements for preparedness and response for radiation emergencies are set out in the safety standards, in particular the 1996 'International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources'. Consensus information on relevant radiation protection criteria was established in 1994 and published in 'Intervention Criteria in a Nuclear or Radiation Emergency'. Several other guides and publications in the area of emergency preparedness and response had previously been issued. The present publication now being issued in the Emergency Preparedness and

Theory of thermoluminescence gamma dose response: The unified interaction model

International Nuclear Information System (INIS)

Horowitz, Y.S.

2001-01-01

We describe the development of a comprehensive theory of thermoluminescence (TL) dose response, the unified interaction model (UNIM). The UNIM is based on both radiation absorption stage and recombination stage mechanisms and can describe dose response for heavy charged particles (in the framework of the extended track interaction model - ETIM) as well as for isotropically ionising gamma rays and electrons (in the framework of the TC/LC geminate recombination model) in a unified and self-consistent conceptual and mathematical formalism. A theory of optical absorption dose response is also incorporated in the UNIM to describe the radiation absorption stage. The UNIM is applied to the dose response supralinearity characteristics of LiF:Mg,Ti and is especially and uniquely successful in explaining the ionisation density dependence of the supralinearity of composite peak 5 in TLD-100. The UNIM is demonstrated to be capable of explaining either qualitatively or quantitatively all of the major features of TL dose response with many of the variable parameters of the model strongly constrained by ancilliary optical absorption and sensitisation measurements

Emergency response in the Newfoundland offshore industry

Energy Technology Data Exchange (ETDEWEB)

Dempsey, J. [Cormorant Ltd., St. John' s, NL (Canada)

2006-07-01

This presentation reviewed current offshore oil activities with respect to safety issues regarding year-round marine operations in a harsh environment. Considerable logistics support is required for all offshore activities, including seismic and geotechnical surveys; exploration and production drilling; well testing; subsea construction; on-site production; and, delivery to market. Response to an offshore emergency must address the urgency of the incident along with stakeholder concerns. This presentation described the different types of emergencies and addressed issues regarding contingency planning; preventative measures; response philosophy; response scope; response at site; emergency management; communications links; and, oil spill response. The following current operations were highlighted: ExxonMobil's production drilling from the gravity-based concrete platform at Hibernia; Petro-Canada's production drilling at the Terra Nova FPSO; Husky Energy's production drilling at White Rose; and Chevron Canada's exploration drilling at the Orphan Basin. It was noted that in an emergency situation, the focus is on the welfare of offshore personnel. On an average day, the total offshore population is in the order of 1000 workers, all registered in the Personnel Logistics System which is updated with the departure of every helicopter from St. John's, Newfoundland or from the offshore platform. It is possible to prepare for foreseeable emergency incidents such as fire, explosion or gas leaks; spills to the marine environment; structural damage or collisions; persons lost at sea; helicopter or support vessel accidents; vessel sinking; sabotage; serious injuries or loss of life; severe ice events; and, loss of well control. The establishment of permanent safety zones at the Hibernia, White Rose and Terra Nova production fields are among the preventative measures, along with standby vessels that provide a rescue service for offshore installations

Emergency response in the Newfoundland offshore industry

International Nuclear Information System (INIS)

Dempsey, J.

2006-01-01

This presentation reviewed current offshore oil activities with respect to safety issues regarding year-round marine operations in a harsh environment. Considerable logistics support is required for all offshore activities, including seismic and geotechnical surveys; exploration and production drilling; well testing; subsea construction; on-site production; and, delivery to market. Response to an offshore emergency must address the urgency of the incident along with stakeholder concerns. This presentation described the different types of emergencies and addressed issues regarding contingency planning; preventative measures; response philosophy; response scope; response at site; emergency management; communications links; and, oil spill response. The following current operations were highlighted: ExxonMobil's production drilling from the gravity-based concrete platform at Hibernia; Petro-Canada's production drilling at the Terra Nova FPSO; Husky Energy's production drilling at White Rose; and Chevron Canada's exploration drilling at the Orphan Basin. It was noted that in an emergency situation, the focus is on the welfare of offshore personnel. On an average day, the total offshore population is in the order of 1000 workers, all registered in the Personnel Logistics System which is updated with the departure of every helicopter from St. John's, Newfoundland or from the offshore platform. It is possible to prepare for foreseeable emergency incidents such as fire, explosion or gas leaks; spills to the marine environment; structural damage or collisions; persons lost at sea; helicopter or support vessel accidents; vessel sinking; sabotage; serious injuries or loss of life; severe ice events; and, loss of well control. The establishment of permanent safety zones at the Hibernia, White Rose and Terra Nova production fields are among the preventative measures, along with standby vessels that provide a rescue service for offshore installations. Supply vessels are also

The development of nuclear power and emergency response

International Nuclear Information System (INIS)

Pan Ziqiang

2007-01-01

Nuclear power is a safe, clean energy, which has been evidenced by the history of nuclear power development. Nuclear power is associated with very low risk but not equal to zero. Accident emergency response and preparedness is a final barrier necessary to reduce potential risks that may arise from nuclear power plants, which must be enhanced. In the course of accident emergency response and preparedness, it is highly necessary to draw domestic and foreign experiences and lessons. Lastly, the paper presents the discussions of some issues which merit attention with respect to emergency response and preparedness in China. (authors)

Using risk based tools in emergency response

International Nuclear Information System (INIS)

Dixon, B.W.; Ferns, K.G.

1987-01-01

Probabilistic Risk Assessment (PRA) techniques are used by the nuclear industry to model the potential response of a reactor subjected to unusual conditions. The knowledge contained in these models can aid in emergency response decision making. This paper presents requirements for a PRA based emergency response support system to date. A brief discussion of published work provides background for a detailed description of recent developments. A rapid deep assessment capability for specific portions of full plant models is presented. The program uses a screening rule base to control search space expansion in a combinational algorithm

Multifraction dose response of growing and resting phase hair follicles

International Nuclear Information System (INIS)

Vegesna, V.; Withers, H.R.

1987-01-01

It has been established in both the clinic and the laboratory that there is a differentiation response to changes in dose per fraction in early and late responding tissues. To study one possible biological reason for differences in early and late responses. The authors selected one kind of cellular entity, the hair follicle, in two different phases of mitotic activity. The follicles are usually in a resting phase (7-12 wks), but mitotic activity can be initiated by plucking the club hairs. This was done on one half of the thorax and then exposing mice to doses of radiation (cesium gamma-ray). Dose responses for epilation between growing (early) and resting (late) follicles were compared for the same mouse. The fractionated response was studied by reducing the dose down to 2.5 Gy/fx. As the literature suggests, the total dose tolerated by a resting (late) follicle increased more than that for a growing (early) follicle

Emergency response facility technical data system of Taiwan Power Company

International Nuclear Information System (INIS)

Lin, E.; Liang, T.M.

1987-01-01

Taiwan Power Company (Taipower) has developed its emergency response facility program since 1981. This program is integrated with the following activities to enhance the emergency response capability of nuclear power plants: (1) survey of the plant instrumentation based on the requirements of R.G. 1.97; (2) improvement of plant specific emergency operating procedures based on the emergency response guidelines developed by the Owners group; (3) implementation of the detailed control room design review with the consideration of human engineering and task analysis; and (4) organization, staff and communication of emergency planning of nuclear power plant. The emergency response facility programs of Taipower are implemented in Chinshan (GE BWR4/MARK I), Kuosheng (GE BWR6/MARK III) and Maanshan (W PWR). The major items included in each program are: (1) to establish new buildings for On-Site Technical Support Center, Near-Site Emergency Operation Facility; (2) to establish an Emergency Executive Center at Taipower headquarters; (3) to establish the communication network between control room and emergency response facilities; and (4) to install a dedicated Emergency Response Facility Technical Data System (ERFTDS) for each plant. The ERFTDS provides the functions of data acquisition, data processing, data storage and display in meeting with the requirements of NUREG 0696. The ERFTDS is designed with plant specific requirements. These specific requirements are expected to be useful not only for the emergency condition but also for normal operation conditions

Radiological emergency response - a functional approach

Energy Technology Data Exchange (ETDEWEB)

Chowdhury, Prosanta [Louisiana Radiation Protection Div., Baton Rouge, LA (United States)

1997-12-31

The radiological emergency response program in the State of Louisiana is discussed. The improved approach intends to maximize the efficiency for both nuclear power plant and radiological emergency response as a whole. Several broad-based components are identified: cluster of `nodes` are generated for each component; these `nodes` may be divided into `sub-nodes` which will contain some `attributes`; `relational bonds` among the `attributes` will exist. When executed, the process begins and continues with the `nodes` assuming a functional and dynamic role based on the nature and characteristics of the `attributes`. The typical response based on stand-alone elements is eliminated; overlapping of functions is avoided, and is produced a well-structure and efficient organization 1 ref., 6 figs.; e-mail: prosanta at deq.state.la.us

Critical target and dose and dose-rate responses for the induction of chromosomal instability by ionizing radiation

Science.gov (United States)

Limoli, C. L.; Corcoran, J. J.; Milligan, J. R.; Ward, J. F.; Morgan, W. F.

1999-01-01

To investigate the critical target, dose response and dose-rate response for the induction of chromosomal instability by ionizing radiation, bromodeoxyuridine (BrdU)-substituted and unsubstituted GM10115 cells were exposed to a range of doses (0.1-10 Gy) and different dose rates (0.092-17.45 Gy min(-1)). The status of chromosomal stability was determined by fluorescence in situ hybridization approximately 20 generations after irradiation in clonal populations derived from single progenitor cells surviving acute exposure. Overall, nearly 700 individual clones representing over 140,000 metaphases were analyzed. In cells unsubstituted with BrdU, a dose response was found, where the probability of observing delayed chromosomal instability in any given clone was 3% per gray of X rays. For cells substituted with 25-66% BrdU, however, a dose response was observed only at low doses (1.0 Gy), the incidence of chromosomal instability leveled off. There was an increase in the frequency and complexity of chromosomal instability per unit dose compared to cells unsubstituted with BrdU. The frequency of chromosomal instability appeared to saturate around approximately 30%, an effect which occurred at much lower doses in the presence of BrdU. Changing the gamma-ray dose rate by a factor of 190 (0.092 to 17.45 Gy min(-1)) produced no significant differences in the frequency of chromosomal instability. The enhancement of chromosomal instability promoted by the presence of the BrdU argues that DNA comprises at least one of the critical targets important for the induction of this end point of genomic instability.

Analysis of emergency response after the Chernobyl accident in Belarus: observed and prevented medical consequences, lessons learned

International Nuclear Information System (INIS)

Buglova, E.; Kenigsberg, J.

1997-01-01

Belarus is one of the most contaminated Republic due to the Chernobyl accident. 23% of the entire area of Belarus was contaminated with radionuclides. To protect the population after the accident different types of protective actions were performed during all phases, based on various temporary dose limits. An analysis of conducted protective actions and lessons obtained during the emergency response is briefly presented

Harderian Gland Tumorigenesis: Low-Dose and LET Response

Energy Technology Data Exchange (ETDEWEB)

Chang, Polly Y. [SRI International, Menlo Park, CA (United States). Biosciences Div.; Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States). Life Sciences Div.; Cucinotta, Francis A. [Univ. of Nevada, Las Vegas, NV (United States). Dept. of Health Physics and Diagnostic Sciences; Bjornstad, Kathleen A. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States). Life Sciences Div.; Bakke, James [SRI International, Menlo Park, CA (United States). Biosciences Div.; Rosen, Chris J. [SRI International, Menlo Park, CA (United States). Biosciences Div.; Du, Nicholas [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States). Life Sciences Div.; Fairchild, David G. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States). Life Sciences Div.; Cacao, Eliedonna [Univ. of Nevada, Las Vegas, NV (United States). Dept. of Health Physics and Diagnostic Sciences; Blakely, Eleanor A. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States). Life Sciences Div.

2016-04-19

Increased cancer risk remains a primary concern for travel into deep space and may preclude manned missions to Mars due to large uncertainties that currently exist in estimating cancer risk from the spectrum of radiations found in space with the very limited available human epidemiological radiation-induced cancer data. Existing data on human risk of cancer from X-ray and gamma-ray exposure must be scaled to the many types and fluences of radiations found in space using radiation quality factors and dose-rate modification factors, and assuming linearity of response since the shapes of the dose responses at low doses below 100 mSv are unknown. The goal of this work was to reduce uncertainties in the relative biological effect (RBE) and linear energy transfer (LET) relationship for space-relevant doses of charged-particle radiation-induced carcinogenesis. The historical data from the studies of Fry et al. and Alpen et al. for Harderian gland (HG) tumors in the female CB6F1 strain of mouse represent the most complete set of experimental observations, including dose dependence, available on a specific radiation-induced tumor in an experimental animal using heavy ion beams that are found in the cosmic radiation spectrum. However, these data lack complete information on low-dose responses below 0.1 Gy, and for chronic low-dose-rate exposures, and there are gaps in the LET region between 25 and 190 keV/μm. In this study, we used the historical HG tumorigenesis data as reference, and obtained HG tumor data for 260 MeV/u silicon (LET ~70 keV/μm) and 1,000 MeV/u titanium (LET ~100 keV/μm) to fill existing gaps of data in this LET range to improve our understanding of the dose-response curve at low doses, to test for deviations from linearity and to provide RBE estimates. Animals were also exposed to five daily fractions of 0.026 or 0.052 Gy of 1,000 MeV/u titanium ions to simulate chronic exposure, and HG tumorigenesis from this fractionated study were compared to the

Proposal of a probabilistic dose-response model

International Nuclear Information System (INIS)

Barrachina, M.

1997-01-01

A biologically updated dose-response model is presented as an alternative to the linear-quadratic model currently in use for cancer risk assessment. The new model is based on the probability functions for misrepair and/or unrepair of DNA lesions, in terms of the radiation damage production rate in the cell (supposedly, a stem cell) and its repair-rate constant. The model makes use, interpreting it on the basis of misrepair probabilities, of the ''dose and dose-rate effectiveness factor'' of ICRP, and provides the way for a continuous extrapolation between the high and low dose-rate regions, ratifying the ''linear non-threshold hypothesis'' as the main option. Anyhow, the model throws some doubts about the additive property of the dose. (author)

Exploring mHealth Participation for Emergency Response Communities

Directory of Open Access Journals (Sweden)

David G. Schwartz

2017-03-01

Full Text Available We explore the challenges of participation by members of emergency response communities who share a similar condition and treatment, and are called upon to participate in emergency events experienced by fellow members. Smartphones and location-based social networking technologies present an opportunity to re-engineer certain aspects of emergency medical response. Life-saving prescription medication extended in an emergency by one individual to another occurs on a micro level, anecdotally documented. We illustrate the issues and our approach through the example of an app to support patients prone to anaphylaxis and prescribed to carry epinephrine auto-injectors. We address unique participation challenges in an mHealth environment in which interventions are primarily short-term interactions which require clear and precise decision-making and constant tracking of potential participants in responding to an emergency medical event. The conflicting effects of diffused responsibility and shared identity are identified as key factors in modeling participation.

Emergency preparedness and response

International Nuclear Information System (INIS)

Griffiths, M.

1996-01-01

After the Chernobyl accident, it became painfully obvious to the international community that there was an urgent need to establish a system for the coordination of international disaster assistance. It became the task of the United Nations Office for Disaster Relief (UNDRO) to develop such a system. The former UNDRO was subsumed into the Department of Humanitarian Affairs (DHA), established in January 1992 on the basis of UN General Assembly Resolution 46/182 adopted in December 1991, and the disaster relief system presently found in DHA is a further evolution of the system established by UNDRO. One particular importance in relation to nuclear accidents is the fact that UNDRO and the International Atomic Energy Agency (IAEA) signed a Memorandum of Understanding defining their respective responsibilities and the need for cooperation in case of accidents involving the unintentional release of nuclear radiation. In essence, the MOU makes it clear that the responsibilities of the IAEA, in connection with accidents at Nuclear Power Plants, related to the technical and radiological aspects, in particular to accident prevention, to the on-site preparedness, and to remedial measures within the 30-km zone outside the NPP. DHA's responsibilities, on the other hand, relate to the general preparedness and the rescue efforts outside the 30 km zone. In this respect, the preparedness and emergency response system is no different from the system employed in any other type of sudden-onset emergency

Low-dose radiation-induced adaptive response in bone marrow cells of mice

International Nuclear Information System (INIS)

Farooqi, Zeba; Kesavan, P.C.

1993-01-01

Using bone marrow cells of whole body irradiated mice, the cytogenetic adaptive response induced by low conditioning doses of gamma-rays was investigated. The conditioning doses (0.025 and 0.05 Gy) were given at a dose-rate of 1.67 Gy/min. The challenging dose of 1 Gy was given at a dose-rate of 0.045 Gy/s. The challenging dose was given at different time intervals after the conditioning dose. The time intervals between the conditioning dose and challenging dose were 2, 7.5, 13, 18.5 and 24 h. When the time interval between the conditioning dose and the challenging dose was 2 h, both conditioning doses (0.025 and 0.05 Gy) reduced the frequency of MNPCEs and chromosomal aberrations in the bone marrow cells. The data collected at different time intervals (7.5, 13, 18.5 h) reveal that the radioadaptive response persisted for a longer time when the lower conditioning dose (0.025 Gy) was given. With the higher conditioning dose (0.05 Gy), the radioadaptive response disappeared after a time interval of 13 h. When the time interval between the conditioning dose and the challenging doses was 18.5 or 24 h, only the lower conditioning dose appeared effective in inducing the radioadaptive response

Medical response to radiation emergencies in Argentina

International Nuclear Information System (INIS)

Gisone, Pablo A.; Perez, Maria del R.; Dubner, Diana L.; Michelin, Severino C.; Vazquez, M.; Demayo, O.

2006-01-01

Although radiation accidents are not frequent, the increasing use of radioisotopes in medicine and industry increases the likelihood of such accidental situations. Additionally, risks posed by the malevolent use of radiation sources have been highlighted during the last few years. In this context, the enhancement of national capabilities for medical assistance of victims in radiation emergencies becomes relevant. This communication describes the organization of medical response to radiation emergencies existing in Argentina. A three-level system for medical response has been developed: pre-hospital response given on-site by local emergency services, assistance provided by emergency departments of local general hospitals and central reference hospitals for treatment of acute radiation syndrome, cutaneous radiation syndrome and internal contamination. An education and training program is regularly executed at the three levels, including theoretical background as well as practical training. Guidelines and protocols for medical handling of victims have been elaborated and implemented. Research and development of new strategies for diagnosis and treatment of radiation injuries are promoted by ARN in close collaboration with physicians belonging to reference hospitals. (author)

Oligodendroglial response to ionizing radiation: Dose and dose-rate response

International Nuclear Information System (INIS)

Levy, R.P.

1991-12-01

An in vitro system using neuroglia from neonatal rat brain was developed to examine the morphologic, immunocytochemical and biochemical response of oligodendroglia to ionizing radiation. Following acute γ-irradiation at day-in-culture (DIC) 8, oligodendrocyte counts at DIC 14 were 55% to 65% of control values after 2 Gy, and 29% to 36% after 5 Gy. Counts increased to near-normal levels at DIC 21 in the 2 Gy group and to 75% of normal in the 5 Gy group. Myelin basic protein levels (MBP) at DIC 14 were 60% of control values after 2 Gy, and 40% after 5 Gy. At DIC 21, MBP after 2 Gy was 45% greater than that observed at DIC 14, but MBP, as a fraction of age-matched control values, dropped from 60% to 50%. Following 5 Gy, absolute MBP changed little between DIC 14 and DIC 21, but decreased from 40% to 25% of control cultures. The response to split-dose irradiation indicated that nearly all sublethal damage in the oligodendrocyte population (and its precursors) was repaired within 3 h to 4 h. A new compartmental cell model for radiation response in vitro of the oligodendrocyte population is proposed and examined in relation to the potential reaction to radiation injury in the brain

Oligodendroglial response to ionizing radiation: Dose and dose-rate response

Energy Technology Data Exchange (ETDEWEB)

Levy, Richard P. [Univ. of California, Berkeley, CA (United States)

1991-12-01

An in vitro system using neuroglia from neonatal rat brain was developed to examine the morphologic, immunocytochemical and biochemical response of oligodendroglia to ionizing radiation. Following acute γ-irradiation at day-in-culture (DIC) 8, oligodendrocyte counts at DIC 14 were 55% to 65% of control values after 2 Gy, and 29% to 36% after 5 Gy. Counts increased to near-normal levels at DIC 21 in the 2 Gy group and to 75% of normal in the 5 Gy group. Myelin basic protein levels (MBP) at DIC 14 were 60% of control values after 2 Gy, and 40% after 5 Gy. At DIC 21, MBP after 2 Gy was 45% greater than that observed at DIC 14, but MBP, as a fraction of age-matched control values, dropped from 60% to 50%. Following 5 Gy, absolute MBP changed little between DIC 14 and DIC 21, but decreased from 40% to 25% of control cultures. The response to split-dose irradiation indicated that nearly all sublethal damage in the oligodendrocyte population (and its precursors) was repaired within 3 h to 4 h. A new compartmental cell model for radiation response in vitro of the oligodendrocyte population is proposed and examined in relation to the potential reaction to radiation injury in the brain.

Oligodendroglial response to ionizing radiation: Dose and dose-rate response

Energy Technology Data Exchange (ETDEWEB)

Levy, R.P.

1991-12-01

An in vitro system using neuroglia from neonatal rat brain was developed to examine the morphologic, immunocytochemical and biochemical response of oligodendroglia to ionizing radiation. Following acute {gamma}-irradiation at day-in-culture (DIC) 8, oligodendrocyte counts at DIC 14 were 55% to 65% of control values after 2 Gy, and 29% to 36% after 5 Gy. Counts increased to near-normal levels at DIC 21 in the 2 Gy group and to 75% of normal in the 5 Gy group. Myelin basic protein levels (MBP) at DIC 14 were 60% of control values after 2 Gy, and 40% after 5 Gy. At DIC 21, MBP after 2 Gy was 45% greater than that observed at DIC 14, but MBP, as a fraction of age-matched control values, dropped from 60% to 50%. Following 5 Gy, absolute MBP changed little between DIC 14 and DIC 21, but decreased from 40% to 25% of control cultures. The response to split-dose irradiation indicated that nearly all sublethal damage in the oligodendrocyte population (and its precursors) was repaired within 3 h to 4 h. A new compartmental cell model for radiation response in vitro of the oligodendrocyte population is proposed and examined in relation to the potential reaction to radiation injury in the brain.

Dose-response of photographic emulsions under gamma irradiation

International Nuclear Information System (INIS)

Tran Dai Nghiep; Do Thi Nguyet Minh; Le Van Vinh

2003-01-01

Photographic emulsion is irradiated under gamma rays irradiation of 137 Cs in the IAEA/WHO secondary standard dosimetry laboratory. Dose-response of the film is established. The sensitivity of the film is determined. The dose-rate effect is studied. (author)

Dose/response relationships and policy formulation

International Nuclear Information System (INIS)

Robinson, P.D.

1981-01-01

The ICRP 26 cost/benefit approach to establishing operational radiation protection guidelines is discussed. The purpose is to aid the policy maker in the decision making process, using as a basis the dose-response curve

Optimal dose-response relationships in voice therapy.

Science.gov (United States)

Roy, Nelson

2012-10-01

Like other areas of speech-language pathology, the behavioural management of voice disorders lacks precision regarding optimal dose-response relationships. In voice therapy, dosing can presumably vary from no measurable effect (i.e., no observable benefit or adverse effect), to ideal dose (maximum benefit with no adverse effects), to doses that produce toxic or harmful effects on voice production. Practicing specific vocal exercises will inevitably increase vocal load. At ideal doses, these exercises may be non-toxic and beneficial, while at intermediate or high doses, the same exercises may actually be toxic or damaging to vocal fold tissues. In pharmacology, toxicity is a critical concept, yet it is rarely considered in voice therapy, with little known regarding "effective" concentrations of specific voice therapies vs "toxic" concentrations. The potential for vocal fold tissue damage related to overdosing on specific vocal exercises has been under-studied. In this commentary, the issue of dosing will be explored within the context of voice therapy, with particular emphasis placed on possible "overdosing".

Maximum likelihood estimation for cytogenetic dose-response curves

International Nuclear Information System (INIS)

Frome, E.L; DuFrain, R.J.

1983-10-01

In vitro dose-response curves are used to describe the relation between the yield of dicentric chromosome aberrations and radiation dose for human lymphocytes. The dicentric yields follow the Poisson distribution, and the expected yield depends on both the magnitude and the temporal distribution of the dose for low LET radiation. A general dose-response model that describes this relation has been obtained by Kellerer and Rossi using the theory of dual radiation action. The yield of elementary lesions is kappa[γd + g(t, tau)d 2 ], where t is the time and d is dose. The coefficient of the d 2 term is determined by the recovery function and the temporal mode of irradiation. Two special cases of practical interest are split-dose and continuous exposure experiments, and the resulting models are intrinsically nonlinear in the parameters. A general purpose maximum likelihood estimation procedure is described and illustrated with numerical examples from both experimental designs. Poisson regression analysis is used for estimation, hypothesis testing, and regression diagnostics. Results are discussed in the context of exposure assessment procedures for both acute and chronic human radiation exposure

Maximum likelihood estimation for cytogenetic dose-response curves

Energy Technology Data Exchange (ETDEWEB)

Frome, E.L; DuFrain, R.J.

1983-10-01

In vitro dose-response curves are used to describe the relation between the yield of dicentric chromosome aberrations and radiation dose for human lymphocytes. The dicentric yields follow the Poisson distribution, and the expected yield depends on both the magnitude and the temporal distribution of the dose for low LET radiation. A general dose-response model that describes this relation has been obtained by Kellerer and Rossi using the theory of dual radiation action. The yield of elementary lesions is kappa(..gamma..d + g(t, tau)d/sup 2/), where t is the time and d is dose. The coefficient of the d/sup 2/ term is determined by the recovery function and the temporal mode of irradiation. Two special cases of practical interest are split-dose and continuous exposure experiments, and the resulting models are intrinsically nonlinear in the parameters. A general purpose maximum likelihood estimation procedure is described and illustrated with numerical examples from both experimental designs. Poisson regression analysis is used for estimation, hypothesis testing, and regression diagnostics. Results are discussed in the context of exposure assessment procedures for both acute and chronic human radiation exposure.

Commercial sugar, an alternative dosemeter for the dose determination in radiological emergency conditions; Azucar comercial, un dosimetro alternativo para la determinacion de dosis en situaciones de emergencia radiologica

Energy Technology Data Exchange (ETDEWEB)

Urena N, F.; Galindo, S. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

1997-07-01

It was carried out the dosimetric evaluation of commercial sugar, with the purpose to determine the feasibility to be able to use this type of substance as a dosimetric material in cases to present some radiological emergency cases. The studied parameters using the Electron Paramagnetic Resonance (EPR) technique were: pre-doses signal or depth signal, dose-response stability, reproducibility, reliability and signal clearing decreasing. (Author)

Analysis of thermal-dose response to heat

International Nuclear Information System (INIS)

Storm, F.; Roe, D.; Drury, B.

1987-01-01

The authors reasoned that if hyperthermia alone has a clinical anti-tumor effect, response should have a thermal dose relationship. The authors analyzed 100 patients with advanced cancer treated with magnetic-induction. Three methods of determining thermal dose were used: (A) t1x10, the lowest temperature sustained throughout the tumor for 30-60min during the first of ten daily treatments, which represents one usual course of ten hourly sessions; (B) t43 (equivalent minutes at 43C) which accounts for non-linear tumor heating by combining serially measured temperatures during the first treatment with a mathematical description of the time-temperature relationship for thermal inactivation or damage; (C) Ct43 (cumulative t43), which represents the t43 value multiplied by the actual number of subsequent daily treatments received. Response was defined as CR+PR+MR. The results show a statistically significant effect of heat alone for t1x10, t43, and Ct43. These analyses demonstrate a thermal-dose relationship between hyperthermia therapy and tumor response as a sole independent variable, which indicates that heat therapy has clinical anti-cancer activity

Functional criteria for emergency response facilities. Technical report (final)

International Nuclear Information System (INIS)

1981-02-01

This report describes the facilities and systems to be used by nuclear power plant licensees to improve responses to emergency situations. The facilities include the Technical Support Center (TSC), Onsite Operational Support Center (OSC), and Nearsite Emergency Operations Facility (EOF), as well as a brief discussion of the emergency response function of the control room. The data systems described are the Safety Parameter Display System (SPDS) and Nuclear Data Link (NDL). Together, these facilities and systems make up the total Emergency Response Facilities (ERFs). Licensees should follow the guidance provided both in this report and in NUREG-0654 (FEMA-REP-1), Revision 1, for design and implementation of the ERFs

Quantitative radiation dose-response relationships for normal tissues in man. II. Response of the salivary glands during radiotherapy

International Nuclear Information System (INIS)

Mossman, K.L.

1983-01-01

A quantitative dose-response curve for salivary gland function in patients during radiotherapy is presented. Salivary-function data used in this study were obtained from four previously published reports. All patients were treated with 60 Co teletherapy to the head and neck using conventional treatment techniques. Salivary dysfunction was determined at specific dose levels by comparing salivary flow rates before therapy with flow rates at specific dose intervals during radiotherapy up to a total dose of 6000 cGy. Fifty percent salivary dysfunction occurred after 1000 cGy and eighty percent dysfunction was observed by the end of the therapy course (6000 cGy). The salivary-function curve was also compared to the previously published dose-response curve for taste function. Comparisons of the two curves indicate that salivary dysfunction precedes taste loss and that the shapes of the dose-response curves are different. A new term, tissue tolerance ratio, defined as the ratio of responses of two tissues given the same radiation dose, was used to make the comparisons between gustatory and salivary gland tissue effects. Measurements of salivary gland function and analysis of dose-response curves may be useful in evaluating chemical modifiers of radiation response

A prototype nuclear emergency response decision making expert system

International Nuclear Information System (INIS)

Chang, C.; Shih, C.; Hong, M.; Yu, W.; Su, M.; Wang, S.

1990-01-01

A prototype of emergency response expert system developed for nuclear power plants, has been fulfilled by Institute of Nuclear Energy Research. Key elements that have been implemented for emergency response include radioactive material dispersion assessment, dynamic transportation evacuation assessment, and meteorological parametric forecasting. A network system consists of five 80386 Personal Computers (PCs) has been installed to perform the system functions above. A further project is still continuing to achieve a more complicated and fanciful computer aid integral emergency response expert system

A model national emergency response plan for radiological accidents

International Nuclear Information System (INIS)

1993-09-01

The IAEA has supported several projects for the development of a national response plan for radiological emergencies. As a results, the IAEA has developed a model National Emergency Response Plan for Radiological Accidents (RAD PLAN), particularly for countries that have no nuclear power plants. This plan can be adapted for use by countries interested in developing their own national radiological emergency response plan, and the IAEA will supply the latest version of the RAD PLAN on computer diskette upon request. 2 tabs

Thermoluminescence dose response of quartz as a function of irradiation temperature

International Nuclear Information System (INIS)

Kitis, G.; Kaldoudi, E.; Charalambous, S.

1990-01-01

The thermoluminescence (TL) response of pure Norwegian quartz as a function of irradiation temperature (T irr ) and dose has been investigated. The TL response of the (150-230 o C) and (230-350 o C) glow curve intervals shows a strong dependence on T irr between 77 and 373 K in the dose range from 54 to 8.4 x 10 4 Gy. Both glow curve intervals also show temperature dependent dose response properties. The 150-230 o C interval is supralinear from the lowest dose (54 Gy). Its maximum supralinearity factor appears at T irr = 293 K. The 230-350 o C interval shows sublinear behaviour below T irr = + 193 K, while at T irr ≥ 273 K it shows the well known dose response curves. Its maximum supralinearity factor appears at T irr = 323 K. The linear response is extended up to 460 Gy at T irr = 273 K and falls to 80 Gy at T irr = 373 K. (author)

Emergency response packaging: A conceptual outline

International Nuclear Information System (INIS)

Luna, R.E.; McClure, J.D.; Bennett, P.C.; Wheeler, T.A.

1992-01-01

The Packaging and Transportation Needs in the 1990's (PATN) component of the Transportation Assessment and Integration (TRAIN) program (DOE Nov. 1991) was designed to survey United States Department of Energy programs, both ongoing and planned, to identify needs for packaging and transportation services over the next decade. PATN also identified transportation elements that should be developed by the DOE Office of Environmental Restoration and Waste Management (DOE EM) Transportation Management Program (TMP). As a result of the predominant involvement of the TMP in radioactive material shipment issues and DOE EM's involvement with waste management issues, the primary focus of PATN was on waste packaging issues. Pending DOE regulations will formalize federal guidelines and regulations for transportation of hazardous and radioactive materials within the boundaries of DOE reservations and facilities and reflect a growing awareness of concern regarding safety environmental responsibility activities on DOE reservations. Future practices involving the transportation of radioactive material within DOE reservations will closely parallel those used for commercial and governmental transportation across the United States. This has added to the perceived need for emergency recovery packaging and emergency response features on primary packaging, for both on-site shipments and shipments between DOE facilities (off-site). Historically, emergency response and recovery functions of packaging have not been adequately considered in packaging design and construction concepts. This paper develops the rationale for emergency response packaging, including both overpack concepts for repackaging compromised packaging and primary packaging redesign to facilitate the recovery of packages via mobile remote handling equipment. The rationale will examine concepts for determination of likely use patterns to identify types of shipments where recovery packaging may have the most favorable payoff

Evaluation criteria for emergency response plans in radiological transportation

International Nuclear Information System (INIS)

Lindell, M.K.; Perry, R.W.

1980-01-01

This paper identifies a set of general criteria which can be used as guides for evaluating emergency response plans prepared in connection with the transportation of radiological materials. The development of criteria takes the form of examining the meaning and role of emergency plans in general, reviewing the process as it is used in connection with natural disasters and other nonnuclear disasters, and explicitly considering unique aspects of the radiological transportation setting. Eight areas of critical importance for such response plans are isolated: notification procedures; accident assessment; public information; protection of the public at risk; other protective responses; radiological exposure control; responsibility for planning and operations; and emergency response training and exercises. (Auth.)

The atmospheric release advisory capability (ARAC): A federal emergency response capability

International Nuclear Information System (INIS)

Dickerson, M.H.; Sullivan, T.J.

1988-03-01

The Atmospheric Release Capability (ARAC) is a Department of Energy (DOE)-sponsored emergency-response service set up to provide real-time prediction of the dose levels and the extent of surface contamination resulting from a broad range of possible occurrences (accidents, spills, extortion threats involving nuclear material, reentry of nuclear-powered satellites, and atmospheric nuclear tests) that could involve the release of airborne radioactive material. During the past decade, ARAC has responded to more than 150 real-time situations, including exercises. The most notable responses include the Three Mile Island accident in Pennsylvania, the Titan II missile accident in Arkansas, the reentry of the USSR's COSMOS-954 into the atmosphere over Canada, the accidental release of uranium hexafluoride from the Sequoyah Facility accident in Oklahoma, and, most recently, the Chernobyl reactor accident in the Soviet Union. ARAC currently supports the emergency-preparedness plans at 50 Department of Defense (DOD) and DOE sites within the US and also responds to accidents that happen elsewhere. Our ARAC center serves as the focal point for data acquisition, data analysis and assessments during a response, using a computer-based communication network to acquire real-time weather data from the accident site and the surrounding region, as well as pertinent accident information. Its three-dimensional computer models for atmospheric dispersion, MATHEW and ADPIC, digest all this information and produce the predictions used in accident assessment. 9 refs., 6 figs., 1 tab

Analysis of emergency response after the Chernobyl accident in Belarus: observed and prevented medical consequences, lessons learned

Energy Technology Data Exchange (ETDEWEB)

Buglova, E.; Kenigsberg, J. [Research Clinical Inst. of Radiation Medicine and Endocrinology, Minsk (Belarus)

1997-12-31

Belarus is one of the most contaminated Republic due to the Chernobyl accident. 23% of the entire area of Belarus was contaminated with radionuclides. To protect the population after the accident different types of protective actions were performed during all phases, based on various temporary dose limits. An analysis of conducted protective actions and lessons obtained during the emergency response is briefly presented 9 refs.

Study on IAEA international emergency response exercise convEx-3

International Nuclear Information System (INIS)

Yamamoto, Kazuya

2007-05-01

The International Atomic Energy Agency (IAEA) carried out a large-scale international emergency response exercise in 2005 under the designated name of ConvEx-3(2005), at Romania. This review report summarizes a study about ConvEx-3(2005) based on several related open literature. The ConvEx-3 was conducted in accordance with Agency's safety standard series and requirements in the field of Emergency Preparedness and Response. The study on the preparation, conduct and evaluation of ConvEx-3(2005) exercise is expected to provide very useful knowledge for development of drills and educational programs conducted by Nuclear Emergency Assistance and Training Center (NEAT). Especially, study on the exercise evaluations is instrumental in improving evaluations of drills planned by the national government and local governments. As international cooperation among Asian countries in the field of nuclear emergency preparedness and response is going to realize, it is very useful to survey and consider scheme and methodology about international emergency preparedness, response and exercise referring the knowledge of this ConvEx-3 study. The lessons learned from this study of ConvEx-3(2005) are summarized in four chapters; methodology of exercises and educational programs, exercise evaluation process, amendments/verification of the emergency response plan of NEAT, and technical issues of systems for emergency response and assistance of NEAT relevant to interface for international emergency communication. (author)

Determination of tolerance dose uncertainties and optimal design of dose response experiments with small animal numbers

International Nuclear Information System (INIS)

Karger, C.P.; Hartmann, G.H.

2001-01-01

Background: Dose response experiments aim to determine the complication probability as a function of dose. Adjusting the parameters of the frequently used dose response model P(D)=1/[1+(D 50 /D) k ] to the experimental data, 2 intuitive quantities are obtained: The tolerance dose D 50 and the slope parameter k. For mathematical reasons, however, standard statistic software uses a different set of parameters. Therefore, the resulting fit parameters of the statistic software as well as their standard errors have to be transformed to obtain D 50 and k as well as their standard errors. Material and Methods: The influence of the number of dose levels on the uncertainty of the fit parameters is studied by a simulation for a fixed number of animals. For experiments with small animal numbers, statistical artifacts may prevent the determination of the standard errors of the fit parameters. Consequences on the design of dose response experiments are investigated. Results: Explicit formulas are presented, which allow to calculate the parameters D 50 and k as well as their standard errors from the output of standard statistic software. The simulation shows, that the standard errors of the resulting parameters are independent of the number of dose levels, as long as the total number of animals involved in the experiment, remains constant. Conclusion: Statistical artifacts in experiments containing small animal numbers may be prevented by an adequate design of the experiment. For this, it is suggested to select a higher number of dose levels, rather than using a higher number of animals per dose level. (orig.) [de

The Radiation Dose-Response of the Human Spinal Cord

International Nuclear Information System (INIS)

Schultheiss, Timothy E.

2008-01-01

Purpose: To characterize the radiation dose-response of the human spinal cord. Methods and Materials: Because no single institution has sufficient data to establish a dose-response function for the human spinal cord, published reports were combined. Requisite data were dose and fractionation, number of patients at risk, number of myelopathy cases, and survival experience of the population. Eight data points for cervical myelopathy were obtained from five reports. Using maximum likelihood estimation correcting for the survival experience of the population, estimates were obtained for the median tolerance dose, slope parameter, and α/β ratio in a logistic dose-response function. An adequate fit to thoracic data was not possible. Hyperbaric oxygen treatments involving the cervical cord were also analyzed. Results: The estimate of the median tolerance dose (cervical cord) was 69.4 Gy (95% confidence interval, 66.4-72.6). The α/β = 0.87 Gy. At 45 Gy, the (extrapolated) probability of myelopathy is 0.03%; and at 50 Gy, 0.2%. The dose for a 5% myelopathy rate is 59.3 Gy. Graphical analysis indicates that the sensitivity of the thoracic cord is less than that of the cervical cord. There appears to be a sensitizing effect from hyperbaric oxygen treatment. Conclusions: The estimate of α/β is smaller than usually quoted, but values this small were found in some studies. Using α/β = 0.87 Gy, one would expect a considerable advantage by decreasing the dose/fraction to less than 2 Gy. These results were obtained from only single fractions/day and should not be applied uncritically to hyperfractionation

Emergency response planning in hospitals, United States: 2003-2004.

Science.gov (United States)

Niska, Richard W; Burt, Catharine W

2007-08-20

This study presents baseline data to determine which hospital characteristics are associated with preparedness for terrorism and natural disaster in the areas of emergency response planning and availability of equipment and specialized care units. Information from the Bioterrorism and Mass Casualty Preparedness Supplements to the 2003 and 2004 National Hospital Ambulatory Medical Care Surveys was used to provide national estimates of variations in hospital emergency response plans and resources by residency and medical school affiliation, hospital size, ownership, metropolitan statistical area status, and Joint Commission accreditation. Of 874 sampled hospitals with emergency or outpatient departments, 739 responded for an 84.6 percent response rate. Estimates are presented with 95 percent confidence intervals. About 92 percent of hospitals had revised their emergency response plans since September 11, 2001, but only about 63 percent had addressed natural disasters and biological, chemical, radiological, and explosive terrorism in those plans. Only about 9 percent of hospitals had provided for all 10 of the response plan components studied. Hospitals had a mean of about 14 personal protective suits, 21 critical care beds, 12 mechanical ventilators, 7 negative pressure isolation rooms, and 2 decontamination showers each. Hospital bed capacity was the factor most consistently associated with emergency response planning and availability of resources.

A review: Development of a microdose model for analysis of adaptive response and bystander dose response behavior.

Science.gov (United States)

Leonard, Bobby E

2008-02-27

Prior work has provided incremental phases to a microdosimetry modeling program to describe the dose response behavior of the radio-protective adaptive response effect. We have here consolidated these prior works (Leonard 2000, 2005, 2007a, 2007b, 2007c) to provide a composite, comprehensive Microdose Model that is also herein modified to include the bystander effect. The nomenclature for the model is also standardized for the benefit of the experimental cellular radio-biologist. It extends the prior work to explicitly encompass separately the analysis of experimental data that is 1.) only dose dependent and reflecting only adaptive response radio-protection, 2.) both dose and dose-rate dependent data and reflecting only adaptive response radio-protection for spontaneous and challenge dose damage, 3.) only dose dependent data and reflecting both bystander deleterious damage and adaptive response radio-protection (AR-BE model). The Appendix cites the various applications of the model. Here we have used the Microdose Model to analyze the, much more human risk significant, Elmore et al (2006) data for the dose and dose rate influence on the adaptive response radio-protective behavior of HeLa x Skin cells for naturally occurring, spontaneous chromosome damage from a Brachytherapy type (125)I photon radiation source. We have also applied the AR-BE Microdose Model to the Chromosome inversion data of Hooker et al (2004) reflecting both low LET bystander and adaptive response effects. The micro-beam facility data of Miller et al (1999), Nagasawa and Little (1999) and Zhou et al (2003) is also examined. For the Zhou et al (2003) data, we use the AR-BE model to estimate the threshold for adaptive response reduction of the bystander effect. The mammogram and diagnostic X-ray induction of AR and protective BE are observed. We show that bystander damage is reduced in the similar manner as spontaneous and challenge dose damage as shown by the Azzam et al (1996) data. We cite

The dose-response relationship for UV-tumorigenesis

International Nuclear Information System (INIS)

Gruijl, F.R. de.

1982-01-01

The main objective of the investigations was to extend the knowledge on experimental UV-carcinogenesis and to use the experimental results as guidelines for developing a dose-response model for UV-carcinogenesis. The animal experiments carried out were all long-term ones. It was decided that - in anticipation of the data to be obtained - a model for such an assessment should be developed using the experimental results available at the start of the present study (1977). This initial study is presented. The results of two animal experiments are presented, which show that UV radiation is capable of inducing a systemic effect that enhances the de novo formation of UV induced tumors. The results of the main experiment are presented. In this experiment groups of mice were subjected to daily exposure to a certain dose of UV radiation in order to find the dose-response relationship. The relation between the daily dose and the duration of the treatment till the appearance of tumors (for instance, as measured by the yield) was ascertained for tumors of different sizes. It appears that the growth of a tumor is dose-independent, and, therefore, only the initiation of a tumor is dose-dependent. Finally an experiment is presented in which it was measured that, if a mouse is subjected to daily UV exposure, the transmission of the epidermis in the shortwave UV region decreases continuously. This decrease is due to hyperplasia of the epidermis, i.e., thickening of the epidermis by an increase in the number of cells per unit surface area. (Auth.)

Emergency response planning and preparedness for transport accidents involving radioactive material

International Nuclear Information System (INIS)

1988-01-01

The purpose of this Guide is to provide assistance to public authorities and others (including consignors and carriers of radioactive materials) who are responsible for ensuring safety in establishing and developing emergency response arrangements for responding effectively to transport accidents involving radioactive materials. This Guide is concerned mainly with the preparation of emergency response plans. It provides information which will assist those countries whose involvement with radioactive materials is just beginning and those which have already developed their industries involving radioactive materials and attendant emergency plans, but may need to review and improve these plans. The need for emergency response plans and the ways in which they are implemented vary from country to country. In each country, the responsible authorities must decide how best to apply this Guide, taking into account the actual shipments and associated hazards. In this Guide the emergency response planning and response philosophy are outlined, including identification of emergency response organizations and emergency services that would be required during a transport accident. General consequences which could prevail during an accident are described taking into account the IAEA Regulations for the Safe Transport of Radioactive Material. 43 refs, figs and tabs

Challenges in designing interactive systems for emergency response

DEFF Research Database (Denmark)

Kristensen, Margit; Kyng, Morten; Nielsen, Esben Toftdahl

2007-01-01

and visions as ways to bridge between fieldwork and literature studies on the one hand and the emerging computer based prototypes on the other. Our case concerns design of innovative interactive systems for support in emergency response, including patient identification and monitoring as well as construction......This paper presents research on participatory design of interactive systems for emergency response. We present the work by going through the design method with a focus on the new elements that we developed for the participatory design toolkit, in particular we emphasize the use of challenges...

Emergency preparedness and response plan for nuclear facilities in Indonesia

International Nuclear Information System (INIS)

Nur Rahmah Hidayati; Pande Made Udiyani

2009-01-01

All nuclear facilities in Indonesia are owned and operated by the National Nuclear Energy Agency (BATAN). The programs and activities of emergency planning and preparedness in Indonesia are based on the existing nuclear facilities, i.e. research reactors, research reactor fuel fabrication plant, radioactive waste treatment installation and radioisotopes production installation. The assessment is conducted to learn of status of emergency preparedness and response plan for nuclear facilities in Indonesia and to support the preparation of future Nuclear Power Plant. The assessment is conducted by comparing the emergency preparedness and response system in Indonesia to the system in other countries such as Japan and Republic of Korea, since the countries have many Nuclear Power Plants and other nuclear facilities. As a result, emergency preparedness response plan for existing nuclear facility in Indonesia has been implemented in many activities such as environmental monitoring program, facility monitoring equipment, and the continuous exercise of emergency preparedness and response. However, the implementation need law enforcement for imposing the responsibility of the coordinators in National Emergency Preparedness Plan. It also needs some additional technical support systems which refer to the system in Japan or Republic of Korea. The systems must be completed with some real time monitors which will support the emergency preparedness and response organization. The system should be built in NPP site before the first NPP will be operated. The system should be connected to an Off Site Emergency Center under coordination of BAPETEN as the regulatory body which has responsibility to control of nuclear energy in Indonesia. (Author)

Responses to emergencies in Mexico and Central America

International Nuclear Information System (INIS)

Diaz, E.F.

1986-01-01

Radiation emergencies have two main aspects: radiation safety, which concerns control of the radiation source, and, more importantly, health effects, which entail diagnoses, treatment, and rehabilitation. The physician participates directly in a radiation emergency because he or she is the professional who knows best the human body and the methodology to re-establish health. However, because these types of incidents are infrequent, many physicians are poorly prepared to deal with such emergencies. Two main aspects of emergency response plans are: (1) prevention, including public education for behavior and planning for appropriate response; and (2) application, including prophylactic measures, assessing the extent of exposure and contamination, controlling public anxiety, and managing and treating the victims

A FTA-based method for risk decision-making in emergency response

DEFF Research Database (Denmark)

Liu, Yang; Li, Hongyan

2014-01-01

Decision-making problems in emergency response are usually risky and uncertain due to the limited decision data and possible evolvement of emergency scenarios. This paper focuses on a risk decisionmaking problem in emergency response with several distinct characteristics including dynamic...... evolvement process of emergency, multiple scenarios, and impact of response actions on the emergency scenarios. A method based on Fault Tree Analysis (FTA) is proposed to solve the problem. By analyzing the evolvement process of emergency, the Fault Tree (FT) is constructed to describe the logical relations...

Explanation of procedure on site medical emergency response for nuclear accident

International Nuclear Information System (INIS)

Liu Yulong; Jiang Zhong

2012-01-01

National occupational health standard-Procedure on Site Medical Emergency Response for Nuclear Accident has been approved and issued by the Ministry of Health. This standard is formulated according to the Emergency Response Law of the People's Republic of China, Law of the People 's Republic of China on Prevention and Control of Occupational Diseases, Regulations on Emergency Measures for Nuclear Accidents at Nuclear Power Plants, and Health Emergency Plans for Nuclear and Radiological Accidents of Ministry of Health, supporting the use of On-site Medical Emergency Planning and Preparedness for Nuclear Accidents and Off-site Medical Emergency Planning and Preparedness for Nuclear Accidents. Nuclear accident on-site medical response procedure is a part of the on-site emergency plan. The standard specifies the basic content and requirements of the nuclear accident on-site medical emergency response procedures of nuclear facilities operating units to guide and regulate the work of nuclear accident on-site medical emergency response of nuclear facilities operating units. The criteria-related contents were interpreted in this article. (authors)

Linear dose response curves in fungi and tradescantia

International Nuclear Information System (INIS)

Unrau, P.

1999-07-01

Tradescantia Clone 02 data suggests that linear non-threshold dose responses are expected to the lowest doses and dose rates of low linear energy transfer (LET) radiation. This is likely to be true for other living organisms even though Clone 02 is radiation sensitive. It is concluded that Clone 02 is partially defective in the RAD 6 pathway for the repair of DNA interstrand cross-links (ISCL) and other loss of coding damage (LCD), based on its cross sensitivities to EMS and ionizing radiation. Tradescantia Clone 02 data showing linear non-threshold induction of somatic genetic events in part reflects the repair deficiency of this Clone. More DNA damage is repaired by recombinational mechanisms in Clone 02 than would occur in a wild-type strain. Two important classes of DNA lesions are induced by ionizing radiation in DNA - double strand breaks (DSB) which are repaired by recombination mechanisms, and loss of coding information damage (LCD), which is repaired by error prone mechanisms but may also be a substrate for recombinational repair. Based on data from yeast, there are two different repair pathways which deal with these differing lesions with different somatic genetic consequences. From yeast, yield cross sections can be derived and applied to DNA damage and repair in Tradescantia. For Clone 02, per lesion, more visible genetic events are scored than in wild-type strains. In a radiation-derived sub-clone, Clone 0106, which is more variable than Clone 02, even more events occur per lesion. This derivative clone, plus breeding experiments, indicate that Clone 02 is heterozygous, or a 'carrier' for a mutant version of a gene in the Tradescantia RAD 6 repair pathway. Clone 02 is, therefore, much like a Fanconi's anemia carrier in a human population, while the Clone 0106 derivative is much like a homozygous Fanconi's anemia patient, with respect to its response to ionizing radiation damage. Two anomalies in its dose response curves for 'pink' loss of

Linear dose response curves in fungi and tradescantia

Energy Technology Data Exchange (ETDEWEB)

Unrau, P. [Atomic Energy of Canada Ltd., Chalk River, Ontario (Canada)

1999-07-15

Tradescantia Clone 02 data suggests that linear non-threshold dose responses are expected to the lowest doses and dose rates of low linear energy transfer (LET) radiation. This is likely to be true for other living organisms even though Clone 02 is radiation sensitive. It is concluded that Clone 02 is partially defective in the RAD 6 pathway for the repair of DNA interstrand cross-links (ISCL) and other loss of coding damage (LCD), based on its cross sensitivities to EMS and ionizing radiation. Tradescantia Clone 02 data showing linear non-threshold induction of somatic genetic events in part reflects the repair deficiency of this Clone. More DNA damage is repaired by recombinational mechanisms in Clone 02 than would occur in a wild-type strain. Two important classes of DNA lesions are induced by ionizing radiation in DNA - double strand breaks (DSB) which are repaired by recombination mechanisms, and loss of coding information damage (LCD), which is repaired by error prone mechanisms but may also be a substrate for recombinational repair. Based on data from yeast, there are two different repair pathways which deal with these differing lesions with different somatic genetic consequences. From yeast, yield cross sections can be derived and applied to DNA damage and repair in Tradescantia. For Clone 02, per lesion, more visible genetic events are scored than in wild-type strains. In a radiation-derived sub-clone, Clone 0106, which is more variable than Clone 02, even more events occur per lesion. This derivative clone, plus breeding experiments, indicate that Clone 02 is heterozygous, or a 'carrier' for a mutant version of a gene in the Tradescantia RAD 6 repair pathway. Clone 02 is, therefore, much like a Fanconi's anemia carrier in a human population, while the Clone 0106 derivative is much like a homozygous Fanconi's anemia patient, with respect to its response to ionizing radiation damage. Two anomalies in its dose response curves for &apos

Toward a unified approach to dose-response modeling in ecotoxicology.

Science.gov (United States)

Ritz, Christian

2010-01-01

This study reviews dose-response models that are used in ecotoxicology. The focus lies on clarification of differences and similarities between models, and as a side effect, their different guises in ecotoxicology are unravelled. A look at frequently used dose-response models reveals major discrepancies, among other things in naming conventions. Therefore, there is a need for a unified view on dose-response modeling in order to improve the understanding of it and to facilitate communication and comparison of findings across studies, thus realizing its full potential. This study attempts to establish a general framework that encompasses most dose-response models that are of interest to ecotoxicologists in practice. The framework includes commonly used models such as the log-logistic and Weibull models, but also features entire suites of models as found in various guidance documents. An outline on how the proposed framework can be implemented in statistical software systems is also provided.

Flattening the Energy Response of a Scintillator Based Gamma Dose Rate Meter Coupled to SiPM

International Nuclear Information System (INIS)

Knafo, Y.; Manor, A.; Ginzburg, D.; Ellenbogen, M.; Osovizky, A.; Wengrowicz, U.; Ghelman, M.; Seif, R.; Mazor, T.; Kadmon, Y.; Cohen, Y.

2014-01-01

Among the newest emerging technologies that are used in the design of personal gamma radiation detection instruments, the silicon photomultiplier (SiPM) light sensor is playing an important role. This type of photo sensor is characterized by low power consumption, small dimensions and high gain. These special characteristics present applicable alternatives for the replacement of traditional gamma sensors based on scintillator coupled to Photomultiplier tubes (PMT) or on Geiger-Muller(G.M.) sensors. For health physics applications, flat energy response is required for a wide range of radio-nuclides emitting gamma rays of different energies. Scintillation based radiation instrumentation provides count rate and amplitude of the measured pulses. These pulses can be split in different bins corresponding to the energy of the measured isotopes and their intensity. The count rate and the energy of the measured events are related to the dose rate. The conversion algorithm applys a different calibration factor for each energy bin in order to provide an accurate dose rate response for a wide range of gamma energies. This work describes the utilization of an innovative approach for dose rate conversion by using the abilities of newest 32-bit microcontroller based ARM core architecture

Staggering the dose of sugammadex lowers risks for severe emergence cough: a randomized control trial.

Science.gov (United States)

P S, Loh; Miskan, M M; Y Z, Chin; Zaki, R A

2017-10-11

Cough on emergence has been reported as a common adverse reaction with sugammadex reversal. We investigated if staggering the dose of sugammadex will reduce emergence cough in a single-center, randomized, double-blinded study. A hundred and twenty ASA 1-3 adults were randomly reversed with 1 mg/kg sugammadex prior to extubation followed by another 1 mg/kg immediately after extubation (staggered group), single dose of 2 mg/kg sugammadex (single bolus group) or neostigmine 0.02 mg/kg with glycopyrrolate (neostigmine group). We found 70% of patients (n = 28) reversed with single boluses of sugammadex had Grade 3 emergence cough compared to 12.5% (n = 5) in the staggered sugammadex group and 17.5% (n = 7) in the neostigmine group (p sugammadex group (n = 14, 35%, p = 0.005). On the other hand, staggering sugammadex lowered risks of developing severe cough (RR 0.2, p sugammadex group and control given neostigmine. In terms of timing, there was no delay in time taken from discontinuing anesthetic agents to reversal and extubation if sugammadex was staggered (emergence time 6.0 ± 3.2 s, p = 0.625 and reversal time 6.5 ± 3.5, p = 0.809). Staggering the dose of sugammadex for reversal will effectively decrease common emergence and early postoperative complications. ANZCTR Number ACTRN12616000116426 . Retrospectively registered on 2nd February 2016.

Emergency response preparedness analysis for radioactive materials transportation

International Nuclear Information System (INIS)

Parentela, E.M.; Burli, S.S.; Sathisan, S.K.; Vodrazka, W.C.

1994-01-01

This paper evaluates the emergency response capabilities of first responders, specifically fire services, within the state of Nevada. It addresses issues relating to the available emergency responders such as general capabilities, jurisdictions, and response times. Graphical displays of the response units and attribute tables were created using GIS ARC/INFO. These coverages, plus the existing Census Bureau TIGER Files and highway network for the state of Nevada, were utilized to determine approximate service areas of each response unit, population density served by each response unit, population density served by each response unit and the areas that can be served by a response unit for 3, 5, 10, and 30 minutes response times. Results of the analysis enabled identification of the critical areas along the proposed highway route corridor

Three-dimensional dose-response models of risk for radiation injury carcinogenesis

International Nuclear Information System (INIS)

Raabe, O.G.

1988-01-01

The use of computer graphics in conjunction with three-dimensional models of dose-response relationships for chronic exposure to ionizing radiation dramaticly clarifies the separate and interactive roles of competing risks. The three dimensions are average dose rate, exposure time, and risk. As an example, the functionally injurious and carcinogenic responses after systemic uptake of Ra-226 by beagles, mice and people with consequent alpha particle irradiation of the bone are represented by three-dimensional dose-rate/time/response surfaces that demonstrate the contributions with the passage of time of the competing deleterious responses. These relationships are further evaluated by mathematical stripping with three-dimensional illustrations that graphically show the resultant separate contribution of each effect. Radiation bone injury predominates at high dose rates and bone cancer at intermediate dose rates. Low dose rates result in spontaneous deaths from natural aging, yielding a type of practical threshold for bone cancer induction. Risk assessment is benefited by the insights that become apparent with these three-dimensional models. The improved conceptualization afforded by them contributes to planning and evaluating epidemiological analyses and experimental studies

Dose response relationship and Alara

International Nuclear Information System (INIS)

Hubert, P.

1986-09-01

In this paper, it will be shown how dose-response relationships allow to give quantitative figures for the detriment of irradiation. At this stage, the detriment is expressed directly as a certain number of health effects, whose valuation is not dealt with here. The present tools for quantifying, their weaknesses and their strenghts, and their scientific basis will be developed

Multi-objective evolutionary emergency response optimization for major accidents

International Nuclear Information System (INIS)

Georgiadou, Paraskevi S.; Papazoglou, Ioannis A.; Kiranoudis, Chris T.; Markatos, Nikolaos C.

2010-01-01

Emergency response planning in case of a major accident (hazardous material event, nuclear accident) is very important for the protection of the public and workers' safety and health. In this context, several protective actions can be performed, such as, evacuation of an area; protection of the population in buildings; and use of personal protective equipment. The best solution is not unique when multiple criteria are taken into consideration (e.g. health consequences, social disruption, economic cost). This paper presents a methodology for multi-objective optimization of emergency response planning in case of a major accident. The emergency policy with regards to protective actions to be implemented is optimized. An evolutionary algorithm has been used as the optimization tool. Case studies demonstrating the methodology and its application in emergency response decision-making in case of accidents related to hazardous materials installations are presented. However, the methodology with appropriate modification is suitable for supporting decisions in assessing emergency response procedures in other cases (nuclear accidents, transportation of hazardous materials) or for land-use planning issues.

Development of emergency response plans for community water ...

African Journals Online (AJOL)

All water services systems, irrespective of size, location etc., should have emergency response plans (ERPs) to guide officials, stakeholders and consumers through emergencies, as part of managing risks in the water supply system. Emergencies in the water supply system may result from, among other causes, natural ...

Communication with the Public in a Nuclear or Radiological Emergency. Emergency Preparedness and Response (Chinese Edition)

International Nuclear Information System (INIS)

2013-01-01

The aim of this publication is to provide practical guidance for public information officers on the preparation for and response to a nuclear or radiological emergency, and to fulfil in part functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), as well as meeting requirements stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, and in IAEA Safety Standards No. GS-R-2, Preparedness and Response for a Nuclear or Radiological Emergency. Under Article 5(a)(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. IAEA Safety Standards Series No. GS-R-2 establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, and specifies that 'All practicable steps shall be taken to provide the public with useful, timely, truthful, consistent and appropriate information throughout a nuclear or radiological emergency' in the response phase. It also requires 'responding to incorrect information and rumours; and responding to requests for information from the public and from the news and information media'. This publication provides guidance in the form of action guides and information sheets that can be easily applied by a State to build a basic capability to respond to a nuclear or radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This publication is published as part of the IAEA's Emergency Preparedness and Response series and complements the Manual for First Responders to a Radiological Emergency in the parts related to the tasks of public information officers. It takes

Communication with the Public in a Nuclear or Radiological Emergency. Emergency Preparedness and Response (French Edition)

International Nuclear Information System (INIS)

2013-01-01

The aim of this publication is to provide practical guidance for public information officers on the preparation for and response to a nuclear or radiological emergency, and to fulfil in part functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), as well as meeting requirements stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, and in IAEA Safety Standards No. GS-R-2, Preparedness and Response for a Nuclear or Radiological Emergency. Under Article 5(a)(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. IAEA Safety Standards Series No. GS-R-2 establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, and specifies that 'All practicable steps shall be taken to provide the public with useful, timely, truthful, consistent and appropriate information throughout a nuclear or radiological emergency' in the response phase. It also requires 'responding to incorrect information and rumours; and responding to requests for information from the public and from the news and information media'. This publication provides guidance in the form of action guides and information sheets that can be easily applied by a State to build a basic capability to respond to a nuclear or radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This publication is published as part of the IAEA's Emergency Preparedness and Response series and complements the Manual for First Responders to a Radiological Emergency in the parts related to the tasks of public information officers. It takes

Communication with the Public in a Nuclear or Radiological Emergency. Emergency Preparedness and Response (Chinese Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-09-01

The aim of this publication is to provide practical guidance for public information officers on the preparation for and response to a nuclear or radiological emergency, and to fulfil in part functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), as well as meeting requirements stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, and in IAEA Safety Standards No. GS-R-2, Preparedness and Response for a Nuclear or Radiological Emergency. Under Article 5(a)(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. IAEA Safety Standards Series No. GS-R-2 establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, and specifies that 'All practicable steps shall be taken to provide the public with useful, timely, truthful, consistent and appropriate information throughout a nuclear or radiological emergency' in the response phase. It also requires 'responding to incorrect information and rumours; and responding to requests for information from the public and from the news and information media'. This publication provides guidance in the form of action guides and information sheets that can be easily applied by a State to build a basic capability to respond to a nuclear or radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This publication is published as part of the IAEA's Emergency Preparedness and Response series and complements the Manual for First Responders to a Radiological Emergency in the parts related to the tasks of public information officers. It takes

Communication with the Public in a Nuclear or Radiological Emergency. Emergency Preparedness and Response (Arabic Edition)

International Nuclear Information System (INIS)

2014-01-01

The aim of this publication is to provide practical guidance for public information officers on the preparation for and response to a nuclear or radiological emergency, and to fulfil in part functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), as well as meeting requirements stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, and in IAEA Safety Standards No. GS-R-2, Preparedness and Response for a Nuclear or Radiological Emergency. Under Article 5(a)(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. IAEA Safety Standards Series No. GS-R-2 establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, and specifies that 'All practicable steps shall be taken to provide the public with useful, timely, truthful, consistent and appropriate information throughout a nuclear or radiological emergency' in the response phase. It also requires 'responding to incorrect information and rumours; and responding to requests for information from the public and from the news and information media'. This publication provides guidance in the form of action guides and information sheets that can be easily applied by a State to build a basic capability to respond to a nuclear or radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This publication is published as part of the IAEA's Emergency Preparedness and Response series and complements the Manual for First Responders to a Radiological Emergency in the parts related to the tasks of public information officers. It takes

Communication with the Public in a Nuclear or Radiological Emergency. Emergency Preparedness and Response (Russian Edition)

International Nuclear Information System (INIS)

2014-01-01

The aim of this publication is to provide practical guidance for public information officers on the preparation for and response to a nuclear or radiological emergency, and to fulfil in part functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), as well as meeting requirements stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, and in IAEA Safety Standards No. GS-R-2, Preparedness and Response for a Nuclear or Radiological Emergency. Under Article 5(a)(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. IAEA Safety Standards Series No. GS-R-2 establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, and specifies that 'All practicable steps shall be taken to provide the public with useful, timely, truthful, consistent and appropriate information throughout a nuclear or radiological emergency' in the response phase. It also requires 'responding to incorrect information and rumours; and responding to requests for information from the public and from the news and information media'. This publication provides guidance in the form of action guides and information sheets that can be easily applied by a State to build a basic capability to respond to a nuclear or radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This publication is published as part of the IAEA's Emergency Preparedness and Response series and complements the Manual for First Responders to a Radiological Emergency in the parts related to the tasks of public information officers. It takes

Communication with the Public in a Nuclear or Radiological Emergency. Emergency Preparedness and Response (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

The aim of this publication is to provide practical guidance for public information officers on the preparation for and response to a nuclear or radiological emergency, and to fulfil in part functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), as well as meeting requirements stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, and in IAEA Safety Standards No. GS-R-2, Preparedness and Response for a Nuclear or Radiological Emergency. Under Article 5(a)(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. IAEA Safety Standards Series No. GS-R-2 establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, and specifies that 'All practicable steps shall be taken to provide the public with useful, timely, truthful, consistent and appropriate information throughout a nuclear or radiological emergency' in the response phase. It also requires 'responding to incorrect information and rumours; and responding to requests for information from the public and from the news and information media'. This publication provides guidance in the form of action guides and information sheets that can be easily applied by a State to build a basic capability to respond to a nuclear or radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This publication is published as part of the IAEA's Emergency Preparedness and Response series and complements the Manual for First Responders to a Radiological Emergency in the parts related to the tasks of public information officers. It takes

Effects of Low Doses of Ionizing Radiation Exposures on Stress-Responsive Gene Expression in Human Embryonic Stem Cells

Directory of Open Access Journals (Sweden)

Mykyta Sokolov

2014-01-01

Full Text Available There is a great deal of uncertainty on how low (≤0.1 Gy doses of ionizing radiation (IR affect human cells, partly due to a lack of suitable experimental model systems for such studies. The uncertainties arising from low-dose IR human data undermine practical societal needs to predict health risks emerging from diagnostic medical tests’ radiation, natural background radiation, and environmental radiological accidents. To eliminate a variability associated with remarkable differences in radioresponses of hundreds of differentiated cell types, we established a novel, human embryonic stem cell (hESC-based model to examine the radiobiological effects in human cells. Our aim is to comprehensively elucidate the gene expression changes in a panel of various hESC lines following low IR doses of 0.01; 0.05; 0.1 Gy; and, as a reference, relatively high dose of 1 Gy of IR. Here, we examined the dynamics of transcriptional changes of well-established IR-responsive set of genes, including CDKN1A, GADD45A, etc. at 2 and 16 h post-IR, representing “early” and “late” radioresponses of hESCs. Our findings suggest the temporal- and hESC line-dependence of stress gene radioresponses with no statistically significant evidence for a linear dose-response relationship within the lowest doses of IR exposures.

Low dose intranasal oxytocin delivered with Breath Powered device dampens amygdala response to emotional stimuli: A peripheral effect-controlled within- subjects randomized dose-response fMRI trial

OpenAIRE

Quintana, Daniel; Westlye, Lars Tjelta; Alnæs, Dag; Rustan, Øyvind; Kaufmann, Tobias; Smerud, Knut Terje; Mahmoud, Ramy; Djupesland, Per G.; Andreassen, Ole Andreas

2016-01-01

It is unclear if and how exogenous oxytocin (OT) reaches the brain to improve social behavior and cognition and what is the optimal dose for OT response. To better understand the delivery routes of intranasal OT administration to the brain and the dose-response, we compared amygdala response to facial stimuli by means of functional magnetic resonance imaging (fMRI) in four treatment conditions, including two different doses of intranasal OT using a novel Breath Powered device, intravenous (IV...

An Ontology-Underpinned Emergency Response System for Water Pollution Accidents

Directory of Open Access Journals (Sweden)

Xiaoliang Meng

2018-02-01

Full Text Available With the unceasing development and maturation of environment geographic information system, the response to water pollution accidents has been digitalized through the combination of monitoring sensors, management servers, and application software. However, most of these systems only achieve the basic and general geospatial data management and functional process tasks by adopting mechanistic water-quality models. To satisfy the sustainable monitoring and real-time emergency response application demand of the government and public users, it is a hotspot to study how to make the water pollution information being semantic and make the referred applications intelligent. Thus, the architecture of the ontology-underpinned emergency response system for water pollution accidents is proposed in this paper. This paper also makes a case study for usability testing of the water ontology models, and emergency response rules through an online water pollution emergency response system. The system contributes scientifically to the safety and sustainability of drinking water by providing emergency response and decision-making to the government and public in a timely manner.

Comparing different technologies for wireless real-time dose rate monitoring for on- and offsite emergency management

International Nuclear Information System (INIS)

Dielmann, R.

2004-01-01

At a nuclear disaster the efficiency of emergency management on-site as well as off-site is closely connected to the quality and reliability of the actual status information. Reliability and short response time of the data communication path are important in the early phase. In order to protect investment and minimize TCO (Total Cost of Ownership) the dose rate measurement systems should also be adequate for the later phase emergency management and rehabilitation of contaminated areas. Based on four years experience the pros and cons of available GSM / GPRS / UMTS / TETRA (Terrestrial Trunked Radio) and satellite based technologies are compared with SkyLINK - a proprietary wireless network technology which is fully owned by the supervising authority or a nuclear installation. The European Commission's decision in 1999 to opt for this state-of-the-art technology within the TACIS program fulfills highest standards for emergency management networks featuring especially: independence of public communication lines, good data availability also in rural areas and in emergency scenarios, fast installation, system startup and training, extreme mobility in emergency cases, high flexibility for changing tasks, very high degree of autonomy, low operating and maintenance costs over a ten year lifetime, long-term reliability of probes and data management system. After more than four years of experience with installations around the world especially those installed around three Russian nuclear power plants a comparison of this reliably operating technology can be done. (author)

Radiation Dose-Response Model for Locally Advanced Rectal Cancer After Preoperative Chemoradiation Therapy

International Nuclear Information System (INIS)

Appelt, Ane L.; Pløen, John; Vogelius, Ivan R.; Bentzen, Søren M.; Jakobsen, Anders

2013-01-01

Purpose: Preoperative chemoradiation therapy (CRT) is part of the standard treatment of locally advanced rectal cancers. Tumor regression at the time of operation is desirable, but not much is known about the relationship between radiation dose and tumor regression. In the present study we estimated radiation dose-response curves for various grades of tumor regression after preoperative CRT. Methods and Materials: A total of 222 patients, treated with consistent chemotherapy and radiation therapy techniques, were considered for the analysis. Radiation therapy consisted of a combination of external-beam radiation therapy and brachytherapy. Response at the time of operation was evaluated from the histopathologic specimen and graded on a 5-point scale (TRG1-5). The probability of achieving complete, major, and partial response was analyzed by ordinal logistic regression, and the effect of including clinical parameters in the model was examined. The radiation dose-response relationship for a specific grade of histopathologic tumor regression was parameterized in terms of the dose required for 50% response, D 50,i , and the normalized dose-response gradient, γ 50,i . Results: A highly significant dose-response relationship was found (P=.002). For complete response (TRG1), the dose-response parameters were D 50,TRG1 = 92.0 Gy (95% confidence interval [CI] 79.3-144.9 Gy), γ 50,TRG1 = 0.982 (CI 0.533-1.429), and for major response (TRG1-2) D 50,TRG1 and 2 = 72.1 Gy (CI 65.3-94.0 Gy), γ 50,TRG1 and 2 = 0.770 (CI 0.338-1.201). Tumor size and N category both had a significant effect on the dose-response relationships. Conclusions: This study demonstrated a significant dose-response relationship for tumor regression after preoperative CRT for locally advanced rectal cancer for tumor dose levels in the range of 50.4-70 Gy, which is higher than the dose range usually considered.

Dose response of bone-targeted enzyme replacement for murine hypophosphatasia.

Science.gov (United States)

Yadav, Manisha C; Lemire, Isabelle; Leonard, Pierre; Boileau, Guy; Blond, Laurent; Beliveau, Martin; Cory, Esther; Sah, Robert L; Whyte, Michael P; Crine, Philippe; Millán, José Luis

2011-08-01

Hypophosphatasia (HPP) features rickets or osteomalacia from tissue-nonspecific alkaline phosphatase (TNSALP) deficiency due to deactivating mutations within the ALPL gene. Enzyme replacement therapy with a bone-targeted, recombinant TNSALP (sALP-FcD(10), renamed ENB-0040) prevents manifestations of HPP when initiated at birth in TNSALP knockout (Akp2(-/-)) mice. Here, we evaluated the dose-response relationship of ENB-0040 to various phenotypic traits of Akp2(-/-) mice receiving daily subcutaneous (SC) injections of ENB-0040 from birth at 0.5, 2.0, or 8.2mg/kg for 43days. Radiographs, μCT, and histomorphometric analyses documented better bone mineralization with increasing doses of ENB-0040. We found a clear, positive correlation between ENB-0040 dose and prevention of mineralization defects of the feet, rib cage, lower limbs, and jaw bones. According to a dose-response model, the ED(80) (the dose that prevents bone defects in 80% of mice) was 3.2, 2.8 and 2.9mg/kg/day for these sites, respectively. Long bones seemed to respond to lower daily doses of ENB-0040. There was also a positive relationship between ENB-0040 dose and survival. Median survival, body weight, and bone length all improved with increasing doses of ENB-0040. Urinary PP(i) concentrations remained elevated in all treatment groups, indicating that while this parameter is a good biochemical marker for diagnosing HPP in patients, it may not be a good follow up marker for evaluating response to treatment when administering bone-targeted TNSALP to mice. These dose-response relationships strongly support the pharmacological efficacy of ENB-0040 for HPP, and provide the experimental basis for the therapeutic range of ENB-0040 chosen for clinical trials. Copyright © 2011 Elsevier Inc. All rights reserved.

An expert system for improving nuclear emergency response

International Nuclear Information System (INIS)

Salame-Alfie, A.; Goldbogen, G.C.; Ryan, R.M.; Wallace, W.A.; Yeater, M.L.

1987-01-01

The accidents at TMI-2 and Chernobyl have produced initiatives aimed at improving nuclear plant emergency response capabilities. Among them are the development of emergency response facilities with capabilities for the acquisition, processing, and diagnosis of data which are needed to help coordinate plant operations, engineering support and management under emergency conditions. An effort in this direction prompted the development of an expert system. EP (EMERGENCY PLANNER) is a prototype expert system that is intended to help coordinate the overall management during emergency conditions. The EP system was built using the GEN-X expert system shell. GEN-X has a variety of knowledge representation mechanisms including AND/OR trees, Decision trees, and IF/THEN tables, and runs on an IBM PC-XT or AT computer or compatible. Among the main features, EP is portable, modular, user friendly, can interact with external programs and interrogate data bases. The knowledge base is made of New York State (NYS) Procedures for Emergency Classification, NYS Radiological Emergency Preparedness Plan (REPP) and knowledge from experts of the NYS Radiological Emergency Preparedness Group and the Office of Radiological Health and Chemistry of the New York Power Authority (NYPA)

Continuous Intravenous Sub-Dissociative Dose Ketamine Infusion for Managing Pain in the Emergency Department

OpenAIRE

Motov, Sergey; Drapkin, Jefferson; Likourezos, Antonios; Beals, Tyler; Monfort, Ralph; Fromm, Christian; Marshall, John

2018-01-01

Introduction: Our objective was to describe dosing, duration, and pre- and post-infusion analgesic administration of continuous intravenous sub-dissociative dose ketamine (SDK) infusion for managing a variety of painful conditions in the emergency department (ED).  Methods: We conducted a retrospective chart review of patients aged 18 and older presenting to the ED with acute and chronic painful conditions who received continuous SDK infusion in the ED for a pe...

Single-dose-response curves of murine gastrointestinal crypt stem cells

International Nuclear Information System (INIS)

Masuda, K.; Withers, H.R.; Mason, K.A.; Chen, K.Y.

1977-01-01

Dose-response curves for the reproductive capacity of crypt stem cells of murine colonic, jejunal, and gastric mucosae exposed in situ to multifractionated gamma ray exposures were analyzed and single-dose-survival curves of these cells were constructed. The following conclusions were drawn: (1) The single-dose-response curves bend downward over a dose range of approximately 200 to 1500 rad; (2) cell death seems to be due to nonrepairable damage at doses less than 250 rad for colon, and 220 rad for jejunum; (3) there are 21, 110, and 140 stem cells per crypt of gastric, colonic, and jejunal mucosa, respectively; and (4) jejunal stem cells are the most radiosensitive and gastric mucosal stem cells are the most resistant

45 CFR 673.5 - Emergency response plan.

Science.gov (United States)

2010-10-01

... ensure that: (a) The vessel owner's or operator's shipboard oil pollution emergency plan, prepared and... Pollution from Ships, 1973, as modified by the Protocol of 1978 relating thereto (MARPOL 73/78), has provisions for prompt and effective response action to such emergencies as might arise in the performance of...

Wind emergency response system

International Nuclear Information System (INIS)

Garrett, A.J.; Buckner, M.R.; Mueller, R.A.

1981-01-01

The WIND system is an automated emergency response system for real-time predictions of the consequences of liquid and airborne releases from SRP. The system consists of a minicomputer and associated peripherals necessary for acquisition and handling of large amounts of meteorological data from a local tower network and the National Weather Service. The minicomputer uses these data and several predictive models to assess the impact of accidental releases. The system is fast and easy to use, and output is displayed both in tabular form and as trajectory map plots for quick interpretation. The rapid response capabilities of the WIND system have been demonstrated in support of SRP operations

Theoretic simulation for CMOS device on total dose radiation response

International Nuclear Information System (INIS)

He Baoping; Zhou Heqin; Guo Hongxia; He Chaohui; Zhou Hui; Luo Yinhong; Zhang Fengqi

2006-01-01

Total dose effect is simulated for C4007B, CC4007RH and CC4011 devices at different absorbed dose rate by using linear system theory. When irradiation response and dose are linear, total dose radiation and post-irradiation annealing at room temperature are determined for one random by choosing absorbed dose rate, and total dose effect at other absorbed dose rate can be predicted by using linear system theory. The simulating results agree with the experimental results at different absorbed dose rate. (authors)

Assembled cross-species perchlorate dose-response data

Data.gov (United States)

U.S. Environmental Protection Agency — This data set contains dose-response data for perchlorate exposure in multiple species. These data were assembled from peer-reviewed studies. Species included in...

Modeling operators' emergency response time for chemical processing operations.

Science.gov (United States)

Murray, Susan L; Harputlu, Emrah; Mentzer, Ray A; Mannan, M Sam

2014-01-01

Operators have a crucial role during emergencies at a variety of facilities such as chemical processing plants. When an abnormality occurs in the production process, the operator often has limited time to either take corrective actions or evacuate before the situation becomes deadly. It is crucial that system designers and safety professionals can estimate the time required for a response before procedures and facilities are designed and operations are initiated. There are existing industrial engineering techniques to establish time standards for tasks performed at a normal working pace. However, it is reasonable to expect the time required to take action in emergency situations will be different than working at a normal production pace. It is possible that in an emergency, operators will act faster compared to a normal pace. It would be useful for system designers to be able to establish a time range for operators' response times for emergency situations. This article develops a modeling approach to estimate the time standard range for operators taking corrective actions or following evacuation procedures in emergency situations. This will aid engineers and managers in establishing time requirements for operators in emergency situations. The methodology used for this study combines a well-established industrial engineering technique for determining time requirements (predetermined time standard system) and adjustment coefficients for emergency situations developed by the authors. Numerous videos of workers performing well-established tasks at a maximum pace were studied. As an example, one of the tasks analyzed was pit crew workers changing tires as quickly as they could during a race. The operations in these videos were decomposed into basic, fundamental motions (such as walking, reaching for a tool, and bending over) by studying the videos frame by frame. A comparison analysis was then performed between the emergency pace and the normal working pace operations

Meteorological considerations in emergency response capability at nuclear power plant

International Nuclear Information System (INIS)

Fairobent, J.E.

1985-01-01

Meteorological considerations in emergency response at nuclear power plants are discussed through examination of current regulations and guidance documents, including discussion of the rationale for current regulatory requirements related to meteorological information for emergency response. Areas discussed include: major meteorological features important to emergency response; onsite meteorological measurements programs, including redundant and backup measurements; access to offsite sources of meteorological information; consideration of real-time and forecast conditions and atmospheric dispersion modeling

A Unified Probabilistic Framework for Dose-Response Assessment of Human Health Effects.

Science.gov (United States)

Chiu, Weihsueh A; Slob, Wout

2015-12-01

When chemical health hazards have been identified, probabilistic dose-response assessment ("hazard characterization") quantifies uncertainty and/or variability in toxicity as a function of human exposure. Existing probabilistic approaches differ for different types of endpoints or modes-of-action, lacking a unifying framework. We developed a unified framework for probabilistic dose-response assessment. We established a framework based on four principles: a) individual and population dose responses are distinct; b) dose-response relationships for all (including quantal) endpoints can be recast as relating to an underlying continuous measure of response at the individual level; c) for effects relevant to humans, "effect metrics" can be specified to define "toxicologically equivalent" sizes for this underlying individual response; and d) dose-response assessment requires making adjustments and accounting for uncertainty and variability. We then derived a step-by-step probabilistic approach for dose-response assessment of animal toxicology data similar to how nonprobabilistic reference doses are derived, illustrating the approach with example non-cancer and cancer datasets. Probabilistically derived exposure limits are based on estimating a "target human dose" (HDMI), which requires risk management-informed choices for the magnitude (M) of individual effect being protected against, the remaining incidence (I) of individuals with effects ≥ M in the population, and the percent confidence. In the example datasets, probabilistically derived 90% confidence intervals for HDMI values span a 40- to 60-fold range, where I = 1% of the population experiences ≥ M = 1%-10% effect sizes. Although some implementation challenges remain, this unified probabilistic framework can provide substantially more complete and transparent characterization of chemical hazards and support better-informed risk management decisions.

Generic Procedures for Medical Response During a Nuclear or Radiological Emergency

International Nuclear Information System (INIS)

2009-01-01

The aim of this manual is to provide the medical community with practical guidance for medical emergency preparedness and response, describing the tasks and actions of different members of the national, regional or local medical infrastructure in accordance with international standards. This document provides generic response procedures for medical personnel responding to different types of radiation emergencies and at the different stages of the emergency response (at the scene of the emergency, pre-hospital, hospital), and during the early post-emergency stage (about 1-2 months afterwards).

Radiological emergencies the first response

International Nuclear Information System (INIS)

2011-11-01

This national training course about radiological emergencies first answer include: Targets and preparation for emergency response in case of a nuclear or radiological accident. Operations center, action guide for fire fighting, medical coverage, forensic test, first aid, basic instrumentation for radiation, safety equipment, monitoring radiation, gamma rays, personnel exposed protection , radiation exposure rate, injury and illness for radiation, cancer risk, contamination, decontamination and treatment, markers, personnel dosimetry, training, medical and equipment transportation, shielded and tools. Psychological, physical (health and illness), economical (agriculture and industry) and environment impacts. Terrorist attacks, security belts. Support and international agreements (IAEA)

Effect of heterogeneity of human population in cell radiosensitivity on the extrapolation of dose-response relationships to low doses

International Nuclear Information System (INIS)

Filyushkin, I.V.; Bragin, Yu.N.; Khandogina, E.K.

1989-01-01

Presented are the results of an investigation of the dose-response relationship for the yield of chromosome aberrations in peripheral blood lymphocytes of persons with some hereditary diseases which represent the high risk group with respect to the increased incidence of malignant tumors and decreased life span. Despite substantially different absolute radiosensitivities of chromosomes, the variations of the alpha/beta ratio determining the extrapolation of experimental dose-response relationships to low doses did not prove to be too high, the mean deviation from the control being 15%. This points to the possible practical use of the dose-response relationships averaged over the human population as a whole

Dose equivalent response of personal neutron dosemeters as a function of angle

International Nuclear Information System (INIS)

Tanner, J.E.; McDonald, J.C.; Stewart, R.D.; Wernli, C.

1997-01-01

The measured and calculated dose equivalent response as a function of angle has been examined for an albedo-type thermoluminescence dosemeter (TLD) that was exposed to unmoderated and D 2 O-moderated 252 Cf neutron sources while mounted on a 40 x 40 15 cm 3 polymethylmethacrylate phantom. The dosemeter used in this study is similar to many neutron personal dosemeters currently in use. The detailed construction of the dosemeter was modelled, and the dose equivalent response was calculated, using the MCNP code. Good agreement was found between the measured and calculated values of the relative dose equivalent angular response for the TLD albedo dosemeter. The relative dose equivalent angular response was also compared with the values of directional and personal dose equivalent as a function of angle published by Siebert and Schuhmacher. (author)

Emergency preparedness and response in transport of radioactive material

International Nuclear Information System (INIS)

Takani, Michio

2008-01-01

Nuclear power has been providing clean, affordable electricity in many parts of the world for nearly half a century. The national and international transport of nuclear fuel cycle materials is essential to support this activity. To sustain the nuclear power industry, fuel cycle materials have to be transported safely and efficiently. The nature of the industry is such that most countries with large-scale nuclear power industries cannot provide all the necessary fuel services themselves and consequently nuclear fuel cycle transport activities are international. The radioactive material transport industry has an outstanding safety record spanning over 45 years; however the transport of radioactive materials cannot and most not be taken for granted. Efficient emergency preparedness and response in the transport of radioactive material is an important element to ensure the maximum safety in accident conditions. The World Nuclear Transport Institute (WNTI), founded by International Nuclear Services (INS) of the United Kingdom, AREVA of France an the Federation of Electric Power Companies (FEPC) of Japan, represents the collective interest of the radioactive material transport sector, and those who rely on safe, effective and reliable transport. As part of its activities, WNTI has conducted two surveys through its members on emergency preparedness and response in the transport of radioactive material and emergency exercises. After recalling the International Atomic Energy Agency approach on emergency response, this paper will be discussing the main conclusion of surveys, in particular the national variations in emergency response and preparedness on the national and local levels of regulations, the emergency preparedness in place, the emergency response organisation (who and how), communication and exercises. (author)

Generic procedures for assessment and response during a radiological emergency

International Nuclear Information System (INIS)

2000-08-01

One of the most important aspects of managing a radiological emergency is the ability to promptly and adequately determine and take actions to protect members of the public and emergency workers. Radiological accident assessment must take account of all critical information available at any time and must be an iterative and dynamic process aimed at reviewing the response as more detailed and complete information becomes available. This manual provides the tools, generic procedures and data needed for an initial response to a non-reactor radiological accident. This manual is one out of a set of IAEA publications on emergency preparedness and response, including Method for the Development of Emergency Response Preparedness for Nuclear or Radiological Accidents (IAEA-TECDOC-953), Generic Assessment Procedures for Determining Protective Actions During a Reactor Accident (IAEA-TECDOC-955) and Intervention Criteria in a Nuclear or Radiation Emergency (Safety Series No. 109)

Effect and adaptive response of lymphocytes DNA induced by low dose irradiation

International Nuclear Information System (INIS)

Du Zeji; Su Liaoyuan; Tian Hailin

1994-09-01

Fluorometric analysis of DNA unwinding (FADU) was conducted and was proved to be an optimal method for studying DNA strand breaks induced by low dose irradiation. The linear dose response curve was obtained. The minimum detected dose was 0.3 Gy. There was no effect of low dose γ-rays (0.5∼8.0 cGy) on DNA strand breaks of quiescent and mitogen-induced lymphocytes. The 0.5∼4.0 cGy γ-rats could induce adaptive response of lymphocytes' DNA strand breaks, especially, at the doses of 2.0 and 4.0 cGy. The challenge doses of 5∼20 Gy could make the adaptive response appearance, and the 15 Gy was the best one. The 3-AB could powerfully inhibit the adaptive response. The repair of DNA strand breaks (37 degree C, 15∼60 min) caused by 15 Gy γ-rays could be promoted by the low dose γ-ray irradiation (2.0 cGy), but no difference was found at 37 degree C, 120 min

Manual for first responders to a radiological emergency. Emergency preparedness and response. Publication date: June 2007

International Nuclear Information System (INIS)

2007-08-01

Under Article 5.a(ii) of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. As stated in IAEA Safety Standards Series No. GS-R-2 'Preparedness and Response for a Nuclear or Radiological Emergency', which establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, 'first responders shall take all practicable and appropriate actions to minimize the consequences of a nuclear or radiological emergency'. The IAEA General Conference, in resolution GC(49)/RES/9, continues to encourage Member States 'to adopt the relevant Agency standards, procedures and practical tools' and underlines 'the need for first responders to have appropriate training for dealing with ionizing radiation during nuclear and radiological emergencies'. This publication is intended to assist in meeting these requirements and to fulfil Article 5 of the Assistance Convention. Its aim is to provide practical guidance for those who will respond during the first few hours to a radiological emergency (referred to here as 'first responders') and for national officials who would support this early response. It provides guidance in the form of action guides, instructions, and supporting data that can be easily applied by a State to build a basic capability to respond to a radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This report, published as part of the IAEA Emergency Preparedness and Response Series, replaces and builds on IAEA-TECDOC-1162 in the area of early response and first responders' actions. It takes account of the

Manual for first responders to a radiological emergency. Emergency preparedness and response. Publication date: October 2006

International Nuclear Information System (INIS)

2006-10-01

Under Article 5.a(ii) of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and results of research relating to response to nuclear or radiological emergencies. As stated in IAEA Safety Standards Series No. GS-R-2 'Preparedness and Response for a Nuclear or Radiological Emergency', which establishes the requirements for an adequate level of preparedness for and response to a nuclear or radiological emergency in any State, 'first responders shall take all practicable and appropriate actions to minimize the consequences of a nuclear or radiological emergency'. The IAEA General Conference, in resolution GC(49)/RES/9, continues to encourage Member States 'to adopt the relevant Agency standards, procedures and practical tools' and underlines 'the need for first responders to have appropriate training for dealing with ionizing radiation during nuclear and radiological emergencies'. This publication is intended to assist in meeting these requirements and to fulfil Article 5 of the Assistance Convention. Its aim is to provide practical guidance for those who will respond during the first few hours to a radiological emergency (referred to here as 'first responders') and for national officials who would support this early response. It provides guidance in the form of action guides, instructions, and supporting data that can be easily applied by a State to build a basic capability to respond to a radiological emergency. This guidance should be adapted to fit the user State's organizational arrangements, language, terminology, concept of operation and capabilities. This report, published as part of the IAEA Emergency Preparedness and Response Series, replaces and builds on IAEA-TECDOC-1162 in the area of early response and first responders' actions. It takes account of the

A Probabilistic Risk Assessment For Emergency Preparedness

International Nuclear Information System (INIS)

Lee, Joomyung; Jae, Moosung; Ahn, Kwangil

2013-01-01

The importance of nuclear power plant PSA has grown up all over the world due to this incident. The main concern of this study is to develop a methodology to carry on an emergency preparedness evaluation and to set an exclusive area, or the emergency response area boundary in order to apply it to domestic reference plants. This study also focuses on evaluating the risk parameter of major nuclides through a sensitivity analysis and a safety assessment by calculating the population dose, early fatality, and cancer fatality rates. A methodology for an emergency preparedness, which can be applied to evaluate the damage of the radioactive release as well as to assess the safety of the accident scenario of a nuclear power plant, has been developed and applied for the reference plants in Korea. By applying a source term analysis, an exclusive zone based on the radioactive dose is obtained. And the results of the health effect assessment based on the release fraction of specific nuclides to public with an effective emergency response activity have been simulated. A methodology utilizing the Level 3 PSA with the actual emergency response activities has been developed and applied to typical nuclear accident situations. The plausible standard for performing an emergency plan is suggested and the valuable information regarding emergency preparedness has been produced in this study. For further works, the sensitivity study on important parameters will be performed to simulate the actual severe accident situations such as sheltering, evacuation, and emergency response activities

Dose Response of Alanine Detectors Irradiated with Carbon Ion Beams

DEFF Research Database (Denmark)

Herrmann, Rochus; Jäkel, Oliver; Palmans, Hugo

2011-01-01

Purpose: The dose response of the alanine detector shows a dependence on particle energy and type, when irradiated with ion beams. The purpose of this study is to investigate the response behaviour of the alanine detector in clinical carbon ion beams and compare the results with model predictions......-dose curves deviate from predictions in the peak region, most pronounced at the distal edge of the peak. Conclusions: The used model and its implementation show a good overall agreement for quasi mono energetic measurements. Deviations in depth-dose measurements are mainly attributed to uncertainties...

Enhancing nuclear emergency response through international co-operation

International Nuclear Information System (INIS)

Ugletveit, F.; Aaltonen, H.

2003-01-01

Full text: A large number of different national plans and procedures have been established and substantial resources allocated world wide with varying comprehensiveness and quality depending an the national requirements and the possible threat scenarios considered. These national plans are only to a small degree harmonized. It is clear that it is the responsibility of the authorities in the respective countries or utilities under their jurisdiction, to decide upon and implement appropriate response actions to a nuclear emergency. The basic needs for responding properly are: infrastructure in terms of plans, procedures etc.; information regarding the accident, its development and consequences; resources in terms of expertise, man power and tools for acquiring and processing information, making assessments and decisions and carry out the actions. When a large number of countries are making assessments and decisions for their own country and providing the public with information, it is important that assessments, decisions and public information become correct, complete and consistent across boarders. In order to achieve this, they should all have access to the same information as basis for their actions. Lack of information or wrong information could easily lead to wrong assessments, wrong decisions and misleading information to the public. If there is a serious nuclear emergency somewhere that could potentially affect several or many States in one way or another, 'everyone' would like to know 'everything' that happens 'everywhere'. In this case, all States should have the obligation to share with the international community the relevant information they have available themselves and that could be of interest for other States responding to the situation. During a serious nuclear or radiological emergency, the demand for different kinds of resources is huge and could, in many countries, probably exceed national capabilities. Looking at the situation in a global

Bulgarian Emergency Response System (BERS) in case of nuclear accident with exposure doses’estimation

Energy Technology Data Exchange (ETDEWEB)

Syrakov, M.; Prodanova, M.; Slavov, K.; Veleva, B.

2015-07-01

A PC-oriented Emergency Response System in case of nuclear accident (BERS) is developed and works operationally in the National Institute of Meteorology and Hydrology (NIMH). The creation and development of BERS was highly stimulated by the ETEX (European Tracer Experiment) project. BERS comprises two main parts - the operational and the accidental ones. The operational part, run automatically every 12 hours, prepares the input meteorological file used by both trajectory and dispersion models, runs the trajectory models, visualizes the results and uploads the maps of trajectories to a dedicated web-site. The accidental part is activated manually when a real radioactive releases occur or during emergency exercises. Its core is the Bulgarian dispersion models EMAP. Outputs are concentration, accumulated deposition and selected doses fields. In the paper, the BERS overall structure is described and examples of its products are presented. (Author)

IEA Response System for Oil Supply Emergencies (2012 update)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-09-05

Emergency response to oil supply disruptions has remained a core mission of the International Energy Agency since its founding in 1974. This information pamphlet explains the decisionmaking process leading to an IEA collective action, the measures available -- focusing on stockdraw -- and finally, the historical background of major oil supply disruptions and the IEA response to them. It also demonstrates the continuing need for emergency preparedness, including the growing importance of engaging key transition and emerging economies in dialogue about energy security.

Nuclear emergencies

International Nuclear Information System (INIS)

1991-01-01

This leaflet, which is in the form of a fold-up chart, has panels of text which summarize the emergencies that could arise and the countermeasures and emergency plans that have been prepared should nuclear accident occur or affect the United Kingdom. The levels of radiation doses at which various measures would be introduced are outlined. The detection and monitoring programmes that would operate is illustrated. The role of NRPB and the responsible government departments are set out together with an explanation of how the National Arrangements for Incidents involving Radioactivity would be coordinated. (UK)

Dose-dependent hepatic transcriptional responses in Atlantic salmon (Salmo salar) exposed to sublethal doses of gamma radiation

Energy Technology Data Exchange (ETDEWEB)

Song, You, E-mail: you.song@niva.no [Norwegian University of Life Sciences (NMBU), Faculty of Environmental Science and Technology, Department of Environmental Sciences (IMV), Centre for Environmental Radioactivity - CERAD, P.O. Box 5003, N-1432 Ås (Norway); Norwegian Institute for Water Research (NIVA), Gaustadalléen 21, N-0349 Oslo (Norway); Salbu, Brit; Teien, Hans-Christian; Heier, Lene Sørlie [Norwegian University of Life Sciences (NMBU), Faculty of Environmental Science and Technology, Department of Environmental Sciences (IMV), Centre for Environmental Radioactivity - CERAD, P.O. Box 5003, N-1432 Ås (Norway); Rosseland, Bjørn Olav [Norwegian University of Life Sciences (NMBU), Faculty of Environmental Science and Technology, Department of Environmental Sciences (IMV), Centre for Environmental Radioactivity - CERAD, P.O. Box 5003, N-1432 Ås (Norway); Norwegian University of Life Sciences (NMBU), Department of Ecology and Natural Resource Management, P.O. Box 5003, N-1432 Ås (Norway); Tollefsen, Knut Erik [Norwegian University of Life Sciences (NMBU), Faculty of Environmental Science and Technology, Department of Environmental Sciences (IMV), Centre for Environmental Radioactivity - CERAD, P.O. Box 5003, N-1432 Ås (Norway); Norwegian Institute for Water Research (NIVA), Gaustadalléen 21, N-0349 Oslo (Norway)

2014-11-15

Highlights: • First study on early stress responses in salmon exposed to low-dose gamma radiation. • Dramatic dose-dependent transcriptional responses characterized. • Multiple modes of action proposed for gamma radiation. - Abstract: Due to the production of free radicals, gamma radiation may pose a hazard to living organisms. The high-dose radiation effects have been extensively studied, whereas the ecotoxicity data on low-dose gamma radiation is still limited. The present study was therefore performed using Atlantic salmon (Salmo salar) to characterize effects of low-dose (15, 70 and 280 mGy) gamma radiation after short-term (48 h) exposure. Global transcriptional changes were studied using a combination of high-density oligonucleotide microarrays and quantitative real-time reverse transcription polymerase chain reaction (qPCR). Differentially expressed genes (DEGs; in this article the phrase gene expression is taken as a synonym of gene transcription, although it is acknowledged that gene expression can also be regulated, e.g., at protein stability and translational level) were determined and linked to their biological meanings predicted using both Gene Ontology (GO) and mammalian ortholog-based functional analyses. The plasma glucose level was also measured as a general stress biomarker at the organism level. Results from the microarray analysis revealed a dose-dependent pattern of global transcriptional responses, with 222, 495 and 909 DEGs regulated by 15, 70 and 280 mGy gamma radiation, respectively. Among these DEGs, only 34 were commonly regulated by all radiation doses, whereas the majority of differences were dose-specific. No GO functions were identified at low or medium doses, but repression of DEGs associated with GO functions such as DNA replication, cell cycle regulation and response to reactive oxygen species (ROS) were observed after 280 mGy gamma exposure. Ortholog-based toxicity pathway analysis further showed that 15 mGy radiation

Integration of radiation monitoring for nuclear emergency response teams

Energy Technology Data Exchange (ETDEWEB)

Olsen, J T; Thompson, N Y [Royal Military Coll. of Canada, Kingston, ON (Canada)

1994-12-31

The Canadian Forces have established Nuclear Emergency Response Teams to cope with potential radiation accidents. Previously, only gamma and high-energy beta radiation could be detected. Recently, new radiation sampling, detecting, and analytical equipment has been bought, including air samplers, beta counters, high-purity germanium gamma detectors, and multi-channel analyzers together with Gamma Vision Software to analyze gamma spectra. The purpose of the present study is to propose a way to use the new equipment, to analyze the results from the gamma and beta detectors, and to integrate the results into a format for decision making. Integration is achieved through the creation of a computer program, Radiation Integration Program (RIP). This program analyzes gross beta counts, and uses them to estimate danger to the thyroid. As well the results from Gamma Vision are converted from Bq to dose rate for several parts of the body. Overall gamma results affecting the thyroid are compared to the beta results to verify the initial estimations.

Towards a coherent conceptual framework for emergency preparedness/response and rehabilitation - the application of the new ICRP recommendations given in ICRP 103

International Nuclear Information System (INIS)

Weiss, W.

2009-01-01

In the past, most emphasis in planning for and response to an emergency situation has been placed on selected protective measures in the early phase of an emergency to keep the doses received below levels where severe deterministic health effects can be excluded and/or where the risk of stochastic effects in the population is considered 'acceptable'. Less emphasis has been placed on the development of comprehensive protection strategies which include considerations of the consequences of all exposure pathways and all phases, e.g. long-term rehabilitation. In its new publication 103, ICRP proposed a coherent conceptual framework for protection in all types of exposure situations including 'emergency exposure situations' and 'existing exposure situations'. In the context of developing protection strategies for these exposure situations, the Commission recommends that national authorities set reference levels between, typically, 20 mSv and 100 mSv annual effective dose (emergency exposure situation) and 1 mSv and 20 mSv (existing exposure situation). In order to optimise protection strategies, it is necessary to identify the dominant exposure pathways, the timescales over which the dose will be received, and the effectiveness of available protection options. The characteristics of the development and implementation of such protection strategies is described.

An overview of the Environmental Response Team's air surveillance procedures at emergency response activities

Energy Technology Data Exchange (ETDEWEB)

Turpin, R.D.; Campagna, P.R. (U.S. Environmental Protection Agency, Edison, NJ (USA))

The Safety and Air Surveillance Section of the United States Environmental Protection Agency's Environmental Response Team responds to emergency air releases such as tire fires and explosions. The air surveillance equipment and procedures used by the organization are described, and case studies demonstrating the various emergency response activities are presented. Air response activities include emergency air responses, occupational and human health air responses and remedial air responses. Monitoring and sampling equipment includes photoionization detectors, combustible gas meters, real-time aerosol monitors, personal sampling pumps, and high flow pumps. Case histories presented include disposal of dioxane from a cotton plant, response to oil well fires in Kuwait, disposal of high pressure cylinders in American Samoa, and response to hurricane Hugo. 3 refs., 1 tab.

Addressing the gap between public health emergency planning and incident response

Science.gov (United States)

Freedman, Ariela M; Mindlin, Michele; Morley, Christopher; Griffin, Meghan; Wooten, Wilma; Miner, Kathleen

2013-01-01

Objectives: Since 9/11, Incident Command System (ICS) and Emergency Operations Center (EOC) are relatively new concepts to public health, which typically operates using less hierarchical and more collaborative approaches to organizing staff. This paper describes the 2009 H1N1 influenza outbreak in San Diego County to explore the use of ICS and EOC in public health emergency response. Methods: This study was conducted using critical case study methodology consisting of document review and 18 key-informant interviews with individuals who played key roles in planning and response. Thematic analysis was used to analyze data. Results: Several broad elements emerged as key to ensuring effective and efficient public health response: 1) developing a plan for emergency response; 2) establishing the framework for an ICS; 3) creating the infrastructure to support response; 4) supporting a workforce trained on emergency response roles, responsibilities, and equipment; and 5) conducting regular preparedness exercises. Conclusions: This research demonstrates the value of investments made and that effective emergency preparedness requires sustained efforts to maintain personnel and material resources. By having the infrastructure and experience based on ICS and EOC, the public health system had the capability to surge-up: to expand its day-to-day operation in a systematic and prolonged manner. None of these critical actions are possible without sustained funding for the public health infrastructure. Ultimately, this case study illustrates the importance of public health as a key leader in emergency response. PMID:28228983

Some issues on nuclear and radiological emergency preparedness and response in China

International Nuclear Information System (INIS)

Pan Ziqiang

1999-01-01

The nuclear emergency preparedness and response have comprehensively been developed over ten years in China. In order to promote the sound development of emergency preparedness and response, it is useful to retrospect the process of emergency preparedness and response, to summarize the experiences and absorb the experiences from foreign countries. The main issues are as follows: 1) The preparedness and response to nuclear and radiological accident is basically the same as the response to any accident involving hazardous material. 2) The classification of emergency planning, not only for nuclear facilities, but also irradiation installation, etc. 3) The hazard assessment-- a top priority. 4) The emergency planning zones. 5) Psychological impact

Dose-response relationships and threshold levels in skin and respiratory allergy

NARCIS (Netherlands)

Arts, J.H.E.; Mommers, C.; Heer, C.de

2006-01-01

A literature study was performed to evaluate dose-response relationships and no-effect levels for sensitization and elicitation in skin- and respiratory allergy. With respect to the skin, dose-response relationships and no-effect levels were found for both intradermal and topical induction, as well

R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

International Nuclear Information System (INIS)

Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho

2012-01-01

Generally speaking, robotic technologies are anticipated to be very useful for hazardous works in nuclear facilities because robotic systems are relatively immune to radiation exposure. But the application of robotic systems for such environments has not been increasing during past 20 years. Applying highly reliable and conservative 'defense in depth' concepts in the design and construction of NPPs, there is very little probability of accidents occurring or radioactive materials being released into the environments. As a precaution, however NPPs are prepared with emergency response procedures and routinely conduct exercises for post accident circumstances based on these procedures. The last year's accident at the Fukushima Daiichi nuclear power plant promotes the needs for remote response technologies based on mobile robotic system to recognize the internal status and mitigate the unanticipated events of nuclear power plants in emergency situations. For initial observation of reactor buildings two robots named 'PackBot' were used because the internal conditions were unknown so as to allow human workers for entrance into the reactor building. But there were severe limitations for the robots to perform the given tasks from various obstacles and poor visibility inside though they provided crucial information such as views of internal structures, dose level and temperature that supported the decision for human worker's entrance. The application of robots for emergency response tasks for post accidents in nuclear facilities is not a new concept. Robots were sent to recover the damaged reactor at Chernobyl where human workers could have received a lifetime dose of radiation in minutes. Based on NRC's TMI 2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. A robot was used for several years equipped with various tools allowing

R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

Energy Technology Data Exchange (ETDEWEB)

Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho [KAERI, Daejeon (Korea, Republic of)

2012-10-15

Generally speaking, robotic technologies are anticipated to be very useful for hazardous works in nuclear facilities because robotic systems are relatively immune to radiation exposure. But the application of robotic systems for such environments has not been increasing during past 20 years. Applying highly reliable and conservative 'defense in depth' concepts in the design and construction of NPPs, there is very little probability of accidents occurring or radioactive materials being released into the environments. As a precaution, however NPPs are prepared with emergency response procedures and routinely conduct exercises for post accident circumstances based on these procedures. The last year's accident at the Fukushima Daiichi nuclear power plant promotes the needs for remote response technologies based on mobile robotic system to recognize the internal status and mitigate the unanticipated events of nuclear power plants in emergency situations. For initial observation of reactor buildings two robots named 'PackBot' were used because the internal conditions were unknown so as to allow human workers for entrance into the reactor building. But there were severe limitations for the robots to perform the given tasks from various obstacles and poor visibility inside though they provided crucial information such as views of internal structures, dose level and temperature that supported the decision for human worker's entrance. The application of robots for emergency response tasks for post accidents in nuclear facilities is not a new concept. Robots were sent to recover the damaged reactor at Chernobyl where human workers could have received a lifetime dose of radiation in minutes. Based on NRC's TMI 2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. A robot was used for several years

Part I. Emergency workers

International Nuclear Information System (INIS)

2004-01-01

This monograph deals with assessment of radiological health effects of the Chernobyl accident for emergency workers (part 1) and the population of the contaminated areas in Russia (part 2). The Chernobyl emergency workers and people living in the contaminated areas of Russia received much lower doses than the population of Hiroshima and Nagasaki and it was unclear whether risks of radiation-induced cancers derived with the Japanese data could be extrapolated to the low dose range However, it was predicted as early as in 1990 that the thyroid cancer incidence might be increasing due to incorporated 131 irradiation. What conclusions can be drawn from regarding cancer incidence among emergency workers and residents of the contaminated areas in Russia and the role of the radiation factor on the basis of the registry data? Leukemia incidence. Leukemia incidence is known to be one of principal indications of radiation effects. The radiation risk for leukemias is 3-4 times higher that for solid cancers and its latent period is estimated to be 2-3 years after exposure. Results of the radiation epidemiological studies discussed in this book show that in the worst contaminated Bryansk region the leukemia incidence rate is not higher than in the country in general. Even though some evidence exists for the dose response relationship, the radiation risks appear to be not statistically significant. Since risks of leukemia are known to be higher for those who were children at exposure, long-term epidemiological studies need to be continued. The study of leukemias among emergency workers strongly suggest the existence of dose response relationship. In those who received external doses more than 0.15 Gy the leukemia incidence rate is two time higher and these emergency workers should be referred to as a group of increased radiation risk. Solid cancers. The obtained results provide no evidence to a radiation-induced increase in solid cancers among residents of the contaminated areas

Emergency Response of Iranian Hospitals Against Disasters: A Practical Framework for Improvement.

Science.gov (United States)

Janati, Ali; Sadeghi-Bazargani, Homayoun; Hasanpoor, Edris; Sokhanvar, Mobin; HaghGoshyie, Elaheh; Salehi, Abdollah

2018-04-01

Hospital emergency management is a continuous process that requires monolithic integration of planning and response attempts with local and national schemes. The aim of the current study is to evaluate emergency response by hospitals against potential disasters in Tabriz, north-west Iran. A cross-sectional study was conducted in the city of Tabriz, in Iran, in 2016. The study population included all hospitals in Tabriz. A total of 18 hospitals were assessed. The hospital emergency response checklist was used to collect data. Tool components included command and control, communication, safety and security, triage, surge capacity, continuity of essential services, human resources, logistics and supply management, and post-disaster recovery. Data entry and analysis were carried out using SPSS software (version 20). The results showed that the emergency response rate of hospitals was 54.26% in Tabriz. The lowest response rates were for Shafaa hospital (18.89%) and the highest response rates were for Razi Hospital (91.67%). The components of hospital emergency response were assessed to be between 48.07% (surge capacity) and 58.95% (communication). On the basis of the World Health Organization checklist, the emergency response rate for hospitals in Tabriz was only 54.26%. Therefore, hospital emergency responses against disasters have to be improved and must be made to reach 100%. It is essential to design a comprehensive framework for hospital emergency response. (Disaster Med Public Health Preparedness. 2018;12:166-171).

Gamma Low-Dose-Rate Ionizing Radiation Stimulates Adaptive Functional and Molecular Response in Human Aortic Endothelial Cells in a Threshold-, Dose-, and Dose Rate-Dependent Manner.

Science.gov (United States)

Vieira Dias, Juliana; Gloaguen, Celine; Kereselidze, Dimitri; Manens, Line; Tack, Karine; Ebrahimian, Teni G

2018-01-01

A central question in radiation protection research is whether low-dose and low-dose-rate (LDR) exposures to ionizing radiation play a role in progression of cardiovascular disease. The response of endothelial cells to different LDR exposures may help estimate risk of cardiovascular disease by providing the biological mechanism involved. We investigated the effect of chronic LDR radiation on functional and molecular responses of human aorta endothelial cells (HAoECs). Human aorta endothelial cells were continuously irradiated at LDR (6 mGy/h) for 15 days and analyzed at time points when the cumulative dose reached 0.05, 0.5, 1.0, and 2.0 Gy. The same doses were administered acutely at high-dose rate (HDR; 1 Gy/min). The threshold for the loss of angiogenic capacity for both LDR and HDR radiations was between 0.5 and 1.0 Gy. At 2.0 Gy, angiogenic capacity returned to normal only for HAoEC exposed to LDR radiation, associated with increased expression of antioxidant and anti-inflammatory genes. Pre-LDR, but not pre-HDR, radiation, followed by a single acute 2.0 Gy challenge dose sustained the expression of antioxidant and anti-inflammatory genes and stimulated angiogenesis. Our results suggest that dose rate is important in cellular response and that a radioadaptive response is involved for a 2.0 Gy dose at LDR.

Gamma Low-Dose-Rate Ionizing Radiation Stimulates Adaptive Functional and Molecular Response in Human Aortic Endothelial Cells in a Threshold-, Dose-, and Dose Rate–Dependent Manner

Science.gov (United States)

Vieira Dias, Juliana; Gloaguen, Celine; Kereselidze, Dimitri; Manens, Line; Tack, Karine; Ebrahimian, Teni G

2018-01-01

A central question in radiation protection research is whether low-dose and low-dose-rate (LDR) exposures to ionizing radiation play a role in progression of cardiovascular disease. The response of endothelial cells to different LDR exposures may help estimate risk of cardiovascular disease by providing the biological mechanism involved. We investigated the effect of chronic LDR radiation on functional and molecular responses of human aorta endothelial cells (HAoECs). Human aorta endothelial cells were continuously irradiated at LDR (6 mGy/h) for 15 days and analyzed at time points when the cumulative dose reached 0.05, 0.5, 1.0, and 2.0 Gy. The same doses were administered acutely at high-dose rate (HDR; 1 Gy/min). The threshold for the loss of angiogenic capacity for both LDR and HDR radiations was between 0.5 and 1.0 Gy. At 2.0 Gy, angiogenic capacity returned to normal only for HAoEC exposed to LDR radiation, associated with increased expression of antioxidant and anti-inflammatory genes. Pre-LDR, but not pre-HDR, radiation, followed by a single acute 2.0 Gy challenge dose sustained the expression of antioxidant and anti-inflammatory genes and stimulated angiogenesis. Our results suggest that dose rate is important in cellular response and that a radioadaptive response is involved for a 2.0 Gy dose at LDR. PMID:29531508

External beam radiotherapy for painful osseous metastases: pooled data dose response analysis

International Nuclear Information System (INIS)

Ben-Josef, Edgar; Shamsa, Falah; Youssef, Emad; Porter, Arthur T.

1999-01-01

Purpose: Although the effectiveness of external beam irradiation in palliation of pain from osseous metastases is well established, the optimal fractionation schedule has not been determined. Clinical studies to date have failed to demonstrate an advantage for higher doses. To further address this issue, we conducted a pooled dose response analysis using data from published Phase III clinical trials. Methods and Materials: Complete response (CR) was used as an endpoint because it was felt to be least susceptible to inconsistencies in assessment.The biological effective dose (BED) was calculated for each schedule using the linear-quadratic model and an α/β of 10. Using SAS version 6.12, the data were fitted using a weighted linear regression, a logistic model, and the spline technique. Finally, BED was categorized, and odds ratios for each level were calculated. Results: CR was assessed early and late in 383 and 1,007 patients, respectively. Linear regression on the early-response data yielded a poor fit and a nonsignificant dose coefficient. With the late-response data, there was an excellent fit (R-square = 0.842) and a highly significant dose coefficient (p = 0.0002). Fitting early CR to a logistic model, we could not establish a significant dose response relationship. However, with the late-response data there was an excellent fit and the dose coefficient was significantly different from zero (0.017 ± 0.00524; p = 0.0012). Application of the spline technique or removal of an outlier resulted in an improved fit (p 0.048 and p = 0.0001, respectively). Using BED of < 14.4 Gy as a reference level, the odds ratios for late CR were 2.29-3.32 (BED of 19.5-51.4 Gy, respectively). Conclusion: Our results demonstrate a clear dose-response for pain relief. Further testing of high intensity regiments is warranted

Integrating Social Media Monitoring Into Public Health Emergency Response Operations.

Science.gov (United States)

Hadi, Tamer A; Fleshler, Keren

2016-10-01

Social media monitoring for public health emergency response and recovery is an essential response capability for any health department. The value of social media for emergency response lies not only in the capacity to rapidly communicate official and critical incident information, but as a rich source of incoming data that can be gathered to inform leadership decision-making. Social media monitoring is a function that can be formally integrated into the Incident Command System of any response agency. The approach to planning and required resources, such as staffing, logistics, and technology, is flexible and adaptable based on the needs of the agency and size and scope of the emergency. The New York City Department of Health and Mental Hygiene has successfully used its Social Media Monitoring Team during public health emergency responses and planned events including major Ebola and Legionnaires' disease responses. The concepts and implementations described can be applied by any agency, large or small, interested in building a social media monitoring capacity. (Disaster Med Public Health Preparedness. 2016;page 1 of 6).

Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies - Training Materials

International Nuclear Information System (INIS)

2013-01-01

These materials are designed for use at a four day training course on the application of cytogenetic dosimetry in preparedness for and response to radiation emergencies. They contain information on: (1) Basics of biological effects of ionizing radiation: Parts 1+2; (2) Basics of dosimetry; (3) dicentric assay; (4) Retrospective dosimetry by translocation analysis; (5) Premature chromosome condensation analysis; (6) Cytokinesis block micronucleus assay; (7) Applied statistics for biodosimetry; (8) Automatic analysis of chromosomal assays; (9) Biodosimetry in mass casualty events; (10) Safety of laboratory staff and quality programmes; (11) Examples of accident investigations; (12) Cytogenetic dose estimation in the criticality accident in Tokaimura; (13) Radiological accidents in Latin America; (14) Radiological accidents in Georgia. Additionally, the CD contains two working sessions with the reference materials for use and a standard training programme. This training course consists of lectures and work sessions that can easily be utilized by a State to build a basic capability in biodosimetry application in a nuclear or radiological emergency

United States Department of Energy radiological emergency response programme - a national capability

International Nuclear Information System (INIS)

Gordon-Hagerty, L.E.

1993-01-01

In order to respond to a radiological emergency, the United States Department of Energy (USDOE) maintains seven emergency response assets and capabilities in support of a radiological emergency of any proportion within the continental United States and abroad. The seven emergency response assets and capabilities include: Accident Response Group; Aerial Measuring Systems; Atmospheric Release Advisory Capability; Federal Radiological Monitoring and Assessment Center; Nuclear Emergency Search Team; Radiation Emergency Assistance Center/Training Site; and Radiological Assistance Program. Presently, USDOE maintains the most comprehensive national radiological emergency response assets in the United States, capable of dealing with any type of emergency involving nuclear materials. In all, the Department's assets are available to support any type of accident/incident involving radioactive materials in coordination with other United States Federal agencies, as well as state and local governments, as required. (author)

Innovations in emergency response plans : making the useful application of the 2007 CDA guidelines for emergency response plans

Energy Technology Data Exchange (ETDEWEB)

Stevenson, A.J. [Columbia Power Corp., Castlegar, BC (Canada)

2008-07-01

Columbia Power Corporation (CPC) changed its perspective and approach to emergency response plans (ERP) between 2002 and 2007 from one of administrative necessity to one of important functional reference. The new 2007 Canadian Dam Association Guidelines helped facilitate that transition for both CPC and all dam owners. As part of the licensing requirements for its new facility, CPC had an ERP commissioned and developed in 2002. A potential dam safety event occurred in 2004, which necessitated the need for the ERP to be put to use. However, at the time, it was found to be lacking in functionality for field personnel. As a result, CPC recognized the significance of having a functional ERP for field staff and undertook a substantial redraft between 2005 and 2007. This paper discussed the development of the ERP with particular reference to assessing the top potential emergency scenarios for the facility; development of response plans for the identified scenarios; a flow chart to guide personnel through the required actions; response checklist; detailed inspection checklists and any required forms, photos or specific information. It was concluded that the new ERP has been well received and has improved facility awareness and emergency preparedness. 1 ref., 2 figs.

Adapting protocols of CT imaging in a pediatric emergency department. Evaluation of image quality and dose

International Nuclear Information System (INIS)

Batista Arce, A.; Gonzalez Lopez, S.; Catalan Acosta, A.; Casares Magaz, O.; Hernandez Armas, O.; Hernandez Armas, J.

2011-01-01

The purpose of this study was to assess qualitatively the picture quality in relation to the radiation dose delivered in CT studies of computer tomograph Pediatric Emergency Department of Hospital Universitario de Canarias (HUC) in order to optimize the technical parameters used these radiological examinations so as to obtain optimal image quality at the lowest possible dose.

Dose assessment and approach to the safety for the public in the emergency. Proceedings

International Nuclear Information System (INIS)

Nakajima, Toshiyuki

1994-03-01

This issue is the collection of the papers presented at the 21st NIRS seminar on Dose Assessment and Approach to the Safety for the Public in the Emergency. The 16 of the presented papers are indexed individually. (J.P.N.)

Quantitative radiation dose-response relationships for normal tissues in man - I. Gustatory tissues response during photon and neutron radiotherapy

International Nuclear Information System (INIS)

Mossman, K.L.

1982-01-01

Quantitative radiation dose-response curves for normal gustatory tissue in man were studied. Taste function, expressed as taste loss, was evaluated in 84 patients who were given either photon or neutron radiotherapy for tumors in the head and neck region. Patients were treated to average tumor doses of 6600 cGy (photon) or 2200 cGy intervals for photon patients and 320-cGy intervals for neutron patients during radiotherapy. The dose-response curves for photons and neutrons were analyzed by fitting a four-parameter logistic equation to the data. Photon and neutron curves differed principally in their relative position along the dose axis. Comparison of the dose-response curves were made by determination of RBE. At 320 cGy, the lowest neutron dose at which taste measurements were made, RBE = 5.7. If this RBE is correct, then the therapeutic gain factor may be equal to or less than 1, indicating no biological advantage in using neutrons over photons for this normal tissue. These studies suggest measurements of taste function and evaluation of dose-response relationships may also be useful in quantitatively evaluating the efficacy of chemical modifiers of radiation response such as hypoxic cell radiosensitizers and radioprotectors

Dose response of artificial irradiation of fluvial sediment sample for ESR dating

International Nuclear Information System (INIS)

Liu Chunru; Yin Gongming; Gao Lu; Li Jianping; Han Fei; Lin Min

2011-01-01

ESR dating samples need be irradiated to obtain dose response curve and the equivalent dose. The artificial dose rate is about 1 x 10 -1 -1 x 10 2 Gy/min, whereas the natural dose rate is about 3 Gy/ka. Therefore, one must be sure whether the much higher artificial dose rate is suitable for the ESR dating study. In this paper, we use different artificial dose rate to irradiate the same fluvial sample and measure the quartz Al centre ESR signal under the same conditions. The dose response curves are compared, in an attempt to gain a preliminary knowledge on that problem and build a good foundation for our ESR dating studies on fluvial samples. (authors)

Guidelines for Use of the Approximate Beta-Poisson Dose-Response Model.

Science.gov (United States)

Xie, Gang; Roiko, Anne; Stratton, Helen; Lemckert, Charles; Dunn, Peter K; Mengersen, Kerrie

2017-07-01

For dose-response analysis in quantitative microbial risk assessment (QMRA), the exact beta-Poisson model is a two-parameter mechanistic dose-response model with parameters α>0 and β>0, which involves the Kummer confluent hypergeometric function. Evaluation of a hypergeometric function is a computational challenge. Denoting PI(d) as the probability of infection at a given mean dose d, the widely used dose-response model PI(d)=1-(1+dβ)-α is an approximate formula for the exact beta-Poisson model. Notwithstanding the required conditions α1, issues related to the validity and approximation accuracy of this approximate formula have remained largely ignored in practice, partly because these conditions are too general to provide clear guidance. Consequently, this study proposes a probability measure Pr(0 (22α̂)0.50 for 0.020.99) . This validity measure and rule of thumb were validated by application to all the completed beta-Poisson models (related to 85 data sets) from the QMRA community portal (QMRA Wiki). The results showed that the higher the probability Pr(0 Poisson model dose-response curve. © 2016 Society for Risk Analysis.

Contraceptive availability during an emergency response in the United States.

Science.gov (United States)

Ellington, Sascha R; Kourtis, Athena P; Curtis, Kathryn M; Tepper, Naomi; Gorman, Susan; Jamieson, Denise J; Zotti, Marianne; Barfield, Wanda

2013-03-01

This article provides the evidence for contraceptive need to prevent unintended pregnancy during an emergency response, discusses the most appropriate types of contraceptives for disaster situations, and details the current provisions in place to provide contraceptives during an emergency response.

Adequate technologies for wireless real-time dose rate monitoring for off-site emergency management

International Nuclear Information System (INIS)

Dielmann, R.; Buerkin, W.

2003-01-01

Full text: What are the requirements for off-site gamma dose rate monitoring systems? What are the pros and cons of available communication technologies? This report gives an overview of modern communication techniques and their applicability for reliable real-time data acquisition as basis for off-site nuclear emergency management. The results of three years operating experience with a wireless gamma dose rate monitoring system, installed around the NPPs of KURSK, KALININ and BALAKOVA (Russia) in the year 2000, are shown. (author)

Pilot website to support international collaboration for dose assessments in a radiation emergency

International Nuclear Information System (INIS)

Livingston, G.K.; Wilkins, R.C.; Ainsbury, E.A.

2011-01-01

Nuclear terrorism has emerged as a significant threat which could require timely medical interventions to reduce potential radiation casualties. Early dose assessments are critical since optimal care depends on knowing a victim's radiation dose. The dicentric chromosome aberration assay is considered the 'gold standard' to estimate the radiation dose because the yield of dicentrics correlates positively with the absorbed dose. Dicentrics have a low background frequency, are independent of age and gender and are relatively easy to identify. This diagnostic test for radiation exposure, however, is labor intensive and any single or small group of laboratories could easily be overwhelmed by a mass casualty event. One solution to this potential problem is to link the global WHO BioDoseNet members via the Internet so multiple laboratories could work cooperatively to screen specimens for dicentric chromosomes and generate timely dose estimates. Inter-laboratory comparison studies have shown that analysis of electronic chromosome images viewed on the computer monitor produces scoring accuracy equivalent to viewing live images in the microscope. This functional equivalence was demonstrated during a comparative study involving five laboratories constructing 60 Co gamma ray calibration curves and was further confirmed when comparing results of blind dose estimates submitted by each laboratory. It has been further validated in two recent WHO BioDoseNet trial exercises where 20 metaphase images were shared by e-mail and 50 images were shared on a test website created for this purpose. The Internet-based exercise demonstrated a high level of concordance among 20 expert scorers who evaluated the same 50 metaphase spreads selected to exhibit no, low, moderate and severe radiation damage. Nineteen of 20 scorers produced dicentric equivalent counts within the 95% confidence limits of the mean. The Chi-squared test showed strong evidence of homogeneity in the data (p = 0

Pilot website to support international collaboration for dose assessments in a radiation emergency

Energy Technology Data Exchange (ETDEWEB)

Livingston, G.K., E-mail: Gordon.Livingston@orise.orau.gov [Oak Ridge Associated Universities, REAC/TS, Radiation Emergency Medicine (REM), P.O. Box 117, Oak Ridge, TN 37831 (United States); Wilkins, R.C., E-mail: Ruth.Wilkins@hc-sc.gc.ca [Health Canada, Consumer and Clinical Radiation Protection Bureau, Ottawa, ON K1A 1C1 (Canada); Ainsbury, E.A., E-mail: liz.ainsbury@hpa.org.uk [Health Protection Agency, Radiation Protection Division, Chilton, Didcot, Oxfordshire OX11 0RQ (United Kingdom)

2011-09-15

Nuclear terrorism has emerged as a significant threat which could require timely medical interventions to reduce potential radiation casualties. Early dose assessments are critical since optimal care depends on knowing a victim's radiation dose. The dicentric chromosome aberration assay is considered the 'gold standard' to estimate the radiation dose because the yield of dicentrics correlates positively with the absorbed dose. Dicentrics have a low background frequency, are independent of age and gender and are relatively easy to identify. This diagnostic test for radiation exposure, however, is labor intensive and any single or small group of laboratories could easily be overwhelmed by a mass casualty event. One solution to this potential problem is to link the global WHO BioDoseNet members via the Internet so multiple laboratories could work cooperatively to screen specimens for dicentric chromosomes and generate timely dose estimates. Inter-laboratory comparison studies have shown that analysis of electronic chromosome images viewed on the computer monitor produces scoring accuracy equivalent to viewing live images in the microscope. This functional equivalence was demonstrated during a comparative study involving five laboratories constructing {sup 60}Co gamma ray calibration curves and was further confirmed when comparing results of blind dose estimates submitted by each laboratory. It has been further validated in two recent WHO BioDoseNet trial exercises where 20 metaphase images were shared by e-mail and 50 images were shared on a test website created for this purpose. The Internet-based exercise demonstrated a high level of concordance among 20 expert scorers who evaluated the same 50 metaphase spreads selected to exhibit no, low, moderate and severe radiation damage. Nineteen of 20 scorers produced dicentric equivalent counts within the 95% confidence limits of the mean. The Chi-squared test showed strong evidence of homogeneity in the data

Thymocyte apoptosis in response to low-dose radiation

International Nuclear Information System (INIS)

Shu-Zheng, Liu; Ying-Chun, Zhang; Ying, Mu; Xu, Su; Jian-Xiang, Liu

1996-01-01

Thymocyte apoptosis was assessed by counting apoptotic bodies with flow cytometry (FCM) and measuring DNA fragmentation with fluorescence spectrophotometry (FSP). J-shaped dose-response curves were obtained after both whole-body irradiation (WBI) of mice and in vitro irradiation of EL4 cells with doses ranging from 0.025 to 4 Gy X-rays. There was a significant reduction of apoptosis rate to below control level with doses within 0.2 Gy, and a dose-dependent increase in apoptosis with doses above 0.5 Gy. When thymocytes were cultured 24 h after WBI with 75 mGy X-rays in complete RPMI 1640 medium, a reduction in apoptosis was observed in the course of incubation for 72 h, and the presence of Con A in the medium accentuated this reduction in a dose- and time-dependent manner. The implications of these observations and the possible molecular mechanisms for future studies are proposed

Sub-dissociative-dose intranasal ketamine for moderate to severe pain in adult emergency department patients.

Science.gov (United States)

Yeaman, Fiona; Meek, Robert; Egerton-Warburton, Diana; Rosengarten, Pamela; Graudins, Andis

2014-06-01

There are currently no studies assessing effectiveness of sub-dissociative intranasal (IN) ketamine as the initial analgesic for adult patients in the ED. The study aims to examine the effectiveness of sub-dissociative IN ketamine as a primary analgesic agent for adult patients in the ED. This is a prospective, observational study of adult ED patients presenting with severe pain (≥6 on 11-point scale at triage). IN ketamine dose was 0.7 mg/kg, with secondary dose of 0.5 mg/kg at 15 min if pain did not improve. After 6 months, initial dose was increased to 1.0 mg/kg with the same optional secondary dose. The primary outcomes are change in VAS rating at 30 min; percentage of patients reporting clinically significant reduction in VAS (≥20 mm) at 30 min; dose resulting in clinically significant pain reduction. Of the 72 patients available for analysis, median age was 34.5 years and 64% were men. Median initial VAS rating was 76 mm (interquartile range [IQR]: 65-82). Median total dose of IN ketamine for all patients was 0.98 mg/kg (IQR: 0.75-1.15, range: 0.59-1.57). Median reduction in VAS rating at 30 min was 24 mm (IQR: 2-45). Forty (56%, 95% CI: 44.0-66.7) reported VAS reduction ≥20 mm, these patients having had a total median ketamine dose of 0.94 mg/kg (IQR: 0.72-1.04). IN ketamine, at a dose of about 1 mg/kg, was an effective analgesic agent in 56% of study patients. The place of IN ketamine in analgesic guidelines for adults requires further investigation. © 2014 Australasian College for Emergency Medicine and Australasian Society for Emergency Medicine.

Low-dose neutron dose response of zebrafish embryos obtained from the Neutron exposure Accelerator System for Biological Effect Experiments (NASBEE) facility

International Nuclear Information System (INIS)

Ng, C.Y.P.; Kong, E.Y.; Konishi, T.; Kobayashi, A.; Suya, N.; Cheng, S.H.; Yu, K.N.

2015-01-01

The dose response of embryos of the zebrafish, Danio rerio, irradiated at 5 h post fertilization (hpf) by 2-MeV neutrons with ≤100 mGy was determined. The neutron irradiations were made at the Neutron exposure Accelerator System for Biological Effect Experiments (NASBEE) facility in the National Institute of Radiological Sciences (NIRS), Chiba, Japan. A total of 10 neutron doses ranging from 0.6 to 100 mGy were employed (with a gamma-ray contribution of 14% to the total dose), and the biological effects were studied through quantification of apoptosis at 25 hpf. The responses for neutron doses of 10, 20, 25, and 50 mGy approximately fitted on a straight line, while those for neutron doses of 0.6, 1 and 2.5 mGy exhibited neutron hormetic effects. As such, hormetic responses were generically developed by different kinds of ionizing radiations with different linear energy transfer (LET) values. The responses for neutron doses of 70 and 100 mGy were significantly below the lower 95% confidence band of the best-fit line, which strongly suggested the presence of gamma-ray hormesis. - Highlights: • Neutron dose response was determined for embryos of the zebrafish, Danio rerio. • Neutron doses of 0.6, 1 and 2.5 mGy led to neutron hormetic effects. • Neutron doses of 70 and 100 mGy accompanied by gamma rays led to gamma-ray hormesis

Utilization of dose assessment models to facilitate off-site recovery operations for accidents at nuclear facilities

International Nuclear Information System (INIS)

Dickerson, M.H.; Foster, K.T.

1989-09-01

One of the most important uses of dose assessment models in response to accidents at nuclear facilities is to help provide guidance to emergency response managers for identifying, and mitigating, the consequences of an accident once the accident has been terminated. By combining results from assessment models with radiological measurements, a qualitative methodology can be developed to aid emergency response managers in determining the total dose received by the population and to minimize future doses through the use of mitigation procedures. To illustrate the methodology, this discussion focuses on the use of models to estimate the dose delivered to the public both during and after a nuclear accident. 4 refs., 10 figs., 1 tab

Emergency response planning in Saskatchewan

International Nuclear Information System (INIS)

Irwin, R.W.

1998-01-01

Release reporting and spill clean-up requirements by Saskatchewan Energy and Mines were reviewed. Wascana's experience in response planning was discussed. It was suggested that the key to prevention was up-front due diligence, including facility and oil well analysis. Details of Wascana's emergency plan, and details of Saskatchewan Energy and Mines release reporting procedures were also provided

Advanced Computational Approaches for Characterizing Stochastic Cellular Responses to Low Dose, Low Dose Rate Exposures

Energy Technology Data Exchange (ETDEWEB)

Scott, Bobby, R., Ph.D.

2003-06-27

OAK - B135 This project final report summarizes modeling research conducted in the U.S. Department of Energy (DOE), Low Dose Radiation Research Program at the Lovelace Respiratory Research Institute from October 1998 through June 2003. The modeling research described involves critically evaluating the validity of the linear nonthreshold (LNT) risk model as it relates to stochastic effects induced in cells by low doses of ionizing radiation and genotoxic chemicals. The LNT model plays a central role in low-dose risk assessment for humans. With the LNT model, any radiation (or genotoxic chemical) exposure is assumed to increase one¡¯s risk of cancer. Based on the LNT model, others have predicted tens of thousands of cancer deaths related to environmental exposure to radioactive material from nuclear accidents (e.g., Chernobyl) and fallout from nuclear weapons testing. Our research has focused on developing biologically based models that explain the shape of dose-response curves for low-dose radiation and genotoxic chemical-induced stochastic effects in cells. Understanding the shape of the dose-response curve for radiation and genotoxic chemical-induced stochastic effects in cells helps to better understand the shape of the dose-response curve for cancer induction in humans. We have used a modeling approach that facilitated model revisions over time, allowing for timely incorporation of new knowledge gained related to the biological basis for low-dose-induced stochastic effects in cells. Both deleterious (e.g., genomic instability, mutations, and neoplastic transformation) and protective (e.g., DNA repair and apoptosis) effects have been included in our modeling. Our most advanced model, NEOTRANS2, involves differing levels of genomic instability. Persistent genomic instability is presumed to be associated with nonspecific, nonlethal mutations and to increase both the risk for neoplastic transformation and for cancer occurrence. Our research results, based on

Current emergency programs for nuclear installations in Japan

International Nuclear Information System (INIS)

Chino, Masamichi

2007-01-01

Large effort has been taken for nuclear emergency programs in Japan especially after the JCO accident. A special law for nuclear emergency was established after the accident. The law extended the scope of emergency preparedness to fuel cycle facilities, research reactors, etc. and clarified the roles and responsibilities of the national government, local governments and license holders. For initial responses, the action levels and action procedures are defined based on environmental doses and specific initial events of NPPs. A senior specialist was dispatched to each site for nuclear emergency and a facility 'Off-site center' to be used as the local emergency headquator was designated at each site. This paper describes the structure of emergency program, responsibility of related organizations and the definition of unusual events for notification and emergency. Emergency preparedness, emergency radiation monitoring and computer-based prediction of on- and off-site situation are also addressed. (author)

Cellular response to low Gamma-ray doses

Energy Technology Data Exchange (ETDEWEB)

Manzanares A, E; Vega C, H R; Leon, L.C. de . [Unidades Academicas de Estudios Nucleares, Universidad Autonoma de Zacatecas, A.P. 336, 98000 Zacatecas (Mexico); Rebolledo D, O; Radillo J, F [Facultad de Ciencias Biologicas y Agropecuarias de la Universidad de Colima, Colima (Mexico)

2002-07-01

Lymphocytes, obtained from healthy donors, were exposed to a low strength gamma-ray field to determine heat shock protein expression in function of radiation dose. Protein identification was carried out using mAb raised against Hsp70 and Hsc70.Hsp70 protein was detected after lymphocyte irradiation. In all cases, an increasing trend of relative amounts of Hsp70 in function to irradiation time was observed. After 1.25 c Gy gamma-ray dose, lymphocytes expressed Hsp70 protein, indicating a threshold response to gamma rays. (Author)

Cellular response to low Gamma-ray doses

International Nuclear Information System (INIS)

Manzanares A, E.; Vega C, H.R.; Leon, L.C. de; Rebolledo D, O.; Radillo J, F.

2002-01-01

Lymphocytes, obtained from healthy donors, were exposed to a low strength gamma-ray field to determine heat shock protein expression in function of radiation dose. Protein identification was carried out using mAb raised against Hsp70 and Hsc70.Hsp70 protein was detected after lymphocyte irradiation. In all cases, an increasing trend of relative amounts of Hsp70 in function to irradiation time was observed. After 1.25 c Gy gamma-ray dose, lymphocytes expressed Hsp70 protein, indicating a threshold response to gamma rays. (Author)

40 CFR 1.47 - Office of Solid Waste and Emergency Response.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Office of Solid Waste and Emergency... ORGANIZATION AND GENERAL INFORMATION Headquarters § 1.47 Office of Solid Waste and Emergency Response. The Office of Solid Waste and Emergency Response (OSWER), under the supervision of the Assistant...

Cytogenetic dose-response and adaptive response in cells of ungulate species exposed to ionizing radiation

International Nuclear Information System (INIS)

Ulsh, B.A.; Miller, S.M.; Mallory, F.F.; Mitchel, R.E.J.; Morrison, D.P.; Boreham, D.R.

2004-01-01

In the studies reported here, the micronucleus assay, a common cytogenetic technique, was used to examine the dose-responses in fibroblasts from three ungulate species (white-tailed deer, woodland caribou, and Indian muntjac) exposed to high doses of ionizing radiation (1-4 Gy of 60 Co gamma radiation). This assay was also used to examine the effects of exposure to low doses (1-100 mGy) typical of what these species experience in a year from natural and anthropogenic environmental sources. An adaptive response, defined as the induction of resistance to a stressor by a prior exposure to a small 'adapting' stress, was observed after exposure to low doses. This work indicates that very small doses are protective for the endpoint examined. The same level of protection was seen at all adapting doses, including 1 radiation track per cell, the lowest possible cellular dose. These results are consistent with other studies in a wide variety of organisms that demonstrate a protective effect of low doses at both cellular and whole-organism levels. This implies that environmental regulations predicated on the idea that even the smallest dose of radiation carries a quantifiable risk of direct adverse consequences to the exposed organism require further examination. Cytogenetic assays provide affordable and feasible biological effects-based alternatives that are more biologically relevant than traditional contaminant concentration-based radioecological risk assessment

Delaware Estuary situation reports. Emergency response: How do emergency management officials address disasters in the Delaware Estuary

International Nuclear Information System (INIS)

Sylves, R.T.

1991-01-01

From hurricanes and other natural threats to oil spills and other manmade emergencies, the Delaware Estuary has experienced a variety of disasters over the years. The toll that these events take on the estuary and those who live on its shores depends largely upon the degree of emergency preparedness, speed of response, and effectiveness of recovery operations. In Emergency Response: How Do Emergency Management Officials Address Disasters in the Delaware Estuary, the latest addition to its Delaware Estuary Situation Report series, the University of Delaware Sea Grant College Program defines emergency management; examines the roles that the Coast Guard, Army Corps of Engineers, and Environmental Protection Agency play in an emergency; and reviews how each of these federal agencies operated during an actual disaster--the 1985 Grand Eagle oil spill. The report was written by Dr. Richard T. Sylves, a professor of political science at the University of Delaware. Sylves has been studying emergency management for the past 15 years, with special emphasis on oil spill preparedness and response in the Mid-Atlantic Region. The Delaware Estuary Situation Report is 12 pages long and contains maps and photographs, as well as a detailed account of response and recovery operations undertaken during the Grand Eagle oil spill. A comparison of the 1985 Grand Eagle spill and the 1989 Presidente Rivera spill also is included

Basic dose response of fluorescent screen-based portal imaging device

International Nuclear Information System (INIS)

Yeo, In Hwan; Yonannes, Yonas; Zhu, Yunping

1999-01-01

The purpose of this study is to investigate fundamental aspects of the dose response of fluorescent screen-based electronic portal imaging devices (EPIDs). We acquired scanned signal across portal planes as we varied the radiation that entered the EPID by changing the thickness and anatomy of the phantom as well as the air gap between the phantom and the EPID. In addition, we simulated the relative contribution of the scintillation light signal in the EPID system. We have shown that the dose profile across portal planes is a function of the air gap and phantom thickness. We have also found that depending on the density change within the phantom geometry, errors associated with dose response based on the EPID scan can be as high as 7%. We also found that scintillation light scattering within the EPID system is an important source of error. This study revealed and demonstrated fundamental characteristics of dose response of EPID, as relative to that of ion chambers. This study showed that EPID based on fluorescent screen cannot be an accurate dosimetry system

Joint radiation emergency management plan of the international organizations. Emergency preparedness and response. Date effective: 1 December 2002

International Nuclear Information System (INIS)

2002-11-01

The Convention on Early Notification of a Nuclear Accident (the 'Early Notification Convention') and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear accident or radiological emergency, with the aim of minimizing the consequences. The International Atomic Energy Agency (IAEA) has specific functions allocated to it under these Conventions, to which, in addition to a number of States, the World Health Organization (WHO), the World Meteorological Organization (WMO) and the Food and Agriculture Organization of the United Nations (FAO) are full Parties. Since 1989, the arrangements between these organizations for facilitating the practical implementation of those articles of the two Conventions that are operational in nature have been documented by the IAEA in the Emergency Notification and Assistance Technical Operations Manual (ENATOM). The manual is intended for use primarily by Contact Points as identified in the Conventions. Pursuant to the obligations placed on it by the Conventions, the IAEA regularly convenes the Inter-Agency Committee on Response to Nuclear Accidents (lACRNA), whose purpose is to co-ordinate the arrangements of the relevant international intergovernmental organizations ('international organizations') for preparing for and responding to nuclear or radiological emergencies. Although the Conventions assign specific response functions and responsibilities to the IAEA and the Parties, various international organizations have - by virtue of their statutory functions or of related legal instruments - general functions and responsibilities that encompass aspects of preparedness and response. Moreover, some regional organizations (e.g. the European Union) are party to legally binding treaties and have

Effects of dose fractionation on the response of alanine dosimetry

International Nuclear Information System (INIS)

Lundahl, Brad; Logar, John; Desrosiers, Marc; Puhl, James

2014-01-01

Alanine dosimetry is well established as a transfer standard and is becoming more prevalently used in routine dosimetry systems for radiation processing. Many routine measurement applications in radiation processing involve absorbed dose measurements resulting from fractioned exposures to ionizing radiation. Fractioning of absorbed dose is identified as an influence quantity (ISO/ASTM, 2013). This paper reports on study results of absorbed dose fractioning characteristics of alanine for gamma and high energy electron beam radiation sources. The results of this study indicate a radiation response difference due to absorbed dose fractioning in response can be observed after four fractionations for high-energy electron beams and no difference up to seven fractions for gamma rays using an ANOVA evaluation method. - Highlights: • Fractioning effects signaled in electron beam using an ANOVA at 6 equal increments. • Fractioning effects not signaled in gamma using an ANOVA up to 7 equal increments. • Insensitivity of alanine to dose fractioning indicates nominal impact on calibration

First response to transportation emergencies involving radioactive materials

International Nuclear Information System (INIS)

1994-01-01

This FEMA/DOE/DOT videocourse describes the basis for procedures to be used by emergency first responders for transportation accidents which involve radioactive materials. Various commercial and government sector radioactive materials shipment programs will be described and will include information about hazards and the elements of safety, proper first response actions, notification procedures, and state or federal assistance during emergencies. Primary audience: fire service and emergency management personnel

The appropriateness of emergency medical service responses in the ...

African Journals Online (AJOL)

The appropriateness of emergency medical service responses in the eThekwini district of KwaZulu-Natal, South Africa. PR Newton, R Naidoo, P Brysiewicz. Abstract. Introduction. Emergency medical services (EMS) are sometimes required to respond to cases that are later found not to be emergencies, resulting in high ...

Radiation dose-response relationship of micronucleus occurrence in pollen mother cells of tradescantia

International Nuclear Information System (INIS)

Kim, Jin Kyu; Kim, Yeon Ku; Song, Hi Sup

1999-01-01

This study was carried out to investigate the radiation dose-response of micronucleus frequencies in Tradescantia pollen mother cells. The number of micronuclei increased in the tetrads as a result of chromosome deletion after irradiation. The maximal frequency of micronucleus showed a good dose-response relationship in the range of dose 0∼50 cGy. On the basis of the relationship, a dose of 1 cGy resulted in two additional micronuclei in 100 tetrads. The radiation dose-response relationship of micronucleus occurrence is prerequisite to biological monitoring of radiation and can be modified for biological risk assessment of toxicants, and to safety test of water or soil integrity

Cytogenetic adaptive response of cultured fish cells to low doses of X-rays

International Nuclear Information System (INIS)

Kurihara, Yasuyuki; Etoh, Hisami; Rienkjkarn, M.

1992-01-01

The adaptive response was examining chromosomal aberrations and micronucleus in cultured fish cells, ULF-23 (mudminnow) and CAF-31 (gold fish). When cultured fish cells were first irradiated with small doses of X-rays, they became less sensitive to subsequent exposures to high doses. The effective adaptive dose was 4.8 cGy-9.5 cGy. Adaptive doses given cells in the G1 phase were more effective than when given in the S phase. The adaptive response was maximal at 5 hours and disappeared at 10 hours after the adaptive dose. The expression of the response was inhibited by treatment with 3-aminobenzamide, as reported for mammalian cells, and with arabinofuranoside cytosine, an inhibitor of DNA polymerase alpha. Caffeine, an inhibitor of post-replicational repair, had no effect on the response. (author)

Cytogenetic adaptive response of cultured fish cells to low doses of X-rays

Energy Technology Data Exchange (ETDEWEB)

Kurihara, Yasuyuki; Etoh, Hisami (National Inst. of Radiological Sciences, Chiba (Japan)); Rienkjkarn, M.

1992-12-01

The adaptive response was examining chromosomal aberrations and micronucleus in cultured fish cells, ULF-23 (mudminnow) and CAF-31 (gold fish). When cultured fish cells were first irradiated with small doses of X-rays, they became less sensitive to subsequent exposures to high doses. The effective adaptive dose was 4.8 cGy-9.5 cGy. Adaptive doses given cells in the G1 phase were more effective than when given in the S phase. The adaptive response was maximal at 5 hours and disappeared at 10 hours after the adaptive dose. The expression of the response was inhibited by treatment with 3-aminobenzamide, as reported for mammalian cells, and with arabinofuranoside cytosine, an inhibitor of DNA polymerase alpha. Caffeine, an inhibitor of post-replicational repair, had no effect on the response. (author).

Preparation, conduct and evaluation of exercises to test preparedness for a nuclear or radiological emergency. Emergency preparedness and response

International Nuclear Information System (INIS)

2005-04-01

The aim of this publication is to serve as a practical tool for the preparation, conduct and evaluation of exercises to test preparedness for response to a nuclear or radiological emergency. It fulfils in part the functions assigned to the IAEA under Article 5.a(ii) of the Convention on Assistance in Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), namely, to collect and disseminate to States Parties and Member States information concerning the methodologies, techniques and available results of research on such emergencies. To ensure effective response to radiation emergencies when needed, provisions should be made for regular training of emergency response personnel. As stated in Preparedness and Response for a Nuclear or Radiological Emergency (Safety Requirements, Safety Standard Series No. GS-R-2), 'The operator and the response organizations shall make arrangements for the selection of personnel and training to ensure that the personnel have the requisite knowledge, skills, abilities, equipment, procedures and other arrangements to perform their assigned response functions'. A further requirement is that 'Exercise programmes shall be conducted to ensure that all specified functions required to be performed for emergency response and all organizational interfaces for facilities in threat category I, II or III and the national level programmes for threat category IV or V are tested at suitable intervals'. In 2004 the IAEA General Conference, in resolution GC(48)/RES/10 encouraged Member States to 'implement the Safety Requirements for Preparedness and Response to a Nuclear or Radiological Emergency'. This document is published as part of the IAEA Emergency Preparedness and Response Series to assist in meeting these requirements and to fulfil Article 5 of the Assistance Convention. It was developed based on a number of assumptions about national and local capabilities. Therefore, the exercise structure, terms and scenarios must be

Incidence of emergency contacts (red responses to Norwegian emergency primary healthcare services in 2007 – a prospective observational study

Directory of Open Access Journals (Sweden)

Hansen Elisabeth

2009-07-01

Full Text Available Abstract Background The municipalities are responsible for the emergency primary health care services in Norway. These services include casualty clinics, primary doctors on-call and local emergency medical communication centres (LEMC. The National centre for emergency primary health care has initiated an enterprise called "The Watchtowers", comprising emergency primary health care districts, to provide routine information (patients' way of contact, level of urgency and first action taken by the out-of-hours services over several years based on a minimal dataset. This will enable monitoring, evaluation and comparison of the respective activities in the emergency primary health care services. The aim of this study was to assess incidence of emergency contacts (potential life-threatening situations, red responses to the emergency primary health care service. Methods A representative sample of Norwegian emergency primary health care districts, "The Watchtowers" recorded all contacts and first action taken during the year of 2007. All the variables were continuously registered in a data program by the attending nurses and sent by email to the National Centre for Emergency Primary Health Care at a monthly basis. Results During 2007 the Watchtowers registered 85 288 contacts, of which 1 946 (2.3% were defined as emergency contacts (red responses, corresponding to a rate of 9 per 1 000 inhabitants per year. 65% of the instances were initiated by patient, next of kin or health personnel by calling local emergency medical communication centres or meeting directly at the casualty clinics. In 48% of the red responses, the first action taken was a call-out of doctor and ambulance. On a national basis we can estimate approximately 42 500 red responses per year in the EPH in Norway. Conclusion The emergency primary health care services constitute an important part of the emergency system in Norway. Patients call the LEMC or meet directly at casualty clinics

Radiation Dose-Response Model for Locally Advanced Rectal Cancer After Preoperative Chemoradiation Therapy

DEFF Research Database (Denmark)

Appelt, A. L.; Ploen, J.; Vogelius, I. R.

2013-01-01

estimated radiation dose-response curves for various grades of tumor regression after preoperative CRT. Methods and Materials: A total of 222 patients, treated with consistent chemotherapy and radiation therapy techniques, were considered for the analysis. Radiation therapy consisted of a combination...... of external-beam radiation therapy and brachytherapy. Response at the time of operation was evaluated from the histopathologic specimen and graded on a 5-point scale (TRG1-5). The probability of achieving complete, major, and partial response was analyzed by ordinal logistic regression, and the effect...... of including clinical parameters in the model was examined. The radiation dose-response relationship for a specific grade of histopathologic tumor regression was parameterized in terms of the dose required for 50% response, D-50,D-i, and the normalized dose-response gradient, gamma(50,i). Results: A highly...

International IAEA Emergency Response Workshop in Fukushima Concludes

International Nuclear Information System (INIS)

2013-01-01

Full text: An IAEA workshop aimed at further strengthening nuclear and radiological emergency preparedness and response capabilities concluded today in Fukushima, Japan. More than 40 participants from 18 countries took part in the four-day Response and Assistance Network (RANET) workshop, which included a field exercise in areas affected following the March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station. During the exercise, participants conducted radiation monitoring and environmental sampling and analysis. They measured the contamination level of the ground surface and conducted gamma spectrum analysis and vehicle-based monitoring - activities that are conducted following any nuclear or radiological incident or emergency. Results were then compared amongst participants. RANET is a network currently comprising 22 countries through which the IAEA can facilitate the provision of expert support and equipment on request under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency. Pat Kenny, IAEA RANET Officer, said the workshop provided an opportunity to practice cooperation between international teams that would be deployed through RANET following an emergency. 'By bringing together so many experts from different countries in one place, the workshop helped us learn how international teams can work together to provide assistance in a nuclear or radiological emergency situation,' he said. 'It also enabled us to improve the coordination of such assistance, and it gave participants the opportunity to learn from each other.' The workshop was the first activity conducted from the IAEA RANET Capacity Building Centre, a new training centre based in the city of Fukushima that was designated earlier this week with the support of the Japanese Foreign Ministry and Fukushima Prefecture. The Centre will host RANET and other training courses, workshops and exercises aimed at enhancing nuclear emergency preparedness and response

A comparison of dose-response models for death from hematological depression

International Nuclear Information System (INIS)

Morris, M.D.; Jones, T.D.

1987-01-01

Many radiation-induced lethality experiments that have been published for various mammalian species have been compiled into a database suitable to study interspecific variability of radiosensitivity, dose-rate dependence of sensitivity, dose-response behavior within each experiment, etc. The data compiled were restricted to continuous and nearly continuous exposures to photon radiations having source energies above 100 keV. Also, photon source energy, exposure geometry, and body weight considerations were used to select studies where the dose to hematopoietic marrow was nearly uniform, i.e., < +- 20%. The data base reflects 13 mammalian test species ranging from mouse to cattle. Some 211 studies were compiled but only 105 were documented in adequate detail to be useful in development and evaluation of dose-response models of interest to practical human exposures. Of the 105 studies, 70 were for various rodent species, and 35 were for nonrodent groups ranging from standard laboratory primates (body weight ∼5 kg) to cattle (body weight 375 kg). This paper considers seven different dose-response models which are tested for validity against those 105 studies. The dose-response models included: a right-skewed extreme value, a left-skewed extreme value model, log-logistic, log-probit, logistic, probit, and Weibull models. In general, the log transformed models did not improve model performance and the extreme value models did not seem consistent with the preponderance of the data. Overall, the probit and the logistic models seemed preferable over the Weibull model. 30 refs., 8 tabs

Low dose effects and non-monotonic dose responses for endocrine active chemicals: Science to practice workshop: Workshop summary

DEFF Research Database (Denmark)

Beausoleil, Claire; Ormsby, Jean-Nicolas; Gies, Andreas

2013-01-01

A workshop was held in Berlin September 12–14th 2012 to assess the state of the science of the data supporting low dose effects and non-monotonic dose responses (“low dose hypothesis”) for chemicals with endocrine activity (endocrine disrupting chemicals or EDCs). This workshop consisted of lectu...

Low dose intranasal oxytocin delivered with Breath Powered device dampens amygdala response to emotional stimuli: A peripheral effect-controlled within-subjects randomized dose-response fMRI trial.

Science.gov (United States)

Quintana, Daniel S; Westlye, Lars T; Alnæs, Dag; Rustan, Øyvind G; Kaufmann, Tobias; Smerud, Knut T; Mahmoud, Ramy A; Djupesland, Per G; Andreassen, Ole A

2016-07-01

It is unclear if and how exogenous oxytocin (OT) reaches the brain to improve social behavior and cognition and what is the optimal dose for OT response. To better understand the delivery routes of intranasal OT administration to the brain and the dose-response, we compared amygdala response to facial stimuli by means of functional magnetic resonance imaging (fMRI) in four treatment conditions, including two different doses of intranasal OT using a novel Breath Powered device, intravenous (IV) OT, which provided similar concentrations of blood plasma OT, and placebo. We adopted a randomized, double-blind, double-dummy, crossover design, with 16 healthy male adults administering a single-dose of these four treatments. We observed a treatment effect on right amygdala activation during the processing of angry and happy face stimuli, with pairwise comparisons revealing reduced activation after the 8IU low dose intranasal treatment compared to placebo. These data suggest the dampening of amygdala activity in response to emotional stimuli occurs via direct intranasal delivery pathways rather than across the blood-brain barrier via systemically circulating OT. This trial is registered at the U.S. National Institutes of Health clinical trial registry (www.clinicaltrials.gov; NCT01983514) and as EudraCT no. 2013-001608-12. Copyright © 2016 Elsevier Ltd. All rights reserved.

Information for nuclear emergency response: a case study based on ANGRA nuclear power plant emergency simulation exercises

International Nuclear Information System (INIS)

Carvalho, Paulo V.R. de

2008-01-01

Full text: Current nuclear emergency management procedures do not always satisfactorily address issues related to the information availability and to how people in emergency control centres use this information to respond to an nuclear accident. The lack of an adequate and prompt information may lead to a response that can be very different from what authorities recommend and thus create confusion, mistrust, and widespread uncertainty. This is a potentially serious problem for emergency planners. An adequate and prompt access to relevant information is a critical requirement that emergency teams face while they work towards reducing the undesired consequences of the emergency. There are three basic types of knowledge according to a conceptual framework developed to deal with emergency response: Previous Personal, Previous and, Current Contextual knowledge. Most decisions in emergency control centres require a dynamic combination of all types of knowledge, particularly the current contextual that comes from the emergency settings, including all information about the activities of other emergency teams. The aim of this paper is to describe the concepts and the structure of a system that aims at storing and disseminating the previous formal and contextual knowledge to help teams make the correct decisions during the evolution of an emergency. The elicitation of critical requirements are provided by a case study based on Cognitive Work Analysis and Naturalistic Decision Making methods, applied to a nuclear emergency response simulation. The framework and a prototype system were tested in a controlled experiment. The paper reports the results of this experiment. (author)

Tactical and strategic decision-making aids for nuclear power plant emergency response

International Nuclear Information System (INIS)

Cain, D.G.

1987-01-01

This paper examines the prospective role of computer-based decision aids for nuclear power plant emergency response. The role of these systems is subordinate to human activities, but in a complementary manner these systems process decision logic more accurately and foster a more thorough understanding of emergency situations than might other wise be possible. Within this context two decision support systems being developed are discussed. Both of these systems utilize technology derived from artificial intelligence, focussing on two different facets of emergency response. An automated emergency operating procedures (EOP) tracking expert system is described as a tactical aid for control room operator response. A reactor emergency action level monitor (REALM) expert system is proposed as a strategic decision aid for site emergency response. The discrimination between tactical and strategic decision-making is an intrinsic part of this examination

Method for the development of emergency response preparedness for nuclear or radiological accidents

International Nuclear Information System (INIS)

2000-03-01

This report supplements IAEA emergency preparedness guidance published in the 1980s, and is consistent with the new international guidance. It provides practical advice for the development of an emergency response capability based on the potential nature and magnitude of the risk. In order to apply this method, emergency planners should have a good understanding of the basic radiological emergency response principles. Therefore, other applicable international guidance should be reviewed before using this report. This report provides a practical step-by-step method for developing integrated user, local and national emergency response capabilities. It can also be used as the basis for conducting an audit of an existing emergency response capability

Method for the development of emergency response preparedness for nuclear or radiological accidents

International Nuclear Information System (INIS)

1998-04-01

This report supplements IAEA emergency preparedness guidance published in the 1980s, and is consistent with the new international guidance. It provides practical advice for the development of an emergency response capability based on the potential nature and magnitude of the risk. In order to apply this method, emergency planners should have a good understanding of the basic radiological emergency response principles. Therefore, other applicable international guidance should be reviewed before using this report. This report provides a practical step-by-step method for developing integrated user, local and national emergency response capabilities. It can also be used as the basis for conducting an audit of an existing emergency response capability

Nigeria status on capabilities for response to nuclear or radiological emergency

International Nuclear Information System (INIS)

Sambo, I.; Elegba, S.B.; Ogharandukun, M.

2007-01-01

The use of nuclear technology has been widely employed and will continue to expand in use in Nigeria particularly in the health, industrial, mining, water resources, agriculture, manufacturing, education and research sectors. Incidents and emergencies cannot therefore be ruled out. Effective national response capabilities are essential to minimize the impacts from nuclear and radiological emergencies, and to build public trust in the safety and security of nuclear technology. The often discussed Nigeria's Nuclear Power Plant (NPP) project cannot occur without enhanced national capabilities to respond to an incidence or emergency. Moreover, increased concern over the use of nuclear or radioactive materials malevolent acts increases the need to broaden response capabilities. This paper examines Nigeria's status on capabilities for response to a nuclear and radiological emergency vis-a-vis international requirements for effective response capabilities

Dose dependent effect of progesterone on hypoxic ventilatory response in newborn rats.

Science.gov (United States)

Hichri, Oubeidallah; Laurin, Jean-C; Julien, Cécile A; Joseph, Vincent; Bairam, Aida

2012-01-01

The effect of progesterone as a respiratory stimulant in newborn subjects is less known than that in adults. This study investigated the dose-response curve (0, 2, 4, and 8 mg/kg, ip) of progesterone on ventilation in non-anesthetized newborn rats at 4- and 12-days old using plethysmography. Progesterone had no effects in the regulation of normoxic ventilation. However, it enhanced the response to moderate hypoxia (FiO(2) 12%, 20 min) in 4- but not in 12-days old pups. This response was similar between the dose of 4 and 8 mg/kg. These observations suggested that progesterone enhances in age- and dose-dependent manner the hypoxic ventilatory response in newborn rats.

A model for inverse dose-rate effects - low dose-rate hyper-sensibility in response to targeted radionuclide therapy

International Nuclear Information System (INIS)

Murray, I.; Mather, S.J.

2015-01-01

Full text of publication follows. The aim of this work was to test the hypothesis that the Linear-Quadratic (LQ) model of cell survival, developed for external beam radiotherapy (EBRT), could be extended to targeted radionuclide therapy (TRT) in order to predict dose-response relationships in a cell line exhibiting low dose hypersensitivity (LDH). Methods: aliquots of the PC-3 cancer cell line were treated with either EBRT or an in-vitro model of TRT (Irradiation of cell culture with Y-90 EDTA over 24, 48, 72 or 96 hours). Dosimetry for the TRT was calculated using radiation transport simulations with the Monte Carlo PENELOPE code. Clonogenic as well as functional biological assays were used to assess cell response. An extension of the LQ model was developed which incorporated a dose-rate threshold for activation of repair mechanisms. Results: accurate dosimetry for in-vitro exposures of cell cultures to radioactivity was established. LQ parameters of cell survival were established for the PC-3 cell line in response to EBRT. The standard LQ model did not predict survival in PC-3 cells exposed to Y 90 irradiation over periods of up to 96 hours. In fact cells were more sensitive to the same dose when irradiation was carried out over 96 hours than 24 hours. I.e. at a lower dose-rate. Deviations from the LQ predictions were most pronounced below a threshold dose-rate of 0.5 Gy/hr. These results led to an extension of the LQ model based upon a dose-rate dependent sigmoid model of single strand DNA repair. This extension to the model resulted in predicted cell survival curves that closely matched the experimental data. Conclusion: the LQ model of cell survival to radiation has been shown to be largely predictive of response to low dose-rate irradiation. However, in cells displaying LDH, further adaptation of the model was required. (authors)

Emergency Response Guideline Development

International Nuclear Information System (INIS)

Gary D Storrick

2007-01-01

Task 5 of the collaborative effort between ORNL, Brazil, and Westinghouse for the International Nuclear Energy Research Initiative entitled 'Development of Advanced Instrumentation and Control for an Integrated Primary System Reactor' focuses on operator control and protection system interaction, with particular emphasis on developing emergency response guidelines (ERGs). As in the earlier tasks, we will use the IRIS plant as a specific example of an integrated primary system reactor (IPSR) design. The present state of the IRIS plant design--specifically, the lack of a detailed secondary system design--precludes establishing detailed emergency procedures at this time. However, we can create a structure for their eventual development. This report summarizes our progress to date. Section 1.2 describes the scope of this effort. Section 2 compares IPSR ERG development to the recent AP1000 effort, and identifies three key plant differences that affect the ERGs and control room designs. The next three sections investigate these differences in more detail. Section 3 reviews the IRIS Safety-by-Design philosophy and its impact on the ERGs. Section 4 looks at differences between the IRIS and traditional loop PWR I and C Systems, and considers their implications for both control room design and ERG development. Section 5 examines the implications of having one operating staff control multiple reactor units. Section 6 provides sample IRIS emergency operating procedures (EOPs). Section 7 summarizes our conclusions

Global approach of emergency response, reflection analysis

International Nuclear Information System (INIS)

Velasco Garcia, E.; Garcia Ahumada, F.; Albaladejo Vidal, S.

1998-01-01

The emergency response management approach must be dealt with adequately within company strategy, since a badly managed emergency situation can adversely affect a company, not only in terms of asset, but also in terms of the negative impact on its credibility, profitability and image. Thereby, it can be said that there are three main supports to manage the response in an emergency situation. a) Diagnosis b) Prognosis. c) Communications. To reach these capabilities it is necessary a co-ordination of different actions at the following levels. i. Facility Operation implies Local level. ii. Facility Property implies National level iii. Local Authority implies Local level iv. National Authority implies National level Taking into account all the last, these following functions must be covered: a) Management: incorporating communication, diagnosis and prognosis areas. b) Decision: incorporating communication and information means. c) Services: in order to facilitate the decision, as well as the execution of this decision. d) Analysis: in order to facilitate the situations that make easier to decide. e) Documentation: to seek the information for the analysts and decision makers. (Author)

Development of an extended framework for emergency response criteria. Interim report for comments

International Nuclear Information System (INIS)

2005-01-01

Experience from response to recent nuclear and radiological emergencies has clearly demonstrated the importance of an efficient response system that includes, among other components, emergency plans, procedures, and internally consistent operational criteria. An analysis of lessons identified from recent responses has shown that a lack of crucial components in the emergency response system could result in major radiological and nonradiological consequences at the national level. One of the reasons for the overwhelming psychological consequences of the Chernobyl and Goiania emergencies was public mistrust of decision-makers, who lost their credibility by frequently changing the criteria for taking action. Moreover, national response arrangements that are incompatible among countries can result in major mistrust by the public. It is considered important to have internationally agreed criteria and guidance for emergency response established in advance of an emergency. Currently there are several IAEA safety standards that contain recommendations for response to radiation emergencies, addressing principles and response criteria. Mindful of the lessons identified from recent emergencies, the IAEA convened in November 2001 a technical committee meeting (TCM) to develop aspects of the technical basis for emergency response to radiation emergencies. At this meeting, the lessons from response to the Chernobyl, Goiania and other emergencies over the past years were examined to identify where revisions were needed to the existing international guidance for response. In particular, the existing international criteria and guidance for taking protective and other actions were examined in the light of these lessons. The objectives of this document are: (1) to propose an extension of existing criteria for undertaking protective and other actions during or following a nuclear or radiological emergency that: addresses the lessons from past emergencies, addresses the recently

Recent developments in the applications of the Regional Atmospheric Modeling System (RAMS) for emergency response planning and operational forecasting at the Kennedy Space Center

International Nuclear Information System (INIS)

Lyons, W.A.; Tremback, C.J.

1996-01-01

The authors will summarize ten years of developing and applying the Regional Atmospheric Modeling System (RAMS) to emergency response and operational dispersion forecasting at the Kennedy Space Center (KSC). RAMS forms the core of two workstation-based operational systems, ERDAS (the Emergency Response Dose Assessment System) and PROWESS (Parallelized RAMS Operational Weather Simulation System) which are undergoing extensive operational testing prior to potential deployment as part of the range forecasting system at KSC. RAMS has been interfaced with HYPACT (the Hybrid Particle and Concentration Transport Model) to produce detailed 3-D dispersion forecasts from a variety of sources including cold spills, routine launch operations, and explosive conflagrations of launch vehicles

Dose response relationship in anti-stress gene regulatory networks.

Science.gov (United States)

Zhang, Qiang; Andersen, Melvin E

2007-03-02

To maintain a stable intracellular environment, cells utilize complex and specialized defense systems against a variety of external perturbations, such as electrophilic stress, heat shock, and hypoxia, etc. Irrespective of the type of stress, many adaptive mechanisms contributing to cellular homeostasis appear to operate through gene regulatory networks that are organized into negative feedback loops. In general, the degree of deviation of the controlled variables, such as electrophiles, misfolded proteins, and O2, is first detected by specialized sensor molecules, then the signal is transduced to specific transcription factors. Transcription factors can regulate the expression of a suite of anti-stress genes, many of which encode enzymes functioning to counteract the perturbed variables. The objective of this study was to explore, using control theory and computational approaches, the theoretical basis that underlies the steady-state dose response relationship between cellular stressors and intracellular biochemical species (controlled variables, transcription factors, and gene products) in these gene regulatory networks. Our work indicated that the shape of dose response curves (linear, superlinear, or sublinear) depends on changes in the specific values of local response coefficients (gains) distributed in the feedback loop. Multimerization of anti-stress enzymes and transcription factors into homodimers, homotrimers, or even higher-order multimers, play a significant role in maintaining robust homeostasis. Moreover, our simulation noted that dose response curves for the controlled variables can transition sequentially through four distinct phases as stressor level increases: initial superlinear with lesser control, superlinear more highly controlled, linear uncontrolled, and sublinear catastrophic. Each phase relies on specific gain-changing events that come into play as stressor level increases. The low-dose region is intrinsically nonlinear, and depending on

Dose response relationship in anti-stress gene regulatory networks.

Directory of Open Access Journals (Sweden)

Qiang Zhang

2007-03-01

Full Text Available To maintain a stable intracellular environment, cells utilize complex and specialized defense systems against a variety of external perturbations, such as electrophilic stress, heat shock, and hypoxia, etc. Irrespective of the type of stress, many adaptive mechanisms contributing to cellular homeostasis appear to operate through gene regulatory networks that are organized into negative feedback loops. In general, the degree of deviation of the controlled variables, such as electrophiles, misfolded proteins, and O2, is first detected by specialized sensor molecules, then the signal is transduced to specific transcription factors. Transcription factors can regulate the expression of a suite of anti-stress genes, many of which encode enzymes functioning to counteract the perturbed variables. The objective of this study was to explore, using control theory and computational approaches, the theoretical basis that underlies the steady-state dose response relationship between cellular stressors and intracellular biochemical species (controlled variables, transcription factors, and gene products in these gene regulatory networks. Our work indicated that the shape of dose response curves (linear, superlinear, or sublinear depends on changes in the specific values of local response coefficients (gains distributed in the feedback loop. Multimerization of anti-stress enzymes and transcription factors into homodimers, homotrimers, or even higher-order multimers, play a significant role in maintaining robust homeostasis. Moreover, our simulation noted that dose response curves for the controlled variables can transition sequentially through four distinct phases as stressor level increases: initial superlinear with lesser control, superlinear more highly controlled, linear uncontrolled, and sublinear catastrophic. Each phase relies on specific gain-changing events that come into play as stressor level increases. The low-dose region is intrinsically nonlinear

Method for the development of emergency response preparedness for nuclear or radiological accidents

International Nuclear Information System (INIS)

1997-07-01

This report supplements IAEA emergency preparedness guidance published in the 1980s, and is consistent with the new international guidance. It provides practical advice for the development of an emergency response capability based on the potential nature and magnitude of the risk. In order to apply this method, emergency planners should have a good understanding of the basic radiological emergency response principles. Therefore, other applicable international guidance should be reviewed before using this report. This report provides a practical step-by-step method for developing integrated user, local and national emergency response capabilities. It can also be used as the basis for conducting an audit of an existing emergency response capability. 14 refs, 4 figs, 4 tabs

A method to adjust radiation dose-response relationships for clinical risk factors

DEFF Research Database (Denmark)

Appelt, Ane Lindegaard; Vogelius, Ivan R

2012-01-01

Several clinical risk factors for radiation induced toxicity have been identified in the literature. Here, we present a method to quantify the effect of clinical risk factors on radiation dose-response curves and apply the method to adjust the dose-response for radiation pneumonitis for patients...

Non-linear dose response of a few plant taxa to acute gamma radiation

International Nuclear Information System (INIS)

George, J.T.; Patel, B.B.; Pius, J.; Narula, B.; Shankhadarwar, S.; Rane, V.A.; Venu-Babu, P.; Eapen, S.; Singhal, R.K.

2014-01-01

Micronuclei induction serves as an essential biomarker of radiation stress in a living system, and the simplicity of its detection technique has made it a widely used indicator of radiation damage. The present study was conducted to reveal the cytological dose-response of a few plant taxa, viz., Allium cepa var. aggregatum Linn., Allium sativum Linn., Chlorophytum comosum (Thunb.) Jacques and Eichhornia crassipes (Mart.) Solms, to low LET gamma radiation with special emphasis on the pattern of micronuclei induced across low and high dose regimes. A tri-phasic non-linear dose-response pattern was observed in the four taxa studied, characterized by a low dose linear segment, a plateau and a high dose linear segment. Despite a similar response trend, the critical doses where the phase transitions occurred varied amongst the plant taxa, giving an indication to their relative radiosensitivities. E. crassipes and A. sativum, with their lower critical doses for slope modifications of phase transitions, were concluded as being more radiosensitive as compared to C. comosum and A. cepa, which had relatively higher critical doses. (author)

Mechanisms and biological importance of photon-induced bystander responses. Do they have an impact on low-dose radiation responses

International Nuclear Information System (INIS)

Tomita, Masanori; Maeda, Munetoshi

2015-01-01

Elucidating the biological effect of low linear energy transfer (LET), low-dose and/or low-dose-rate ionizing radiation is essential in ensuring radiation safety. Over the past two decades, non-targeted effects, which are not only a direct consequence of radiation-induced initial lesions produced in cellular DNA but also of intra- and inter-cellular communications involving both targeted and non-targeted cells, have been reported and are currently defining a new paradigm in radiation biology. These effects include radiation-induced adaptive response, low-dose hypersensitivity, genomic instability, and radiation-induced bystander response (RIBR). RIBR is generally defined as a cellular response that is induced in non-irradiated cells that receive bystander signals from directly irradiated cells. RIBR could thus play an important biological role in low-dose irradiation conditions. However, this suggestion was mainly based on findings obtained using high-LET charged-particle radiations. The human population (especially the Japanese, who are exposed to lower doses of radon than the world average) is more frequently exposed to low-LET photons (X-rays or γ-rays) than to high-LET charged-particle radiation on a daily basis. There are currently a growing number of reports describing a distinguishing feature between photon-induced bystander response and high-LET RIBR. In particular, photon-induced by-stander response is strongly influenced by irradiation dose, the irradiated region of the targeted cells, and p53 status. The present review focuses on the photon-induced bystander response, and discusses its impact on the low-dose radiation effect. (author)

Clarification of TMI action plan requirements. Requirements for emergency response capability

International Nuclear Information System (INIS)

1983-01-01

This document, Supplement 1 to NUREG-0737, is a letter from D. G. Eisenhut, Director of the Division of Licensing, NRR, to licensees of operating power reactors, applicants for operating licenses, and holders of construction permits forwarding post-TMI requirements for emergency response capability which have been approved for implementation. On October 30, 1980, the NRC staff issued NUREG-0737, which incorporated into one document all TMI-related items approved for implementation by the Commission at that time. In this NRC report, additional clarification is provided regarding Safety Parameter Display Systems, Detailed Control Room Design Reviews, Regulatory Guide 1.97 (Revision 2) - Application to Emergency Response Facilities, Upgrade of Emergency Operating Procedures, Emergency Response Facilities, and Meteorological Data

Radiological emergency preparedness (REP) program

International Nuclear Information System (INIS)

Kwiatkowski, D.H.

1995-01-01

This talk focuses on the accomplishments of Radiological Emergency Preparedness Program. Major topics include the following: strengthening the partnership between FEMA, the States, and the Industry; the Standard Exercise Report Format (SERF); Multi-year performance partnership agreement (MYPPA); new REP Program guidance; comprehensive exercise program; federal radiological emergency response plan (FRERP); international interest; REP user fee; implementation EPA PAGs and Dose Limits; Contamination monitoring standard for portal monitors; guidance documents and training

Investigation of vacuum pumping on the dose response of the MAGAS normoxic polymer gel dosimeter

International Nuclear Information System (INIS)

Venning, AJ.; Canberra Hospital, Canberra; University of Sydney, Sydney; Mather, ML.; Baldock, C.

2005-01-01

The effect of vacuum pumping on the dose response of the MAGAS polymer gel dosimeter has been investigated. A delay of several days post-manufacture before irradiation was previously necessary due to the slow oxygen scavenging of ascorbic acid. The MAGAS polymer gel dosimeter was vacuum pumped before gelation to remove dissolved oxygen. The MAGAS polymer gel dosimeter was poured into glass screw-top vials, which were irradiated at various times, post-manufacture to a range of doses. Magnetic resonance imaging techniques were used to determine the R2-dose response and /?2-dose sensitivity of the MAGAS polymer gel. The results were compared with a control batch of MAGAS polymer gel that was not vacuum pumped. It was shown that vacuum pumping on the MAGAS polymer gel solution immediately prior to sealing in glass screw-top vials initially increases the R2-dose response and R2-dose sensitivity of the dosimeter. An increase in the .R2-dose response and i?2-dose sensitivity was observed with increasing time between manufacture and irradiation. Over the range of post-manufacture irradiation times investigated, the greatest i?2-dose response and if 2 -dose sensitivity occurred at 96 hours

Collaborative situational mapping during emergency response

NARCIS (Netherlands)

Gunawan, L.T.; Oomes, A.H.J.; Neerincx, M.; Brinkman, W.-P.; Alers, H.

2009-01-01

During emergency response, individuals observe only part of the picture, sharing of information is needed to get the required complete picture. The aim of our study is to get insight in the collaborative mapping process in order to derive requirements for a map-sharing tool. First, we analyzed the

Response of human and rabbit lymphocytes to low doses of X-rays

International Nuclear Information System (INIS)

Fabry, L.

1982-01-01

The response of human and rabbit lymphocytes to low doses of X-rays was studied by the yields of dicentrics in first division metaphases. For both species, the dose-response curve was best fitted to the linear-quadratic model with a linear component predominating up to 67 and 42 rad respectively for man and rabbit. A calibration curve (5-400 rad) was obtained by combining the present results on man with previous data at higher doses. On the other hand, it appears that, at low doses, the radiosentivity of human lymphocytes is significantly higher than that of rabbit lymphocytes [fr

Response of cellulose nitrate track detectors to electron doses

CERN Document Server

Segovia, N; Moreno, A; Vazquez-Polo, G; Santamaría, T; Aranda, P; Hernández, A

1999-01-01

In order to study alternative dose determination methods, the bulk etching velocity and the latent track annealing of LR 115 track detectors was studied during electron irradiation runs from a Pelletron accelerator. For this purpose alpha irradiated and blank detectors were exposed to increasing electron doses from 10.5 to 317.5 kGy. After the irradiation with electrons the detectors were etched under routine conditions, except for the etching time, that was varied for each electron dose in order to reach a fixed residual thickness. The variation of the bulk etching velocity as a function of each one of the electron doses supplied, was interpolated in order to obtain dosimetric response curves. The observed annealing effect on the latent tracks is discussed as a function of the total electron doses supplied and the temperature.

Emergency Preparedness and Response at Nuclear Power Plants in Pakistan

Energy Technology Data Exchange (ETDEWEB)

Khan, L. A.; Qamar, M. A.; Liaquat, M.R., E-mail: samasl@yahoo.com [Pakistan Atomic Energy Commission, Islamabad (Pakistan)

2014-10-15

Emergency preparedness and response arrangements at Nuclear Power Plants (NPPs) in Pakistan have been reevaluated in the light of Fukushima Daiichi accident. Appropriate measures have been taken to strengthen and effectively implement the on-site and off-site emergency plans. Verification of these plans is conducted through regulatory review and by witnessing periodic emergency drills and exercises conducted by the NPPs in the fulfilment of the regulatory requirements. Emergency Planning Zones (EPZs) have been revised at NPPs. A multi discipline reserve force has been formed for assistance during severe accidents. Nuclear Emergency Management System (NEMS) has been established at the national level in order to make necessary arrangements for responding to nuclear and radiological emergencies. Training programs for first responders and medical professionals have been launched. Emergencies coordination centres have been established at national and corporate levels. Public awareness program has been initiated to ensure that the surrounding population is provided with appropriate information on emergency planning and response. To share national and international operational experience, Pakistan has arranged various workshops and developed a strong link with International Atomic Energy Agency (IAEA). (author)

Evaluating nuclear power plant crew performance during emergency response drills

International Nuclear Information System (INIS)

Rabin, D.

1999-01-01

The Atomic Energy Control Board (AECB) is responsible for the regulation of the health, safety and environmental consequences of nuclear activities in Canada. Recently, the Human Factors Specialists of the AECB have become involved in the assessment of emergency preparedness and emergency response at nuclear facilities. One key contribution to existing AECB methodology is the introduction of Behaviourally Anchored Rating Scales (BARS) to measure crew interaction skills during emergency response drills. This report presents results of an on-going pilot study to determine if the BARS provide a reliable and valid means of rating the key dimensions of communications, openness, task coordination and adaptability under simulated emergency circumstances. To date, the objectivity of the BARS is supported by good inter-rater reliability while the validity of the BARS is supported by the agreement between ratings of crew interaction and qualitative and quantitative observations of crew performance. (author)

Emergency Response Data System (ERDS) implementation

International Nuclear Information System (INIS)

Jolicoeur, J.

1991-06-01

The US Nuclear Regulatory Commission has begun implementation of the Emergency Response Data System (ERDS) to upgrade its ability to acquire data from nuclear power plants in the event of an emergency at the plant. ERDS provides a direct real-time transfer of data from licensee plant computers to the NRC Operations Center. The system has been designed to be activated by the licensee during an emergency which has been classified at an ALERT or higher level. The NRC portion of ERDS will receive the data stream, sort and file the data. The users will include the NRC Operations Center, the NRC Regional Office of the affected plant, and if requested the States which are within the ten mile EPZ of the site. The currently installed Emergency Notification System will be used to supplement ERDS data. This report provides the minimum guidance for implementation of ERDS at licensee sites. It is intended to be used for planning implementation under the current voluntary program as well as for providing the minimum standards for implementing the proposed ERDS rule. 4 refs., 3 figs

Emergency Response Data System (ERDS) implementation

International Nuclear Information System (INIS)

Jolicoeur, J.

1990-04-01

The US Nuclear Regulatory Commission has begun implementation of the Emergency Response Data System (ERDS) to upgrade its ability to acquire data from nuclear power plants in the event of an emergency at the plant. ERDS provides a direct real-time transfer of data from licensee plant computers to the NRC Operations Center. The system has been designed to be activated by the licensee during an emergency which has been classified at an ALERT or higher level. The NRC portion of ERDS will receive the data stream, sort and file the data. The users will include the NRC Operations Center, the NRC Regional Office of the affected plant, and if requested the States which are within the ten mile EPZ of the site. The currently installed Emergency Notification System will be used to supplement ERDS data. This report provides the minimum guidance for implementation of ERDS at licensee sites. It is intended to be used for planning implementation under the current voluntary program as well as for providing the minimum standards for implementing the proposed ERDS rule

Expert system technology to support emergency response: its prospects and limitations

International Nuclear Information System (INIS)

Belardo, S.; Wallace, W.A.

1988-01-01

The capabilities for computer technologies to provide decision support in emergency response are now well recognized. The information flow prior to, during, and after potentially catastrophic events must be managed in order to have effective response. We feel strongly that computer technology can be a crucial component in this management process. We will first review a relatively new facet of computer technology - expert systems. We will then provide a conceptual framework for decision making under crisis, a situation typified by emergency response. We follow with a discussion of a prototype expert system for response to an accident at a nuclear power generation facility. Our final section discusses the potential advantages and limitations of expert system technology in emergency response. (author)

Radiological and nuclear emergency preparedness and response. How well are we prepared?

International Nuclear Information System (INIS)

Geick, Gunther H.G.; Herrmann, Andre R.; Koch, Doris; Meisenberg, Oliver; Rauber, Dominique; Stuerm, Rolf P.; Weiss, Wolfgang; Miska, Horst; Schoenhacker, Stefan

2011-01-01

The contributions to this topic are dealing, in a broad overview, with important aspects of Nuclear Emergency Preparedness and Response, like the influence of the new ICRP recommendations number 103 and number 109 on emergency preparedness and on planning for response, possible problems in installing and operating emergency care centres, experience from exercises as well as the training of response personnel in Austria and Germany. Finally, measures in emergency preparedness with regard to a dirty bomb attack are reported by means of an INEX-4-exercise in Switzerland. (orig.)

Employer Requirements to Work during Emergency Responses: Key Ethics Considerations.

Science.gov (United States)

Rutkow, Lainie; Taylor, Holly A; Powell, Tia

2017-03-01

Local health departments and their employees are at the forefront of emergency preparedness and response. Yet, recent studies have found that some local public health workers are unwilling to report to work in a variety of disaster scenarios. This can greatly compromise a response, as many local health departments need "all hands on deck" to effectively meet increased demands. To address these concerns, local health departments have employed varied policy strategies to ensure that employees do report to work. After describing different approaches taken by local health departments throughout the United States, we briefly identify and explore key ethics considerations that arise for local health departments when employees are required to report to work for emergency responses. We then discuss how these ethics considerations may inform local health department practices intended to promote a robust emergency response.

Elements of a national emergency response system for nuclear accidents

International Nuclear Information System (INIS)

Dickerson, M.H.

1987-01-01

The purpose of this paper is to suggest elements for a general emergency response system, employed at a national level, to detect, evaluate and assess the consequences of a radiological atmospheric release occurring within or outside of national boundaries. These elements are focused on the total aspect of emergency response ranging from providing an initial alarm to a total assessment of the environmental and health effects. Elements of the emergency response system are described in such a way that existing resources can be directly applied if appropriate; if not, newly developed or an expansion of existing resources can be employed. The major thrust of this paper is toward a philosophical discussion and general description of resources that would be required to implementation. If the major features of this proposal system are judged desirable for implementation, then the next level of detail can be added. The philosophy underlying this paper is preparedness - preparedness through planning, awareness and the application of technology. More specifically, it is establishment of reasonable guidelines including the definition of reference and protective action levels for public exposure to accidents involving nuclear material; education of the public, government officials and the news media; and the application of models and measurements coupled to computer systems to address a series of questions related to emergency planning, response and assessment. It is the role of a proven national emergency response system to provide reliable, quality-controlled information to decision makers for the management of environmental crises

State-level emergency preparedness and response capabilities.

Science.gov (United States)

Watkins, Sharon M; Perrotta, Dennis M; Stanbury, Martha; Heumann, Michael; Anderson, Henry; Simms, Erin; Huang, Monica

2011-03-01

Prior assessments of public health readiness had identified gaps in radiation preparedness. In recent years, preparedness planning has involved an "all-hazards" approach. Current assessment of the national status related to radiation public health emergency preparedness capabilities at the state and local health department levels was needed. A survey of state health departments related to radiation readiness was undertaken in 2010 by the Council of State and Territorial Epidemiologists (CSTE). States with nuclear power plants were instructed to consider their responses exclusive of capabilities and resources related to the plants given that the emergency response plans for nuclear power plants are specific and unique. Thirty-eight (76%) state health departments responded to the survey, including 26 of the 31 states with nuclear power plants. Specific strengths noted at the state level included that the majority of states had a written radiation response plan and most plans include a detailed section for communications issues during a radiation emergency. In addition, more than half of the states indicated that their relationship with federal partners is sufficient to provide resources for radiation emergencies, indicating the importance states placed on federal resources and expertise. Specific weaknesses are discussed and include that most states had completed little to no planning for public health surveillance to assess potential human health impacts of a radiation event; less than half had written plans to address exposure assessment, environmental sampling, human specimen collection and analysis, and human health assessment. Few reported having sufficient resources to do public health surveillance, radiation exposure assessment, laboratory functions and other capabilities. Levels of planning, resources and partnerships varied among states, those with nuclear power plants were better prepared. Gaps were evident in all states; however and additional training and

The MESORAD dose assessment model: Computer code

International Nuclear Information System (INIS)

Ramsdell, J.V.; Athey, G.F.; Bander, T.J.; Scherpelz, R.I.

1988-10-01

MESORAD is a dose equivalent model for emergency response applications that is designed to be run on minicomputers. It has been developed by the Pacific Northwest Laboratory for use as part of the Intermediate Dose Assessment System in the US Nuclear Regulatory Commission Operations Center in Washington, DC, and the Emergency Management System in the US Department of Energy Unified Dose Assessment Center in Richland, Washington. This volume describes the MESORAD computer code and contains a listing of the code. The technical basis for MESORAD is described in the first volume of this report (Scherpelz et al. 1986). A third volume of the documentation planned. That volume will contain utility programs and input and output files that can be used to check the implementation of MESORAD. 18 figs., 4 tabs

Shared dosimetry error in epidemiological dose-response analyses

International Nuclear Information System (INIS)

Stram, Daniel O.; Preston, Dale L.; Sokolnikov, Mikhail; Napier, Bruce; Kopecky, Kenneth J.; Boice, John; Beck, Harold; Till, John; Bouville, Andre; Zeeb, Hajo

2015-01-01

Radiation dose reconstruction systems for large-scale epidemiological studies are sophisticated both in providing estimates of dose and in representing dosimetry uncertainty. For example, a computer program was used by the Hanford Thyroid Disease Study to provide 100 realizations of possible dose to study participants. The variation in realizations reflected the range of possible dose for each cohort member consistent with the data on dose determinates in the cohort. Another example is the Mayak Worker Dosimetry System 2013 which estimates both external and internal exposures and provides multiple realizations of 'possible' dose history to workers given dose determinants. This paper takes up the problem of dealing with complex dosimetry systems that provide multiple realizations of dose in an epidemiologic analysis. In this paper we derive expected scores and the information matrix for a model used widely in radiation epidemiology, namely the linear excess relative risk (ERR) model that allows for a linear dose response (risk in relation to radiation) and distinguishes between modifiers of background rates and of the excess risk due to exposure. We show that treating the mean dose for each individual (calculated by averaging over the realizations) as if it was true dose (ignoring both shared and unshared dosimetry errors) gives asymptotically unbiased estimates (i.e. the score has expectation zero) and valid tests of the null hypothesis that the ERR slope β is zero. Although the score is unbiased the information matrix (and hence the standard errors of the estimate of β) is biased for β≠0 when ignoring errors in dose estimates, and we show how to adjust the information matrix to remove this bias, using the multiple realizations of dose. The use of these methods in the context of several studies including, the Mayak Worker Cohort, and the U.S. Atomic Veterans Study, is discussed

TL response of citrine samples for high-dose dosimetry

International Nuclear Information System (INIS)

Teixeira, Maria Ines; Caldas, Linda V.E.

2011-01-01

The possibility of using samples of Brazilian stones as quartz, amethyst, topaz, etc. for high-dose dosimetry has been studied in recent years at IPEN, using the thermoluminescence technique (TL). In this work, the TL properties of citrine samples were studied. They were exposed to different doses of gamma radiation ( 60 Co). The natural citrine stone was extracted from a mine in Minas Gerais state, Brazil; it is a tectosilicate ranked as one of three-dimensional structure, showing clear yellow to golden brown color. The natural citrine stone is classified as quartz (SiO 2 ), and it has a lower symmetry and more compact reticulum. The citrine stone samples were powdered, and the selected grains were mixed with Teflon in the proportion 2 (Teflon):1 (Citrine). The mixture was pressed and sintered for production of Citrine -Teflon pellets of 50 mg. The TL emission curve showed two peaks at 160 deg C and 220 deg C. To remove the TL peak (160 deg C) of the sintered citrine pellet glow curves, different thermal treatments were tested during several time intervals. The TL dose-response curve between 50 Gy and 100 kGy, the reproducibility of TL response and the lower detection dose were obtained. The preliminary results show that citrine may be useful for high-dose dosimetry. (author)

Bayesian Dose-Response Modeling in Sparse Data

Science.gov (United States)

Kim, Steven B.

This book discusses Bayesian dose-response modeling in small samples applied to two different settings. The first setting is early phase clinical trials, and the second setting is toxicology studies in cancer risk assessment. In early phase clinical trials, experimental units are humans who are actual patients. Prior to a clinical trial, opinions from multiple subject area experts are generally more informative than the opinion of a single expert, but we may face a dilemma when they have disagreeing prior opinions. In this regard, we consider compromising the disagreement and compare two different approaches for making a decision. In addition to combining multiple opinions, we also address balancing two levels of ethics in early phase clinical trials. The first level is individual-level ethics which reflects the perspective of trial participants. The second level is population-level ethics which reflects the perspective of future patients. We extensively compare two existing statistical methods which focus on each perspective and propose a new method which balances the two conflicting perspectives. In toxicology studies, experimental units are living animals. Here we focus on a potential non-monotonic dose-response relationship which is known as hormesis. Briefly, hormesis is a phenomenon which can be characterized by a beneficial effect at low doses and a harmful effect at high doses. In cancer risk assessments, the estimation of a parameter, which is known as a benchmark dose, can be highly sensitive to a class of assumptions, monotonicity or hormesis. In this regard, we propose a robust approach which considers both monotonicity and hormesis as a possibility. In addition, We discuss statistical hypothesis testing for hormesis and consider various experimental designs for detecting hormesis based on Bayesian decision theory. Past experiments have not been optimally designed for testing for hormesis, and some Bayesian optimal designs may not be optimal under a