TSD-DOSE: A radiological dose assessment model for treatment, storage, and disposal facilities

International Nuclear Information System (INIS)

Pfingston, M.; Arnish, J.; LePoire, D.; Chen, S.-Y.

1998-01-01

Past practices at US Department of Energy (DOE) field facilities resulted in the presence of trace amounts of radioactive materials in some hazardous chemical wastes shipped from these facilities. In May 1991, the DOE Office of Waste Operations issued a nationwide moratorium on shipping all hazardous waste until procedures could be established to ensure that only nonradioactive hazardous waste would be shipped from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. To aid in assessing the potential impacts of shipments of mixed radioactive and chemically hazardous wastes, a radiological assessment computer model (or code) was developed on the basis of detailed assessments of potential radiological exposures and doses for eight commercial hazardous waste TSD facilities. The model, called TSD-DOSE, is designed to incorporate waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste-handling operations at a TSD facility. The code is intended to provide both DOE and commercial TSD facilities with a rapid and cost-effective method for assessing potential human radiation exposures from the processing of chemical wastes contaminated with trace amounts of radionuclides

Assessment of radiological hazards of naturally occurring radioactive materials in cement industry

International Nuclear Information System (INIS)

Aslam, M.; Gul, R.; Ara, T.; Hussain, M.

2012-01-01

A study on the radiological hazard in Portland cement due to the presence of naturally occurring radioactive materials is being carried out. The Portland cement manufactured in the Islamabad/Rawalpindi region of Pakistan, intermediate products (clinker) and the various raw materials which compose the product have been analysed for 226 Ra, 232 Th and 40 K using a gamma spectrometry system with a N-type high-purity germanium detector of 80 % relative efficiency. From the measured gamma ray spectra, specific activities were determined. The mean values of the total specific activity of 226 Ra, 232 Th and 40 K are 34.2±11.9, 29.1±3.6 and 295.1±66.9 Bq kg -1 , respectively in Portland cement, 28.4±8.7, 11.3±1.7 and 63.1±17.3 Bq kg -1 , respectively in lime stone, 8.2±1.9, 16.2±3.9 and 187.7±53.2 Bq kg -1 , respectively in gypsum, 34.7±13.1, 41.2±6.7 and 187.6±17.2 Bq kg -1 , respectively in clay, 41.1±11.8, 39.3±6.9 and 195.1±29.2 Bq kg -1 , respectively in laterite and 51.1±18.2, 23.2±1.2 and 258.4±15.3 Bq kg -1 , respectively in clinker. The radium equivalent activities (Ra eq ), external hazard index (H ex ), internal hazard index (H in ), absorbed dose rate in air (D) and annual effective dose rate (E eff ) were also determined. The measured activity concentrations for these radio nuclides and radiological indices were compared with the reported national and international data. All these measured values are comparable with the worldwide data reported in UNSCEAR publications. (authors)

Factor analysis on hazards for safety assessment in decommissioning workplace of nuclear facilities using a semantic differential method

Energy Technology Data Exchange (ETDEWEB)

Jeong, Kwan-Seong [Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)], E-mail: ksjeongl@kaeri.re.kr; Lim, Hyeon-Kyo [Chungbuk National University, 410 Sungbong-ro, Heungduk-gu, Cheongju, Chungbuk 361-763 (Korea, Republic of)

2009-10-15

The decommissioning of nuclear facilities must be accomplished according to its structural conditions and radiological characteristics. An effective risk analysis requires basic knowledge about possible risks, characteristics of potential hazards, and comprehensive understanding of the associated cause-effect relationships within a decommissioning for nuclear facilities. The hazards associated with a decommissioning plan are important not only because they may be a direct cause of harm to workers but also because their occurrence may, indirectly, result in increased radiological and non-radiological hazards. Workers need to be protected by eliminating or reducing the radiological and non-radiological hazards that may arise during routine decommissioning activities as well as during accidents. Therefore, to prepare the safety assessment for decommissioning of nuclear facilities, the radiological and non-radiological hazards should be systematically identified and classified. With a semantic differential method of screening factor and risk perception factor, the radiological and non-radiological hazards are screened and identified.

Hazards assessment for the INEL Landfill Complex

International Nuclear Information System (INIS)

Knudsen, J.K.; Calley, M.B.

1994-02-01

This report documents the hazards assessment for the INEL Landfill Complex (LC) located at the Idaho National Engineering Laboratory, which is operated by EG ampersand G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and the DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes the hazards that are significant enough to warrant consideration in a facility's operational emergency management program. The area surrounding the LC, the buildings and structures at the LC, and the processes that are used at the LC are described in this report. All hazardous materials, both radiological and nonradiological, at the LC were identified and screened against threshold quantities according to DOE Order 5500.3A guidance. Asbestos at the Asbestos Pit was the only hazardous material that exceeded its specified threshold quantity. However, the type of asbestos received and the packaging practices used are believed to limit the potential for an airborne release of asbestos fibers. Therefore, in accordance with DOE Order 5500.3A guidance, no further hazardous material characterization or analysis was required for this hazards assessment

Hazards assessment for the INEL Landfill Complex

Energy Technology Data Exchange (ETDEWEB)

Knudsen, J.K.; Calley, M.B.

1994-02-01

This report documents the hazards assessment for the INEL Landfill Complex (LC) located at the Idaho National Engineering Laboratory, which is operated by EG&G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and the DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes the hazards that are significant enough to warrant consideration in a facility`s operational emergency management program. The area surrounding the LC, the buildings and structures at the LC, and the processes that are used at the LC are described in this report. All hazardous materials, both radiological and nonradiological, at the LC were identified and screened against threshold quantities according to DOE Order 5500.3A guidance. Asbestos at the Asbestos Pit was the only hazardous material that exceeded its specified threshold quantity. However, the type of asbestos received and the packaging practices used are believed to limit the potential for an airborne release of asbestos fibers. Therefore, in accordance with DOE Order 5500.3A guidance, no further hazardous material characterization or analysis was required for this hazards assessment.

Building 894 hazards assessment document

International Nuclear Information System (INIS)

Banda, Z.; Williams, M.

1996-07-01

The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with Building 894. The entire inventory was subjected to the screening criteria for potential airborne impact to onsite and offsite individuals out of which 9 chemicals were kept for further evaluation. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance at which a postulated facility event will produce consequences exceeding the Early Severe Health Effects threshold is 130 meters. The highest emergency classification is a General Emergency. The Emergency Planning Zone is a nominal 130 meter area that conforms to DOE boundaries and physical/jurisdictional boundaries such as fence lines and streets

Building 6630 hazards assessment document

International Nuclear Information System (INIS)

Williams, M.; Banda, Z.

1996-10-01

The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with Building 6630. The entire inventory was subjected to the screening criteria for potential airborne impact to onsite and offsite individuals out of which one chemical was kept for further evaluation. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the chemical release site, the atmospheric conditions, and the circumstances of the release. The greatest distance at which a postulated facility event will produce consequences exceeding the Early Severe Health Effects threshold is 76 meters. The highest emergency classification is an Alert. The Emergency Planning Zone is a nominal 100 meter area that conforms to DOE boundaries and physical/jurisdictional boundaries such as fence lines and streets

Assessment of natural radionuclides and its radiological hazards from tiles made in Nigeria

Science.gov (United States)

Joel, E. S.; Maxwell, O.; Adewoyin, O. O.; Ehi-Eromosele, C. O.; Embong, Z.; Saeed, M. A.

2018-03-01

Activity concentration of 10 different brands of tiles made in Nigeria were analyzed using High purity Germanium gamma detector and its hazard indices such as absorbed dose rate, radium equivalent activity, external Hazard Index (Hex), internal Hazard Index (Hin), Annual Effective Dose (mSv/y), Gamma activity Index (Iγ) and Alpha Index (Iα) were determined. The result showed that the average activity concentrations of radionuclides (226Ra, 232Th and 40K) content are within the recommended limit. The average radium equivalent is within the recommended limit of 370 Bq/kg. The result obtained further showed that the mean values for the absorbed dose rate (D), external and internal hazard index, the annual effective dose (AEDR) equivalent, gamma activity index and Alpha Index were: 169.22 nGyh-1, 0.95 and 1.14, 1.59 mSv/y, 1.00 Sv yr-1 and 0.34 respectively. The result established that radiological hazards such as absorbed dose rate, internal hazard, annual effective dose rate, gamma activity index and Alpha Index for some samples are found to be slightly close or above international recommended values. The result for the present study was compared with tiles sample from others countries, it was observed that the concentration of tiles made in Nigeria and other countries are closer, however recommends proper radiation monitoring for some tiles made in Nigeria before usage due to the long term health effect.

Advanced Materials Laboratory hazards assessment document

Energy Technology Data Exchange (ETDEWEB)

Barnett, B.; Banda, Z.

1995-10-01

The Department of Energy Order 55OO.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the AML. The entire inventory was screened according to the potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance at which a postulated facility event will produce consequences exceeding the Early Severe Health Effects threshold is 23 meters. The highest emergency classification is a General Emergency. The Emergency Planning Zone is a nominal area that conforms to DOE boundaries and physical/jurisdictional boundaries such as fence lines and streets.

An Assessment of Radiological Hazards from Gold Mine Tailings in the Province of Gauteng in South Africa

Science.gov (United States)

Kamunda, Caspah; Mathuthu, Manny; Madhuku, Morgan

2016-01-01

Radiological hazards associated with exposure to Naturally Occurring Radionuclides Materials from gold mine tailings in the province of Gauteng in South Africa were evaluated. A comparison was made with soil samples from a control area. In this study, gamma spectroscopy was used to measure the activity concentrations of these radionuclides in 56 soil samples from the mine tailings and 10 soil samples from the control area. The average activity concentrations in Bq∙kg−1 for Uranium-238, Thorium-232, and Potassium-40 from the mine tailings were found to be 785.3 ± 13.7, 43.9 ± 1.0 and 427.0 ± 13.1, respectively. On the other hand, the average activity concentrations in Bq∙kg−1 for Uranium-238, Thorium-232, and Potassium-40 from the control area were found to be 17.0.1 ± 0.4, 22.2 ± 0.5 and 496.8 ± 15.2, respectively. Radiological hazard parameters calculated from these activity concentrations were higher than recommended safe limits. In particular, calculated average values for the external hazard (Hex) and the internal hazard (Hin) from the mine tailings were found to be 2.4 and 4.5. Both these values were higher than unity, posing a significant health risk to the population in the area. PMID:26797624

The radiogenic hazards of working in a radiology department

International Nuclear Information System (INIS)

Russell, J.G.B.

1992-01-01

The author assesses the risks incurred by the medical personnel working in a radiology department with regard to the new estimates of risk levels for ionizing radiation delivered at low dose rates and low doses (UNSCEAR, 1988; NRPB, 1988; ICRP, 1991). It is emphasised that in deciding if the cancer has been caused by an occupational exposure, the factors to be taken into account are the radiosensitivity of the organ involved, the dose the organ has received and the time of the appearance of the cancer. Figures are provided for the radiation doses and risk of fatality of medical workers. A comparison is made with the risk of death from working in various industries. It appears that for the majority of medical radiation workers the radiogenic hazard is slight but that the hazards can be substantial for the higher dose workers. 13 refs., 2 tabs.; 1 fig

Assessment of natural radioactivity and radiological hazards in building materials used in Yan'an, China.

Science.gov (United States)

Lu, Xinwei; Li, Nan; Yang, Guang; Zhao, Caifeng

2013-03-01

The concentration of natural radionuclides in commonly used building materials collected from Yan'an, China, was determined using gamma ray spectroscopy with a NaI(Tl) detector. The activity concentration of ²²⁶Ra, ²³²Th, and ⁴⁰K in the studied building materials ranges from 9.4-73.1, 11.5-86.9, and 258.9-1,055.1 Bq kg⁻¹, respectively. The concentrations for these natural radionuclides were compared with the reported data of other countries and the world mean values for soil. The radium equivalent activity (Raeq), external hazard index (Hex), internal hazard index (Hin), indoor air absorbed dose rate, and annual effective dose rate due to natural radionuclides in samples were estimated to assess radiological hazards for people living in dwellings made of the studied building materials. The calculated Raeq values of all building materials (75.7-222.1 Bq kg⁻¹) are lower than the limit of 370 Bq kg⁻¹. The values of Hex and Hin are less than unity. The mean values of indoor air absorbed dose rates of all building materials (101.0 ± 14.1-177.0 ± 6.8 nGy h⁻¹) are higher than the world population-weighted average of 84 nGy h⁻¹, while the mean values of annual effective dose range from 0.50 ± 0.07-0.87 ± 0.03 mSv y⁻¹, which are lower than the recommended limit of 1 mSv y⁻¹. It is found that these materials may be used safely as construction materials and do not pose significant radiation hazards to inhabitants.

Limits of the comparison between radiological and chemical hazards

International Nuclear Information System (INIS)

Maximilien, R.; Bounolleau, B.

2003-01-01

The primary reason for comparing radiological and chemical hazards is, in the absence of knowledge of similarities between underlying mechanisms, the comparability of the methods used to evaluate their long-term consequences, especially at low doses: carcinogenicity, mutagenicity and effects on reproduction. For radiations, the evaluation is performed above all in terms of risk quantification while for chemicals hazard identification is the main concern. (authors)

Radiology of adverse reactions to drugs and toxic hazards

International Nuclear Information System (INIS)

Ansell, G.

1989-01-01

The book reviews the contribution offered by radiological methods to detection of lesions, confirmation of tentative diagnoses, and differentiation of lesions. The radiological methods discussed cover the conventional roentgenology as well as computed tomography, ultrasonography, scintiscanning, and NMR tomography, which are the useful tools for the very important task, to detect and define the manifestations of adverse reactions and toxic hazards, in order to commence treatment in time. (orig.) With 154 figs [de

Radiological hazard assessment at the Monte Bello Islands

International Nuclear Information System (INIS)

Cooper, M.B.; Martin, L.J.; Wilks, M.J.; Wiliams, G.A.

1990-12-01

Field and laboratory measurements are described and data presented which enabled dose assessments for exposure to artificial radionuclides at the Monte Bello Islands, the sites of U.K. atomic weapons tests in 1952 and 1956. The report focuses on quantifying the inhalation hazard as exposure via the ingestion and wound contamination pathways is considered inconsequential. Surface soil concentrations of radionuclides and particle size analyses are presented for various sampling sites. Analyses of the distribution with depth indicated that, in general, the activity is more or less uniformly mixed through the top 40 mm, although in a few cases the top 10 mm contains the bulk of the activity. The 239 Pu/ 241 Am activity ratios were measured for selected samples. The only potential hazards to health from residual radioactive contamination on the Monte Bello Islands are due to the inhalation of actinides (specifically plutonium and americium) and from the external gamma-radiation field. Only one area, in the fallout plume of HURRICANE to the north-west of Main Beach, is a potential inhalation hazard. For an average inhalable dust loading of 0.1 mg/m 3 , three days occupancy of the most contaminated site will result in a committed effective dose equivalent of 1 mSv. The two ground zeros could not be considered inhalation hazards, considering the small areas concerned and the habits of visitors (full-time occupancy, over a period of one year or more, of the most contaminated sites at either of the G1 or G2 ground zeros would be required to reach 1 mSv). 25 refs., 23 tabs., 3 figs

Lessons learned from joint working group report on assessment and management of cancer risks from radiological and chemical hazards

International Nuclear Information System (INIS)

Myers, D.K.

1997-01-01

Regulation of radiological hazards to humans is greatly simplified by the existence of the International Commission on Radiological Protection (ICRP). The average RBE values or radiation weighting factors recommended by the ICRP are based on non-human data. The ICRP has also indicated that 'the standard of environmental control needed to protect man to the degree currently thought desirable will ensure that other species are not put at risk.' This statement appears to be supported by technical publications from other organizations. Two published objections by AECB staff to the scientific technical background of the ICRP statement do not offer any good reason to reject this ICRP statement. A brief summary is given of the joint working group report on the topic indicated in the title. It is noted that regulators of cancer-causing chemicals have in general paid less attention to natural sources than have the regulators of radiological hazards. Most non-human species are exposed to about 1 millisievert (mSv) equivalent dose of radiation per year from natural sources. Caribou and organisms living underground are noted as examples where radiation exposures from natural sources are considerably higher. The natural biota is in general remarkably resistant, both in the laboratory and in field studies, to the effects of high doses of radiation. A recent review by the International Atomic Agency concluded that dose rates below the equivalent of 400 mSv per year are unlikely to after the survival of non-human species. It is recommended that caution and common sense be applied in any future research on radiological protection of non-human species in the environment in Canada. Many of the proposed U.S. regulations to control chemical and radiation in the environment are not cost-effective. It is to be hoped that efforts to protect non-human species from potential radiological hazards in Canada do not slide into a similar kind of irrational quagmire. (author)

Perspectives on the chemical and radiological hazards of uranium

International Nuclear Information System (INIS)

Stansbury, P.S.

1987-01-01

Uranium is unique among the elements because it presents chemical and radiological hazards of comparable magnitude. Although the biological effects of a heavy metal damaging the kidneys are vastly different from the actions of an alpha-emitting nuclide in the lung or bone tissues, there are some perceptual and phenomenological similarities of note to health physicists. In a broad sense, the amount of uranium that could cause chemical kidney damage or pose a radiation hazard could go unnoticed in the work place. Once taken into the body, the chemical action or the radiological insult progresses without any warning signals. Ultrasensitive bioassay techniques could detect the presence of uranium in the body and quantify an intake that is known to have occurred. The adverse health effect of either the chemical or radiological mode of action is catastrophic: kidney failure on one hand, cancer on the other. Two other parallelisms should be noted. The natural loss of nephrons is part of the aging process. Similarly 15 to 20% of the population die of naturally caused cancer. Thus, the effects of uranium exposure mimic natural effects in unexposed populations. There are suspected adverse health effects at low levels of exposure to uranium. Even though there may be good reasons for suspecting low-level effects, both chemical and radiological, there is very little definitive evidence that these effects occur in human populations. 7 refs., 1 fig., 1 tab

Radiological assessments, environmental monitoring, and study design

International Nuclear Information System (INIS)

Hansen, W.R.; Elle, D.R.

1980-01-01

Studies of the behavior of transuranic elements in the environment form the basic data for applied programs in radiological assessment, environmental monitoring, derivation of radiation-protection standards, and environmental impact statements. This chapter introduces some of the major information requirements of these applications of transuranic research data. Characteristics of the source terms from nuclear activities usually are needed for an analysis of environmental pathways or deployment of monitoring systems. Major inhalation and ingestion pathways are considered in assessments of hazards from transuranics and are discussed from the viewpoint of research needed

Chemical and radiological vulnerability assessment in urban areas

Directory of Open Access Journals (Sweden)

Stojanović Božidar

2006-01-01

Full Text Available Cities and towns are faced with various types of threat from the extraordinary events involving chemical and radiological materials as exemplified by major chemical accidents, radiological incidents, fires, explosions, traffic accidents, terrorist attacks, etc. On the other hand, many sensitive or vulnerable assets exist within cities, such as: settlements, infrastructures, hospitals, schools, churches, businesses, government, and others. Besides emergency planning, the land use planning also represents an important tool for prevention or reduction of damages on people and other assets due to unwanted events. This paper considers development of method for inclusion vulnerability assessment in land use planning with objective to assess and limit the consequences in cities of likely accidents involving hazardous materials. We made preliminary assessment of criticality and vulnerability of the assets within Belgrade city area in respect to chemical sites and transportation roads that can be exposed to chemical accidents, or terrorist attacks.

Simulation Technology Laboratory Building 970 hazards assessment document

International Nuclear Information System (INIS)

Wood, C.L.; Starr, M.D.

1994-11-01

The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Simulation Technology Laboratory, Building 970. The entire inventory was screened according to the potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distances at which a postulated facility event will produce consequences exceeding the ERPG-2 and Early Severe Health Effects thresholds are 78 and 46 meters, respectively. The highest emergency classification is a Site Area Emergency. The Emergency Planning Zone is 100 meters

ASSESSING CHEMICAL HAZARDS AT THE PLUTONIUM FINISHING PLANT FOR PLANNING FUTURE DECONTAMINATION AND DECOMMISSIONING

International Nuclear Information System (INIS)

HOPKINS, A.M.; KLOS, D.B.; MINETT, M.J.

2007-01-01

This paper documents the fiscal year (FY) 2006 assessment to evaluate potential chemical and radiological hazards associated with vessels and piping in the former plutonium process areas at Hanford's Plutonium Finishing Plant (PFP). Evaluations by PFP engineers as design authorities for specific systems and other subject-matter experts were conducted to identify the chemical hazards associated with transitioning the process areas for the long-term layup of PFP before its eventual final decontamination and decommissioning (D and D). D and D activities in the main process facilities were suspended in September 2005 for a period of between 5 and 10 years. A previous assessment conducted in FY 2003 found that certain activities to mitigate chemical hazards could be deferred safely until the D and D of PFP, which had been scheduled to result in a slab-on-grade condition by 2009. As a result of necessary planning changes, however, D and D activities at PFP will be delayed until after the 2009 time frame. Given the extended project and plant life, it was determined that a review of the plant chemical hazards should be conducted. This review to determine the extended life impact of chemicals is called the ''Plutonium Finishing Plant Chemical Hazards Assessment, FY 2006''. This FY 2006 assessment addresses potential chemical and radiological hazard areas identified by facility personnel and subject-matter experts who reevaluated all the chemical systems (items) from the FY 2003 assessment. This paper provides the results of the FY 2006 chemical hazards assessment and describes the methodology used to assign a hazard ranking to the items reviewed

Assessment for the management of NORM wastes in conventional hazardous and nonhazardous waste landfills

Energy Technology Data Exchange (ETDEWEB)

Mora, Juan C., E-mail: jc.mora@ciemat.es [Unit for Radiation Protection of the Public and the Environment (PRPYMA), CIEMAT, Avda. Complutense, 40, 28040 Madrid (Spain); Energy Engineering Department, Power Engineering, Nuclear Area, ETSII, UNED (Spain); Baeza, Antonio [LARUEX, Dpt. Applied Physics, Faculty of Veterinary Science, University of Extremadura, Avda. Universidad, s/n, 10071 Cáceres (Spain); Robles, Beatriz [Unit for Radiation Protection of the Public and the Environment (PRPYMA), CIEMAT, Avda. Complutense, 40, 28040 Madrid (Spain); Sanz, Javier [Energy Engineering Department, Power Engineering, Nuclear Area, ETSII, UNED (Spain)

2016-06-05

Highlights: • Before 2010 NORM waste is managed as non-radioactive, disposed in landfills. • After 2010 radiological impact of the management of NORM wastes must be assessed. • Quantities that can be disposed in hazardous or non-hazardous landfills are given. • Uncertainty analysis is included to provide consistency to the calculations. - Abstract: Naturally Occurring Radioactive Materials (NORM) wastes are generated in huge quantities in several industries and their management has been carried out under considerations of industrial non-radioactive wastes, before the concern on the radioactivity content was included in the legislation. Therefore these wastes were conditioned using conventional methods and the waste disposals were designed to isolate toxic elements from the environment for long periods of time. Spanish regulation for these conventional toxic waste disposals includes conditions that assure adequate isolation to minimize the impact of the wastes to the environment in present and future conditions. After 1996 the radiological impact of the management of NORM wastes is considered and all the aspects related with natural radiations and the radiological control regarding the management of residues from NORM industries were developed in the new regulation. One option to be assessed is the disposal of NORM wastes in hazardous and non-hazardous waste disposals, as was done before this new regulation. This work analyses the management of NORM wastes in these landfills to derive the masses that can be disposed without considerable radiological impact. Generic dose assessments were carried out under highly conservative hypothesis and a discussion on the uncertainty and variability sources was included to provide consistency to the calculations.

Assessment for the management of NORM wastes in conventional hazardous and nonhazardous waste landfills

International Nuclear Information System (INIS)

Mora, Juan C.; Baeza, Antonio; Robles, Beatriz; Sanz, Javier

2016-01-01

Highlights: • Before 2010 NORM waste is managed as non-radioactive, disposed in landfills. • After 2010 radiological impact of the management of NORM wastes must be assessed. • Quantities that can be disposed in hazardous or non-hazardous landfills are given. • Uncertainty analysis is included to provide consistency to the calculations. - Abstract: Naturally Occurring Radioactive Materials (NORM) wastes are generated in huge quantities in several industries and their management has been carried out under considerations of industrial non-radioactive wastes, before the concern on the radioactivity content was included in the legislation. Therefore these wastes were conditioned using conventional methods and the waste disposals were designed to isolate toxic elements from the environment for long periods of time. Spanish regulation for these conventional toxic waste disposals includes conditions that assure adequate isolation to minimize the impact of the wastes to the environment in present and future conditions. After 1996 the radiological impact of the management of NORM wastes is considered and all the aspects related with natural radiations and the radiological control regarding the management of residues from NORM industries were developed in the new regulation. One option to be assessed is the disposal of NORM wastes in hazardous and non-hazardous waste disposals, as was done before this new regulation. This work analyses the management of NORM wastes in these landfills to derive the masses that can be disposed without considerable radiological impact. Generic dose assessments were carried out under highly conservative hypothesis and a discussion on the uncertainty and variability sources was included to provide consistency to the calculations.

Philosophy of radiological protection and radiation hazard protection law

International Nuclear Information System (INIS)

Kai, Michiaki; Kawano, Takao

2013-01-01

The radiation protection and the human safety in radiation facilities are strictly controlled by law. There are rules on the radiation measurement, too. In the present review, philosophy of the radiological protection and the radiation hazard protection law is outlined with reference to ICRP recommendations. (J.P.N.)

Radiological hazards to uranium miners

International Nuclear Information System (INIS)

1990-05-01

The purpose of the present document is to review and assess the occupational hazards to uranium miners in Canada. Amendments to regulations set the maximum permissible dose to uranium miners at 50 mSv per year. Uranium miners are exposed to radon and thoron progeny, external gamma radiation and long-lived alpha-emitting radionuclides in dust. The best estimate for the lifetime risk of inhaled radon progeny is about 3 x 10 -4 lung cancers per WLM for the average miner, with a range of uncertainty from about 1 -6 x 10 -4 per WLM. This central value is nearly twice as high as that recommended by the ICRP in 1981. The probability of serious biological consequences following exposure to external gamma rays is currently under review but is expected to be in the range of 3 - 6 x 10 -2 Sv -1 . Dosimetric calculations indicate that the stochastic risks per WLM of thoron progeny are about one-third of those for radon progeny. The annual limits on intake of inhaled ore dusts recommended by the ICRP are probably too low by at least a factor of two for the type of ore and dust normally encountered in underground uranium mines in Ontario; this is due in part to the fact that the average diameter of these dusts is five times greater than the value used by the ICRP. Radiological exposures of uranium miners in Canada were reviewed. The biological impact of these exposures were compared with those of conventional accidents on the basis of the years of normal life expectancy that are lost or seriously impaired due to occupational hazards. The objectives in considering all occupational risks are to reduce the total risk from all causes and to use funds spent for health protection as effectively as possible

Assessment of the natural radioactivity and its radiological hazards in prospective ore deposit sites in Southwestern Nigeria

International Nuclear Information System (INIS)

Ifeoluwa, O.P.; Obed, R.O. I.

2014-01-01

Assessment of the natural radioactivity was conducted in three Southwestern states, Ekiti, Kogi and Kwara in Nigeria spanning over approximately a 9,000 km 2 on earmarked prospective ore deposits sites where thirty six (36) top soil samples were collected then taken to the laboratory for analysis so as to determine and deduce its radiological hazards and health implication prior to exploitation/exploration. The samples collected at 36 locations, mainly undisturbed and virgin lands could determine the annual effective dose (mSv.y -1 ) and the average absorbed dose (nGy/h) for a person living in the rural community along the axis and this was found to be approximately 0.114 mSvy -1 and 93.60±14.4 nGyh -1 respectively. Other health indices are drawn up in the tables found below.

Assessment and management of cancer risks from radiological and chemical hazards

International Nuclear Information System (INIS)

1998-01-01

A Joint Working Group was established in April 1995 by the President of the Atomic Energy Control Board (AECB) and the Assistant Deputy Minister of the Health Protection Branch of Health Canada to examine the similarities, disparities and inconsistencies between the levels of risk considered acceptable for regulating ionizing radiation and those considered acceptable for regulating chemical and microbiological hazards. During the process of collecting, analysing and interpreting information, the Joint Working Group realized that its terms of reference as written presented a major difficulty because of the lack of consensus on acceptable levels of risk. Consequently it decided that the most reasonable way to proceed was to compare the risk assessment and management processes used to protect the public from radiation, chemicals and microbiological hazards. This report concentrates on the assessment and management of ionizing radiation and genotoxic chemicals (which both cause cancer by damaging the DNA in cells) and pays less attention to non-genotoxic effects and microbiological hazards. The report also examines public more than occupational exposures and exposures from man-made rather than naturally occurring agents. (author)

Sandia Administrative Micrographics Facility, Building 802: Hazards assessment document

International Nuclear Information System (INIS)

Swihart, A.

1994-12-01

The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Sandia Administrative Micrographics Facility, Building 802. The entire inventory was screened according to the potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance at which a postulated facility event will produce consequences exceeding the Early Severe Health Effects threshold is 33 meters. The highest emergency classification is a Site Area Emergency. The Emergency Planning Zone is 75 meters

Regulatory aspects of radiological hazards in mines and works

International Nuclear Information System (INIS)

Metcalf, P.E.; Guy, M.S.C.; Van Sittert, J.M.O.

1987-01-01

The mining and processing of ores containing uranium and thorium can give rise to exposure to ionizing radiation via various pathways to both persons employed in mines and works and to members of the general public living in the vicinity of such facilities. Such exposures to radiation will not give rise to unacceptable levels of risk provided the source of such exposure are identified, quantified and controlled. In order to establish the necessary regulatory framework to ensure such identification, quantification and control, regulations are currently being promulgated under the Mines and Works Act to require that activities involving nuclear hazard material resulting from the mining and processing of materials containing uranium and thorium will be subject to such conditions that will ensure compliance with a system of radiation dose limitation laid down. It is proposed that conditions be established for each mine and works in the form of a Code of Practice specific to the facility, the provisions of which will be commensurate with the potential magnitude of the particular radiological hazards prevailing at that facility. Generic guidelines will be made available to enable suitable Codes of Practice to be drawn up. This paper discusses the various radiological hazards that may have to be considered, the scope and content of the generic guidelines and the dose limitation system with which it will be necessary to comply. 5 refs., 2 tabs

Radiological hazards

International Nuclear Information System (INIS)

Hamilton, M.

1984-01-01

The work of the (United Kingdom) National Radiological Protection Board is discussed. The following topics are mentioned: relative contributions to genetically significant doses of radiation from various sources; radon gas in non-coal mines and in dwelling houses; effects of radiation accidents; radioactive waste disposal; radiological protection of the patient in medicine; microwaves, infrared radiation and cataracts; guidance notes for use with forthcoming Ionising Radiations Regulations; training courses; personal dosimetry service; work related to European Communities. (U.K.)

Glass Formulation and Fabrication Laboratory, Building 864, Hazards assessment document

Energy Technology Data Exchange (ETDEWEB)

Banda, Z.; Wood, C.L.

1995-08-01

The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Glass Formulation and Fabrication Laboratory, Building 864. The entire inventory was screened according to the potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distances at which a postulated facility event will produce consequences exceeding the ERPG-2 threshold is 96 meters. The highest emergency classification is a Site Area Emergency. The Emergency Planning Zone is 100 meters.

ICPP radiological and toxicological sabotage analysis

International Nuclear Information System (INIS)

Kubiak, V.R.; Mortensen, F.G.

1995-01-01

In June of 1993, the Department of Energy (DOE) issued Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes which states that all significant radiological and toxicological hazards at Department facilities must be examined for potential sabotage. This analysis has been completed at the Idaho Chemical Processing Plant (ICPP). The ICPP radiological and toxicological hazards include spent government and commercial fuels, Special Nuclear Materials (SNM), high-level liquid wastes, high-level solid wastes, and process and decontamination chemicals. The analysis effort included identification and assessment of quantities of hazardous materials present at the facility; identification and ranking of hazardous material targets; development of worst case scenarios detailing possible sabotage actions and hazard releases; performance of vulnerability assessments using table top and computer methodologies on credible threat targets; evaluation of potential risks to the public, workers, and the environment; evaluation of sabotage risk reduction options; and selection of cost effective prevention and mitigation options

Evaluation of natural radioactivity and radiological hazards caused by different marbles of India

International Nuclear Information System (INIS)

Ramasamy, V.; Ponnusamy, V.; Hemalatha, J.; Meenakshisundaram, V.; Gajendiran, V.

2005-01-01

The samples used in this study are of various coloured varieties of marbles collected from marble dealers. The specific activity concentration of 238 U, 232 Th and 40 K has been determined by gamma ray spectrometry. The materials showed concentrations of 238 U, 232 Th and 40 K which were found to be dramatically variable depending on mineral content and type of formation. Using FTIR and thin section analyses, quartz, feldspar, calcite and mafic minerals present in the samples have been determined quantitatively. From our experimental data, it can be seen that the geochemical parameters such as SiO 2 or mafic minerals or CaCO 3 may be considered to be an appropriate index to select the marbles of low radiological risk. The average specific activities of 40 K are found to be higher than 232 Th, 238 U. The ratio of Th/U was calculated and correlated. Assessment of radiological hazards was made by calculating radium equivalent activities, external and internal hazard indices which were found to vary from 30.92 to 54.45, 0.08 to 0.14 and 0.10 to 0.17 Bq/kg, respectively. The observed values are lower than the recommended limits. (author)

Radiological field survey problems and solutions

International Nuclear Information System (INIS)

Deming, E.J.; Boerner, A.J.

1986-01-01

Situations often arise during radiological field surveys which require the health physicist to improvise and/or make spot decisions. At times these situations can be humorous, but they can also present hazards more serious than normal radiological considerations. This presentation will depict various problematic situations encountered by Oak Ridge Associated Universities Radiological Site Assessment Program in the course of performing field environmental surveys. Detailing these potential hazards can alert other field survey groups to problems they may encounter

Applying radiological emergency planning experience to hazardous materials emergency planning within the nuclear industry

International Nuclear Information System (INIS)

Foltman, A.; Newsom, D.; Lerner, K.

1988-01-01

The nuclear industry has extensive radiological emergency planning (REP) experience that is directly applicable to hazardous materials emergency planning. Recently, the Feed Materials Production Center near Cincinnati, Ohio, successfully demonstrated such application. The REP experience includes conceptual bases and standards for developing plans that have been tested in hundreds of full-scale exercises. The exercise program itself is also well developed. Systematic consideration of the differences between chemical and radiological hazards shows that relatively minor changes to the REP bases and standards are necessary. Conduct of full-scale, REP-type exercises serves to test the plans, provide training, and engender confidence and credibility

Natural radioactivity and radiological hazards of building materials in Xianyang, China

International Nuclear Information System (INIS)

Lu Xinwei; Yang Guang; Ren Chunhui

2012-01-01

Common building materials collected from Xianyang, China were analyzed for the natural radioactivity of 226 Ra, 232 Th and 40 K using γ-ray spectroscopy. The average activity concentration of 226 Ra, 232 Th and 40 K in the studied building materials ranges from 13.4 to 69.9, 13.1–99.1 and 124.7–915.1 Bq kg −1 , respectively. The measured activity concentrations for these radionuclides were compared with the reported data of other countries and with the worldwide average activity of soil. To assess the radiation hazard of the natural radioactivity in all samples to the people, the radium equivalent activity, external hazard index, internal hazard index, indoor absorbed dose rate and total annual effective dose were estimated. The radium equivalent activities of the studied samples are below the internationally accepted values. The external hazard index and internal hazard index of all analyzed building materials are less than unity. The mean values of indoor absorbed dose rate for all building materials except for lime are higher than the world population-weighted average of 84 nGy h −1 and the total annual effective dose values of building materials are lower than 1 mSv y −1 except for some cyan brick samples. The study shows the measured building materials do not pose significant source of radiation hazard and are safe for use in the construction of dwellings. - Highlights: ► Natural radioactivity in building materials was determined by gamma ray spectrometry. ► The radiological hazard of studied building materials is within the recommended safety limit. ► Most of the studied building materials do not pose significant radiation risk to residents.

The Bristol Radiology Report Assessment Tool (BRRAT): Developing a workplace-based assessment tool for radiology reporting skills

International Nuclear Information System (INIS)

Wallis, A.; Edey, A.; Prothero, D.; McCoubrie, P.

2013-01-01

Aim: To review the development of a workplace-based assessment tool to assess the quality of written radiology reports and assess its reliability, feasibility, and validity. Materials and methods: A comprehensive literature review and rigorous Delphi study enabled the development of the Bristol Radiology Report Assessment Tool (BRRAT), which consists of 19 questions and a global assessment score. Three assessors applied the assessment tool to 240 radiology reports provided by 24 radiology trainees. Results: The reliability coefficient for the 19 questions was 0.79 and the equivalent coefficient for the global assessment scores was 0.67. Generalizability coefficients demonstrate that higher numbers of assessors and assessments are needed to reach acceptable levels of reliability for summative assessments due to assessor subjectivity. Conclusion: The study methodology gives good validity and strong foundation in best-practice. The assessment tool developed for radiology reporting is reliable and most suited to formative assessments

Radiological and hazardous material characterization report for the south portion of the 313 Building

International Nuclear Information System (INIS)

Harris, R.A.

1995-12-01

The objective of the characterization was to determine the extent of radiological contamination and presence of hazardous materials, to allow the preparation of an accurate cost estimate, and to plan for pre-demolition cleanup work to support building isolation. The scope of services for the project included the following tasks: Records Review and Interviews; Site Reconnaissance; Radiological Survey; and Sampling and Analysis

The Bristol Radiology Report Assessment Tool (BRRAT): developing a workplace-based assessment tool for radiology reporting skills.

Science.gov (United States)

Wallis, A; Edey, A; Prothero, D; McCoubrie, P

2013-11-01

To review the development of a workplace-based assessment tool to assess the quality of written radiology reports and assess its reliability, feasibility, and validity. A comprehensive literature review and rigorous Delphi study enabled the development of the Bristol Radiology Report Assessment Tool (BRRAT), which consists of 19 questions and a global assessment score. Three assessors applied the assessment tool to 240 radiology reports provided by 24 radiology trainees. The reliability coefficient for the 19 questions was 0.79 and the equivalent coefficient for the global assessment scores was 0.67. Generalizability coefficients demonstrate that higher numbers of assessors and assessments are needed to reach acceptable levels of reliability for summative assessments due to assessor subjectivity. The study methodology gives good validity and strong foundation in best-practice. The assessment tool developed for radiology reporting is reliable and most suited to formative assessments. Copyright © 2013 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

Introduction to radiological performance assessment

International Nuclear Information System (INIS)

Moss, G.

1995-02-01

A radiological performance assessment is conducted to provide reasonable assurance that performance objectives for low-level radioactive waste (LLW) disposal will be met. Beginning in the early stages of development, a radiological performance assessment continues through the operational phase, and is instrumental in the postclosure of the facility. Fundamental differences exist in the regulation of commercial and defense LLW, but the radiological performance assessment process is essentially the same for both. The purpose of this document is to describe that process in a concise and straightforward manner. This document focuses on radiological performance assessment as it pertains to commercial LLW disposal, but is applicable to US Department of Energy sites as well. Included are discussions on performance objectives, site characterization, and how a performance assessment is conducted. A case study is used to illustrate how the process works as a whole. A bibliography is provided to assist in locating additional information

Assessment of radiological and non-radiological hazards in the nuclear fuel cycle - The Indian experience

International Nuclear Information System (INIS)

Krishnamony, S.; Gopinath, D.V.

1996-01-01

Design and operational aspects of nuclear fuel cycle facilities have several features that distinguish them from nuclear power plants. These are related to (i) the nature of operations which are chiefly mining, metallurgical and chemical; (ii) the nature and type of radio-active materials handled, their specific activities and inventories; and (iii) the physical and chemical processes involved and the associated containment provisions. Generally the radioactive materials are present in an already highly dispersible or mobile form, in the form of solutions, slurries and powders, often associated with a wide variety of reactive and corrosive chemicals. There are further marked differences between the front-end and back-end of the fuel cycle. Whereas the front-end is characterized by the presence of large quantities of low specific activity naturally occurring radioactive materials, the back-end is characterized by high specific activities and concentrations of fission products and actinides. Radioactive characteristics of waste arisings are also different in different phases of the nuclear fuel cycle. Potential for internal exposure in the occupational environment is another distinguishing feature as compared with the more common designs of nuclear power reactors. Potential for accidents, their phenomenology and the resulting consequences are also markedly different in fuel cycle operations. The non-radiological hazards in fuel cycle operations are also of significance, since the operations are mostly mining, metallurgical and chemical in nature. These aspects are examined and evaluated in this paper, based on the Indian experience. (author). 12 refs, 10 tabs

Radiological hazards of Narghile (hookah, shisha, goza) smoking: activity concentrations and dose assessment

Energy Technology Data Exchange (ETDEWEB)

Khater, Ashraf E.M. [National Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo (Egypt); Physics Department, College of Sciences, King Saud University, P.O. Box 2455, 11451 Riyadh (Saudi Arabia)], E-mail: khater_ashraf@yahoo.com; Abd El-Aziz, Nawal S. [National Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo (Egypt); Al-Sewaidan, Hamed A. [Physics Department, College of Sciences, King Saud University, P.O. Box 2455, 11451 Riyadh (Saudi Arabia); Chaouachi, Kamal [DIU Tobaccology, University of Paris XI-XII (France)

2008-12-15

Narghile (hookah, shisha, goza, 'water-pipe') smoking has become fashionable worldwide. Its tobacco pastes, known as moassel and jurak, are not standardized and generally contain about 30-50% (sometimes more) tobacco, molasses/juice of sugarcane, various spices and dried fruits (particularly in jurak) and, in the case of moassel, glycerol and flavoring essences. Tobacco contains minute amounts of radiotoxic elements such as {sup 210}Pb, {sup 210}Po and uranium, which are inhaled via smoking. Only very few data have been published on the concentrations of natural radionuclides in narghile tobacco mixtures. Consequently, the aim of this study was to draw first conclusions on the potential hazards of radioactivity in moassel tobacco in relation to narghile smoking. The results indicate the existence of a wide range in the radioactivity contents where the average (range) activity concentrations of {sup 238}U, {sup 234}Th {sup 226}Ra, {sup 210}Pb, {sup 210}Po, {sup 232}Th and {sup 40}K, in Bq/kg dry weight were 55 (19-93), 11 (3-23), 3 (1.2-8), 14 (3-29), 13 (7-32), 7 (4-10) and 719 (437-1044) Bq/kg dry weight, respectively. The average concentrations of natural radionuclides in moassel tobacco pastes are comparable to their concentration in Greek cigarettes and tobacco leaves, and lower than that of Brazilian tobacco leaves. The distribution pattern of these radionuclides after smoking, between smoke, ash and filter, is unknown, except for {sup 210}Po during cigarette smoking and from one existing study during moassel smoking. Radiological dose assessment due to intake of natural radionuclides was calculated and the possible radio-toxicity of the measured radionuclides is briefly discussed.

Radiological optimization

International Nuclear Information System (INIS)

Zeevaert, T.

1998-01-01

Radiological optimization is one of the basic principles in each radiation-protection system and it is a basic requirement in the safety standards for radiation protection in the European Communities. The objectives of the research, performed in this field at the Belgian Nuclear Research Centre SCK-CEN, are: (1) to implement the ALARA principles in activities with radiological consequences; (2) to develop methodologies for optimization techniques in decision-aiding; (3) to optimize radiological assessment models by validation and intercomparison; (4) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (5) to develop methods and programmes to assist decision-makers during a nuclear emergency; (6) to support the policy of radioactive waste management authorities in the field of radiation protection; (7) to investigate existing software programmes in the domain of multi criteria analysis. The main achievements for 1997 are given

Radiological hazard indices and elemental composition of Brazilian and Swiss ornamental rocks

Energy Technology Data Exchange (ETDEWEB)

El Hajj, T.M. [Universidade Federal de Alfenas (UNIFAL), Pocos de Caldas, MG (Brazil); Silva, P.S.C.; Santos, A., E-mail: pscsilva@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Gandolla, M.P.A. [Universita della Svizzera Italiana (USI), Lugano (Switzerland); Dantas, G.A.S.A.; Delboni Junior, H. [Universidade de Sao Paulo (USP), SP (Brazil)

2017-09-01

The objective of this paper was to evaluate the radiological risk index of ornamental rocks sold both in Brazil and Europe and to correlate their radioactive content with their chemical composition. The {sup 238}U, {sup 232}Th and {sup 40}K mean values were 62 ± 65, 122 ± 111, 1126 ± 516 Bq kg{sup -1} for Brazilian and 93 ± 59, 70 ± 67 and 1005 ± 780 Bq kg{sup -1} for Swiss samples, respectively. The radiological index: radium equivalent, external hazard index, absorbed dose rate in air, annual gonadal equivalent dose, annual effective dose equivalent, and excess lifetime cancer risk for Brazilian and Swiss samples were calculated. The main contribution for the radiological indices observed was the radionuclide {sup 232}Th, which is associated with REE, Br, Hf, Na, Rb, Sb and Zr in the rock matrix. (author)

Transportation of Hazardous Materials Emergency Preparedness Hazards Assessment

Energy Technology Data Exchange (ETDEWEB)

Blanchard, A.

2000-02-28

This report documents the Emergency Preparedness Hazards Assessment (EPHA) for the Transportation of Hazardous Materials (THM) at the Department of Energy (DOE) Savannah River Site (SRS). This hazards assessment is intended to identify and analyze those transportation hazards significant enough to warrant consideration in the SRS Emergency Management Program.

Transportation of Hazardous Materials Emergency Preparedness Hazards Assessment

International Nuclear Information System (INIS)

Blanchard, A.

2000-01-01

This report documents the Emergency Preparedness Hazards Assessment (EPHA) for the Transportation of Hazardous Materials (THM) at the Department of Energy (DOE) Savannah River Site (SRS). This hazards assessment is intended to identify and analyze those transportation hazards significant enough to warrant consideration in the SRS Emergency Management Program

Transportation of hazardous materials emergency preparedness hazards assessment

International Nuclear Information System (INIS)

Blanchard, A.

2000-01-01

This report documents the Emergency Preparedness Hazards Assessment (EPHA) for the Transportation of Hazardous Materials (THM) at the Department of Energy (DOE) Savannah River Site (SRS). This hazards assessment is intended to identify and analyze those transportation hazards significant enough to warrant consideration in the SRS Emergency Management Program

Radiation protection during radiological examinations of children

International Nuclear Information System (INIS)

Claus, D.; Gillet, R.; Wambersie, A.

The dose delivered to children during radiological examinations were assessed and their variations compared with an experimental model. It is shown how to make good radiological examinations limiting the dose delivered to children and reducing the hazard to the medical staff [fr

Topographical mapping system for radiological and hazardous environments acceptance testing

International Nuclear Information System (INIS)

Armstrong, G.A.; Dochat, G.R.

1997-01-01

During the summer of 1996, the Topographical Mapping System (TMS) for hazardous and radiological environments and its accompanying three-dimensional (3-D) visualization tool, the Interactive Computer-Enhanced Remote-Viewing System (ICERVS), were delivered to Oak Ridge National Laboratory (ORNL). ORNL and Mechanical Technology, Inc., performed final acceptance testing of the TMS during the next eight months. The TMS was calibrated and characterized during this period. This paper covers the calibration, characterization, and acceptance testing of the TMS. Development of the TMS and ICERVS was initiated by the US Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs) at DOE sites across the country. DOE required a 3-D, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is the mapping of the interior of USTs as part of DOE's waste characterization and remediation efforts and to obtain baseline data on the content of the storage tank interiors as well as data on changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Washington site, the TMS is designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid, variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention

Topographical mapping system for radiological and hazardous environments acceptance testing

Science.gov (United States)

Armstrong, Gary A.; Dochat, G. R.

1997-09-01

During the summer of 1996, the topographical mapping system (TMS) for hazardous and radiological environments and its accompanying three-dimensional (3-D) visualization tool, the interactive computer-enhanced remote-viewing system (ICERVS), were delivered to Oak Ridge National Laboratory (ORNL). ORNL and Mechanical Technology, Inc., performed final acceptance testing of the TMS during the next eight months. The TMS was calibrated and characterized during this period. This paper covers the calibration, characterization, and acceptance testing of the TMS. Development of the TMS and the ICERVS was initiated by the U.S. Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs) at DOE sites across the country. DOE required a 3-D, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is the mapping of the interior of USTs as part of DOE's waste characterization and remediation efforts and to obtain baseline data on the content of the storage tank interiors as well as data on changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Washington site, the TMS is designed to be a self-contained, compact, reconfigurable system that is capable of providing rapid, variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention.

EVALUATING ROBOT TECHNOLOGIES AS TOOLS TO EXPLORE RADIOLOGICAL AND OTHER HAZARDOUS ENVIRONMENTS

International Nuclear Information System (INIS)

Curtis W. Nielsen; David I. Gertman; David J. Bruemmer; R. Scott Hartley; Miles C. Walton

2008-01-01

There is a general consensus that robots could be beneficial in performing tasks within hazardous radiological environments. Most control of robots in hazardous environments involves master-slave or teleoperation relationships between the human and the robot. While teleoperation-based solutions keep humans out of harms way, they also change the training requirements to accomplish a task. In this paper we present a research methodology that allowed scientists at Idaho National Laboratory to identify, develop, and prove a semi-autonomous robot solution for search and characterization tasks within a hazardous environment. Two experiments are summarized that validated the use of semi-autonomy and show that robot autonomy can help mitigate some of the performance differences between operators who have different levels of robot experience, and can improve performance over teleoperated systems

The radiological hazards of some radionuclides in Mariout and Brullus Lakes, Egypt

International Nuclear Information System (INIS)

Dar, M.A.; El Saharty, A.A.

2012-01-01

Mariout and Brullus were considered two of the highly fish productive lakes in Egypt as well as they widely used to drain huge quantities of industrial wastewater, sewage and agriculture drainage. Thousands of peoples inhabited the areas around the lakes and depend on them completely in their lives. The activities of 238 U, 232 Th and 40 K were measured in the upper most part of the surface sediments of the two lakes using gamma ray spectrophotometery. Brullus Lake recorded significantly higher 238 U and 232 Th and lower 40 K (17.22±2.49 Bq/kg, 10.0 ±56 Bq/kg and 299.7±17.78 Bq/kg) than Mariout Lake (12.65±1.53 Bq/kg, 7.24±0.76 Bq/kg and 518.75±46.24 Bq/kg respectively). Inversely, the mean average of absorbed dose rate (D), annual effective dose rate (mSvy -1 ), radium equivalent (Ra eq ), external hazard index (H ex ) and the representative level index (Iγr) were; 32.01 nGy/h, 0.04 mSv/y, 62.95 Bq/kg, 0.17 and 0.50 at Mariout Lake higher than those in Brullus lake (26.42 nGy/h, 0.03 mSv/y, 54.25 Bq/kg, 0.15 and 0.41) respectively. The recorded and calculated values were lower than the acceptable limits published in the different localities around the world. The activity distributions of the radiological hazards show the highest intensities in the western part of Mariout Lake and decreasing gradually eastward and north eastward affecting by the drainage agriculture water from Kabary Drain, Umum Drain, S.W. Basin and Nubaria Canal. At Brullus Lake, the radiological hazard intensities were concentrated in the west and southwest influenced by Zaglul Drain, Rosetta Drain, Brembal canal, Drain 11, Drain 9, Drain 8 and partially by Drain 1 while the lowest intensities were in the north and northeast affecting by the interaction with the Mediterranean Sea. K-40 recorded positive correlations and significant linear regression relationships with radiological hazard parameters at Mariout Like meaning that 40 K is the main gamma emitter in the lake, while the

New U.K. safety legislation and its effects on the control of radiological hazards

International Nuclear Information System (INIS)

Bell, B.H.J.; Luxon, S.G.

1977-01-01

This paper explains the objectives of the Health and Safety at Work etc Act 1974 and refers in particular to its effects on the control of hazards at nuclear installations and, more widely, on the control of radiological hazards generally. It deals also with the changes resulting from the setting up of the Health and Safety Commission and its Executive under the new Act, and the effects of these changes on the work of the Nuclear Installations Inspectorate. (auth.) [fr

Natural radioactivity (226Ra, 232Th and 40K) and assessment of radiological hazards in the Kestanbol granitoid, Turkey.

Science.gov (United States)

Canbaz, Buket; Cam, N Füsun; Yaprak, Günseli; Candan, Osman

2010-09-01

The surveys of natural gamma-emitting radionuclides in rocks and soils from the Ezine plutonic area were conducted during 2007. Direct dose measurement using a survey meter was carried out simultaneously. The present study, which is part of the survey, analysed the activity concentrations of (238)U, (232)Th and (40)K in granitoid samples from all over the region by HPGe gamma spectrometry. The activity concentrations of (226)Ra ranged from 94 to 637 Bq kg(-1), those of (232)Th ranged from 120 to 601 Bq kg(-1)and those of (40)K ranged from 1074 to 1527 Bq kg(-1) in the analysed rock samples from different parts of the pluton. To evaluate the radiological hazard of the natural radioactivity in the samples, the absorbed dose rate (D), the annual effective dose rate, the radium equivalent activity (Ra(eq)) and the external (H(ex)) hazard index were calculated according to the UNSCEAR 2000 report. The thorium-to-uranium concentration ratios were also estimated.

Offsite transportation hazards assessment

International Nuclear Information System (INIS)

Burnside, M.E.

1997-01-01

This report documents the emergency preparedness Hazards Assessment for the offsite transportation of hazardous material from the Hanford Site. The assessment is required by the US Department of Energy (DOE) Order 151.1. Offsite transportation accidents are categorized using the DOE system to assist communication within the DOE and assure that appropriate assistance is provided to the people in charge at the scene. The assistance will initially include information about the load and the potential hazards. Local authorities will use the information to protect the public following a transportation accident. This Hazards Assessment will focus on the material being transported from the Hanford Site. Shipments coming to Hanford are the responsibility of the shipper and the carrier and, therefore, are not included in this Hazards Assessment, unless the DOE elects to be the shipper of record

Estimation of possible radiological hazards from natural radioactivity in commercially-utilized ornamental and countertops granite tiles

International Nuclear Information System (INIS)

Turhan, Şeref

2012-01-01

Highlights: ► The study presents the activity concentrations of radionuclides in granite tile samples. ► The activity concentrations of radionuclides are measured by gamma spectrometer.. ► In this study, possible radiological hazards from usage of these materials are estimated. ► The external exposure index and internal index are calculated. ► The indoor absorbed gamma dose rate and the corresponding annual effective dose are evaluated. - Abstract: The aim of this study is to estimate natural radioactivity levels of commercially-utilized ornamental or countertops granite tiles collected from major retailers in Turkey and possible radiological hazards from usage of these materials by calculating external exposure and internal index, indoor absorbed gamma dose rate and the corresponding annual effective dose. The activity concentrations of 226 Ra, 232 Th and 40 K were determined for 42 kinds of different granite tiles using high-resolution gamma-ray spectrometer. The activity concentration of 226 Ra, 232 Th and 40 K varied from 9.2 to 192.5 Bq kg −1 (with a mean of 88.4 ± 6.9 Bq kg −1 ), 7.5 to 344.6 Bq kg −1 (with a mean of 95.3 ± 10.0 Bq kg −1 ) and 92.1 to 4155.9 Bq kg −1 (with a mean of 1055.2 ± 103.0 Bq kg −1 ), respectively. The estimated radiological hazard indices were revised in the light of the relevant national and international legislation and guidance. The values of the radiological hazard indices were found to be within relevant all limit values for superficial materials. The indoor absorbed gamma dose rates estimated from the activity concentrations of 226 Ra, 232 Th and 40 K and the corresponding annual effective doses varied from 4.74 to 85.27 nGy h −1 and 0.02 to 0.42 mSv, respectively.

Emergency radiological monitoring and analysis: Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

1995-01-01

The US Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. The FRERP authorizes the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC), which is established to coordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted State(s) and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division (M ampersand A) is responsible for coordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis, and quality assurance. To assure consistency, completeness, and the quality of the data produced, a methodology and procedures manual is being developed. This paper discusses the structure, assets, and operations of the FRMAC M ampersand A and the content and preparation of the manual

The DOE policy for protection against radiological and toxicological sabotage

International Nuclear Information System (INIS)

Hassell, C. Jr.; Callahan, S.; Myers, D.

1995-01-01

In response to a Department of Energy Office of Security Evaluations study on radiological and toxicological sabotage, the Under Secretary of Energy has directed that all departmental elements initiate analyses to determine the extent of radiological and toxicological sabotage threats within the department. To accomplish this, a plan was adopted whereby radioactive and other hazardous materials at DOE sites would be assessed by an interdisciplinary team as to quantities, ranked according to their hazards, subjected to a vulnerability assessment, and appropriate upgrades selected and monitored. This paper is a discussion of those efforts

Analysis and radiological assessment of survey results and samples from the beaches around Sellafield

International Nuclear Information System (INIS)

Webb, G.A.M.; Fry, F.A.

1983-12-01

After radioactive sea debris had been found on beaches near the BNFL, Sellafield, plant, NRPB was asked by the Department of the Environment to analyse some of the samples collected and to assess the radiological hazard to members of the public. A report is presented containing an analysis of survey reports for the period 19 November - 4 December 1983 and preliminary results of the analysis of all samples received, together with the Board's recommendations. (author)

A comparison of radiological risk assessment models: Risk assessment models used by the BEIR V Committee, UNSCEAR, ICRP, and EPA (for NESHAP)

International Nuclear Information System (INIS)

Wahl, L.E.

1994-03-01

Radiological risk assessments and resulting risk estimates have been developed by numerous national and international organizations, including the National Research Council's fifth Committee on the Biological Effects of Ionizing Radiations (BEIR V), the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), and the International Commission on Radiological Protection (ICRP). A fourth organization, the Environmental Protection Agency (EPA), has also performed a risk assessment as a basis for the National Emission Standards for Hazardous Air Pollutants (NESHAP). This paper compares the EPA's model of risk assessment with the models used by the BEIR V Committee, UNSCEAR, and ICRP. Comparison is made of the values chosen by each organization for several model parameters: populations used in studies and population transfer coefficients, dose-response curves and dose-rate effects, risk projection methods, and risk estimates. This comparison suggests that the EPA has based its risk assessment on outdated information and that the organization should consider adopting the method used by the BEIR V Committee, UNSCEAR, or ICRP

Radiological hazards of TENORM in precipitated calcium carbonate generated as waste at nitrophosphate fertilizer plant in Pakistan

Energy Technology Data Exchange (ETDEWEB)

Javied, Sabiha, E-mail: sabihajavied@yahoo.com [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Nilore 45650, Islamabad (Pakistan); Akhtar, Nasim [Nuclear Institute for Agriculture and Biology (NIAB), Jhang Road, Faisalabad (Pakistan); Tufail, M. [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Nilore 45650, Islamabad (Pakistan)

2011-08-15

Highlights: {yields} NORM (naturally occurring radioactive material) in phosphate rock (PR) is converted to TENORM (technologically enhanced naturally occurring radioactive material) as a result of chemical processing of the PR to make phosphate fertilizers. {yields} Precipitated calcium carbonate (PCC) is generated as process waste during nitrophosphate fertilizer production, which contains TENORM. {yields} Activity concentration of the radionuclide in the TENORM was measured using gamma spectrometry and radiological hazard was derived from the measured activities. {yields} Radiological pollution in the environment from TENORM in the PCC has been addressed. {yields} Restricted application of the PCC dose not pose a significant radiological hazard. -- Abstract: The NORM (naturally occurring radioactive material) in phosphate rock is transferred as TENORM (technologically enhanced naturally occurring radioactive material) to phosphatic fertilizers and to the waste generated by the chemical processes. The waste generated at the NP (nitrophosphate) fertilizer plant at Multan in Pakistan is PCC (precipitated calcium carbonate). Thirty samples of the PCC were collected from the heaps of the waste near the fertilizer plant. Activity concentrations of radionuclides in the waste samples were measured by using the technique of gamma ray spectrometry consisting of coaxial type HPGe (high purity germanium) detector coupled with a PC (personal computer) based MCA (multichannel analyzer) through a spectroscopy amplifier. Activity concentrations of {sup 226}Ra, {sup 232}Th and {sup 40}K in the waste samples were determined to be 273 {+-} 23 (173-398), 32 {+-} 4 (26-39) and 56 {+-} 5 (46-66) Bq kg{sup -1} respectively. The activity concentration of {sup 226}Ra in the PCC waste was found to be higher than that in naturally occurring calcium carbonate (limestone and marble) and in worldwide soil. Radiological hazard was estimated from indoor and outdoor exposure to gamma rays from

Seismic hazard assessment: Issues and alternatives

Science.gov (United States)

Wang, Z.

2011-01-01

Seismic hazard and risk are two very important concepts in engineering design and other policy considerations. Although seismic hazard and risk have often been used inter-changeably, they are fundamentally different. Furthermore, seismic risk is more important in engineering design and other policy considerations. Seismic hazard assessment is an effort by earth scientists to quantify seismic hazard and its associated uncertainty in time and space and to provide seismic hazard estimates for seismic risk assessment and other applications. Although seismic hazard assessment is more a scientific issue, it deserves special attention because of its significant implication to society. Two approaches, probabilistic seismic hazard analysis (PSHA) and deterministic seismic hazard analysis (DSHA), are commonly used for seismic hazard assessment. Although PSHA has been pro-claimed as the best approach for seismic hazard assessment, it is scientifically flawed (i.e., the physics and mathematics that PSHA is based on are not valid). Use of PSHA could lead to either unsafe or overly conservative engineering design or public policy, each of which has dire consequences to society. On the other hand, DSHA is a viable approach for seismic hazard assessment even though it has been labeled as unreliable. The biggest drawback of DSHA is that the temporal characteristics (i.e., earthquake frequency of occurrence and the associated uncertainty) are often neglected. An alternative, seismic hazard analysis (SHA), utilizes earthquake science and statistics directly and provides a seismic hazard estimate that can be readily used for seismic risk assessment and other applications. ?? 2010 Springer Basel AG.

Identification of Potential Hazard using Hazard Identification and Risk Assessment

Science.gov (United States)

Sari, R. M.; Syahputri, K.; Rizkya, I.; Siregar, I.

2017-03-01

This research was conducted in the paper production’s company. These Paper products will be used as a cigarette paper. Along in the production’s process, Company provides the machines and equipment that operated by workers. During the operations, all workers may potentially injured. It known as a potential hazard. Hazard identification and risk assessment is one part of a safety and health program in the stage of risk management. This is very important as part of efforts to prevent occupational injuries and diseases resulting from work. This research is experiencing a problem that is not the identification of potential hazards and risks that would be faced by workers during the running production process. The purpose of this study was to identify the potential hazards by using hazard identification and risk assessment methods. Risk assessment is done using severity criteria and the probability of an accident. According to the research there are 23 potential hazard that occurs with varying severity and probability. Then made the determination Risk Assessment Code (RAC) for each potential hazard, and gained 3 extreme risks, 10 high risks, 6 medium risks and 3 low risks. We have successfully identified potential hazard using RAC.

Methods for assessing the long term radiological consequences of radionuclide entry into groundwater

International Nuclear Information System (INIS)

Maul, P.R.

1983-01-01

The methods have been developed to model the transport of radionuclides in groundwater, based on an analytical approach to the governing transport equations, are sufficiently general to enable assessments to be made of the long term radiological significance of groundwater contamination for a range of possible problems. Although the methods are not as flexible as those based on numerical solutions of the transport equations, they have several advantages, including reduced computing time. The methods described can be used to identify critical parameters and assess the significance of data uncertainties in ground-water transport calculations. Such an analysis, combined with experimental measurements where necessary, can provide a sound basis for assessing potential radiation hazards. (U.K.)

TSD-DOSE : a radiological dose assessment model for treatment, storage, and disposal facilities

International Nuclear Information System (INIS)

Pfingston, M.

1998-01-01

In May 1991, the U.S. Department of Energy (DOE), Office of Waste Operations, issued a nationwide moratorium on shipping slightly radioactive mixed waste from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. Studies were subsequently conducted to evaluate the radiological impacts associated with DOE's prior shipments through DOE's authorized release process under DOE Order 5400.5. To support this endeavor, a radiological assessment computer code--TSD-DOSE (Version 1.1)--was developed and issued by DOE in 1997. The code was developed on the basis of detailed radiological assessments performed for eight commercial hazardous waste TSD facilities. It was designed to utilize waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste handling operations at a TSD facility. The code has since been released for use by DOE field offices and was recently used by DOE to evaluate the release of septic waste containing residual radioactive material to a TSD facility licensed under the Resource Conservation and Recovery Act. Revisions to the code were initiated in 1997 to incorporate comments received from users and to increase TSD-DOSE's capability, accuracy, and flexibility. These updates included incorporation of the method used to estimate external radiation doses from DOE's RESRAD model and expansion of the source term to include 85 radionuclides. In addition, a detailed verification and benchmarking analysis was performed

Radiological safety and risk assessment

International Nuclear Information System (INIS)

Hunter, P.H.; Barg, D.C.; Baird, R.D.; Card, D.H.; de Souza, F.; Elder, J.; Felthauser, K.; Jensen, C.; Winkler, V.

1982-02-01

A brief radiological safety and risk assessment of a nuclear power generation center with an adjacent on-site waste disposal facility at a specific site in the State of Utah is presented. The assessment was conducted to assist in determining the feasibility and practicality of developing a nuclear energy center (NEC) in Utah consisting of nine 1250 MWe nuclear pressurized water reactor (PWR) electrical generating units arranged in 3 clusters of 3 units each known as triads. The site selected for this conceptual study is in the Horse Bench area about 15 miles directly south of the town of Green River, Utah. The radiological issues included direct radiation exposures to on-site workers and the off-site population, release of radioactive material, and effects of these releases for both normal operations and accidental occurrences. The basic finding of this study is that the concept of an NEC in the Green River area, specifically at the Horse Bench site, is radiologically feasible

Assessment of radiological hazards of tin mining and ore processing in Jos, Nigeria

International Nuclear Information System (INIS)

Ibeanu, I.

1999-01-01

On the Jos Plateau were found uncontrolled tailing heaps generated from Tin Mining Activities. To assess the associated radiological hazards, an abandoned tailing dump ground was investigated with the residents as the critical population. The mean activity concentrations of 4 0K , 226 Ra and 232 Th in the 60 analyzed soil samples were 1251.7±478.4, 3867.5±1282.7 and 8301.9±2862.6 Bqkg -1 , respectively with a mean computed dose rate of 7.2±1.6 μGyh -1 . An annual mean outdoor effective dose of 8.9±0.9mSvy -1 was estimated. Also the activity concentrations of 40 K, 226 Ra and 232 Th in the 60 control soil samples were 447.0±68.0, 37.4±7.4 and 115.4±16.7 Bqkg -1 , respectively with a mean dose rate of 0.11±0.01 μGyh -1 . To account for the internal exposure, vegetables and root crops commonly grown and consumed in the area were assayed. Six varieties of vegetables and five varieties of root crops were analyzed. An internal annual mean effective dose of 148.98±8.14μSvy -1 was estimated. The verification of dose limit compliance for members of the public demands that: External Dose/Dose Limit + Intake (ingested)/ALI (ingestion) + Intake (inhaled)/ALI (inhalation) ≤ 1. Based on obtained data above, there is non-compliance with the dose limit, since the first term of the compliance formula is much greater than unity. There is therefore a need for an intervention to prevent radiation over exposure of the members of the public. The calculated cancer mortality risk for external and internal exposure scenarios for 226 Ra and 232 Th were (1.67±0.33) x 10 -6 (0.00017%) and (3.41±0.14) x 10 -6 (0.00034%), respectively. The 226 Ra radionuclide contributed about 96.09% of the risk in the external scenario with only 3.09% from the 232 Th while in the internal, the 226 Ra contributed only 70.38%. The combined external and internal (ingestion) risk is (5.08±0.36) x 10 -6 /year. (author)

Emergency radiological monitoring and analysis United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

1994-01-01

The United States Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. Following a major radiological incident the FRERP authorizes the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC). The FRMAC is established to coordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted states and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division is responsible for coordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis and quality assurance. This program includes: (1) Aerial Radiological Monitoring - Fixed Wing and Helicopter, (2) Field Monitoring and Sampling, (3) Radioanalysis - Mobile and Fixed Laboratories, (4) Radiation Detection Instrumentation - Calibration and Maintenance, (5) Environmental Dosimetry, and (6) An integrated program of Quality Assurance. To assure consistency, completeness and the quality of the data produced, a methodology and procedures handbook is being developed. This paper discusses the structure, assets and operations of FRMAC monitoring and analysis and the content and preparation of this handbook

Environmental Tools and Radiological Assessment

Science.gov (United States)

This presentation details two tools (SADA and FRAMES) available for use in environmental assessments of chemicals that can also be used for radiological assessments of the environment. Spatial Analysis and Decision Assistance (SADA) is a Windows freeware program that incorporate...

Assessment of natural radioactivity and associated radiological risks from tiles used in Kajang, Malaysia

Science.gov (United States)

Abdullahi, S.; Ismail, A. F.; Samat, S. B.; Yasir, M. S.

2018-04-01

The activity concentration and radiological risk of commonly used flooring materials (tiles) in Malaysia were studied. The natural radionuclide concentrations of 226Ra, 232Th and 40K were measured using high-purity germanium detector. The average concentration of 226Ra, 232Th and 40K in the samples were 65.75±1.1 Bq kg-1, 61.92±1.43 Bq kg-1 and 617.77±6.72 Bq kg-1 respectively. The mean concentration of radium equivalent activity, absorbed dose rate, external and internal hazard indices and annual effective dose equivalent were 195.21±2.88 Bq kg-1, 92.75±1.27 nGy h-1, 0.53±0.01, 0.7±0.01 and 0.44±0.0 mSv y-1 respectively. The aim was to assess the possible radiological risks attributed from the tile materials. Even though, the activity concentrations were higher than worldwide average values, but none of the radiological impact parameters exceeded the maximum recommended values. Hence, it was concluded that, contribution of tiles to radiation exposure is negligible and therefore, radiologically safe to use as building materials.

Radiological assessement of Crohn's disease

International Nuclear Information System (INIS)

Florio, F.; Palladino, M.; Stella, P.; Barbi, E.

1987-01-01

Fifty-eight consecutive cases of patients affected by Crohn's disease, with ileum (23/58), colon (10/58) and ileo-colic (25/58) involvement were studied. A good overall sensitivity was reached by the radiological procedures employed (barium meal, barium enema, enterclysis). Enterclysis is proposed as a second-step method for the study of ileum involvement, because it provides a quite precise assessement of disease stage and extent. Some criteria for a rational use of current radiological procedures in follow-up of both surgically and medically treated patients are proposed. Moreover it is suggested that better coordination of anatomo-radiological and clinical aspects could improve the therapeutic approach and prognostic judgement in such cases

Radiological assessment. A textbook on environmental dose analysis

Energy Technology Data Exchange (ETDEWEB)

Till, J.E.; Meyer, H.R. (eds.)

1983-09-01

Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides.

Radiological assessment. A textbook on environmental dose analysis

International Nuclear Information System (INIS)

Till, J.E.; Meyer, H.R.

1983-09-01

Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides

Radiological impact assessment to the environment due to waste from disposal of porcelain.

Science.gov (United States)

Morsi, Tarek; Hegazy, Rehab; Badawy, Wael

2017-06-01

The present study aimed to assess the radiological parameters from gamma rays due to the uncontrolled disposal of porcelain waste to the environment. Qualitative and quantitative identification of radionuclides in the investigated samples was carried out by means of a high-purity germanium (HPGe) detector. The average activity concentrations of the local porcelain samples were measured as 208.28 Bq/kg for 226 Ra, 125.73 Bq/kg for 238 U, 84.94 Bq/kg for 232 Th and 1033.61 Bq/kg for 40 K, respectively. The imported samples had an average activity of 240.57 Bq/kg for 226 Ra, 135.56 Bq/kg for 238 U, 115.74 Bq/kg for 232 Th and 1312.49 Bq/kg for 40 K, respectively. Radiological parameters and the radium equivalent Ra eq for the investigated samples were calculated. The external and internal hazard indices, representative level index (I γ ), alpha index (I α ), and the exemption level (I x ), were estimated to be higher than the recommended value (unity), while the average activity concentrations for the studied samples were higher than recommended levels. In conclusion, we are concerned that disposal of porcelain in the environment might be a significant hazard.

Dose assessment in radiological accidents

International Nuclear Information System (INIS)

Donkor, S.

2013-04-01

The applications of ionizing radiation bring many benefits to humankind, ranging from power generation to uses in medicine, industry and agriculture. Facilities that use radiation source require special care in the design and operation of equipment to prevent radiation injury to workers or to the public. Despite considerable development of radiation safety, radiation accidents do happen. The purpose of this study is therefore to discuss how to assess doses to people who will be exposed to a range of internal and external radiation sources in the event of radiological accidents. This will go a long way to complement their medical assessment thereby helping to plan their treatment. Three radiological accidents were reviewed to learn about the causes of those accidents and the recommendations that were put in place to prevent recurrence of such accidents. Various types of dose assessment methods were discussed.(au)

Radiological health assessment of natural radioactivity in the vicinity of Obajana cement factory, North Central Nigeria

Directory of Open Access Journals (Sweden)

Omoniyi Matthew Isinkaye

2015-01-01

Full Text Available Measurements of activity concentrations of natural radionuclides in and around Obajana cement factory, North Central Nigeria have been carried out in this study to determine the activity levels of natural radionuclides in different environmental matrices in order to assess the radiological health hazards associated with the use of these matrices by the local population. A low-background Pb-shielded gamma spectroscopic counting assembly utilizing NaI (Tl detector was employed for the measurements. The results show that sediment samples have the highest activity concentrations of all the radionuclides relative to soil, farmland soil, and rock samples. The radium equivalent activity and indoor gamma dose rates together with the corresponding annual effective indoor doses evaluated were found to be lower than their permissible limits. It suffices to say, that contrary to age-long fear of radiation risks to the population in the vicinity of the cement factory, no excessive radiological health hazards either indoors and/or outdoors is envisaged. Therefore, the environmental matrices around the factory could be used without any restrictions.

Federal Radiological Monitoring and Assessment Center: Phase I Response

International Nuclear Information System (INIS)

Riland, C.; Bowman, D.R.; Lambert, R.; Tighe, R.

1999-01-01

A Federal Radiological Monitoring and Assessment Center (FRMAC) is established in response to a Lead Federal Agency (LFA) or State request when a radiological emergency is anticipated or has occurred. The FRMAC coordinates the off-site monitoring, assessment, and analysis activities during such an emergency. The FRMAC response is divided into three phases. FRMAC Phase 1 is a rapid, initial-response capability that can interface with Federal or State officials and is designed for a quick response time and rapid radiological data collection and assessment. FRMAC Phase 1 products provide an initial characterization of the radiological situation and information on early health effects to officials responsible for making and implementing protective action decisions

Development of a technical guide for the identification of radiological sources of potential exposure and/or contamination

International Nuclear Information System (INIS)

Reyes, R.; Scott, A.; Falo, G.; Collins, J.; Szrom, F.; Collins, D.

1999-01-01

Radiological assessment of sites with radioactive residues starts with the identification of potential sources. The US Army Center for Health Promotion and Preventive Medicine (USACHPPM) has developed a technical guide that summarizes sources of potential radiological exposures of both civilian and military origin. These sources include those found in the natural environment, in the nuclear fuel cycle, in medical and industrial settings, in the transportation of radioactive materials, in US Army commodities and foreign materiel, and in the use and storage of nuclear weapons. This technical guide is intended to foster awareness of radiological hazards and to provide the reader with the knowledge necessary to take the first step in radiological health risk assessment: recognition of the hazard. Furthermore, this guide can be used in conjunction with other technical guides for performing radiological surveys and field dose assessments in war or peacetime operations. (author)

Development of mobile radiological assessment laboratory

International Nuclear Information System (INIS)

Pujari, R.N.; Saindane, Shashank S.; Jain, Amit; Parmar, Jayesh; Narsaiah, M.V.R.; Pote, M.B.; Murali, S.; Chaudhury, Probal

2018-01-01

During any emergency situations real-time radiation measurements and the fast analysis of the measured radiological data are of crucial importance. The newly developed mobile vehicle based laboratory known as 'Radiological Assessment Laboratory' (RAL) can be used for real time measurements in different radiation emergency scenarios, such as the release of radioactive materials from a radiological/nuclear incident, during search of an orphan source or during radioisotope transportation. RAL is equipped with several high sensitive detectors/systems such as NaI(Tl) gamma spectrometers, large size plastic scintillators and air-sampler, along with GPS and data transfer capability through GSM modem

Radiological risk assessment of a radioactively contaminated site

International Nuclear Information System (INIS)

Devgun, J.S.

1990-01-01

A limited-scope preliminary assessment of radiological risk has been conducted at a radioactively contaminated site under current site use conditions and based on the available preliminary radiological characterization data for the site. The assessment provides useful input to the remedial action planning for the site. 8 refs., 1 fig., 2 tabs

Teaching and Assessing Professionalism in Radiology Resident Education.

Science.gov (United States)

Kelly, Aine Marie; Gruppen, Larry D; Mullan, Patricia B

2017-05-01

Radiologists in teaching hospitals and in practices with residents rotating through are involved in the education of their residents. The Accreditation Council for Graduate Medical Education requires evidence that trainees are taught and demonstrate competency not only in medical knowledge and in patient care-the historic focus of radiology education-but also in the so-called non-interpretative core competencies, which include professionalism and interpersonal skills. In addition to accreditation agencies, the prominent assessment practices represented by the American Board of Radiology core and certifying examinations for trainees, as well as Maintenance of Certification for practitioners, are planning to feature more non-interpretative competency assessment, including professionalism to a greater extent. Because professionalism was incorporated as a required competency in medical education as a whole, more clarity about the justification and expected content for teaching about competence in professionalism, as well as greater understanding and evidence about appropriate and effective teaching and assessment methods, have emerged. This article summarizes justifications and expectations for teaching and assessing professionalism in radiology residents and best practices on how to teach and evaluate professionalism that can be used by busy radiology faculty in their everyday practice supervising radiology residents. Copyright © 2017 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

Plutonium Finishing Plant (PFP) hazards assessment

International Nuclear Information System (INIS)

Campbell, L.R.

1998-01-01

This report documents the hazards assessment for the Plutonium Finishing Plant (PFP) located on the US Department of Energy (DOE) Hanford Site. This hazards assessment was conducted to provide the emergency planning technical basis for the PFP. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification

Federal Radiological Monitoring and Assessment Center Phased Response Operations

International Nuclear Information System (INIS)

Riland, C.A.; Bowman, D.R.

1999-01-01

A Federal Radiological Monitoring and Assessment Center (FRMAC) is established in response to the Lead Federal Agency (LFA) or state request when a major radiological emergency is anticipated of has occurred. The FRMAC becomes a coalition of federal off-site monitoring and assessment activities to assist the LFA, state(s), local, and tribal authorities. State, local, and tribal authorities are invited to co-locate and prioritize monitoring and assessment efforts in the FRMAC. The Department of Energy is tasked by the Federal Radiological Emergency Response Plan to coordinate the FRMAC

Hazardous radiological waste-dental and environmental perspective

International Nuclear Information System (INIS)

Tripathi, Anurag

2014-01-01

Dental radiology is concerned with maxillo-facial radiological diagnostic procedure. It is meant for patient welfare and to generate diagnostically useful information, which can be utilized for patient welfare. If injudiciously used, it can become a source of harmful effluents and solid waste, which may pose risk to health and environment. Professionals of dental radiology should be aware about their responsibility to dispose such waste in the rightful manner to fulfil their medical pledge and ethics of doing no harm. (author)

Federal Radiological Monitoring and Assessment Center Overview of FRMAC Operations

International Nuclear Information System (INIS)

1998-01-01

In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response Plan. This cooperative effort will ensure that all federal radiological assistance fully supports their efforts to protect the public. the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of Federal Radiological Monitoring and Assessment Center (FRMAC) describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas

Accelerator driven systems from the radiological safety point of view

Indian Academy of Sciences (India)

application of the probabilistic safety analysis technique by assessing the probability and ... Technological and theoretical developments necessary for more precise .... Monte Carlo-based) to enable quick estimation of radiological hazards.

Predictions of models for environmental radiological assessment

International Nuclear Information System (INIS)

Peres, Sueli da Silva; Lauria, Dejanira da Costa; Mahler, Claudio Fernando

2011-01-01

In the field of environmental impact assessment, models are used for estimating source term, environmental dispersion and transfer of radionuclides, exposure pathway, radiation dose and the risk for human beings Although it is recognized that the specific information of local data are important to improve the quality of the dose assessment results, in fact obtaining it can be very difficult and expensive. Sources of uncertainties are numerous, among which we can cite: the subjectivity of modelers, exposure scenarios and pathways, used codes and general parameters. The various models available utilize different mathematical approaches with different complexities that can result in different predictions. Thus, for the same inputs different models can produce very different outputs. This paper presents briefly the main advances in the field of environmental radiological assessment that aim to improve the reliability of the models used in the assessment of environmental radiological impact. The intercomparison exercise of model supplied incompatible results for 137 Cs and 60 Co, enhancing the need for developing reference methodologies for environmental radiological assessment that allow to confront dose estimations in a common comparison base. The results of the intercomparison exercise are present briefly. (author)

Chemical Hazards and Safety Issues in Fusion Safety Design

International Nuclear Information System (INIS)

Cadwallader, L.C.

2003-01-01

Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard

222 S Laboratory complex hazards assessment

International Nuclear Information System (INIS)

Sutton, L.N.

1998-01-01

This report documents the hazards assessment for the 222-S Analytical Laboratory located on the US Department of Energy (DOE) Hanford Site. Operation of the laboratory is the responsibility of Waste Management Federal Services, Inc. (WMFS). This hazards assessment was conducted to provide the emergency planning technical basis for the 222-S Facility. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification

Portrayal of radiology in a major medical television series: How does it influence the perception of radiology among patients and radiology professionals?

International Nuclear Information System (INIS)

Heye, T.; Merkle, E.M.; Boll, D.T.; Leyendecker, J.R.; Gupta, R.T.

2016-01-01

To assess how the portrayal of Radiology on medical TV shows is perceived by patients and radiology professionals. In this IRB-approved study with patient consent waived, surveys were conducted among adult patients scheduled for radiological examinations and radiology professionals. The questionnaire investigated medical TV watching habits including interest in medical TV shows, appearance of radiological examination/staff, radiology's role in diagnosis-making, and rating of the shows' accuracy in portraying radiology relative to reality. One hundred and twenty-six patients and 240 professionals (133 technologists, 107 radiologists) participated. 63.5 % patients and 63.2 % technologists rated interest in medical TV shows ≥5 (scale 1-10) versus 38.3 % of radiologists. All groups noted regular (every 2nd/3rd show) to >1/show appearance of radiological examinations in 58.5-88.2 % compared to 21.0-46.2 % for radiological staff appearance. Radiology played a role in diagnosis-making regularly to >1/show in 45.3-52.6 %. There is a positive correlation for interest in medical TV and the perception that radiology is accurately portrayed for patients (r = 0.49; P = 0.001) and technologists (r = 0.38; P = 0.001) but not for radiologists (r = 0.01). The majority of patients perceive the portrayed content as accurate. Radiologists should be aware of this cultivation effect to understand their patients' behaviour which may create false expectations towards radiological examinations and potential safety hazards. (orig.)

Assessment of the radiological conditions in areas of Kuwait with residues of depleted uranium

International Nuclear Information System (INIS)

Cabianca, T.; Danesi, P.R.; Linsley, G.

2004-01-01

The 1991 Gulf War was the first conflict in which DU munitions were used extensively. After this conflict, questions arose regarding the possible link between exposure to ionizing radiation from DU and harmful biological effects. In view of these concerns, the Government of Kuwait, in February 2001, requested the IAEA to conduct an assessment to evaluate the possible radiological impact of residues of DU munitions from the 1991 Gulf War at 11 locations in Kuwait. For this purpose, the IAEA assembled a team of senior experts, who visited Kuwait in September 2001 to carry out a preliminary assessment of the sites and to evaluate the available information. In February 2002 scientists from the IAEA, the Spiez Laboratory (Switzerland), representing UNEP, and the Radiation Protection Department of the Ministry of Health of Kuwait, carried out a sampling campaign at these sites. Around 200 environmental samples, including soil, water and vegetation, were collected during the campaign and subsequently analysed. This study constitutes the first comprehensive radiological assessment of compliance with international radiation protection criteria and standards for areas with residues of DU munitions conducted under the auspices of the IAEA. The findings of this investigation indicate that DU does not pose a radiological hazard to the population of Kuwait. Annual radiation doses arising from exposure to DU residues would be of a few micro-sieverts, well below the annual doses from natural sources of radiation and far below the reference level recommended by the IAEA as a criterion to help establish whether remedial actions are necessary. DU penetrators can still be found at some of the locations visited. Prolonged skin contact with these residues is the only possible pathway that could result in exposures of radiological significance. As long as access to these areas remains restricted, the likelihood that members of the public could come into contact with these residues is low

Assessment of natural radioactivity and radiation hazard indices in different soil samples from Assiut governorate

International Nuclear Information System (INIS)

Issa, S.A.M.; Uosif, M.A.M.; Hefni, M.A.; El-Kamel, A.H; Nesreen, A.A.

2013-01-01

Natural radioactive materials under certain conditions can reach hazard radiological levels. So, it becomes necessary to study the natural radioactivity levels in soil to assess the dose for the population in order to know the health risks and to have a baseline for future changes in the environmental radioactivity due to human activities. Determine the radioactivity concentration of 226 Ra, 232 Th and 40 K in surface and 20 cm soil samples collected beside Assiut fertilizer plant, Assiut government in south Upper Egypt, to assess their contribution to the external dose exposure. The contents of natural radionuclides 226 Ra, 232 Th and 40 K were measured in investigated samples by using gamma spectrometry [NaI (Tl) 3”x 3”]. The total absorbed dose rate, annual effective dose rate, radium equivalent, excess lifetime cancer risk and the external hazard index, which resulted from the natural radionuclides in soil, were calculated

Assessment of LANL hazardous waste management documentation

International Nuclear Information System (INIS)

Davis, K.D.; Hoevemeyer, S.S.; Stirrup, T.S.; Jennrich, E.A.; Lund, D.M.

1991-04-01

The objective of this report is to present findings from evaluating the Los Alamos National Laboratory (LANL) ''Hazardous Waste Acceptance Criteria Receipt at TA-54, Area L'' to determine if it meets applicable DOE requirements. The guidelines and requirements for the establishment of a Hazardous Waste Acceptance Criteria (HW-WAC) are found in 40 CFR 260 to 270 and DOE Order 5820.2A. Neither set of requirements specifically require a WAC for the management of hazardous waste; however, the use of such documentation is logical and is consistent with the approach required for the management of radioactive waste. The primary purpose of a HW-WAC is to provide generators and waste management with established criteria that must be met before hazardous waste can be acceptable for treatment, storage and/or disposal. An annotated outline for a generic waste acceptance criteria was developed based on the requirements of 40 CFR 260 to 270 and DOE Order 5820.2A. The outline contains only requirements for hazardous waste, it does not address the radiological components of low-level mixed waste. The outline generated from the regulations was used for comparison to the LANL WAC For Chemical and Low-level Mixed Waste Receipt at TA-54, Area L. The major elements that should be addressed by a hazardous waste WAC were determined to be as follows: Waste Package/Container Requirements, Waste Forms, Land Disposal Restrictions, and Data Package-Certification ampersand Documentation

Radiological Worker II Training, Course 20301 (Live), Course 12909 (Test)

Energy Technology Data Exchange (ETDEWEB)

Harris, Jimmy D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-01-13

Radiological worker training is the basic building block for any additional radiological training you may receive. Upon completing radiological worker training, you will have the basic knowledge needed to work safely, using proper radiological practices, in areas where radiological hazards exist. You will also have a better understanding of the hazards and responsibilities associated with radiological work to help prevent the carelessness that can occur when working continually with or around radioactive material. This course does not qualify you for any specific radiological work. You may be required to take additional training at individual facilities to address facility- and job-specific hazards and procedures.

Conventional radiology: fixed installations in medical environment

International Nuclear Information System (INIS)

2010-01-01

This document presents the different procedures, the different types of specific hazards, the analysis of risks, their assessment and the preventive methods with regard to radioprotection in the case of fixed conventional radiology equipment in medical environment. It indicates and describes the concerned personnel, the course of procedures, the hazards, the identification of the risk associated with ionizing radiation, the risk assessment and the determination of exposure levels (definition of regulated areas, personnel categories), the strategy aimed at controlling the risk (risk reduction, technical measures concerning the installation or the personnel, teaching and information, prevention, incident), the different measures of medical monitoring, the assessment of risk control, and other risks. An appendix proposes an example of workstation assessment

Probabilistic seismic hazard assessment. Gentilly 2

International Nuclear Information System (INIS)

1996-03-01

Results of this probabilistic seismic hazard assessment were determined using a suite of conservative assumptions. The intent of this study was to perform a limited hazard assessment that incorporated a range of technically defensible input parameters. To best achieve this goal, input selected for the hazard assessment tended to be conservative with respect to selection of attenuation modes, and seismicity parameters. Seismic hazard estimates at Gentilly 2 were most affected by selection of the attenuation model. Alternative definitions of seismic source zones had a relatively small impact on seismic hazard. A St. Lawrence Rift model including a maximum magnitude of 7.2 m b in the zone containing the site had little effect on the hazard estimate relative to other seismic source zonation models. Mean annual probabilities of exceeding the design peak ground acceleration, and the design response spectrum for the Gentilly 2 site were computed to lie in the range of 0.001 to 0.0001. This hazard result falls well within the range determined to be acceptable for nuclear reactor sites located throughout the eastern United States. (author) 34 refs., 6 tabs., 28 figs

Documentation of in-training assessment for radiology trainees

International Nuclear Information System (INIS)

Long, Gillian

2001-01-01

AIM: To determine if the assessment of radiology trainees can be improved by modifying the in-training assessment form issued by the Royal College of Radiologists (RCR). MATERIALS AND METHODS: A qualitative study comparing the RCR assessment form with other alternative forms in use in the U.K. Individual semi-structured interviews were conducted with trainees (21) and trainers (18) in Sheffield to collect their views on the RCR form and an alternative form introduced on the North Trent Training Scheme. A postal questionnaire was sent to Heads of Training (24) to find out what assessment forms were in use at other centres and collect their views on the different forms. RESULTS: Trainees and trainers in Sheffield were virtually unanimous in their support of the new North Trent assessment form. The main advantages perceived were the encouragement of appraisal, setting of objectives and feedback from the trainees. Six other radiology training centres were using alternative assessment forms and all believed their forms had advantages over the RCR in-training assessment form. CONCLUSION: The results of this study suggest that the assessment process for radiology trainees can be improved by modifications to the RCR in-training assessment form and allows various recommendations to be made. Long, G. (2001)

Federal Radiological Monitoring and Assessment Center Analytical Response

International Nuclear Information System (INIS)

Nielsen, E.C.

2003-01-01

The Federal Radiological Monitoring and Assessment Center (FR-MAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local government s, in the event of a major radiological emergency in the United States. The FR-MAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant FR-om the incident, which will increase sample management challenges. This paper addresses emergency radioanalytical capability and capacity and its utilization during FR-MAC operations

The Volcanic Hazards Assessment Support System for the Online Hazard Assessment and Risk Mitigation of Quaternary Volcanoes in the World

Directory of Open Access Journals (Sweden)

Shinji Takarada

2017-12-01

Full Text Available Volcanic hazards assessment tools are essential for risk mitigation of volcanic activities. A number of offline volcanic hazard assessment tools have been provided, but in most cases, they require relatively complex installation procedure and usage. This situation causes limited usage of volcanic hazard assessment tools among volcanologists and volcanic hazards communities. In addition, volcanic eruption chronology and detailed database of each volcano in the world are essential key information for volcanic hazard assessment, but most of them are isolated and not connected to and with each other. The Volcanic Hazard Assessment Support System aims to implement a user-friendly, WebGIS-based, open-access online system for potential hazards assessment and risk-mitigation of Quaternary volcanoes in the world. The users can get up-to-date information such as eruption chronology and geophysical monitoring data of a specific volcano using the direct link system to major volcano databases on the system. Currently, the system provides 3 simple, powerful and notable deterministic modeling simulation codes of volcanic processes, such as Energy Cone, Titan2D and Tephra2. The system provides deterministic tools because probabilistic assessment tools are normally much more computationally demanding. By using the volcano hazard assessment system, the area that would be affected by volcanic eruptions in any location near the volcano can be estimated using numerical simulations. The system is being implemented using the ASTER Global DEM covering 2790 Quaternary volcanoes in the world. The system can be used to evaluate volcanic hazards and move this toward risk-potential by overlaying the estimated distribution of volcanic gravity flows or tephra falls on major roads, houses and evacuation areas using the GIS-enabled systems. The system is developed for all users in the world who need volcanic hazards assessment tools.

Multicentre Assessment of Radiology Request Form Completion in ...

African Journals Online (AJOL)

An important element in the multidisciplinary approach to patient management is communications among clinicians. As most of the patients attending any hospital have to go through the department of radiology, the pattern and attitude of clinicians to the completion of radiology request forms was assessed in three teaching ...

A probabilistic tsunami hazard assessment for Indonesia

Science.gov (United States)

Horspool, N.; Pranantyo, I.; Griffin, J.; Latief, H.; Natawidjaja, D. H.; Kongko, W.; Cipta, A.; Bustaman, B.; Anugrah, S. D.; Thio, H. K.

2014-11-01

Probabilistic hazard assessments are a fundamental tool for assessing the threats posed by hazards to communities and are important for underpinning evidence-based decision-making regarding risk mitigation activities. Indonesia has been the focus of intense tsunami risk mitigation efforts following the 2004 Indian Ocean tsunami, but this has been largely concentrated on the Sunda Arc with little attention to other tsunami prone areas of the country such as eastern Indonesia. We present the first nationally consistent probabilistic tsunami hazard assessment (PTHA) for Indonesia. This assessment produces time-independent forecasts of tsunami hazards at the coast using data from tsunami generated by local, regional and distant earthquake sources. The methodology is based on the established monte carlo approach to probabilistic seismic hazard assessment (PSHA) and has been adapted to tsunami. We account for sources of epistemic and aleatory uncertainty in the analysis through the use of logic trees and sampling probability density functions. For short return periods (100 years) the highest tsunami hazard is the west coast of Sumatra, south coast of Java and the north coast of Papua. For longer return periods (500-2500 years), the tsunami hazard is highest along the Sunda Arc, reflecting the larger maximum magnitudes. The annual probability of experiencing a tsunami with a height of > 0.5 m at the coast is greater than 10% for Sumatra, Java, the Sunda islands (Bali, Lombok, Flores, Sumba) and north Papua. The annual probability of experiencing a tsunami with a height of > 3.0 m, which would cause significant inundation and fatalities, is 1-10% in Sumatra, Java, Bali, Lombok and north Papua, and 0.1-1% for north Sulawesi, Seram and Flores. The results of this national-scale hazard assessment provide evidence for disaster managers to prioritise regions for risk mitigation activities and/or more detailed hazard or risk assessment.

A~probabilistic tsunami hazard assessment for Indonesia

Science.gov (United States)

Horspool, N.; Pranantyo, I.; Griffin, J.; Latief, H.; Natawidjaja, D. H.; Kongko, W.; Cipta, A.; Bustaman, B.; Anugrah, S. D.; Thio, H. K.

2014-05-01

Probabilistic hazard assessments are a fundamental tool for assessing the threats posed by hazards to communities and are important for underpinning evidence based decision making on risk mitigation activities. Indonesia has been the focus of intense tsunami risk mitigation efforts following the 2004 Indian Ocean Tsunami, but this has been largely concentrated on the Sunda Arc, with little attention to other tsunami prone areas of the country such as eastern Indonesia. We present the first nationally consistent Probabilistic Tsunami Hazard Assessment (PTHA) for Indonesia. This assessment produces time independent forecasts of tsunami hazard at the coast from tsunami generated by local, regional and distant earthquake sources. The methodology is based on the established monte-carlo approach to probabilistic seismic hazard assessment (PSHA) and has been adapted to tsunami. We account for sources of epistemic and aleatory uncertainty in the analysis through the use of logic trees and through sampling probability density functions. For short return periods (100 years) the highest tsunami hazard is the west coast of Sumatra, south coast of Java and the north coast of Papua. For longer return periods (500-2500 years), the tsunami hazard is highest along the Sunda Arc, reflecting larger maximum magnitudes along the Sunda Arc. The annual probability of experiencing a tsunami with a height at the coast of > 0.5 m is greater than 10% for Sumatra, Java, the Sunda Islands (Bali, Lombok, Flores, Sumba) and north Papua. The annual probability of experiencing a tsunami with a height of >3.0 m, which would cause significant inundation and fatalities, is 1-10% in Sumatra, Java, Bali, Lombok and north Papua, and 0.1-1% for north Sulawesi, Seram and Flores. The results of this national scale hazard assessment provide evidence for disaster managers to prioritise regions for risk mitigation activities and/or more detailed hazard or risk assessment.

Radioactivity, radiological risk and metal pollution assessment in marine sediments from Calabrian selected areas, southern Italy

Science.gov (United States)

Caridi, F.; Messina, M.; Faggio, G.; Santangelo, S.; Messina, G.; Belmusto, G.

2018-02-01

The two most significant categories of physical and chemical pollutants in sediments (radionuclides and metals) were investigated in this article, in order to evaluate pollution levels in marine sediments from eight different selected sites of the Calabria region, south of Italy. In particular samples were analyzed to determine natural and anthropic radioactivity and metal concentrations, in order to assess any possible radiological hazard, the level of contamination and the possible anthropogenic impact in the investigated area. Activity concentrations of 226Ra, 232Th, 40K and 137Cs were measured by High Purity Germanium (HPGe) gamma spectrometry. The obtained results show that, for radium (in secular equilibrium with uranium), the specific activity ranges from ( 14 ± 1) Bq/kg dry weight (d.w.) to ( 54 ± 9) Bq/kg d.w.; for thorium, from ( 12 ± 1) Bq/kg d.w. to ( 83 ± 8) Bq/kg d.w.; for potassium, from ( 470 ± 20) Bq/kg d.w. to ( 1000 ± 70) Bq/kg d.w. and for cesium it is lower than the minimum detectable activity value. The absorbed gamma dose rate in air (D), the annual effective dose equivalent (AEDE) outdoor and the external hazard index ( H_ex) were calculated to evaluate any possible radiological risk, mainly due to the use of marine sediments for the beach nourishment. The results show low levels of radioactivity, thus discarding any significant radiological risk. Some metals (As, Cd, Cr tot, Hg, Ni, Pb, Cu, Zn, Mn and Fe), that could be released into the environment by both natural and anthropogenic sources, were investigated through inductively coupled plasma mass spectrometry (ICP-MS) measurements and compared with the limits set by the Italian Legislation, to assess any possible contamination. Experimental results show that they are much lower than the contamination threshold value, thus excluding their presence as pollutants. The degree of sediment contaminations were quantified using enrichment factor ( EF) and geoaccumulation index ( I geo) for

Analysis of radioactive contaminations and radiological hazard in Poland after the Chernobyl reactor accident

International Nuclear Information System (INIS)

Zarnowiecki, K.

1988-01-01

It is a report on radiological impact in Poland following the Chernobyl reactor accident prepared in the Central Laboratory for Radiological Protection. The results of measurement and its analysis are presented. Isotopic composition of the contamined air and the concentration of radionuclides are determined. The trajectories of the airborne radioactive material movement from Chernobyl to Poland at the last days of April 1986 are presented. Assessment of the radiological risk of the population is done. 38 refs., 20 figs., 11 tabs. (M.F.W.)

Tank farms hazards assessment

International Nuclear Information System (INIS)

Broz, R.E.

1994-01-01

Hanford contractors are writing new facility specific emergency procedures in response to new and revised US Department of Energy (DOE) Orders on emergency preparedness. Emergency procedures are required for each Hanford facility that has the potential to exceed the criteria for the lowest level emergency, an Alert. The set includes: (1) a facility specific procedure on Recognition and Classification of Emergencies, (2) area procedures on Initial Emergency Response and, (3) an area procedure on Protective Action Guidance. The first steps in developing these procedures are to identify the hazards at each facility, identify the conditions that could release the hazardous material, and calculate the consequences of the releases. These steps are called a Hazards Assessment. The final product is a document that is similar in some respects to a Safety Analysis Report (SAR). The document could br produced in a month for a simple facility but could take much longer for a complex facility. Hanford has both types of facilities. A strategy has been adopted to permit completion of the first version of the new emergency procedures before all the facility hazards Assessments are complete. The procedures will initially be based on input from a task group for each facility. This strategy will but improved emergency procedures in place sooner and therefore enhance Hanford emergency preparedness. The purpose of this document is to summarize the applicable information contained within the Waste Tank Facility ''Interim Safety Basis Document, WHC-SD-WM-ISB-001'' as a resource, since the SARs covering Waste Tank Operations are not current in all cases. This hazards assessment serves to collect, organize, document and present the information utilized during the determination process

INTERNAL HAZARDS ANALYSIS FOR LICENSE APPLICATION

Energy Technology Data Exchange (ETDEWEB)

R.J. Garrett

2005-02-17

The purpose of this internal hazards analysis is to identify and document the internal hazards and potential initiating events associated with preclosure operations of the repository at Yucca Mountain. Internal hazards are those hazards presented by the operation of the facility and by its associated processes that can potentially lead to a radioactive release or cause a radiological hazard. In contrast to external hazards, internal hazards do not involve natural phenomena and external man-made hazards. This internal hazards analysis was performed in support of the preclosure safety analysis and the License Application for the Yucca Mountain Project. The methodology for this analysis provides a systematic means to identify internal hazards and potential initiating events that may result in a radiological hazard or radiological release during the repository preclosure period. These hazards are documented in tables of potential internal hazards and potential initiating events (Section 6.6) for input to the repository event sequence categorization process. The results of this analysis will undergo further screening and analysis based on the criteria that apply to the performance of event sequence analyses for the repository preclosure period. The evolving design of the repository will be re-evaluated periodically to ensure that internal hazards that have not been previously evaluated are identified.

INTERNAL HAZARDS ANALYSIS FOR LICENSE APPLICATION

International Nuclear Information System (INIS)

Garrett, R.J.

2005-01-01

The purpose of this internal hazards analysis is to identify and document the internal hazards and potential initiating events associated with preclosure operations of the repository at Yucca Mountain. Internal hazards are those hazards presented by the operation of the facility and by its associated processes that can potentially lead to a radioactive release or cause a radiological hazard. In contrast to external hazards, internal hazards do not involve natural phenomena and external man-made hazards. This internal hazards analysis was performed in support of the preclosure safety analysis and the License Application for the Yucca Mountain Project. The methodology for this analysis provides a systematic means to identify internal hazards and potential initiating events that may result in a radiological hazard or radiological release during the repository preclosure period. These hazards are documented in tables of potential internal hazards and potential initiating events (Section 6.6) for input to the repository event sequence categorization process. The results of this analysis will undergo further screening and analysis based on the criteria that apply to the performance of event sequence analyses for the repository preclosure period. The evolving design of the repository will be re-evaluated periodically to ensure that internal hazards that have not been previously evaluated are identified

Radiation Protection Research: Radiological Assessment

International Nuclear Information System (INIS)

Zeevaert, T.

2000-01-01

The objectives of SCK-CEN's research in the field of radiological impact assessment are (1) to elaborate and to improve methods and guidelines for the evaluation of restoration options for contaminated sites; (2) to develop, test and improve biosphere models for the performance assessment of radioactive waste disposal in near-surface or geological repositories; (3) to asses the impact of releases from nuclear or industrial installations. Main achievements in these areas for 2000 are summarised

PUREX facility hazards assessment

International Nuclear Information System (INIS)

Sutton, L.N.

1994-01-01

This report documents the hazards assessment for the Plutonium Uranium Extraction Plant (PUREX) located on the US Department of Energy (DOE) Hanford Site. Operation of PUREX is the responsibility of Westinghouse Hanford Company (WHC). This hazards assessment was conducted to provide the emergency planning technical basis for PUREX. DOE Order 5500.3A requires an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification. In October of 1990, WHC was directed to place PUREX in standby. In December of 1992 the DOE Assistant Secretary for Environmental Restoration and Waste Management authorized the termination of PUREX and directed DOE-RL to proceed with shutdown planning and terminal clean out activities. Prior to this action, its mission was to reprocess irradiated fuels for the recovery of uranium and plutonium. The present mission is to establish a passively safe and environmentally secure configuration at the PUREX facility and to preserve that condition for 10 years. The ten year time frame represents the typical duration expended to define, authorize and initiate follow-on decommissioning and decontamination activities

Onsite transportation hazards assessment

International Nuclear Information System (INIS)

Burnside, M.E.

1998-01-01

This report documents the emergency preparedness Hazards Assessment for the onsite transportation of hazardous material at the Hanford Site. The assessment is required by US Department of Energy (DOE) Order 5500.3A and provides the technical basis for the emergency classification and response procedures. A distinction is made between onsite for the purpose of emergency preparedness and onsite for the purpose of applying US Department of Transportation (DOT) regulations. Onsite for the purpose of emergency preparedness is considered to be within the physical boundary of the entire Hanford Site. Onsite for the purpose of applying DOT regulations is north of the Wye Barricade

Assessment of radiological protection systems among diagnostic radiology facilities in North East India.

Science.gov (United States)

Singh, Thokchom Dewan; Jayaraman, T; Arunkumar Sharma, B

2017-03-01

This study aims to assess the adequacy level of radiological protection systems available in the diagnostic radiology facilities located in three capital cities of North East (NE) India. It further attempts to understand, using a multi-disciplinary approach, how the safety codes/standards in diagnostic radiology framed by the Atomic Energy Regulatory Board (AERB) and the International Atomic Energy Agency (IAEA) to achieve adequate radiological protection in facilities, have been perceived, conceptualized, and applied accordingly in these facilities. About 30 diagnostic radiology facilities were randomly selected from three capitals of states in NE India; namely Imphal (Manipur), Shillong (Meghalaya) and Guwahati (Assam). A semi-structured questionnaire developed based on a multi-disciplinary approach was used for this study. It was observed that radiological practices undertaken in these facilities were not exactly in line with safety codes/standards in diagnostic radiology of the AERB and the IAEA. About 50% of the facilities had registered/licensed x-ray equipment with the AERB. More than 80% of the workers did not use radiation protective devices, although these devices were available in the facilities. About 85% of facilities had no institutional risk management system. About 70% of the facilities did not carry out periodic quality assurance testing of their x-ray equipment or surveys of radiation leakage around the x-ray room, and did not display radiation safety indicators in the x-ray rooms. Workers in these facilities exhibited low risk perception about the risks associated with these practices. The majority of diagnostic radiology facilities in NE India did not comply with the radiological safety codes/standards framed by the AERB and IAEA. The study found inadequate levels of radiological protection systems in the majority of facilities. This study suggests a need to establish firm measures that comply with the radiological safety codes/standards of the

Federal Radiological Monitoring and Assessment Center. The analytical response

International Nuclear Information System (INIS)

Nielsen, E.C.

2005-01-01

The Federal Radiological Monitoring and Assessment Center (FRMAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local governments, in the event of a major radiological emergency in the United States. The FRMAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant from the incident, which will increase sample management challenges. Emergency radioanalytical capability and capacity and its utilization during FRMAC operations are discussed. (author)

The Coastal Hazard Wheel system for coastal multi-hazard assessment & management in a changing climate

DEFF Research Database (Denmark)

Appelquist, Lars Rosendahl; Halsnæs, Kirsten

2015-01-01

This paper presents the complete Coastal Hazard Wheel (CHW) system, developed for multi-hazard-assessment and multi-hazard-management of coastal areas worldwide under a changing climate. The system is designed as a low-tech tool that can be used in areas with limited data availability...... screening and management. The system is developed to assess the main coastal hazards in a single process and covers the hazards of ecosystem disruption, gradual inundation, salt water intrusion, erosion and flooding. The system was initially presented in 2012 and based on a range of test......-applications and feedback from coastal experts, the system has been further refined and developed into a complete hazard management tool. This paper therefore covers the coastal classification system used by the CHW, a standardized assessment procedure for implementation of multi-hazard-assessments, technical guidance...

Methodology for assessing the radiological impact on environment

International Nuclear Information System (INIS)

Zhang Yongxing

1988-01-01

During the 1940s, the early stages of nuclear programmes, the assessment of the radionuclides released to the environment was first initiated for the large nuclear facilities, with emphasis placed on environmental monitoring. The radiological assessment is a quantitative process of estimating the impact on human, resulting from the releases of the radionuclides to the environment. It is a multidisciplinary subject including identification of source terms, environmental transport and dispersion, health effect evaluation and so on. This paper briefly, but comprehensively, describes the methodology for the assessment of the environmental radiological consequence, and discusses the trend of various research fields related to the subject

Uncertainty on shallow landslide hazard assessment: from field data to hazard mapping

Science.gov (United States)

Trefolini, Emanuele; Tolo, Silvia; Patelli, Eduardo; Broggi, Matteo; Disperati, Leonardo; Le Tuan, Hai

2015-04-01

Shallow landsliding that involve Hillslope Deposits (HD), the surficial soil that cover the bedrock, is an important process of erosion, transport and deposition of sediment along hillslopes. Despite Shallow landslides generally mobilize relatively small volume of material, they represent the most hazardous factor in mountain regions due to their high velocity and the common absence of warning signs. Moreover, increasing urbanization and likely climate change make shallow landslides a source of widespread risk, therefore the interest of scientific community about this process grown in the last three decades. One of the main aims of research projects involved on this topic, is to perform robust shallow landslides hazard assessment for wide areas (regional assessment), in order to support sustainable spatial planning. Currently, three main methodologies may be implemented to assess regional shallow landslides hazard: expert evaluation, probabilistic (or data mining) methods and physical models based methods. The aim of this work is evaluate the uncertainty of shallow landslides hazard assessment based on physical models taking into account spatial variables such as: geotechnical and hydrogeologic parameters as well as hillslope morphometry. To achieve this goal a wide dataset of geotechnical properties (shear strength, permeability, depth and unit weight) of HD was gathered by integrating field survey, in situ and laboratory tests. This spatial database was collected from a study area of about 350 km2 including different bedrock lithotypes and geomorphological features. The uncertainty associated to each step of the hazard assessment process (e.g. field data collection, regionalization of site specific information and numerical modelling of hillslope stability) was carefully characterized. The most appropriate probability density function (PDF) was chosen for each numerical variable and we assessed the uncertainty propagation on HD strength parameters obtained by

Radiological Protection Criteria for the Safety of LILW Repository in Croatia

International Nuclear Information System (INIS)

Levanat, I.; Lokner, V.; Subasic, D.

2000-01-01

Preparations for a LILW repository development in Croatia, conducted by APO Hazardous Waste Management Agency, have reached a point where the first safety assessment of the prospective facility is being attempted. For evaluation of the calculated radiological impact in the assessed option of repository development, a set of radiological protection criteria should be included in the definition of the assessment context. The Croatian regulations do not explicitly require that the repository development be supported by such safety assessment process, and do not provide a specific set of radiological criteria intended for the repository assessment which would be suitable for the constrained optimization of protection. For the initial safety assessment iterations of the prospective repository, which will address long term performance of the facility for various design and other safety options, we propose to use relatively simple radiological protection criteria, consisting only of individual dose and risk constraints for the general population. The numerical values for these constraints are established in accordance with the recognized international recommendations and in compliance with all possibly relevant Croatian safety requirements. (author)

Radiology education. The evaluation and assessment of clinical competence

International Nuclear Information System (INIS)

Hibbert, Kathryn M.; Van Deven, Teresa; Chhem, Rethy K.; Nagasaki Univ.; Wang, Shih-chang; Royal Australian and New Zealand College of Radiologists, Sydney

2012-01-01

Third volume of a trilogy devoted to radiology education and improvement of medical imaging students' learning, teaching, and scholarship. Reviews the philosophies, theories, and principles that underpin assessment and evaluation in radiology education. Includes a series of rich case studies. Written by an international group of experienced educators and medical professionals. This book reviews the philosophies, theories, and principles that underpin assessment and evaluation in radiology education, highlighting emerging practices and work done in the field. The sometimes conflicting assessment and evaluation needs of accreditation bodies, academic programs, trainees, and patients are carefully considered. The final section of the book examines assessment and evaluation in practice, through the development of rich case studies reflecting the implementation of a variety of approaches. This is the third book in a trilogy devoted to the scholarship of radiology education and is the culmination of an important initiative to improve medical imaging students' learning, teaching, and scholarship by bringing together experienced educators and medical professionals. The previous two books focused on the culture and the learning organizations in which our future radiologists are educated and on the application of educational principles in the education of radiologists. Here, the trilogy comes full circle: attending to the assessment and evaluation of the education of its members has much to offer back to the learning of the organization.

A methodology for physically based rockfall hazard assessment

Directory of Open Access Journals (Sweden)

G. B. Crosta

2003-01-01

Full Text Available Rockfall hazard assessment is not simple to achieve in practice and sound, physically based assessment methodologies are still missing. The mobility of rockfalls implies a more difficult hazard definition with respect to other slope instabilities with minimal runout. Rockfall hazard assessment involves complex definitions for "occurrence probability" and "intensity". This paper is an attempt to evaluate rockfall hazard using the results of 3-D numerical modelling on a topography described by a DEM. Maps portraying the maximum frequency of passages, velocity and height of blocks at each model cell, are easily combined in a GIS in order to produce physically based rockfall hazard maps. Different methods are suggested and discussed for rockfall hazard mapping at a regional and local scale both along linear features or within exposed areas. An objective approach based on three-dimensional matrixes providing both a positional "Rockfall Hazard Index" and a "Rockfall Hazard Vector" is presented. The opportunity of combining different parameters in the 3-D matrixes has been evaluated to better express the relative increase in hazard. Furthermore, the sensitivity of the hazard index with respect to the included variables and their combinations is preliminarily discussed in order to constrain as objective as possible assessment criteria.

Federal Radiological Monitoring and Assessment Center (FRMAC) overview of FRMAC operations

International Nuclear Information System (INIS)

1996-02-01

In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response plan (FRERP). This cooperative effort will assure the designated Lead Federal Agency (LFA) and the state(s) that all federal radiological assistance fully supports their efforts to protect the public. The mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) Operations describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas. These off-site areas may include one or more affected states

Radiological impact assessment within the IAEA Arctic Assessment Project (IASAP)

DEFF Research Database (Denmark)

Scott, E.M.; Gurbutt, P.; Harmes, I.

1998-01-01

As part of the International Arctic Seas Assessment Project (IASAP) of IAEA, a working group was created to model the dispersal and transfer of radionuclides released from radioactive waste disposed of in the Kara Sea and bays of Novaya Zemlya and to assess the radiological impact. Existing models...

Implementing DOE guidance for hazards assessments at Rocky Flats Plant

International Nuclear Information System (INIS)

Zimmerman, G.A.

1993-01-01

Hazards Assessments are performed for a variety of activities and facilities at Rocky Flats Plant. Prior to 1991, there was no guidance for performing Hazards Assessments. Each organization that performed Hazards Assessments used its own methodology with no attempt at standardization. In 1991, DOE published guidelines for the performance of Hazards Assessments for Emergency Planning (DOE-EPG-5500.1, ''Guidance for a Hazards Assessment Methodology''). Subsequently, in 1992, DOE published a standard for the performance of Hazards Assessments (DOE-STD-1027-92, ''Hazard Categorization and Accident Analysis, Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports''). Although these documents are a step in the direction of standardization, there remains a great deal of interpretation and subjective implementation in the performance of Hazards Assessments. Rocky Flats Plant has initiated efforts to develop a uniform and standard process to be used for Hazards Assessments

IAEA Perspectives on Radiological Characterisation

International Nuclear Information System (INIS)

O'Sullivan, Patrick; Ljubenov, Vladan

2012-01-01

Requirements for characterization of radiological and other hazards in nuclear facilities are reflected in the IAEA Safety Standards. WS-R-5, Safety Requirements for Decommissioning of Facilities using Radioactive Material, includes a requirement that 'During the preparation of the final decommissioning plan, the extent and type of radioactive material (irradiated and contaminated structures and components) at the facility shall be determined by means of a detailed characterization survey and on the basis of records collected during the operational period'. The subsidiary Safety Guide WS-G-2.1, Decommissioning of Nuclear Power Plants and Research Reactors, further elaborates that 'A survey of radiological and non-radiological hazards provides an important input for the safety assessment and for implementing a safe approach during the work'. Although the characterisation requirements addressed in the Safety Standards relate primarily to the detailed survey activities undertaken following the shutdown of the facility, it is evident that radiological characterization is of relevance to all major phases of the lifetime of a nuclear facility, including: - the siting phase - baseline surveys are undertaken to determine background radiation levels; - the construction phase - construction materials are retained to support future calculations of radioactivity distributions; - the operational phase - surveys are done regularly, with additional surveys being required following incidents involving plant contamination; - the transition phase - detailed radiological surveys are required to support the development of the final decommissioning plan; and - the closure phase - a final survey of the site and any remaining structures will be needed to support an application for release of the site from regulatory control. In the case of facilities that are already shut down, the main purpose of radiological characterisation is to provide a reliable database of information on the

The Emergency Radiological Monitoring and Analysis Division of the United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

2000-01-01

The U.S. Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. The FRERP authorises the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC), which is established to co-ordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted States and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division is responsible for co-ordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis, and quality assurance. This program includes: 1. Aerial Radiological Monitoring - Fixed-Wing and Helicopter; 2. Field Monitoring and Sampling; 3. Radioanalysis - Mobile and Fixed Laboratories; 4. Radiation Detection Instrumentation - Calibration and Maintenance; 5. Environmental Dosimetry; 6. Integrated program of Quality Assurance. To assure consistency, completeness, and the quality of the data produced, a methodology and procedures manual is being developed. This paper discusses the structure, assets, and operations of the FRMAC Monitoring and Analysis Division and the content and preparation of the manual. (author)

Radiological Risk Assessment and Survey of Radioactive Contamination for Foodstuffs

International Nuclear Information System (INIS)

Lee, W.R.; Lee, C.W.; Choi, K.S.

2007-11-01

After the Chernobyl nuclear accident in 1986, a radiological dose assessment and a survey of a radioactive contamination for foodstuffs have been investigated by many countries such as EU, Japan, USA. In the case of Japan which is similar to our country for the imported regions of foodstuffs, there were some instances of the excess for regulation on the maximum permitted levels of radioactive contamination among some imported foodstuffs. Concerns about the radioactive contamination of foodstuffs are increased because of the recently special situation (Nuclear test of North Korea). The purpose of this study is a radiological dose assessment and a survey of a radioactive contamination for foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Analytical results of the collected samples are below MDA. In this project, the model of radiological dose assessment via the food chain was also developed and radiological dose assessment was conducted based on surveys results of a radioactive contamination for foodstuffs in the Korean open markets since 2002. The results of radiological dose assessment are far below international reference level. It shows that public radiation exposure via food chain is well controlled within the international guide level. However, the radioactive contamination research of imported foodstuffs should be continuous considering the special situation(nuclear test of North Korea). These results are used to manage the radioactive contamination of the imported foodstuffs and also amend the regulation on the maximum permitted levels of radioactive contamination of foodstuffs

Waste Encapsulation and Storage Facility (WESF) Hazards Assessment

International Nuclear Information System (INIS)

COVEY, L.I.

2000-01-01

This report documents the hazards assessment for the Waste Encapsulation and Storage Facility (WESF) located on the U.S. Department of Energy (DOE) Hanford Site. This hazards assessment was conducted to provide the emergency planning technical basis for WESF. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification

Soil depth profiles and radiological assessment of natural radionuclides in forest ecosystem

International Nuclear Information System (INIS)

Manigandan, P.K.; Chandar Shekar, B.

2017-01-01

We measured the distribution of three naturally occurring radionuclides, "2"3"8U, "2"3"2Th, and "4"0K, in soil samples collected from a rainforest in the Western Ghats of India. For each surface sample, we calculated average activity concentration, outdoor terrestrial γ dose rate, annual effective dose equivalent (AEDE), and radiation hazard index. The activity concentrations of surface samples were randomly distributed over space, but differed slightly with different soil depths. The concentration of "2"3"2Th and the average terrestrial γ dose rates were slightly higher than the world averages, so slightly high γ radiation appears to be a general characteristic of the Western Ghats. However, all radiological hazard indices were within the limits proposed by the International Commission on Radiological Protection. The results reported here indicate that, except for "2"3"2Th, the naturally occurring radionuclides in the forest soils of the Western Ghats were within the ranges specified by United Nations Scientific Committee on the Effects of Atomic Radiation for undisturbed virgin soils.

Soil depth profiles and radiological assessment of natural radionuclides in forest ecosystem

Energy Technology Data Exchange (ETDEWEB)

Manigandan, P.K. [Al Musanna College of Technology, Muscat (Oman); Chandar Shekar, B. [Bharathiar Univ., Coimbatore (India). Kongunadu Arts and Science College

2017-08-01

We measured the distribution of three naturally occurring radionuclides, {sup 238}U, {sup 232}Th, and {sup 40}K, in soil samples collected from a rainforest in the Western Ghats of India. For each surface sample, we calculated average activity concentration, outdoor terrestrial γ dose rate, annual effective dose equivalent (AEDE), and radiation hazard index. The activity concentrations of surface samples were randomly distributed over space, but differed slightly with different soil depths. The concentration of {sup 232}Th and the average terrestrial γ dose rates were slightly higher than the world averages, so slightly high γ radiation appears to be a general characteristic of the Western Ghats. However, all radiological hazard indices were within the limits proposed by the International Commission on Radiological Protection. The results reported here indicate that, except for {sup 232}Th, the naturally occurring radionuclides in the forest soils of the Western Ghats were within the ranges specified by United Nations Scientific Committee on the Effects of Atomic Radiation for undisturbed virgin soils.

Hazard waste risk assessment

International Nuclear Information System (INIS)

Hawley, K.A.; Napier, B.A.

1986-01-01

Pacific Northwest Laboratory continued to provide technical assistance to the Department of Energy (DOE) Office of Operational Safety (OOS) in the area of risk assessment for hazardous and radioactive-mixed waste management. The overall objective is to provide technical assistance to OOS in developing cost-effective risk assessment tools and strategies for bringing DOE facilities into compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA or Superfund) and the Resource Conservation and Recovery Act (RCRA). Major efforts during FY 1985 included (1) completing the modification of the Environmental Protection Agency (EPA) Hazard Ranking System (HRS) and developing training manuals and courses to assist in field office implementation of the modified Hazard Ranking System (mHRS); (2) initiating the development of a system for reviewing field office HRS/mHRS evaluations for appropriate use of data and appropriate application of the methodology; (3) initiating the development of a data base management system to maintain all field office HRS/mHRS scoring sheets and to support the master OOS environmental data base system; (4) developing implementation guidance for Phase I of the DOE CERCLA Program, Installation Assessment; (5) continuing to develop an objective, scientifically based methodology for DOE management to use in establishing priorities for conducting site assessments under Phase II of the DOE CERCLA Program, Confirmation; and (6) participating in developing the DOE response to EPA on the proposed listing of three sites on the National Priorities List

A probabilistic approach to Radiological Environmental Impact Assessment

International Nuclear Information System (INIS)

Avila, Rodolfo; Larsson, Carl-Magnus

2001-01-01

Since a radiological environmental impact assessment typically relies on limited data and poorly based extrapolation methods, point estimations, as implied by a deterministic approach, do not suffice. To be of practical use for risk management, it is necessary to quantify the uncertainty margins of the estimates as well. In this paper we discuss how to work out a probabilistic approach for dealing with uncertainties in assessments of the radiological risks to non-human biota of a radioactive contamination. Possible strategies for deriving the relevant probability distribution functions from available empirical data and theoretical knowledge are outlined

Workplace-based assessment in radiology-where to now?

Energy Technology Data Exchange (ETDEWEB)

Augustine, K. [Department of Radiology, Southmead Hospital, North Bristol NHS Trust, Bristol BS10 5NB (United Kingdom); McCoubrie, P., E-mail: paul.mccoubrie@nbt.nhs.u [Department of Radiology, Southmead Hospital, North Bristol NHS Trust, Bristol BS10 5NB (United Kingdom); Wilkinson, J.R. [Department of Cardiology, St Bartholomew' s Hospital, London (United Kingdom); McKnight, L. [Department of Radiology, Morriston Hospital, Swansea (United Kingdom)

2010-04-15

Assessment of doctors is in a state of flux. Traditional methods of assessment have been critically examined and found inherently limited. The wholesale shift towards outcome-orientated education in the last 10 years has led to the relatively rapid development of a radically different method of assessment. This method focuses on assessing what doctors do in everyday practice rather than written or practical simulations. Known collectively as 'workplace-based assessment' tools, these have been embraced in North America, whereas they have been more cautiously adopted in the UK. However, many of these assessment tools have not been rigorously studied and, moreover, few have been specifically developed for assessing radiologists. However, they are likely to be incorporated into radiology training in the near future. This paper critically analyses both the underpinning assumptions behind this method and the evidence behind existing tools, and looks at the work that is required to develop, adopt or adapt such tools for use in radiology.

Workplace-based assessment in radiology-where to now?

International Nuclear Information System (INIS)

Augustine, K.; McCoubrie, P.; Wilkinson, J.R.; McKnight, L.

2010-01-01

Assessment of doctors is in a state of flux. Traditional methods of assessment have been critically examined and found inherently limited. The wholesale shift towards outcome-orientated education in the last 10 years has led to the relatively rapid development of a radically different method of assessment. This method focuses on assessing what doctors do in everyday practice rather than written or practical simulations. Known collectively as 'workplace-based assessment' tools, these have been embraced in North America, whereas they have been more cautiously adopted in the UK. However, many of these assessment tools have not been rigorously studied and, moreover, few have been specifically developed for assessing radiologists. However, they are likely to be incorporated into radiology training in the near future. This paper critically analyses both the underpinning assumptions behind this method and the evidence behind existing tools, and looks at the work that is required to develop, adopt or adapt such tools for use in radiology.

Radiological assessment of radioactive contamination on private clothing

International Nuclear Information System (INIS)

Schartmann, F.; Thierfeldt, S.

2003-01-01

In the very rare, cases where private clothing of persons working in a nuclear installation are inadvertently contaminated and this contamination is not detected when leaving the facility, there may be radiological consequences for this person as well as for members of his or her family. The VGB (Technische Vereinigung der Grosskraftwerksbetreiber) in Germany has investigated in detail the spread of contamination in nuclear power plants. Part of this evaluation programme was a radiological analysis which has been carried out by Brenk Systemplanung GmbH (Aachen/Germany). The radiological analysis started with the definition of the source term. It is highly unlikely that activities of more than 5 kBq 60 Co could leave a plant undetected on the body or the clothes. Nevertheless activities up to 50 kBq and different nuclide vectors were regarded. It has been found that 60 Co is the most important contaminant. The radiological analysis focusses on two types of contamination: particles and surface contamination. The pathways by which such a contamination can lead to an exposure by external irradiation or by ingestion depend on the type of contamination and are analysed in detail. For example, a particle could be retained in pockets or other parts of clothing and may lead to prolonged external irradiation until the piece of clothing is washed. The analysis is performed on the basis of conservative to realistic assumptions. In conclusion, the analysis has shown that especially particle contamination needs to be focussed on. However, by the advanced detection equipment in German plants doses which may pose a health hazard can safely be excluded. (authors)

Development of a real-time radiological dose assessment system

Energy Technology Data Exchange (ETDEWEB)

Han, Moon Hee; Lee, Young Bok; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae; Choi, Young Gil

1997-07-01

A radiological dose assessment system named FADAS has been developed. This system is necessary to estimated the radiological consequences against a nuclear accident. Mass-consistent wind field module was adopted for the generation of wind field over the whole domain using the several measured wind data. Random-walk dispersion module is used for the calculation of the distribution of radionuclides in the atmosphere. And volume-equivalent numerical integration method has been developed for the assessment of external gamma exposure given from a randomly distributed radioactive materials and a dose data library has been made for rapid calculation. Field tracer experiments have been carried out for the purpose of analyzing the site-specific meteorological characteristics and increasing the accuracy of wind field generation and atmospheric dispersion module of FADAS. At first, field tracer experiment was carried out over flat terrain covered with rice fields using the gas samplers which were designed and manufactured by the staffs of KAERI. The sampled gas was analyzed using gas chromatograph. SODAR and airsonde were used to measure the upper wind. Korean emergency preparedness system CARE was integrated at Kori 4 nuclear power plants in 1995. One of the main functions of CARE is to estimate the radiological dose. The developed real-time dose assessment system FADAS was adopted in CARE as a tool for the radiological dose assessment. (author). 79 refs., 52 tabs., 94 figs.

Federal Radiological Monitoring and Assessment Center (FRMAC): Overview of FRMAC operations

International Nuclear Information System (INIS)

1993-09-01

The purpose of this Management Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) is to explain the federal preparation for a radiological accident and to describe the subsequent response activities which provide radiological monitoring and assessment outside the boundaries of the monitoring which support the radiological accident site. In the event of a radiological accident, federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the accident scene under the umbrella of the Federal Radiological Emergency Response Plan (FRERP). This cooperative effort will assure the state(s) and the Lead Federal Agency (LFA) that all federal technical assistance is fully supporting their efforts to protect the public and will provide these monitoring results in a working data center for immediate use by the state(s) and LFA decision makers. The federal agencies do not relinquish their statutory responsibilities. However, the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibility

283-E and 283-W hazards assessment

International Nuclear Information System (INIS)

Sutton, L.N.

1994-01-01

This report documents the hazards assessment for the 200 area water treatment plants 283-E and 283-W located on the US DOE Hanford Site. Operation of the water treatment plants is the responsibility of ICF Kaiser Hanford Company (ICF KH). This hazards assessment was conducted to provide emergency planning technical basis for the water treatment plants. This document represents an acceptable interpretation of the implementing guidance document for DOE ORDER 5500.3A which requires an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification

Assessment of the radiological impact of the transport of radioactive materials

International Nuclear Information System (INIS)

1986-12-01

In order to facilitate the assessment of the radiological impact of transport, and to guide the collection of data for future assessments, the IAEA convened a technical committee (The Technical Committee on the Assessment of the Radiological Impact from the Transport of Radioactive Materials; TC-556) in Vienna, Austria on 21-25 October 1985. The Terms of Reference called for this committee ''to collect and assess data on the radiation exposure of workers and the public during the transport of radioactive material, and to develop a summary statement, reflecting current practice and current state of knowledge, on the radiological impact of transport.'' This technical document provides the summary statement developed by TC-556. The statement should be viewed as an interim assessment since it utilized only data then available, or made available, to the committee. This document consists of three Sections: Section I - Background Information to the Summary Statement (prepared by the Secretariat); Section II - The Summary Statement on the Radiological Impact of the Transport of Radioactive Materials (developed by TC-556); and Section III - Recommendations for Future Assessments (a summary of statements and conclusions provided in the TC-556 Chairman's Report)

Radiological Impacts Assessment during Normal Decommissioning Operation for EU-APR

Energy Technology Data Exchange (ETDEWEB)

Hwang, Do Hyun; Lee, Keun Sung [KHNP CRI, Daejeon (Korea, Republic of); Lee, ChongHui [KEPCO Engineering and Construction, Gimcheon (Korea, Republic of)

2016-10-15

In this paper, radiological impacts on human beings during normal execution of the decommissioning operations from the current standard design of EU-APR which has been modified and improved from its original design of APR1400 to comply with EUR, are evaluated. Decommissioning is the final phase in the life cycle of a nuclear installation, covering all activities from shutdown and removal of fissile material to environmental restoration of the site. According to article 5.4 specified in chapter 2.20 of European Utility Requirements (EUR), all relevant radiological impacts on human being should be considered during the environmental assessment of decommissioning, including external exposure from direct radiation of plant and other radiation sources, and internal exposure due to inhalation and ingestion. In this paper, radiological impacts on human beings during normal circumstances of the decommissioning operation were evaluated from the current standard design of EU-APR based on the simple transport model and practical generic methodology for assessing the radiological impact provided by IAEA. The results of dose assessment fulfilled the dose limit for all scenarios.

Probabilistic tsunami hazard assessment for Point Lepreau Generating Station

Energy Technology Data Exchange (ETDEWEB)

Mullin, D., E-mail: dmullin@nbpower.com [New Brunswick Power Corporation, Point Lepreau Generating Station, Point Lepreau (Canada); Alcinov, T.; Roussel, P.; Lavine, A.; Arcos, M.E.M.; Hanson, K.; Youngs, R., E-mail: trajce.alcinov@amecfw.com, E-mail: patrick.roussel@amecfw.com [AMEC Foster Wheeler Environment & Infrastructure, Dartmouth, NS (Canada)

2015-07-01

In 2012 the Geological Survey of Canada published a preliminary probabilistic tsunami hazard assessment in Open File 7201 that presents the most up-to-date information on all potential tsunami sources in a probabilistic framework on a national level, thus providing the underlying basis for conducting site-specific tsunami hazard assessments. However, the assessment identified a poorly constrained hazard for the Atlantic Coastline and recommended further evaluation. As a result, NB Power has embarked on performing a Probabilistic Tsunami Hazard Assessment (PTHA) for Point Lepreau Generating Station. This paper provides the methodology and progress or hazard evaluation results for Point Lepreau G.S. (author)

Wind hazard assessment for Point Lepreau Generating Station

International Nuclear Information System (INIS)

Mullin, D.; Moland, M.; Sciaudone, J.C.; Twisdale, L.A.; Vickery, P.J.; Mizzen, D.R.

2015-01-01

In response to the CNSC Fukushima Action Plan, NB Power has embarked on a wind hazard assessment for the Point Lepreau Generating Station site that incorporates the latest up to date wind information and modeling. The objective was to provide characterization of the wind hazard from all potential sources and estimate wind-driven missile fragilities and wind pressure fragilities for various structures, systems and components that would provide input to a possible high wind Probabilistic Safety Assessment. The paper will discuss the overall methodology used to assess hazards related to tornadoes, hurricanes and straight-line winds, and site walk-down and hazard/fragility results. (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)

A Transparent Framework for guiding Radiological and Non-Radiological Contaminated Land Risk Assessments

International Nuclear Information System (INIS)

Lee, Alex; Mathers, Dan

2003-01-01

A framework is presented that may be used as a transparent guidance to both radiological and non-radiological risk assessments. This framework has been developed by BNFL, with external consultation, to provide a systematic approach for identifying key system drivers and to guide associated research packages in light of data deficiencies and sources of model uncertainty. The process presented represents an advance on existing working practices yet combines regulator philosophy to produce a robust, comprehensive, cost-effective and transparent work package. It aims at lending added confidence to risk models thereby adding value to the decision process

Endodontic radiology, practice, and knowledge of radiation biology, hazard, and protection among clinical dental students and interns

Directory of Open Access Journals (Sweden)

Joan Emien Enabulele

2015-01-01

Full Text Available Objective: To evaluate the practice and knowledge of endodontic radiology as well as assess the knowledge of radiation biology, hazard, and protection among clinical dental students and interns. Materials and Methods: Cross-sectional study of clinical dental students and interns at University of Benin and University of Benin Teaching hospital respectively. Data was collected using a questionnaire which covered practice and knowledge of endodontic radiography, knowledge of radiation biology, hazard, and protection. Data was analyzed using Statistical Package for Social Sciences (SPSS version 17.0. Result: Seventy participants were included in the study, 40% were final year students and 24.3% house officers. Majority (95.7% agreed that they exposed radiographs as part of endodontic treatment. Only 18.6% knew that the apices of teeth should be 3mm from the border of the X-ray film, while 24.3% knew that 3mm of periapical bone should be visible on X-ray. Less than half (31.4% knew that paralleling technique was the technique of choice for endodontic radiography and this was statistically Significant in relationship to the status of the of the respondents. A few (4.3% of the respondents had knowledge of new horizons in endodontic imaging. Half of the respondents knew that damage by X-rays is mainly due to formation of free radicals. The most frequently reported radiation hazards was reduced salivary flow, while the least reported was rampant caries. Most knew how to protect patients, themselves, and other persons while exposing radiographs. Conclusion: There is need for inclusion of endodontic radiography in the undergraduate curriculum to ensure proper and correct radiographs during endodontic procedure.

Advanced Manufacturing Processes Laboratory Building 878 hazards assessment document

Energy Technology Data Exchange (ETDEWEB)

Wood, C.; Thornton, W.; Swihart, A.; Gilman, T.

1994-07-01

The introduction of the hazards assessment process is to document the impact of the release of hazards at the Advanced Manufacturing Processes Laboratory (AMPL) that are significant enough to warrant consideration in Sandia National Laboratories` operational emergency management program. This hazards assessment is prepared in accordance with the Department of Energy Order 5500.3A requirement that facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment provides an analysis of the potential airborne release of chemicals associated with the operations and processes at the AMPL. This research and development laboratory develops advanced manufacturing technologies, practices, and unique equipment and provides the fabrication of prototype hardware to meet the needs of Sandia National Laboratories, Albuquerque, New Mexico (SNL/NM). The focus of the hazards assessment is the airborne release of materials because this requires the most rapid, coordinated emergency response on the part of the AMPL, SNL/NM, collocated facilities, and surrounding jurisdiction to protect workers, the public, and the environment.

Advanced Manufacturing Processes Laboratory Building 878 hazards assessment document

International Nuclear Information System (INIS)

Wood, C.; Thornton, W.; Swihart, A.; Gilman, T.

1994-07-01

The introduction of the hazards assessment process is to document the impact of the release of hazards at the Advanced Manufacturing Processes Laboratory (AMPL) that are significant enough to warrant consideration in Sandia National Laboratories' operational emergency management program. This hazards assessment is prepared in accordance with the Department of Energy Order 5500.3A requirement that facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment provides an analysis of the potential airborne release of chemicals associated with the operations and processes at the AMPL. This research and development laboratory develops advanced manufacturing technologies, practices, and unique equipment and provides the fabrication of prototype hardware to meet the needs of Sandia National Laboratories, Albuquerque, New Mexico (SNL/NM). The focus of the hazards assessment is the airborne release of materials because this requires the most rapid, coordinated emergency response on the part of the AMPL, SNL/NM, collocated facilities, and surrounding jurisdiction to protect workers, the public, and the environment

Methodology to assess the radiological sensitivity of soils: Application to Spanish soils

International Nuclear Information System (INIS)

Trueba Alonso, C.

2005-01-01

A methodology, based on standard physical and chemical soil properties, has been developed to estimate the radiological sensitivity of soils to a 137 C s and 90 S r contamination. In this framework, the soil radiological sensitivity is defined as the soil capability to mobilise or to retain these radionuclides. The purpose of this methodology is to assess, in terms of radiological sensitivity indexes, the behaviour of 137 C s and 90 S r in soils and their fluxes to man, considering two exposure pathways, the external irradiation exposure and the internal exposure from ingestion. The methodology is applied to the great variety of soil types found in Spain, where the soil profile is the reference unit for the assessment. The results for these soil types show, that their basic soil properties are the key to categorise the radiological sensitivity according to the risks considered. The final categorisation allows to identify soils specially sensible and improves the radiological impact assessment predictions. (Author)

Cursory radiological assessment: Battelle Columbus Laboratory Decommissioning and Decontamination Project

International Nuclear Information System (INIS)

Smith, W.H.; Munyon, W.J.; Mosho, G.D.; Robinet, M.J.; Wynveen, R.A.

1988-10-01

This document reports on the results obtained from a cursory radiological assessment of various properties at the Battelle Columbus Laboratory, Columbia, Ohio. The cursory radiological assessment is part of a preliminary investigation for the Battelle Columbus Laboratory Decommissioning and Decontamination Project. The radiological assessment of Battelle Columbus Laboratory's two sites included conducting interior and exterior building surveys and collecting and analyzing air, sewer system, and soil samples. Direct radiological surveys were made of floor, wall, and overhead areas. Smear surveys were made on various interior building surfaces as well as the exterior building vents. Air samples were collected in select areas to determine concentrations of Rn-222, Rn-220, and Rn-219 daughters, in addition to any long-lived radioactive particulates. Radon-222 concentrations were continuously monitored over a 24-hr period at several building locations using a radon gas monitoring system. The sanitary sewer systems at King Avenue, West Jefferson-North, and West Jefferson-South were each sampled at select locations. All samples were submitted to the Argonne Analytical Chemistry Laboratory for various radiological and chemical analyses. Environmental soil corings were taken at both the King Avenue and West Jefferson sites to investigate the potential for soil contamination within the first 12-inches below grade. Further subsurface investigations at the West Jefferson-North and West Jefferson-South areas were conducted using soil boring techniques. 4 refs., 10 figs., 10 tabs

FIRE HAZARDS ANALYSIS - BUSTED BUTTE

International Nuclear Information System (INIS)

Longwell, R.; Keifer, J.; Goodin, S.

2001-01-01

The purpose of this fire hazards analysis (FHA) is to assess the risk from fire within individual fire areas at the Busted Butte Test Facility and to ascertain whether the DOE fire safety objectives are met. The objective, identified in DOE Order 420.1, Section 4.2, is to establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: (1) The occurrence of a fire related event. (2) A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees. (3) Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards. (4) Property losses from a fire and related events exceeding limits established by DOE. Critical process controls and safety class systems being damaged as a result of a fire and related events

Probabilistic seismic hazard assessment of NW and central ...

Indian Academy of Sciences (India)

The Himalayan region has undergone significant development and to ensure safe and secure progress in such a seismically vulnerable region there is a need for hazard assessment. For seismic hazard assessment, it is important to assess the quality, consistency, and homogeneity of the seismicity data collected from ...

Exploration of resilience assessments for natural hazards

Science.gov (United States)

Lo Jacomo, Anna; Han, Dawei; Champneys, Alan

2017-04-01

The occurrence of extreme events due to natural hazards is difficult to predict. Extreme events are stochastic in nature, there is a lack of long term data on their occurrence, and there are still gaps in our understanding of their physical processes. This difficulty in prediction will be exacerbated by climate change and human activities. Yet traditional risk assessments measure risk as the probability of occurrence of a hazard, multiplied by the consequences of the hazard occurring, which ignores the recovery process. In light of the increasing concerns on disaster risks and the related system recovery, resilience assessments are being used as an approach which complements and builds on traditional risk assessments and management. In mechanical terms, resilience refers to the amount of energy per unit volume that a material can absorb while maintaining its ability to return to its original shape. Resilience was first applied in the fields of psychology and ecology, and more recently has been used in areas such as social sciences, economics, and engineering. A common metaphor for understanding resilience is the stability landscape. The landscape consists of a surface of interconnected basins, where each basin represents different states of a system, which is a point on the stability landscape. The resilience of the system is its capacity and tendency to remain within a particular basin. This depends on the topology of the landscape, on the system's current position, and on its reaction to different shocks and stresses. In practical terms, resilience assessments have been conducted for various purposes in different sectors. These assessments vary in their required inputs, the methodologies applied, and the output they produce. Some measures used for resilience assessments are hazard independent. These focus on the intrinsic capabilities of a system, for example the insurance coverage of a community, or the buffer capacity of a water storage reservoir. Other

Non-nuclear radiological emergencies. Special plan for radiological risk of the Valencian Community

International Nuclear Information System (INIS)

Rodríguez Rodrigo, I.; Piles Alepuz, I.; Peiró Juan, J.; Calvet Rodríguez, D.

2015-01-01

After the publication of the Radiological Hazard Basic Directive, Generalitat (the regional government in Valencian Community) initiated the edition of the pertinent Special Plan, with the objective to assemble the response of all the Security and Emergency Agencies, including the Armed Forces, in a radiological emergency affecting the territory of the Valencian Community, under a single hierarchy command. Being approved and homologated the Radiological Hazard Special Plan, Generalitat has undertaken the implementation process planned to finish in June 2015. Following the same process as other Plans, implementation is organized in a first informative stage, followed of a formative and training stage, and finishing with an activation exercise of the Plan. At the end of the process, is expected that every Agency will know their functions, the structure and organization in which the intervention takes place, the resources needed, and adapt their protocols to the Plan requirements. From the beginning, it has been essential working together with the Nuclear Safety Council, as is established in the agreement signed in order to collaborate in Planning, Preparedness and Response in Radiological Emergencies. [es

Decision Strategy: Radiological Evaluations: Air

International Nuclear Information System (INIS)

Sohier, A.

2000-01-01

The objectives of SCK-CEN's R and D programme on off-site emergency management are (1) to improve methods to assess in real time the radiological impact to the population and the environment during a nuclear emergency; (2) to support and advise the Belgian authorities on specific problems concerning existing and potential hazards from exposure to ionising radiation in normal and accidental conditions; (3) to organise training courses on off-site emergency response to nuclear accidents. Main achievements in 1999 are reported on

Supplemental Hazard Analysis and Risk Assessment - Hydrotreater

Energy Technology Data Exchange (ETDEWEB)

Lowry, Peter P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wagner, Katie A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-04-01

A supplemental hazard analysis was conducted and quantitative risk assessment performed in response to an independent review comment received by the Pacific Northwest National Laboratory (PNNL) from the U.S. Department of Energy Pacific Northwest Field Office (PNSO) against the Hydrotreater/Distillation Column Hazard Analysis Report issued in April 2013. The supplemental analysis used the hazardous conditions documented by the previous April 2013 report as a basis. The conditions were screened and grouped for the purpose of identifying whether additional prudent, practical hazard controls could be identified, using a quantitative risk evaluation to assess the adequacy of the controls and establish a lower level of concern for the likelihood of potential serious accidents. Calculations were performed to support conclusions where necessary.

Radio-ecological characterization and radiological assessment in support of regulatory supervision of legacy sites in northwest Russia

International Nuclear Information System (INIS)

Sneve, M.K.; Kiselev, M.; Shandala, N.K.

2014-01-01

The Norwegian Radiation Protection Authority has been implementing a regulatory cooperation program in the Russian Federation for over 10 years, as part of the Norwegian government's Plan of Action for enhancing nuclear and radiation safety in northwest Russia. The overall long-term objective has been the enhancement of safety culture and includes a special focus on regulatory supervision of nuclear legacy sites. The initial project outputs included appropriate regulatory threat assessments, to determine the hazardous situations and activities which are most in need of enhanced regulatory supervision. In turn, this has led to the development of new and updated norms and standards, and related regulatory procedures, necessary to address the often abnormal conditions at legacy sites. This paper presents the experience gained within the above program with regard to radio-ecological characterization of Sites of Temporary Storage for spent nuclear fuel and radioactive waste at Andreeva Bay and Gremikha in the Kola Peninsula in northwest Russia. Such characterization is necessary to support assessments of the current radiological situation and to support prospective assessments of its evolution. Both types of assessments contribute to regulatory supervision of the sites. Accordingly, they include assessments to support development of regulatory standards and guidance concerning: control of radiation exposures to workers during remediation operations; emergency preparedness and response; planned radionuclide releases to the environment; development of site restoration plans, and waste treatment and disposal. Examples of characterization work are presented which relate to terrestrial and marine environments at Andreeva Bay. The use of this data in assessments is illustrated by means of the visualization and assessment tool (DATAMAP) developed as part of the regulatory cooperation program, specifically to help control radiation exposure in operations and to support

42 CFR 482.26 - Condition of participation: Radiologic services.

Science.gov (United States)

2010-10-01

... radiologic services, particularly ionizing radiology procedures, must be free from hazards for patients and... qualified full-time, part-time, or consulting radiologist must supervise the ionizing radiology services and... osteopathy who is qualified by education and experience in radiology. (2) Only personnel designated as...

ZZ RADDECAY, Decay Data Library for Radiological Assessment

International Nuclear Information System (INIS)

2000-01-01

Description of program or function: - Format: special format defined in documentation. - Nuclides: 500 nuclides of interest in the nuclear fuel cycle, environmental problems, nuclear medicine, fusion reactor technology, and radiological protection assessment. - Origin: DLC-80/DRALIST. ZZ-RADDECAY is a data library of half-lives, radioactive daughter nuclides, probabilities per decay and decay product energies for alpha particles, positrons, electrons, X-rays, and gamma-rays. The current data base contains approximately 500 nuclides of interest in the nuclear fuel cycle, environmental problems, nuclear medicine, fusion reactor technology, and radiological protection assessment. RADIATION DECAY VERSION 2 March 1997: This application is being provided by Aptec as 'Freeware' with permission of the author Mr. Charles Hacker, Engineering and Applied Science, Griffith University, Australia

Federal Radiological Monitoring and Assessment Center (FRMAC), US response to major radiological accidents

International Nuclear Information System (INIS)

Mueller, P.G.

2000-01-01

radiological materials from: Nuclear Fuel Cycle Facilities, Space Craft Launches, Weapon (Department of Defence or DOE) Transportation, Weapon Production Facilities, Spacecraft Re-entry (domestic or foreign), Terrorist Incidents, High-Level Waste Transportation, Nuclear Power Plants. Key to the FRERP would be the establishment of the Federal Radiological Monitoring and Assessment Center (FRMAC). Development and implementation was assigned to DOE as the agency most capable of providing sufficient resources, assets, and support. In 1987, DOE subsequently assigned programmatic responsibility, with limited funding, to the Nevada Operations Office in Las Vegas, Nevada. (author)

A radiological dose assessment for the Port Hope conversion facility

International Nuclear Information System (INIS)

Garisto, N.C.; Cooper, F.; Janes, A.; Stager, R.; Peters, R.

2011-01-01

The Port Hope Conversion Facility (PHCF) receives uranium trioxide for conversion to uranium hexafluoride (UF 6 ) or uranium dioxide (UO 2 ). The PHCF Site has a long history of industrial use. A Radiological Dose Assessment was undertaken as part of a Site Wide Risk Assessment. This assessment took into account all possible human receptors, both workers and members of the public. This paper focuses on a radiological assessment of dose to members of the public. The doses to members of the public from terrestrial pathways were added to the doses from aquatic pathways to obtain overall dose to receptors. The benchmark used in the assessment is 1 mSv/y. The estimated doses related to PHCF operations are much lower than the dose limit. (author)

Use of the Hazard Prediction and Assessment Capability (HPAC) at the Savannah River Site

International Nuclear Information System (INIS)

BUCKLEY, ROBERT

2004-01-01

This report provides background information on the implementation of the Hazard Prediction and Assessment Capability (HPAC) software package at the Savannah River Site for atmospheric modeling. Developed by the Defense Threat Reduction Agency (DTRA), HPAC is actually a suite of models that allows for various modes of release of radiological, chemical and biological agents, generates interpolated meteorological data fields based on inputted meteorology, and transports the material using a tested transport and diffusion model. A discussion of meteorological data availability for direct use by HPAC is given, and is important for applications to emergency response. An evaluation of the data input methodology for a release from SRS is examined, as well as an application to the World Trade Center attacks in New York City in September 2001. Benefits of the newer versions of HPAC now in use are then discussed. These include access to more meteorological data sources and improved graphical cap abilities. The HPAC software package is another tool to help the Atmospheric Technologies Group (ATG) provide atmospheric transport and dispersion predictions in the event of hazardous atmospheric releases

Assessment of radiological properties of wastes from urban decontamination procedures

International Nuclear Information System (INIS)

Da Silva, D.N.G.; Guimarães, J.R.D.; Rochedo, E.R.R.; Rochedo, P.R.R.; De Luca, C.

2015-01-01

One important activity associated to urban areas contaminated from accidental releases to the atmosphere of nuclear power plants is the management of radioactive wastes generated from decontamination procedures. This include the collection, conditioning, packing, transport and temporary/final disposition. The final destination is defined usually through a political decision. Thus, transport of packed radioactive wastes shall depend on decisions not just under the scope of radiological protection issues. However, the simulations performed to assess doses for the public and decontamination workers allows the estimate of radiological aspects related to the waste generated and these characteristics may be included in a multi-criteria decision tool aiming to support, under the radiological protection point of view, the decision-making process on post-emergency procedures. Important information to decision makers are the type, amount and activity concentration of wastes. This work describes the procedures to be included in the urban area model to account for the assessment of qualitative and quantitative description of wastes. The results will allow the classification of different procedures according to predefined criteria that shall then feed the multi-criteria assessment tool, currently under development, considering basic radiological protection aspects of wastes generated by the different available cleanup procedures on typical tropical urban environments. (authors)

Decision Strategy: Radiological Evaluations: Air

Energy Technology Data Exchange (ETDEWEB)

Sohier, A

2000-07-01

The objectives of SCK-CEN's R and D programme on off-site emergency management are (1) to improve methods to assess in real time the radiological impact to the population and the environment during a nuclear emergency; (2) to support and advise the Belgian authorities on specific problems concerning existing and potential hazards from exposure to ionising radiation in normal and accidental conditions; (3) to organise training courses on off-site emergency response to nuclear accidents. Main achievements in 1999 are reported on.

Medical Ethics in Radiology

International Nuclear Information System (INIS)

Kim, Kyung Won; Park, Jae Hyung; Yoon, Soon Ho

2010-01-01

According to the recent developments in radiological techniques, the role of radiology in the clinical management of patients is ever increasing and in turn, so is the importance of radiology in patient management. Thus far, there have been few open discussions about medical ethics related to radiology in Korea. Hence, concern about medical ethics as an essential field of radiology should be part of an improved resident training program and patient management. The categories of medical ethics related with radiology are ethics in the radiological management of patient, the relationship of radiologists with other medical professionals or companies, the hazard level of radiation for patients and radiologists, quality assurance of image products and modalities, research ethics, and other ethics issues related to teleradiology and fusion imaging. In order to achieve the goal of respectful progress in radiology as well as minimizing any adverse reaction from other medical professions or society, we should establish a strong basis of medical ethics through the continuous concern and self education

Hazard assessment for Romania–Bulgaria crossborder region

International Nuclear Information System (INIS)

Solakov, Dimcho; Simeonova, Stela; Alexandrova, Irena; Trifonova, Petya; Ardeleanu, Luminita; Cioflan, Carmen

2014-01-01

Among the many kinds of natural and man-made disasters, earthquakes dominate with regard to their social and economical impact on the urban environment. Global seismic hazard and vulnerability to earthquakes are steadily increasing as urbanisation and development occupy more areas that are prone to effects of strong earthquakes. The assessment of the seismic hazard is particularly important, because it provides valuable information for seismic safety and disaster mitigation, and it supports decision making for the benefit of society. The main objective of this study is to assess the seismic hazard for Romania-Bulgaria cross-border region on the basis of integrated basic geo-datasets

Role of the Federal Radiological Monitoring and Assessment Center (FRMAC) following a radiological accident

International Nuclear Information System (INIS)

Doyle, J.F. III.

1986-01-01

The Federal Radiological Emergency Response Plan (FRERP) calls for the Department of Energy to establish a Federal Radiological Monitoring and Assessment Center (FRMAC) immediately following a major radiological accident to coordinate all federal off-site monitoring efforts in support of the State and the Cognizant Federal Agency (CFA) for the facility or material involved in the accident. Some accidents are potentailly very complex and may require hundreds of radiation specialists to ensure immediate protection of the public and workers in the area, and to identify priorities for the Environmental Protection Agency (EPA) long-term efforts once the immediate protective actions have been carried out. The FRMAC provides a working environment with today's high technology tools (i.e., communication, computers, management procedures, etc.) to assure that the State and CFA decision makers have the best possible information in a timely manner on which to act. The FRMAC planners also recognize an underlying responsibility to continuously document such operations in order to provide the State, the CFA, and the EPA the technical information they will require for long term assessments. In addition, it is fully recognized that information collected and actions taken by the FRMAC will be subjected to the same scrutiny as other parts of the accident and the overall response

Handling of overexposed persons in radiological emergencies

International Nuclear Information System (INIS)

Estrada, E.

2000-01-01

The purpose of this standard procedure of the criteria in case of radiological emergencies is to describe the standard procedures used to define an radiological accident in terms of the doses received, and to describe the medical procedures for diagnoses and treatment of health hazards caused by external and internal irradiation in radiological emergencies

A review of radiological hazards associated with tin by-product mineral processing industry in the SEATRAD centre member countries

International Nuclear Information System (INIS)

Udompornwirat, S.

1993-01-01

Radiological hazards associated with the tin by-product mineral processing industry has recently become an issue of concern in the SEATRAD Centre member countries namely, Indonesia, Malaysia and Thailand. The SEATRAD Centre, with the assistance of a United Nations Development Program consultant, carried out an investigation on radioactivity problems at twelve tin by-product mineral processing plants in Malaysia and Thailand. The investigation included a survey of external gamma radiation levels and dust sampling for internal dose estimation as well as characterising the potential sources of radiation exposure in the plants. This paper reviews the nature of the tin by-product mineral processing industry and the general levels of associated radiological hazards. In addition, data provided by the government organisations in the member countries are reviewed. Typical annual effective doses experienced by the industry's workers are estimated on the basis of existing information, and possible measures to reduce exposure are discussed. It is concluded that the estimated median effective dose experienced by the workers is about 18 to 19 mSv per annum. Maximum exposures may exceed 200 mSv per annum. The important exposure pathways are external gamma radiation and internal radiation arising through intake of radioactive dust. 5 refs., 2 tabs., 4 figs

Conceptual geoinformation model of natural hazards risk assessment

Science.gov (United States)

Kulygin, Valerii

2016-04-01

Natural hazards are the major threat to safe interactions between nature and society. The assessment of the natural hazards impacts and their consequences is important in spatial planning and resource management. Today there is a challenge to advance our understanding of how socio-economical and climate changes will affect the frequency and magnitude of hydro-meteorological hazards and associated risks. However, the impacts from different types of natural hazards on various marine and coastal economic activities are not of the same type. In this study, the conceptual geomodel of risk assessment is presented to highlight the differentiation by the type of economic activities in extreme events risk assessment. The marine and coastal ecosystems are considered as the objects of management, on the one hand, and as the place of natural hazards' origin, on the other hand. One of the key elements in describing of such systems is the spatial characterization of their components. Assessment of ecosystem state is based on ecosystem indicators (indexes). They are used to identify the changes in time. The scenario approach is utilized to account for the spatio-temporal dynamics and uncertainty factors. Two types of scenarios are considered: scenarios of using ecosystem services by economic activities and scenarios of extreme events and related hazards. The reported study was funded by RFBR, according to the research project No. 16-35-60043 mol_a_dk.

Assessing storm erosion hazards

NARCIS (Netherlands)

Ranasinghe, Ranasinghe W M R J B; Callaghan, D.; Ciavola, Paolo; Coco, Giovanni

2017-01-01

The storm erosion hazard on coasts is usually expressed as an erosion volume and/or associated episodic coastline retreat. The accurate assessment of present-day and future storm erosion volumes is a key task for coastal zone managers, planners and engineers. There are four main approaches that can

Application of improved topsis method to comprehensive assessment of radiological environmental quality

International Nuclear Information System (INIS)

Shi Dongsheng; Di Yuming; Zhou Chunlin

2007-01-01

TOPSIS is a method for multiobjective decision-making, which can be applied to comprehensive assessment of radiological environmental quality. This paper introduces the principle of TOPSIS method and sets up the model of improved TOPSIS method, discusses the application of improved TOPSIS method to comprehensive assessment of radiological environmental quality. This method sufficiently makes use of the information of the optimal matrix. Analysis of practical examples using MATLAB program shows that it is objectively reasonable and feasible to comprehensively assess radiological environmental quality by improved TOPSIS method. This paper also provides the result of optimum number of sites and compares it with optimal index method based on TOPSIS method and traditional method. (authors)

Flood hazard assessment in areas prone to flash flooding

Science.gov (United States)

Kvočka, Davor; Falconer, Roger A.; Bray, Michaela

2016-04-01

Contemporary climate projections suggest that there will be an increase in the occurrence of high-intensity rainfall events in the future. These precipitation extremes are usually the main cause for the emergence of extreme flooding, such as flash flooding. Flash floods are among the most unpredictable, violent and fatal natural hazards in the world. Furthermore, it is expected that flash flooding will occur even more frequently in the future due to more frequent development of extreme weather events, which will greatly increase the danger to people caused by flash flooding. This being the case, there will be a need for high resolution flood hazard maps in areas susceptible to flash flooding. This study investigates what type of flood hazard assessment methods should be used for assessing the flood hazard to people caused by flash flooding. Two different types of flood hazard assessment methods were tested: (i) a widely used method based on an empirical analysis, and (ii) a new, physically based and experimentally calibrated method. Two flash flood events were considered herein, namely: the 2004 Boscastle flash flood and the 2007 Železniki flash flood. The results obtained in this study suggest that in the areas susceptible to extreme flooding, the flood hazard assessment should be conducted using methods based on a mechanics-based analysis. In comparison to standard flood hazard assessment methods, these physically based methods: (i) take into account all of the physical forces, which act on a human body in floodwater, (ii) successfully adapt to abrupt changes in the flow regime, which often occur for flash flood events, and (iii) rapidly assess a flood hazard index in a relatively short period of time.

Application of the ICRP approach for radiological protection of the marine environment in generic impact assessments

Energy Technology Data Exchange (ETDEWEB)

Kliaus, Viktoryia [Republican Scientific-Practical Centre of Hygiene, Laboratory of Radiation Safety, Akademicheskaya str. 8, 220012, Minsk (Belarus); Telleria, Diego M. [IAEA-Assessment and Management of Environmental Releases Unit, Wagramer Strasse 5 - PO Box 100, A-1400, Vienna (Austria); Cabianca, Tiberio [Centre for Radiation, Chemical and Environmental Hazards, PHE, Chilton, Didcot, Oxfordshire OX11 0RQ (United Kingdom)

2014-07-01

This paper presents a way to use the ICRP approach for protection of the environment in generic assessments of the radiological impact of radioactive releases to the marine environment. Generic assessments of radiological impact to the environment are needed in certain circumstances, for example, when input data are limited or when the likely radiological consequences are expected to be not significant. Under these circumstances the effort in performing the assessment must be commensurate with the potential radiological consequences. The generic assessment described in this paper is a simple tool which provides reasonable and cautious results and is applicable to multiple exposure scenarios associated with the assessment of the radiological impact of releases to the marine the environment. This generic assessment can be also used to provide preliminary results which, when compared to radiological criteria, may determine the need of further specific assessments. The ICRP based its approach to protect the environment in the definition of a set of reference animals and plants and the use of related radiological criteria, in the form of derived consideration reference levels. The paper discusses selection and exposure conditions of the reference animals and plants, methods to estimate their doses and the use of the radiological criteria, for the purpose of a generic assessment. The IAEA is elaborating applications of these generic impact assessments presented in the paper to be included in international guidance under development. (authors)

Research progress of non-human species radiological impact and assessment

International Nuclear Information System (INIS)

Bai Xiaoping; Zhu Hao; Mao Yawei; Zheng Wei; Du Hongyan

2014-01-01

In recent years, with the development of radiological protection conception and the improvement of requirement about non-human species protection, much more attention has been paid gradually to biota radiation impact. Research and development of non-human species protection impact and its assessment at home and abroad are introduced, then RESRAD-BIOTA and ERICA which are comparatively mature codes in the world are compared and analyzed, at last some suggestions about research and assessment work of non-human species radiological impact in the future in China are provided. (authors)

Radiological protection criteria risk assessments for waste disposal options

International Nuclear Information System (INIS)

Hill, M.D.

1982-01-01

Radiological protection criteria for waste disposal options are currently being developed at the National Radiological Protection Board (NRPB), and, in parallel, methodologies to be used in assessing the radiological impact of these options are being evolved. The criteria and methodologies under development are intended to apply to all solid radioactive wastes, including the high-level waste arising from reprocessing of spent nuclear fuel (because this waste will be solidified prior to disposal) and gaseous or liquid wastes which have been converted to solid form. It is envisaged that the same criteria will be applied to all solid waste disposal options, including shallow land burial, emplacement on the ocean bed (sea dumping), geological disposal on land and sub-seabed disposal

Seismic hazard assessment in the Ibero-Maghreb region

Energy Technology Data Exchange (ETDEWEB)

Jimenez, M.J.; Garcia fernandez, M. [Consejo Superior de Investigaciones Cientifcas, Barcelona (Spain). Inst. of Earth Sciences; GSAHP Ibero-Maghreb Working Group

1999-12-01

The paper illustrates the contribution of the Ibero-Maghreb region to the global GSHAP (Global Seismic Hazard Assessment Program) map: for the first time, a map of regional hazard source zones is presented and agreement on a common procedure for hazard computation in the region has been achieved.

Emergency preparedness hazards assessment for selected 100 Area Bechtel Hanford, Inc. facilities

International Nuclear Information System (INIS)

1997-07-01

The emergency preparedness hazards assessment for Bechtel Hanford Inc. (BHI) facilities in the 100 Areas of the Hanford Site. The purpose of a hazards assessment is to identify the hazardous material at each facility, identify the conditions that could release the hazardous material, and calculate the consequences of the releases. The hazards assessment is the technical basis for the facility emergency plans and procedures. There are many other buildings and past- practice burial grounds, trenches, cribs, etc., in the 100 Areas that may contain hazardous materials. Undisturbed buried waste sites that are not near the Columbia River are outside the scope of emergency preparedness hazards assessments because there is no mechanism for acute release to the air or ground water. The sites near the Columbia River are considered in a separate flood hazards assessment. This hazards assessment includes only the near-term soil remediation projects that involve intrusive activities

Residual radioactivity investigation and radiological assessments for self-disposal of concrete waste in nuclear fuel processing facility

International Nuclear Information System (INIS)

Seol, Jeung Gun; Ryu, Jae Bong; Cho, Suk Ju; Yoo, Sung Hyun; Song, Jung Ho; Baek, Hoon; Kim, Seong Hwan; Shin, Jin Seong; Park, Hyun Kyoun

2007-01-01

In this study, domestic regulatory requirement was investigated for self-disposal of concrete waste from nuclear fuel processing facility. And after self-disposal as landfill or recycling/reuse, the exposure dose was evaluated by RESRAD Ver. 6.3 and RESRAD BUILD Ver. 3.3 computing code for radiological assessments of the general public. Derived clearance level by the result of assessments for the exposure dose of the general public is 0.1071Bq/g (3.5% enriched uranium) for landfill and 0.05515 Bq/cm 2 (5% enriched uranium) for recycling/reuse respectively. Also, residual radioactivity of concrete waste after decontamination was investigated in this study. The result of surface activity is 0.01Bq/cm 2 for emitter and the result of radionuclide analysis for taken concrete samples from surface of concrete waste is 0.0297Bq/g for concentration of 238 U, below 2w/o for enrichment of 235 U and 0.0089Bq/g for artificial contamination of 238 U respectively. Therefore, radiological hazard of concrete waste by self-disposal as landfill and recycling/reuse is below clearance level to comply with clearance criterion provided for Notice No. 2001-30 of the MOST and Korea Atomic Energy Act

Assessment of Safety Parameters for Radiological Explosion Based on Gaussian Dispersion Model

Energy Technology Data Exchange (ETDEWEB)

Pandey, Alok [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Yu, Hyungjoon; Kim, Hong Suk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-10-15

These sources if used with explosive (called RDD - radiological dispersion device), can cause dispersion of radioactive material resulting in public exposure and contamination of the environment. Radiological explosion devices are not weapons for the mass destruction like atom bombs, but can cause the death of few persons and contamination of large areas. The reduction of the threat of radiological weapon attack by terrorist groups causing dispersion of radioactive material is one of the priority tasks of the IAEA Nuclear Safety and Security Program.Emergency preparedness is an essential part for reducing and mitigating radiological weapon threat. Preliminary assessment of dispersion study followed by radiological explosion and its quantitative effect will be helpful for the emergency preparedness team for an early response. The effect of the radiological dispersion depends on various factors like radioisotope, its activity, physical form, amount of explosive used and meteorological factors at the time of an explosion. This study aim to determine the area affected by the radiological explosion as pre assessment to provide feedback to emergency management teams for handling and mitigation the situation after an explosion. Most practical scenarios of radiological explosion are considered with conservative approach for the assessment of the area under a threat for emergency handling and management purpose. Radioisotopes under weak security controls can be used for a radiological explosion to create terror and socioeconomic threat for the public. Prior assessment of radiological threats is helpful for emergency management teams to take prompt decision about evacuation of the affected area and other emergency handling actions. Comparable activities of Co-60 source used in radiotherapy and Sr-90 source of disused and orphaned RTGs with two different quantities of TNT were used for the scenario development of radiological explosion. In the Basic Safety Standard (BSS

Assessment of Safety Parameters for Radiological Explosion Based on Gaussian Dispersion Model

International Nuclear Information System (INIS)

Pandey, Alok; Yu, Hyungjoon; Kim, Hong Suk

2014-01-01

These sources if used with explosive (called RDD - radiological dispersion device), can cause dispersion of radioactive material resulting in public exposure and contamination of the environment. Radiological explosion devices are not weapons for the mass destruction like atom bombs, but can cause the death of few persons and contamination of large areas. The reduction of the threat of radiological weapon attack by terrorist groups causing dispersion of radioactive material is one of the priority tasks of the IAEA Nuclear Safety and Security Program.Emergency preparedness is an essential part for reducing and mitigating radiological weapon threat. Preliminary assessment of dispersion study followed by radiological explosion and its quantitative effect will be helpful for the emergency preparedness team for an early response. The effect of the radiological dispersion depends on various factors like radioisotope, its activity, physical form, amount of explosive used and meteorological factors at the time of an explosion. This study aim to determine the area affected by the radiological explosion as pre assessment to provide feedback to emergency management teams for handling and mitigation the situation after an explosion. Most practical scenarios of radiological explosion are considered with conservative approach for the assessment of the area under a threat for emergency handling and management purpose. Radioisotopes under weak security controls can be used for a radiological explosion to create terror and socioeconomic threat for the public. Prior assessment of radiological threats is helpful for emergency management teams to take prompt decision about evacuation of the affected area and other emergency handling actions. Comparable activities of Co-60 source used in radiotherapy and Sr-90 source of disused and orphaned RTGs with two different quantities of TNT were used for the scenario development of radiological explosion. In the Basic Safety Standard (BSS

Occupational exposures to uranium: processes, hazards, and regulations

International Nuclear Information System (INIS)

Stoetzel, G.A.; Fisher, D.R.; McCormack, W.D.; Hoenes, G.R.; Marks, S.; Moore, R.H.; Quilici, D.G.; Breitenstein, B.D.

1981-04-01

The United States Uranium Registry (USUR) was formed in 1978 to investigate potential hazards from occupational exposure to uranium and to assess the need for special health-related studies of uranium workers. This report provides a summary of Registry work done to date. The history of the uranium industry is outlined first, and the current commercial uranium industry (mining, milling, conversion, enrichment, and fuel fabrication) is described. This description includes information on basic processes and areas of greatest potential radiological exposure. In addition, inactive commercial facilities and other uranium operations are discussed. Regulation of the commercial production industry for uranium fuel is reported, including the historic development of regulations and the current regulatory agencies and procedures for each phase of the industry. A review of radiological health practices in the industry - facility monitoring, exposure control, exposure evaluation, and record-keeping - is presented. A discussion of the nonradiological hazards of the industry is provided, and the final section describes the tissue program developed as part of the Registry

Volcanic Hazard Assessments for Nuclear Installations: Methods and Examples in Site Evaluation

International Nuclear Information System (INIS)

2016-07-01

To provide guidance on the protection of nuclear installations against the effects of volcanoes, the IAEA published in 2012 IAEA Safety Standards Series No. SSG-21, Volcanic Hazards in Site Evaluation for Nuclear Installations. SSG-21 addresses hazards relating to volcanic phenomena, and provides recommendations and general guidance for evaluation of these hazards. Unlike seismic hazard assessments, models for volcanic hazard assessment have not undergone decades of review, evaluation and testing for suitability in evaluating hazards at proposed nuclear installations. Currently in volcanology, scientific developments and detailed methodologies to model volcanic phenomena are evolving rapidly.This publication provides information on detailed methodologies and examples in the application of volcanic hazard assessment to site evaluation for nuclear installations, thereby addressing the recommendations in SSG-21. Although SSG-21 develops a logical framework for conducting a volcanic hazard assessment, this publication demonstrates the practicability of evaluating the recommendations in SSG-21 through a systematic volcanic hazard assessment and examples from Member States. The results of this hazard assessment can be used to derive the appropriate design bases and operational considerations for specific nuclear installations

Radiological dose assessment of Department of Energy Pinellas Plant waste proposed for disposal at Laidlaw Environmental Services of South Carolina, Inc

International Nuclear Information System (INIS)

Socolof, M.L.; Lee, D.W.

1996-05-01

The U.S. Department of Energy (DOE) Pinellas Plant in Largo, FL is proposing to ship and dispose of hazardous sludge, listed as F006 waste, to the Laidlaw Environmental Services of South Carolina, Inc. (Laidlaw) treatment, storage, and disposal facility in Pinewood, South Carolina. This sludge contains radioactive tritium in concentrations of about 28 pCi/g. The objective of this study is to assess the possible radiological impact to workers at the Laidlaw facility and members of the public due to the handling, processing, and burial of the DOE waste containing tritium

Radiological dose assessment of Department of Energy Pinellas Plant waste proposed for disposal at Laidlaw Environmental Services of South Carolina, Inc.

Energy Technology Data Exchange (ETDEWEB)

Socolof, M.L.; Lee, D.W.

1996-05-01

The U.S. Department of Energy (DOE) Pinellas Plant in Largo, FL is proposing to ship and dispose of hazardous sludge, listed as F006 waste, to the Laidlaw Environmental Services of South Carolina, Inc. (Laidlaw) treatment, storage, and disposal facility in Pinewood, South Carolina. This sludge contains radioactive tritium in concentrations of about 28 pCi/g. The objective of this study is to assess the possible radiological impact to workers at the Laidlaw facility and members of the public due to the handling, processing, and burial of the DOE waste containing tritium.

User's guide to the radionuclide inventory and hazard code INVENT

International Nuclear Information System (INIS)

Nancarrow, D.J.; Thorne, M.C.

1986-05-01

This report constitutes the user's guide to the radionuclide inventory and hazard index code INVENT and provides an explanation of the mathematical basis of the code, the database used and operation of the code. INVENT was designed to facilitate the post-closure radiological assessment of land-based repositories for low and intermediate-level wastes. For those radionuclides identified to be of potential significance, it allows the calculation of time-dependent radionuclide activities, hazard indices for both inhalation and ingestion of activity, and photon spectra. (author)

Preliminary radiological assessments of low-level waste repositories

International Nuclear Information System (INIS)

Nancarrow, D.J.; Sumerling, T.J.; Ashton, J.

1988-06-01

Preliminary assessments of the post-closure radiological impact from the disposal of low-level radioactive wastes in shallow engineered facilities at four sites are presented. This provides a framework to practice and refine a methodology that could be used, on behalf of the Department, for independent assessment of any similar proposal from Nirex. Information and methodological improvements that would be required are identified. (author)

Radioactive Waste Management Complex low-level waste radiological performance assessment

Energy Technology Data Exchange (ETDEWEB)

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

Radioactive Waste Management Complex low-level waste radiological performance assessment

International Nuclear Information System (INIS)

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected

Landslides Hazard Assessment Using Different Approaches

Directory of Open Access Journals (Sweden)

Coman Cristina

2017-06-01

Full Text Available Romania represents one of Europe’s countries with high landslides occurrence frequency. Landslide hazard maps are designed by considering the interaction of several factors which, by their joint action may affect the equilibrium state of the natural slopes. The aim of this paper is landslides hazard assessment using the methodology provided by the Romanian national legislation and a very largely used statistical method. The final results of these two analyses are quantitative or semi-quantitative landslides hazard maps, created in geographic information system environment. The data base used for this purpose includes: geological and hydrogeological data, digital terrain model, hydrological data, land use, seismic action, anthropic action and an inventory of active landslides. The GIS landslides hazard models were built for the geographical area of the Iasi city, located in the north-east side of Romania.

Preliminary hazards analysis -- vitrification process

International Nuclear Information System (INIS)

Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P.

1994-06-01

This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility's construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment

Preliminary hazards analysis -- vitrification process

Energy Technology Data Exchange (ETDEWEB)

Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P. [Science Applications International Corp., Pleasanton, CA (United States)

1994-06-01

This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility`s construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment.

Seismic hazard assessment of the Hanford region, Eastern Washington State

International Nuclear Information System (INIS)

Youngs, R.R.; Coppersmith, K.J.; Power, M.S.; Swan, F.H. III

1985-01-01

A probabilistic seismic hazard assessment was made for a site within the Hanford region of eastern Washington state, which is characterized as an intraplate region having a relatively low rate of seismic activity. Probabilistic procedures, such as logic trees, were utilized to account for the uncertainties in identifying and characterizing the potential seismic sources in the region. Logic trees provide a convenient, flexible means of assessing the values and relative likelihoods of input parameters to the hazard model that may be dependent upon each other. Uncertainties accounted for in this way include the tectonic model, segmentation, capability, fault geometry, maximum earthquake magnitude, and earthquake recurrence rate. The computed hazard results are expressed as a distribution from which confidence levels are assessed. Analysis of the results show the contributions to the total hazard from various seismic sources and due to various earthquake magnitudes. In addition, the contributions of uncertainties in the various source parameters to the uncertainty in the computed hazard are assessed. For this study, the major contribution to uncertainty in the computed hazard are due to uncertainties in the applicable tectonic model and the earthquake recurrence rate. This analysis serves to illustrate some of the probabilistic tools that are available for conducting seismic hazard assessments and for analyzing the results of these studies. 5 references, 7 figures

Assessment of Chemical and Radiological Vulnerabilities

International Nuclear Information System (INIS)

SETH, S.S.

2000-01-01

Following the May 14, 1997 chemical explosion at Hanford's Plutonium Reclamation Facility, the Department of Energy Richland Operations Office and its prime contractor, Fluor Hanford, Inc., completed an extensive assessment to identify and address chemical and radiological safety vulnerabilities at all facilities under the Project Hanford Management Contract. This was a challenging undertaking because of the immense size of the problem, unique technical issues, and competing priorities. This paper focuses on the assessment process, including the criteria and methodology for data collection, evaluation, and risk-based scoring. It does not provide details on the facility-specific results and corrective actions, but discusses the approach taken to address the identified vulnerabilities

Radiological Assistance Program, DOE Region 6 response plan

International Nuclear Information System (INIS)

Jakubowski, F.M.

1993-02-01

This program plan meets all the requirements identified in DOE Order 5530.3, Radiological Assistance Program and supports those requirements leading to the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC) as required by DOE 5530-5. Requests for radiological assistance may come from other DOE facilities, Federal or state agencies, tribal officials, or from any private corporation or individual. Many of the requests will be handled by a telephone call, a conference or a letter, teletype or memorandum. Other requests for assistance may involve radioactive material in serious accidents, fire, personal injuries, contamination or possible hazards to the general public. Some occurrences may require the dispatch of trained personnel equipped with radiation monitoring instruments and related equipment necessary to evaluate, control and neutralize the hazard. The primary responsibility for incidents involving radioactive material always remains with the party having custody of the radioactive materials. In addition, the DOE recognizes that the assistance provided shall not in any way preempt state, tribal, or local authority and/or responsibility on state or tribal properties. Toward this end, DOE assistance for non-DOE radioactive materials, is limited to technical assistance, advice, measurement and other resources as deemed necessary by the local authorities but excludes DOE interface with the public media. This is a function handled by the local or state Incident Commander

Radiological Risk Assessment and Cask Materials Qualification for Disposed Sealed Radioactive Sources Transport

International Nuclear Information System (INIS)

Margeanu, C.A.; Olteanu, G.; Bujoreanu, D.

2009-01-01

The hazardous waste problem imposes to respect national and international agreed regulations regarding their transport, taking into account both for maintaining humans, goods and environment exposure under specified limits, during transport and specific additional operations, and also to reduce impact on the environment. The paper follows to estimate the radiological risk and cask materials qualification according to the design specifications for disposed sealed radioactive sources normal transport situation. The shielding analysis has been performed by using Oak Ridge National Laboratory's SCALE 5 programs package. For thermal analysis and cask materials qualification ANSYS computer code has been used. Results have been obtained under the framework of Advanced system for monitoring of hazardous waste transport on the Romanian territory Research Project which main objective consists in implementation of a complex dual system for on-line monitoring both for transport special vehicle and hazardous waste packages, with data automatic transmission to a national monitoring center

Discussion on the method of environmental radiological impact assessment for the highway construction project

International Nuclear Information System (INIS)

Qiu Guohua

2008-01-01

Based on the characteristics and environmental radiological impact of the highway construction project, the basic procedure of environmental radiological impact assessment for the highway construction project is put forward, including analysis and determination of contamination sources, selection of evaluation factors, determination of assessment range and dose limit, environmental investigation, environmental impact prediction and assessment. The working method of each procedure is analyzed. (authors)

Radionuclide content in laundry detergents commercially available on the Serbian market and assessment of radiological environmental hazards

Directory of Open Access Journals (Sweden)

Vukanac Ivana S.

2017-01-01

Full Text Available Laundry detergents are chemicals widely used in everyday life, and in numerous industry branches. In order to perceive the radiological aspect of environmental pollution by wastewater, the analysis of laundry detergents available on the Serbian market was undertaken. Laundry detergent samples were measured by means of gamma spectrometry and the results are presented in this paper. Analysis of the obtained activity concentrations showed that laundry detergents in Serbia mostly fulfill the international recommendation and requirements regarding the phosphate content. Besides that, the content of the detected radionuclides in laundry detergent samples indicates the minor radiological risk to the environment via wastewaters. [Project of the Serbian Ministry of Education, Science and Technological Development, Grant no. 171018

RASCAL [Radiological Assessment System for Consequence AnaLysis]: A screening model for estimating doses from radiological accidents

International Nuclear Information System (INIS)

Sjoreen, A.L.; Athey, G.F.; Sakenas, C.A.; McKenna, T.J.

1988-01-01

The Radiological Assessment System for Consequence AnaLysis (RASCAL) is a new MS-DOS-based dose assessment model which has been written for the US Nuclear Regulatory Commission for use during response to radiological emergencies. RASCAL is designed to provide crude estimates of the effects of an accident while the accident is in progress and only limited information is available. It has been designed to be very simple to use and to run quickly. RASCAL is unique in that it estimates the source term based on fundamental plant conditions and does not rely solely on release rate estimation (e.g., Ci/sec of I-131). Therefore, it can estimate consequences of accidents involving unmonitored pathways or projected failures. RASCAL will replace the older model, IRDAM. 6 refs

Radiological impact of natural radioactivity in Egyptian phosphate rocks, phosphogypsum and phosphate fertilizers

International Nuclear Information System (INIS)

El-Bahi, S.M.; Sroor, A.; Mohamed, Gehan Y.; El-Gendy, N.S.

2017-01-01

In this study, the activity concentrations of the natural radionuclides in phosphate rocks and its products were measured using a high- purity germanium detector (HPGe). The obtained activity results show remarkable wide variation in the radioactive contents for the different phosphate samples. The average activity concentration of "2"3"5U, "2"3"8U, "2"2"6Ra, "2"3"2Th and "4"0K was found as (45, 1031, 786, 85 and 765 Bq/kg) for phosphate rocks, (28, 1234, 457, 123 and 819 Bq/kg) for phosphate fertilizers, (47, 663, 550, 79 and 870 Bq/kg) for phosphogypsum and (25, 543, 409, 54 and 897 Bq/kg) for single super phosphate respectively. Based on the measured activities, the radiological parameters (activity concentration index, absorbed gamma dose rate in outdoor and indoor and the corresponding annual effective dose rates and total excess lifetime cancer risk) were estimated to assess the radiological hazards. The total excess lifetime cancer risk (ELCR) has been calculated and found to be high in all samples, which related to high radioactivity, representing radiological risk for the health of the population. - Highlights: • Level of radioactivity of phosphate rocks and by-products samples. • The radiological health hazard parameters. • Radiological risk to the health of the population. • The excess lifetime cancer risk factor.

Toward uniform probabilistic seismic hazard assessments for Southeast Asia

Science.gov (United States)

Chan, C. H.; Wang, Y.; Shi, X.; Ornthammarath, T.; Warnitchai, P.; Kosuwan, S.; Thant, M.; Nguyen, P. H.; Nguyen, L. M.; Solidum, R., Jr.; Irsyam, M.; Hidayati, S.; Sieh, K.

2017-12-01

Although most Southeast Asian countries have seismic hazard maps, various methodologies and quality result in appreciable mismatches at national boundaries. We aim to conduct a uniform assessment across the region by through standardized earthquake and fault databases, ground-shaking scenarios, and regional hazard maps. Our earthquake database contains earthquake parameters obtained from global and national seismic networks, harmonized by removal of duplicate events and the use of moment magnitude. Our active-fault database includes fault parameters from previous studies and from the databases implemented for national seismic hazard maps. Another crucial input for seismic hazard assessment is proper evaluation of ground-shaking attenuation. Since few ground-motion prediction equations (GMPEs) have used local observations from this region, we evaluated attenuation by comparison of instrumental observations and felt intensities for recent earthquakes with predicted ground shaking from published GMPEs. We then utilize the best-fitting GMPEs and site conditions into our seismic hazard assessments. Based on the database and proper GMPEs, we have constructed regional probabilistic seismic hazard maps. The assessment shows highest seismic hazard levels near those faults with high slip rates, including the Sagaing Fault in central Myanmar, the Sumatran Fault in Sumatra, the Palu-Koro, Matano and Lawanopo Faults in Sulawesi, and the Philippine Fault across several islands of the Philippines. In addition, our assessment demonstrates the important fact that regions with low earthquake probability may well have a higher aggregate probability of future earthquakes, since they encompass much larger areas than the areas of high probability. The significant irony then is that in areas of low to moderate probability, where building codes are usually to provide less seismic resilience, seismic risk is likely to be greater. Infrastructural damage in East Malaysia during the 2015

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

International Nuclear Information System (INIS)

Dionne, B.J.; Morris, S. III; Baum, J.W.

1998-03-01

The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique

Assessment of radiation hazards associated with tailing and sediment from an abandoned gold mine in Ilesa and an active tantalite mine in Ijero, southwest Nigeria

Energy Technology Data Exchange (ETDEWEB)

Isinkaye, O. [Ekiti State University (Nigeria)

2014-07-01

The implication of indiscriminate or unregulated mining activities has been pointed out as a major risk to human health and the environment. In order to assess the potential radiological hazards pose to the environment due to mining activities in southwest Nigeria, the activity concentrations of {sup 40}K, {sup 226}Ra and {sup 232}Th was determined in tailing and sediment from two mines within the study area. The samples were analysed by gamma spectrometry with low background NaI(Tl) detector. The activity concentrations of {sup 40}K, {sup 226}Ra and {sup 232}Th in all the measured samples ranged from 249.66-1459.25 BqKg{sup -1}, 7.62-50.31 Bqkg{sup -1} and 12.68-234.18 Bqkg{sup -1}, respectively in soil while in sediment samples, the values ranged from 241.86-1590.40 Bqkg{sup -1}, 9.86-74.8 Bqkg{sup -1} and 15.47-145.46 Bqkg{sup -1} for {sup 40}K, {sup 226}Ra and {sup 232}Th, respectively. In order to evaluate the radiological hazards due to the concentrations of natural radionuclides in the samples, the radium equivalent activity, external hazard index, absorbed gamma dose rates and the annual effective dose rates were determined. All these hazard indexes have mean values which are higher than the world average values but are all within their acceptable limits. Document available in abstract form only. (authors)

Radiological hazard from coal-fired power plants in Poland

International Nuclear Information System (INIS)

Nowina-Konopka, M.

1991-01-01

The radiobiological hazard of Polish population due to coal combustion for electric power production was assessed. Activity concentrations of the elementary radionuclides in coal and all kinds of ashes were measured. The ATMO computer program was applied to calculate the annual increase of the activity concentration in the air and of the annual increase of activity falling on the ground. Exposition by inhalation, oral ingestion and external irradiation was taken into account. The assessed value of irradiation was taken into account. The assessed value of individual effective dose equivalent commitments for the critical group is 0.1 mSv, i.e. 4% of the total dose rate from natural radiation. The collective effective dose equivalent commitments received of all sources by an inhabitant of Poland as a consequence of annual coal combustion in Polish CPP is 367 manSv/a (i.e. 47 manSv per GWa), i.e. 0.4% of the dose from natural radiation. (author). 11 refs, 3 figs, 8 tabs

Assessment of natural radioactivity levels and radiation hazards due to cement industry

International Nuclear Information System (INIS)

El-Taher, A.; Abdel Halim, A.S.

2010-01-01

The cement industry is considered as one of the basic industries that plays an important role in the national economy of developing countries. Activity concentrations of 226 Ra, 232 Th and 40 K in Assiut cement and other local cement types from different Egyptian factories has been measured by using γ-ray spectrometry. From the measured γ-ray spectra, specific activities were determined. The measured activity concentrations for these natural radionuclides were compared with the reported data for other countries. The average values obtained for 226 Ra, 232 Th and 40 K activity concentration in different types of cement are lower than the corresponding global values reported in UNSCEAR publications. The obtained results show that the averages of radiation hazard parameters for Assiut cement factory are lower than the acceptable level of 370 Bq kg -1 for radium equivalent Ra eq , 1 for level index Iγr, the external hazard index Hex ≤1 and 59 (nGy h -1 ) for absorbed dose rate. The manufacturing operation reduces the radiation hazard parameters. Cement does not pose a significant radiological hazard when used for construction of buildings.

Natural radionuclide and radiological assessment of building materials in high background radiation areas of Ramsar, Iran.

Science.gov (United States)

Bavarnegin, Elham; Moghaddam, Masoud Vahabi; Fathabadi, Nasrin

2013-04-01

Building materials, collected from different sites in Ramsar, a northern coastal city in Iran, were analyzed for their natural radionuclide contents. The measurements were carried out using a high resolution high purity Germanium (HPGe) gamma-ray spectrometer system. The activity concentration of (226)Ra, (232)Th, and (40)K content varied from below the minimum detection limit up to 86,400 Bqkg(-1), 187 Bqkg(-1), and 1350 Bqkg(-1), respectively. The radiological hazards incurred from the use of these building materials were estimated through various radiation hazard indices. The result of this survey shows that values obtained for some samples are more than the internationally accepted maximum limits and as such, the use of them as a building material pose significant radiation hazard to individuals.

Application of the Coastal Hazard Wheel methodology for coastal multi-hazard assessment and management in the state of Djibouti

Directory of Open Access Journals (Sweden)

Lars Rosendahl Appelquist

2014-01-01

Full Text Available This paper presents the application of a new methodology for coastal multi-hazard assessment and management in a changing global climate on the state of Djibouti. The methodology termed the Coastal Hazard Wheel (CHW is developed for worldwide application and is based on a specially designed coastal classification system that incorporates the main static and dynamic parameters determining the characteristics of a coastal environment. The methodology provides information on the hazards of ecosystem disruption, gradual inundation, salt water intrusion, erosion and flooding and can be used to support management decisions at local, regional and national level, in areas with limited access to geophysical data. The assessment for Djibouti applies a geographic information system (GIS to develop a range of national hazard maps along with relevant hazard statistics and is showcasing the procedure for applying the CHW methodology for national hazard assessments. The assessment shows that the coastline of Djibouti is characterized by extensive stretches with high or very high hazards of ecosystem disruption, mainly related to coral reefs and mangrove forests, while large sections along the coastlines of especially northern and southern Djibouti have high hazard levels for gradual inundation. The hazard of salt water intrusion is moderate along most of Djibouti’s coastline, although groundwater availability is considered to be very sensitive to human ground water extraction. High or very high erosion hazards are associated with Djibouti’s sedimentary plains, estuaries and river mouths, while very high flooding hazards are associated with the dry river mouths.

The radiological assessment system for consequence analysis - RASCAL

International Nuclear Information System (INIS)

Sjoreen, A.L.; Ramsdell, J.V.; Athey, G.F.

1996-01-01

The Radiological Assessment System for Consequence Analysis, Version 2.1 (RASCAL 2.1) has been developed for use during a response to radiological emergencies. The model estimates doses for comparison with U.S. Environmental Protection Agency (EPA) Protective Action Guides (PAGs) and thresholds for acute health effects. RASCAL was designed to be used by U.S. Nuclear Regulatory Commission (NRC) personnel who report to the site of a nuclear accident to conduct an independent evaluation of dose and consequence projections and personnel who conduct training and drills on emergency responses. It allows consideration of the dominant aspects of the source term, transport, dose, and consequences. RASCAL consists of three computational tools: ST-DOSE, FM-DOSE, and DECAY. ST-DOSE computes source term, atmospheric transport, and dose to man from accidental airborne releases of radionuclides. The source-term calculations are appropriate for accidents at U.S. power reactors. FM-DOSE computes doses from environmental concentrations of radionuclides in the air and on the ground. DECAY computes radiological decay and daughter in-growth. RASCAL 2.1 is a DOS application that can be run under Windows 3.1 and 95. RASCAL has been the starting point for other accident consequence models, notably INTERRAS, an international version of RASCAL, and HASCAL, an expansion of RASCAL that will model radiological, biological, and chemical accidents

Radiology resident MR and CT image analysis skill assessment using an interactive volumetric simulation tool - the RadioLOG project

International Nuclear Information System (INIS)

Gondim Teixeira, Pedro Augusto; Leplat, Christophe; Cendre, Romain; Hossu, Gabriela; Felblinger, Jacques; Blum, Alain; Braun, Marc

2017-01-01

Assess the use of a volumetric simulation tool for the evaluation of radiology resident MR and CT interpretation skills. Forty-three participants were evaluated with a software allowing the visualisation of multiple volumetric image series. There were 7 medical students, 28 residents and 8 senior radiologists among the participants. Residents were divided into two sub-groups (novice and advanced). The test was composed of 15 exercises on general radiology and lasted 45 min. Participants answered a questionnaire on their experience with the test using a 5-point Likert scale. This study was approved by the dean of the medical school and did not require ethics committee approval. The reliability of the test was good with a Cronbach alpha value of 0.9. Test scores were significantly different in all sub-groups studies (p < 0.0225). The relation between test scores and the year of residency was logarithmic (R"2 = 0.974). Participants agreed that the test reflected their radiological practice (3.9 ± 0.9 on a 5-point scale) and was better than the conventional evaluation methods (4.6 ± 0.5 on a 5-point scale). This software provides a high quality evaluation tool for the assessment of the interpretation skills in radiology residents. (orig.)

Radiology resident MR and CT image analysis skill assessment using an interactive volumetric simulation tool - the RadioLOG project

Energy Technology Data Exchange (ETDEWEB)

Gondim Teixeira, Pedro Augusto; Leplat, Christophe [CHRU-Nancy Hopital Central, Service d' Imagerie Guilloz, Nancy (France); Universite de Lorraine, IADI U947, Nancy (France); Cendre, Romain [INSERM, CIC-IT 1433, Nancy (France); Hossu, Gabriela; Felblinger, Jacques [Universite de Lorraine, IADI U947, Nancy (France); INSERM, CIC-IT 1433, Nancy (France); Blum, Alain [CHRU-Nancy Hopital Central, Service d' Imagerie Guilloz, Nancy (France); Braun, Marc [CHRU-Nancy Hopital Central, Service de Neuroradiologie, Nancy (France)

2017-02-15

Assess the use of a volumetric simulation tool for the evaluation of radiology resident MR and CT interpretation skills. Forty-three participants were evaluated with a software allowing the visualisation of multiple volumetric image series. There were 7 medical students, 28 residents and 8 senior radiologists among the participants. Residents were divided into two sub-groups (novice and advanced). The test was composed of 15 exercises on general radiology and lasted 45 min. Participants answered a questionnaire on their experience with the test using a 5-point Likert scale. This study was approved by the dean of the medical school and did not require ethics committee approval. The reliability of the test was good with a Cronbach alpha value of 0.9. Test scores were significantly different in all sub-groups studies (p < 0.0225). The relation between test scores and the year of residency was logarithmic (R{sup 2} = 0.974). Participants agreed that the test reflected their radiological practice (3.9 ± 0.9 on a 5-point scale) and was better than the conventional evaluation methods (4.6 ± 0.5 on a 5-point scale). This software provides a high quality evaluation tool for the assessment of the interpretation skills in radiology residents. (orig.)

Radiation hazards and protection of patient in diagnostic radiology

International Nuclear Information System (INIS)

Agarwal, Y.C.; Haldar, P.K.

1980-01-01

Biological radiation effects such as somatic certainty effects, somatic stochastic effects and genetic effects are described. Diagnostic radiology, therefore, involves risk to the patient in case of undesirable exposures and in particular to the fetus. Gonad doses in diagnostic radiology which may lead to genetic effects have been found to vary within a wide range. To avoid somatic certainty and to keep genetic effects to a minimum, some suggestions are enumerated. They deal with the choice of technique, proper positioning, use of calibrated equipment and use of techniques like xerography, ultrasonography, thermography etc. (M.G.B.)

Radiological assessment of the PET facility

International Nuclear Information System (INIS)

Discacciatti, Adrian; Cruzate, Juan A.; Bomben, Ana M.; Carelli, Jorge; Namias, Mario

2008-01-01

The radiological assessment of a Positron Emission Tomography (PET) facility consists of the evaluation of the annual effective dose to workers exposed occupationally and to members of the public. This evaluation takes into account the radionuclide involved, the characteristics of the facility, the working procedure and the expected number of patients per year. This paper details the methodology used by the Nuclear Regulatory Authority (in Spanish ARN) to independently assess the design of PET facilities considering only radioprotection aspects. The results of the evaluation are compared with the design requirements established in the ARN regulations to determine whether or not, the facility complies with those requirements, both for workers and for members of the public. As an example of the above mentioned methodology, this paper presents the assessment of a PET facility located in Buenos Aires called Fundacion Centro Diagnostico Nuclear (FCDN). (author)

Probabilistic seismic hazard assessment for Point Lepreau Generating Station

Energy Technology Data Exchange (ETDEWEB)

Mullin, D. [New Brunswick Power Corp., Point Lepreau Generating Station, Lepreau, New Brunswick (Canada); Lavine, A. [AMEC Foster Wheeler Environment and Infrastructure Americas, Oakland, California (United States); Egan, J. [SAGE Engineers, Oakland, California (United States)

2015-09-15

A Probabilistic Seismic Hazard Assessment (PSHA) has been performed for the Point Lepreau Generating Station (PLGS). The objective is to provide characterization of the earthquake ground shaking that will be used to evaluate seismic safety. The assessment is based on the current state of knowledge of the informed scientific and engineering community regarding earthquake hazards in the site region, and includes two primary components-a seismic source model and a ground motion model. This paper provides the methodology and results of the PLGS PSHA. The implications of the updated hazard information for site safety are discussed in a separate paper. (author)

Probabilistic seismic hazard assessment for Point Lepreau Generating Station

Energy Technology Data Exchange (ETDEWEB)

Mullin, D., E-mail: dmullin@nbpower.com [New Brunswick Power Corporation, Point Lepreau Generating Station, Point Lepreau, NB (Canada); Lavine, A., E-mail: alexis.lavine@amecfw.com [AMEC Foster Wheeler Environment & Infrastructure Americas, Oakland, CA (United States); Egan, J., E-mail: jegan@sageengineers.com [SAGE Engineers, Oakland, CA (United States)

2015-07-01

A Probabilistic Seismic Hazard Assessment (PSHA) has been performed for the Point Lepreau Generating Station (PLGS). The objective is to provide characterization of the earthquake ground shaking that will be used to evaluate seismic safety. The assessment is based on the current state of knowledge of the informed scientific and engineering community regarding earthquake hazards in the site region, and includes two primary components--a seismic source model and a ground motion model. This paper provides the methodology and results of the PLGS PSHA. The implications of the updated hazard information for site safety are discussed in a separate paper. (author)

Probabilistic Seismic Hazard Assessment for Northeast India Region

Science.gov (United States)

Das, Ranjit; Sharma, M. L.; Wason, H. R.

2016-08-01

Northeast India bounded by latitudes 20°-30°N and longitudes 87°-98°E is one of the most seismically active areas in the world. This region has experienced several moderate-to-large-sized earthquakes, including the 12 June, 1897 Shillong earthquake ( M w 8.1) and the 15 August, 1950 Assam earthquake ( M w 8.7) which caused loss of human lives and significant damages to buildings highlighting the importance of seismic hazard assessment for the region. Probabilistic seismic hazard assessment of the region has been carried out using a unified moment magnitude catalog prepared by an improved General Orthogonal Regression methodology (Geophys J Int, 190:1091-1096, 2012; Probabilistic seismic hazard assessment of Northeast India region, Ph.D. Thesis, Department of Earthquake Engineering, IIT Roorkee, Roorkee, 2013) with events compiled from various databases (ISC, NEIC,GCMT, IMD) and other available catalogs. The study area has been subdivided into nine seismogenic source zones to account for local variation in tectonics and seismicity characteristics. The seismicity parameters are estimated for each of these source zones, which are input variables into seismic hazard estimation of a region. The seismic hazard analysis of the study region has been performed by dividing the area into grids of size 0.1° × 0.1°. Peak ground acceleration (PGA) and spectral acceleration ( S a) values (for periods of 0.2 and 1 s) have been evaluated at bedrock level corresponding to probability of exceedance (PE) of 50, 20, 10, 2 and 0.5 % in 50 years. These exceedance values correspond to return periods of 100, 225, 475, 2475, and 10,000 years, respectively. The seismic hazard maps have been prepared at the bedrock level, and it is observed that the seismic hazard estimates show a significant local variation in contrast to the uniform hazard value suggested by the Indian standard seismic code [Indian standard, criteria for earthquake-resistant design of structures, fifth edition, Part

Probabilistic Tsunami Hazard Assessment: the Seaside, Oregon Pilot Study

Science.gov (United States)

Gonzalez, F. I.; Geist, E. L.; Synolakis, C.; Titov, V. V.

2004-12-01

A pilot study of Seaside, Oregon is underway, to develop methodologies for probabilistic tsunami hazard assessments that can be incorporated into Flood Insurance Rate Maps (FIRMs) developed by FEMA's National Flood Insurance Program (NFIP). Current NFIP guidelines for tsunami hazard assessment rely on the science, technology and methodologies developed in the 1970s; although generally regarded as groundbreaking and state-of-the-art for its time, this approach is now superseded by modern methods that reflect substantial advances in tsunami research achieved in the last two decades. In particular, post-1990 technical advances include: improvements in tsunami source specification; improved tsunami inundation models; better computational grids by virtue of improved bathymetric and topographic databases; a larger database of long-term paleoseismic and paleotsunami records and short-term, historical earthquake and tsunami records that can be exploited to develop improved probabilistic methodologies; better understanding of earthquake recurrence and probability models. The NOAA-led U.S. National Tsunami Hazard Mitigation Program (NTHMP), in partnership with FEMA, USGS, NSF and Emergency Management and Geotechnical agencies of the five Pacific States, incorporates these advances into site-specific tsunami hazard assessments for coastal communities in Alaska, California, Hawaii, Oregon and Washington. NTHMP hazard assessment efforts currently focus on developing deterministic, "credible worst-case" scenarios that provide valuable guidance for hazard mitigation and emergency management. The NFIP focus, on the other hand, is on actuarial needs that require probabilistic hazard assessments such as those that characterize 100- and 500-year flooding events. There are clearly overlaps in NFIP and NTHMP objectives. NTHMP worst-case scenario assessments that include an estimated probability of occurrence could benefit the NFIP; NFIP probabilistic assessments of 100- and 500-yr

Are seismic hazard assessment errors and earthquake surprises unavoidable?

Science.gov (United States)

Kossobokov, Vladimir

2013-04-01

Why earthquake occurrences bring us so many surprises? The answer seems evident if we review the relationships that are commonly used to assess seismic hazard. The time-span of physically reliable Seismic History is yet a small portion of a rupture recurrence cycle at an earthquake-prone site, which makes premature any kind of reliable probabilistic statements about narrowly localized seismic hazard. Moreover, seismic evidences accumulated to-date demonstrate clearly that most of the empirical relations commonly accepted in the early history of instrumental seismology can be proved erroneous when testing statistical significance is applied. Seismic events, including mega-earthquakes, cluster displaying behaviors that are far from independent or periodic. Their distribution in space is possibly fractal, definitely, far from uniform even in a single segment of a fault zone. Such a situation contradicts generally accepted assumptions used for analytically tractable or computer simulations and complicates design of reliable methodologies for realistic earthquake hazard assessment, as well as search and definition of precursory behaviors to be used for forecast/prediction purposes. As a result, the conclusions drawn from such simulations and analyses can MISLEAD TO SCIENTIFICALLY GROUNDLESS APPLICATION, which is unwise and extremely dangerous in assessing expected societal risks and losses. For example, a systematic comparison of the GSHAP peak ground acceleration estimates with those related to actual strong earthquakes, unfortunately, discloses gross inadequacy of this "probabilistic" product, which appears UNACCEPTABLE FOR ANY KIND OF RESPONSIBLE SEISMIC RISK EVALUATION AND KNOWLEDGEABLE DISASTER PREVENTION. The self-evident shortcomings and failures of GSHAP appeals to all earthquake scientists and engineers for an urgent revision of the global seismic hazard maps from the first principles including background methodologies involved, such that there becomes: (a) a

Urban Heat Wave Hazard Assessment

Science.gov (United States)

Quattrochi, D. A.; Jedlovec, G.; Crane, D. L.; Meyer, P. J.; LaFontaine, F.

2016-12-01

Heat waves are one of the largest causes of environmentally-related deaths globally and are likely to become more numerous as a result of climate change. The intensification of heat waves by the urban heat island effect and elevated humidity, combined with urban demographics, are key elements leading to these disasters. Better warning of the potential hazards may help lower risks associated with heat waves. Moderate resolution thermal data from NASA satellites is used to derive high spatial resolution estimates of apparent temperature (heat index) over urban regions. These data, combined with demographic data, are used to produce a daily heat hazard/risk map for selected cities. MODIS data are used to derive daily composite maximum and minimum land surface temperature (LST) fields to represent the amplitude of the diurnal temperature cycle and identify extreme heat days. Compositing routines are used to generate representative daily maximum and minimum LSTs for the urban environment. The limited effect of relative humidity on the apparent temperature (typically 10-15%) allows for the use of modeled moisture fields to convert LST to apparent temperature without loss of spatial variability. The daily max/min apparent temperature fields are used to identify abnormally extreme heat days relative to climatological values in order to produce a heat wave hazard map. Reference to climatological values normalizes the hazard for a particular region (e.g., the impact of an extreme heat day). A heat wave hazard map has been produced for several case study periods and then computed on a quasi-operational basis during the summer of 2016 for Atlanta, GA, Chicago, IL, St. Louis, MO, and Huntsville, AL. A hazard does not become a risk until someone or something is exposed to that hazard at a level that might do harm. Demographic information is used to assess the urban risk associated with the heat wave hazard. Collectively, the heat wave hazard product can warn people in urban

Oak Ridge Y-12 Plant Emergency Management Hazards Assessment (EMHA) Process

International Nuclear Information System (INIS)

Bailiff, E.G.; Bolling, J.D.

2000-01-01

This report establishes requirements and standard methods for the development and maintenance of the Emergency Management Hazards Assessment (EMHA) process used by the lead and all event contractors at the Y-12 Plant for emergency planning and preparedness. The EMHA process provides the technical basis for the Y-12 emergency management program. The instructions provides in this report include methods and requirements for performing the following emergency management activities at Y-12: hazards identification; hazards survey, and hazards assessment

Aiding alternatives assessment with an uncertainty-tolerant hazard scoring method.

Science.gov (United States)

Faludi, Jeremy; Hoang, Tina; Gorman, Patrick; Mulvihill, Martin

2016-11-01

This research developed a single-score system to simplify and clarify decision-making in chemical alternatives assessment, accounting for uncertainty. Today, assessing alternatives to hazardous constituent chemicals is a difficult task-rather than comparing alternatives by a single definitive score, many independent toxicological variables must be considered at once, and data gaps are rampant. Thus, most hazard assessments are only comprehensible to toxicologists, but business leaders and politicians need simple scores to make decisions. In addition, they must balance hazard against other considerations, such as product functionality, and they must be aware of the high degrees of uncertainty in chemical hazard data. This research proposes a transparent, reproducible method to translate eighteen hazard endpoints into a simple numeric score with quantified uncertainty, alongside a similar product functionality score, to aid decisions between alternative products. The scoring method uses Clean Production Action's GreenScreen as a guide, but with a different method of score aggregation. It provides finer differentiation between scores than GreenScreen's four-point scale, and it displays uncertainty quantitatively in the final score. Displaying uncertainty also illustrates which alternatives are early in product development versus well-defined commercial products. This paper tested the proposed assessment method through a case study in the building industry, assessing alternatives to spray polyurethane foam insulation containing methylene diphenyl diisocyanate (MDI). The new hazard scoring method successfully identified trade-offs between different alternatives, showing finer resolution than GreenScreen Benchmarking. Sensitivity analysis showed that different weighting schemes in hazard scores had almost no effect on alternatives ranking, compared to uncertainty from data gaps. Copyright © 2016 Elsevier Ltd. All rights reserved.

Radiological risk assessment for radioactive contamination at landfill site

International Nuclear Information System (INIS)

Devgun, J.S.

1990-01-01

A limited-scope preliminary assessment of radiological risk has been conducted for a landfill site where radioactive residues resulting from past uranium ore processing operations are present. Potential radiation doses to an individual under different scenarios have been predicted using the RESRAD computer code. The assessment provides useful input to the remedial action planning for the site that is currently underway. 7 refs., 6 figs., 3 tabs

South Tank Farm underground storage tank inspection using the topographical mapping system for radiological and hazardous environments

International Nuclear Information System (INIS)

Armstrong, G.A.; Burks, B.L.; Hoesen, S.D. van

1997-07-01

During the winter of 1997 the Topographical Mapping System (TMS) for hazardous and radiological environments and the Interactive Computer-Enhanced Remote-Viewing System (ICERVS) were used to perform wall inspections on underground storage tanks (USTs) W5 and W6 of the South Tank Farm (STF) at Oak Ridge National Laboratory (ORNL). The TMS was designed for deployment in the USTs at the Hanford Site. Because of its modular design, the TMS was also deployable in the USTs at ORNL. The USTs at ORNL were built in the 1940s and have been used to store radioactive waste during the past 50 years. The tanks are constructed with an inner layer of Gunite trademark that has been spalling, leaving sections of the inner wall exposed. Attempts to quantify the depths of the spalling with video inspection have proven unsuccessful. The TMS surface-mapping campaign in the STF was initiated to determine the depths of cracks, crevices, and/or holes in the tank walls and to identify possible structural instabilities in the tanks. The development of the TMS and the ICERVS was initiated by DOE for the purpose of characterization and remediation of USTs at DOE sites across the country. DOE required a three-dimensional, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is mapping the interiors of USTs as part of DOE's waste characterization and remediation efforts, to obtain both baseline data on the content of the storage tank interiors and changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Site, the TMS has been designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention

Rockfall Hazard Process Assessment : Implementation Report

Science.gov (United States)

2017-10-01

The Montana Department of Transportation (MDT) commissioned a new research program to improve assessment and management of its rock slope assets. The Department implemented a Rockfall Hazard Rating System (RHRS) program in 2005 and wished to add valu...

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

International Nuclear Information System (INIS)

Dionne, B.J.; Morris, S.C. III; Baum, J.W.

1998-01-01

The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report

Medical rescue for nuclear or radiologic emergencies

International Nuclear Information System (INIS)

Chen Xiaohua; Nie Suifeng

2011-01-01

Nuclear or radiologic emergencies are defined as incidents that are caused by radioactive substance or by other sources of radiation and can pose a serious hazard to public health. In case of nuclear or radiologic emergencies, radioactive rays will damage the human body and bring about psychological and mental stress, resulting in a series of social psychological effects. The key to medical rescue for nuclear or radiologic emergencies is to take effective measures which can minimize the body harm resulting from nuclear or radiologic emergencies and maintain social stability. This article reviews the personnel protection, on-the-spot salvage, treatments of various harm, and prevention of public psychological effect following nuclear or radiologic emergencies. (authors)

Surface Fire Hazards Analysis Technical Report-Constructor Facilities

International Nuclear Information System (INIS)

Flye, R.E.

2000-01-01

The purpose of this Fire Hazards Analysis Technical Report (hereinafter referred to as Technical Report) is to assess the risk from fire within individual fire areas to ascertain whether the U.S. Department of Energy (DOE) fire safety objectives are met. The objectives identified in DOE Order 420.1, Change 2, Facility Safety, Section 4.2, establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: The occurrence of a fire or related event; A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees, the public, or the environment; Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards; Property losses from a fire and related events exceeding defined limits established by DOE; and Critical process controls and safety class systems being damaged as a result of a fire and related events

Wicked Problems in Natural Hazard Assessment and Mitigation

Science.gov (United States)

Stein, S.; Steckler, M. S.; Rundle, J. B.; Dixon, T. H.

2017-12-01

Social scientists have defined "wicked" problems that are "messy, ill-defined, more complex than we fully grasp, and open to multiple interpretations based on one's point of view... No solution to a wicked problem is permanent or wholly satisfying, which leaves every solution open to easy polemical attack." These contrast with "tame" problems in which necessary information is available and solutions - even if difficult and expensive - are straightforward to identify and execute. Updating the U.S.'s aging infrastructure is a tame problem, because what is wrong and how to fix it are clear. In contrast, addressing climate change is a wicked problem because its effects are uncertain and the best strategies to address them are unclear. An analogous approach can be taken to natural hazard problems. In tame problems, we have a good model of the process, good information about past events, and data implying that the model should predict future events. In such cases, we can make a reasonable assessment of the hazard that can be used to develop mitigation strategies. Earthquake hazard mitigation for San Francisco is a relatively tame problem. We understand how the earthquakes result from known plate motions, have information about past earthquakes, and have geodetic data implying that future similar earthquakes will occur. As a result, it is straightforward to develop and implement mitigation strategies. However, in many cases, hazard assessment and mitigation is a wicked problem. How should we prepare for a great earthquake on plate boundaries where tectonics favor such events but we have no evidence that they have occurred and hence how large they may be or how often to expect them? How should we assess the hazard within plates, for example in the New Madrid seismic zone, where large earthquakes have occurred but we do not understand their causes and geodetic data show no strain accumulating? How can we assess the hazard and make sensible policy when the recurrence of

Frequency distribution of specific activities and radiological hazard assessment in surface beach sand samples collected in Bangsaen beach in Chonburi province, Thailand

Science.gov (United States)

Changkit, N.; Boonkrongcheep, R.; Youngchauy, U.; Polthum, S.; Kessaratikoon, P.

2017-09-01

The specific activities of natural radionuclides (40K, 226Ra and 232Th) in 50 surface beach sand samples collected from Bangsaen beach in Chonburi province in the easthern region of Thailand, were measured and evaluated. Experimental results were obtained by using a high-purity germanium (HPGe) detector and gamma spectrometry analysis system in the special laboratory at Thailand Institute of Nuclear Technology (Public Organization). The IAEA-SOIL-375 reference material was used to analyze the concentration of 40K, 226Ra and 232Th in all samples. It was found that the specific activities of 40K, 226Ra and 232Th were ranged from 510.85 - 771.35, 8.17 - 17.06 and 4.25 - 15.68 Bq/kg. Furthermore, frequency distribution of the specific activities were studied, analyzed and found to be the asymmetrical distribution by using a statistical computer program. Moreover, four radiological hazard indices for the investigated area were also calculated by using the median values of specific activities of 40K, 226Ra and 232Th. The results were also compared with the Office of Atoms for Peace (OAP) annual report data, Thailand and global radioactivity measurement and evaluations.

LAV@HAZARD: a web-GIS interface for volcanic hazard assessment

Directory of Open Access Journals (Sweden)

Giovanni Gallo

2011-12-01

Full Text Available Satellite data, radiative power of hot spots as measured with remote sensing, historical records, on site geological surveys, digital elevation model data, and simulation results together provide a massive data source to investigate the behavior of active volcanoes like Mount Etna (Sicily, Italy over recent times. The integration of these heterogeneous data into a coherent visualization framework is important for their practical exploitation. It is crucial to fill in the gap between experimental and numerical data, and the direct human perception of their meaning. Indeed, the people in charge of safety planning of an area need to be able to quickly assess hazards and other relevant issues even during critical situations. With this in mind, we developed LAV@HAZARD, a web-based geographic information system that provides an interface for the collection of all of the products coming from the LAVA project research activities. LAV@HAZARD is based on Google Maps application programming interface, a choice motivated by its ease of use and the user-friendly interactive environment it provides. In particular, the web structure consists of four modules for satellite applications (time-space evolution of hot spots, radiant flux and effusion rate, hazard map visualization, a database of ca. 30,000 lava-flow simulations, and real-time scenario forecasting by MAGFLOW on Compute Unified Device Architecture.

Development of an auditable safety analysis in support of a radiological facility classification

International Nuclear Information System (INIS)

Kinney, M.D.; Young, B.

1995-01-01

In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23

MARC - the NRPB methodology for assessing radiological consequences of accidental releases of activity

International Nuclear Information System (INIS)

Clarke, R.H.; Kelly, G.N.

1981-12-01

The National Radiological Protection Board has developed a methodology for the assessment of the public health related consequences of accidental releases of radionuclides from nuclear facilities. The methodology consists of a suite of computer programs which predict the transfer of activity from the point of release to the atmosphere through to the population. The suite of programs is entitled MARC; Methodology for Assessing Radiological Consequences. This report describes the overall framework and philosophy utilised within MARC. (author)

Waste receiving and processing (WRAP) module 1 hazards assessment. Revision 1

International Nuclear Information System (INIS)

Sutton, L.N.

1997-01-01

This report documents the hazards assessment for the Waste Receiving and Processing Module I (WRAP 1) located on the U.S. Department of Energy (DOE) Hanford Site. Operation of the WRAP 1 is the responsibility of Rust Federal Services Hanford (RFSH). This hazards assessment was conducted to provide the emergency planning technical basis for the WRAP 1. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification

Methodology for Radiological Risk Assessment of Deep Borehole Disposal Operations

Energy Technology Data Exchange (ETDEWEB)

Hardin, Ernest; Su, Jiann-Cherng; Peretz, Fred(ORNL)

2017-03-01

The primary purpose of the preclosure radiological safety assessment (that this document supports) is to identify risk factors for disposal operations, to aid in design for the deep borehole field test (DBFT) engineering demonstration.

Bi-annual report 1994-1995. Research and operational activities of Central Laboratory for Radiological Protection

International Nuclear Information System (INIS)

1996-01-01

BI-annual report of Central Laboratory for Radiological Protection, Warsaw, shows its activities in 1994-1995. The general information and organization of CLOR have been performed in the opening part of the report. The second part contains extended abstracts of scientific activities especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, dosimetry problems, calibration and standardization of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of CLOR scientific staff issued in the period of 1994-1995

Bi-annual report 1994-1995. Research and operational activities of Central Laboratory for Radiological Protection

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

BI-annual report of Central Laboratory for Radiological Protection, Warsaw, shows its activities in 1994-1995. The general information and organization of CLOR have been performed in the opening part of the report. The second part contains extended abstracts of scientific activities especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, dosimetry problems, calibration and standardization of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of CLOR scientific staff issued in the period of 1994-1995.

Bi-annual report 1992-1993. Operational and research activities of Central Laboratory for Radiological Protection

International Nuclear Information System (INIS)

1994-06-01

Bi-annual report of Central Laboratory for Radiological Protection, Warsaw shows its activities in 1992-1993. The general information and organization of CLOR have been shown in the first part of the report. The second part contains extended abstracts of scientific activity, especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, personal dosimetry, calibration and periodical control of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of scientists of CLOR issued in the period of 1992-1993

Bi-annual report 1992-1993. Operational and research activities of Central Laboratory for Radiological Protection

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-06-01

Bi-annual report of Central Laboratory for Radiological Protection, Warsaw shows its activities in 1992-1993. The general information and organization of CLOR have been shown in the first part of the report. The second part contains extended abstracts of scientific activity, especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, personal dosimetry, calibration and periodical control of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of scientists of CLOR issued in the period of 1992-1993.

An assessment of the radiological impact of uranium mining in northern Saskatchewan

International Nuclear Information System (INIS)

1986-06-01

This report presents the findings of a study which investigated the regional radiological impact of uranium mining in northern Saskatchewan. The study was performed by IEC Beak Consultants Ltd. under a contract awarded by Environment Canada in partnership with the Atomic Energy Control Board. This preliminary assessment suggests there is a negligible combined regional radiological impact from simultaneous operation of the three operating mines investigated as part of the present study. The mines are spaced too far apart for any superposition of emissions to be significantly greater than a small fraction of background levels. The most exposed individual not directly associated with any of the mining operations is estimated to receive a total radiation dose equal to about 3% of the dose due to natural background radiations. This increment is equivalent to the increment in natural background that would be received by an individual moving from Vancouver to Wollaston Post, before mining began in the area, as a result of reduced atmospheric shielding from cosmic radiation. Radiological impacts on biota are estimated to have insignficant effects on natural populations in all cases. However, since the study only investigates the effects of operational releases of radionuclides, the results do not imply that uranium mining developments will or will not have significant long-term radiological impact on northern Saskatchewan. Radiological impact assessments described in this report are estimates only. There are some uncertainties in the available data and modelling methodology. The radiological impact of abandoned tailings areas was not included in this study

Development and application of portable mobile gamma spectrometry system (PMGSS) for realtime online radiological assessment

International Nuclear Information System (INIS)

Patil, S.S.; Padmanabhan, N.; Sharma, R.; Singh, R.; Pradeepkumar, K.S.

2008-01-01

A state of art mobile monitoring system is a prime requirement to combat the challenging radiological situations. In the event of any radiological/nuclear Emergencies an effective, realistic methodology of radiological measurements is an asset. In this context, a highly sensitive real-time online mobile monitoring system having features and provision to display the important parameters will be an essential tool in the course of radiological impact assessment. This paper, describes the efforts that has been made towards providing a useful Portable Mobile Gamma Spectrometry System (PMGSS) and developing applications so as to enhance its usefulness in quick radiological impact assessment and to initiate the proper countermeasures during any Nuclear/Radiological emergency situation in public domain. The system uses a NaI(Tl) detector, a global positioning system (GPS) and a laptop PC for storage, analysis and graphical representation of the acquired data. PMGSS is a highly sensitive, portable and reliable radiation monitoring equipment with capability of qualitative and quick estimation of the radioisotopes. The system was used for the mobile radiological mapping of Bangalore and Mumbai city and demonstrated its capability for use in environmental radiation monitoring during any radiological emergency requirement the results of which are presented here. (abstract)

Radiological assessment for bauxite mining and alumina refining.

Science.gov (United States)

O'Connor, Brian H; Donoghue, A Michael; Manning, Timothy J H; Chesson, Barry J

2013-01-01

Two international benchmarks assess whether the mining and processing of ores containing Naturally Occurring Radioactive Material (NORM) require management under radiological regulations set by local jurisdictions. First, the 1 Bq/g benchmark for radionuclide head of chain activity concentration determines whether materials may be excluded from radiological regulation. Second, processes may be exempted from radiological regulation where occupational above-background exposures for members of the workforce do not exceed 1 mSv/year. This is also the upper-limit of exposure prescribed for members of the public. Alcoa of Australia Limited (Alcoa) has undertaken radiological evaluations of the mining and processing of bauxite from the Darling Range of Western Australia since the 1980s. Short-term monitoring projects have demonstrated that above-background exposures for workers do not exceed 1 mSv/year. A whole-of-year evaluation of above-background, occupational radiological doses for bauxite mining, alumina refining and residue operations was conducted during 2008/2009 as part of the Alcoa NORM Quality Assurance System (NQAS). The NQAS has been guided by publications from the International Commission on Radiological Protection (ICRP), the International Atomic Energy Agency (IAEA) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). The NQAS has been developed specifically in response to implementation of the Australian National Directory on Radiation Protection (NDRP). Positional monitoring was undertaken to increase the accuracy of natural background levels required for correction of occupational exposures. This is important in view of the small increments in exposure that occur in bauxite mining, alumina refining and residue operations relative to natural background. Positional monitoring was also undertaken to assess the potential for exposure in operating locations. Personal monitoring was undertaken to characterise exposures in Similar

Radiological safety assessment of transporting radioactive waste to the Gyeongju disposal facility in Korea

Energy Technology Data Exchange (ETDEWEB)

Jeong, Jong Tae; Baik, Min Hoon; Kang, Mun Ja; Ahn, Hong Joo; Hwang, Doo Seong; Hong, Dae Seok; Jeong, Yong Hwan; Kim, Kyung Su [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-12-15

A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI), Daejeon, Korea. We considered two kinds of wastes: (1) operation wastes generated from the routine operation of facilities; and (2) decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incident-free (normal) transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

Radiological Safety Assessment of Transporting Radioactive Wastes to the Gyeongju Disposal Facility in Korea

Directory of Open Access Journals (Sweden)

Jongtae Jeong

2016-12-01

Full Text Available A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI, Daejeon, Korea. We considered two kinds of wastes: (1 operation wastes generated from the routine operation of facilities; and (2 decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incident-free (normal transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

Natural radioactivity in some building materials and assessment of the associated radiation hazards

Energy Technology Data Exchange (ETDEWEB)

Kasumovic, Amira; Hankic, Ema; Kasic, Amela; Adrovic, Feriz [Tuzla Univ. (Bosnia and Herzegovina). Dept. of Physics

2018-04-01

The results of the specific activities of {sup 232}Th, {sup 226}Ra and {sup 40}K measured in samples of commonly used building materials in Bosnia and Herzegovina are presented. Measurements were performed by gamma-ray spectrometer with coaxial HPGe detector. The surface radon exhalation and mass exhalation rates for selected building materials were also measured. The determined values of specific activities were in range from 3.16 ± 0.81 Bq kg{sup -1} to 64.79 ± 6.16 Bq kg{sup -1} for {sup 232}Th, from 2.46 ± 0.95 Bq kg{sup -1} to 53.89 ± 3.67 Bq kg{sup -1} for {sup 226}Ra and from 28.44 ± 7.28 Bq kg{sup -1} to 557.30 ± 93.38 Bq kg{sup -1} for {sup 40}K. The radium equivalent activity, the activity concentration index, the external and internal hazard indices as well as the absorbed dose rate in indoor air and the corresponding annual effective dose, due to gamma-ray emission from the radioactive nuclides in the building material, were evaluated in order to assess the radiation hazards for people. The measured specific activities of the natural radioactive nuclides in all investigated building materials were compared with the published results for building materials from other European countries. It can be noted that the results from this study are similar to the data for building materials from neighbouring countries and for building materials used in the EU Member States. The radiological hazard parameters of the building materials were all within the recommended limits for safety use.

Correlation of radiological assessment of congestive heart failure with left ventricular end-diastolic pressure

International Nuclear Information System (INIS)

Herman, P.G.; Kahn, A.; Kallman, C.E.; Rojas, K.A.; Bodenheimer, M.M.

1988-01-01

Left ventricular end-diastolic pressure (LVEDP) has been considered a reliable indicator of left ventricular function. The purpose of this study was to correlate the radiologic assessment of congestive heart failure with LVEDP. The population of the study consisted of 85 consecutive cases in four ranges of LVEDP ( 24). The PA chest radiographs obtained 1 day prior to cardiac catherization were assessed for radiological evidence of congestive heart failure and were graded from normal to abnormal (0-3). The results will be summarized in the authors' presentation. The discordance of radiological assessment of congestive heart failure in patients with elevated LVEDP will be discussed in light of recent advances in pathophysiologic understanding of left ventricular function and the impact of new classes of drugs in the management of these patients

Determining procedures for simulation-based training in radiology: a nationwide needs assessment.

Science.gov (United States)

Nayahangan, Leizl Joy; Nielsen, Kristina Rue; Albrecht-Beste, Elisabeth; Bachmann Nielsen, Michael; Paltved, Charlotte; Lindorff-Larsen, Karen Gilboe; Nielsen, Bjørn Ulrik; Konge, Lars

2018-01-09

New training modalities such as simulation are widely accepted in radiology; however, development of effective simulation-based training programs is challenging. They are often unstructured and based on convenience or coincidence. The study objective was to perform a nationwide needs assessment to identify and prioritize technical procedures that should be included in a simulation-based curriculum. A needs assessment using the Delphi method was completed among 91 key leaders in radiology. Round 1 identified technical procedures that radiologists should learn. Round 2 explored frequency of procedure, number of radiologists performing the procedure, risk and/or discomfort for patients, and feasibility for simulation. Round 3 was elimination and prioritization of procedures. Response rates were 67 %, 70 % and 66 %, respectively. In Round 1, 22 technical procedures were included. Round 2 resulted in pre-prioritization of procedures. In round 3, 13 procedures were included in the final prioritized list. The three highly prioritized procedures were ultrasound-guided (US) histological biopsy and fine-needle aspiration, US-guided needle puncture and catheter drainage, and basic abdominal ultrasound. A needs assessment identified and prioritized 13 technical procedures to include in a simulation-based curriculum. The list may be used as guide for development of training programs. • Simulation-based training can supplement training on patients in radiology. • Development of simulation-based training should follow a structured approach. • The CAMES Needs Assessment Formula explores needs for simulation training. • A national Delphi study identified and prioritized procedures suitable for simulation training. • The prioritized list serves as guide for development of courses in radiology.

Probabilistic seismic hazard assessment of southern part of Ghana

Science.gov (United States)

Ahulu, Sylvanus T.; Danuor, Sylvester Kojo; Asiedu, Daniel K.

2018-05-01

This paper presents a seismic hazard map for the southern part of Ghana prepared using the probabilistic approach, and seismic hazard assessment results for six cities. The seismic hazard map was prepared for 10% probability of exceedance for peak ground acceleration in 50 years. The input parameters used for the computations of hazard were obtained using data from a catalogue that was compiled and homogenised to moment magnitude (Mw). The catalogue covered a period of over a century (1615-2009). The hazard assessment is based on the Poisson model for earthquake occurrence, and hence, dependent events were identified and removed from the catalogue. The following attenuation relations were adopted and used in this study—Allen (for south and eastern Australia), Silva et al. (for Central and eastern North America), Campbell and Bozorgnia (for worldwide active-shallow-crust regions) and Chiou and Youngs (for worldwide active-shallow-crust regions). Logic-tree formalism was used to account for possible uncertainties associated with the attenuation relationships. OpenQuake software package was used for the hazard calculation. The highest level of seismic hazard is found in the Accra and Tema seismic zones, with estimated peak ground acceleration close to 0.2 g. The level of the seismic hazard in the southern part of Ghana diminishes with distance away from the Accra/Tema region to a value of 0.05 g at a distance of about 140 km.

Probabilistic seismic hazard assessment of southern part of Ghana

Science.gov (United States)

Ahulu, Sylvanus T.; Danuor, Sylvester Kojo; Asiedu, Daniel K.

2017-12-01

This paper presents a seismic hazard map for the southern part of Ghana prepared using the probabilistic approach, and seismic hazard assessment results for six cities. The seismic hazard map was prepared for 10% probability of exceedance for peak ground acceleration in 50 years. The input parameters used for the computations of hazard were obtained using data from a catalogue that was compiled and homogenised to moment magnitude (Mw). The catalogue covered a period of over a century (1615-2009). The hazard assessment is based on the Poisson model for earthquake occurrence, and hence, dependent events were identified and removed from the catalogue. The following attenuation relations were adopted and used in this study—Allen (for south and eastern Australia), Silva et al. (for Central and eastern North America), Campbell and Bozorgnia (for worldwide active-shallow-crust regions) and Chiou and Youngs (for worldwide active-shallow-crust regions). Logic-tree formalism was used to account for possible uncertainties associated with the attenuation relationships. OpenQuake software package was used for the hazard calculation. The highest level of seismic hazard is found in the Accra and Tema seismic zones, with estimated peak ground acceleration close to 0.2 g. The level of the seismic hazard in the southern part of Ghana diminishes with distance away from the Accra/Tema region to a value of 0.05 g at a distance of about 140 km.

Radiological assessments for resettlement of Rongelap in the Republic of the Marshall Islands

International Nuclear Information System (INIS)

1994-01-01

The Committee on Radiological Safety in the Marshall Islands was established by the National Research Council in response to a request from the US Department of Energy (DOE) to assist the department in evaluating radiological conditions on certain atolls in the Republic of the Marshall Islands, especially Rongelap Atoll. The need stems from the provisions of a memorandum of understanding (MOU) established between the Republic of the Marshall Islands and the US in 1992. That agreement sets out criteria and stipulations pertaining to the resettlement of Rongelap Atoll. The issue of resettlement itself originated in the desire for the people of the Marshall Islands to return to the atolls from which they were evacuated as a consequence of nuclear-weapons testing by the US during the 1940s and 1950s. The National Research Council was asked to review the scientific studies undertaken by the US Department of Energy to determine if reliable and modern scientific methodology was being used to assess the potential hazard, if any, to persons who might return to live on Rongelap Atoll. A crucial provision of the MOU is that resettlement will occur only if no person returning to Rongelap and substituting on a native-foods-only diet will receive a calculated annual whole-body radiation dose equivalent of more than 100 mrem above background. The MOU also presents an action level of 17 pCi/g for the concentration of transuranic contamination, i.e., plutonium and americium, in soils below which mitigation will be considered unnecessary

Consequence Assessment for Potential Scenarios of Radiological Terrorists Events

International Nuclear Information System (INIS)

Shin, Hyeongki; Kim, Juyoul

2007-01-01

Radiological dispersal device (RDD) means any method used to deliberately disperse radioactive material to create terror or harm. Dirty bomb is an example of RDD, which usually consists of radioactive material and unconventional explosive. Dirty bomb was a problem long before September 11, 2001. In 1987, the Iraqi government tested a one-ton radiological bomb. The Iraqi tests confirmed that a dirty bomb is not effective as weapons of mass destruction (WMD) and that its main value is as a psychological weapon. In 1995, Chechen rebels buried a dirty bomb in a park in Moscow threatening to detonate one in the future if their demands were not met. Another good example of potential dirty bomb effects was an incident in Goiania, Brazil on September 18, 1987, where an orphaned medical source containing 1,375 Ci of Cs-137 resulted the death of four people and extensive environmental contamination. The purposes of radiological terrorists events are not to destroy or damage the target but to disperse radioactivity in the environment. They inflict panic on a public and economic damage by disruption of business. They also have influence on enormous clean-up costs by spreading radioactive contamination including secondary impacts on water supply reservoirs. Generally, two major long-term concerns following a RDD are human health and economic impacts. In this study, we developed potential scenarios of radiological terrorists events and performed their radiological consequence assessments in terms of total effective dose equivalent (TEDE), projected cumulative external and internal dose, and ground deposition of radioactivity

Consequence Assessment for Potential Scenarios of Radiological Terrorists Events

Energy Technology Data Exchange (ETDEWEB)

Shin, Hyeongki [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Kim, Juyoul [Seoul National University, Seoul (Korea, Republic of)

2007-07-01

Radiological dispersal device (RDD) means any method used to deliberately disperse radioactive material to create terror or harm. Dirty bomb is an example of RDD, which usually consists of radioactive material and unconventional explosive. Dirty bomb was a problem long before September 11, 2001. In 1987, the Iraqi government tested a one-ton radiological bomb. The Iraqi tests confirmed that a dirty bomb is not effective as weapons of mass destruction (WMD) and that its main value is as a psychological weapon. In 1995, Chechen rebels buried a dirty bomb in a park in Moscow threatening to detonate one in the future if their demands were not met. Another good example of potential dirty bomb effects was an incident in Goiania, Brazil on September 18, 1987, where an orphaned medical source containing 1,375 Ci of Cs-137 resulted the death of four people and extensive environmental contamination. The purposes of radiological terrorists events are not to destroy or damage the target but to disperse radioactivity in the environment. They inflict panic on a public and economic damage by disruption of business. They also have influence on enormous clean-up costs by spreading radioactive contamination including secondary impacts on water supply reservoirs. Generally, two major long-term concerns following a RDD are human health and economic impacts. In this study, we developed potential scenarios of radiological terrorists events and performed their radiological consequence assessments in terms of total effective dose equivalent (TEDE), projected cumulative external and internal dose, and ground deposition of radioactivity.

Patients as partners in radiology education: an innovative approach to teaching and assessing patient-centered communication.

Science.gov (United States)

Lown, Beth A; Sasson, J Pierre; Hinrichs, Peg

2008-04-01

Effective communication is essential for high quality care, yet little is known about radiologists' communication with patients, what constitutes "best communication practices," and how best to teach and evaluate it. We piloted educational strategies and an assessment instrument to teach and evaluate radiologists' communication skills. We focused on communication in the diagnostic mammography suite, where patient-radiologist interactions are often intense and stressful. We adapted existing instruments to create a Radiology Communication Skills Assessment Tool (RCSAT). We piloted an educational program that included patients as teachers and raters of interpersonal and communication skills, and implemented a radiology objective structured clinical examination (OSCE). We measured radiology residents' self-assessed skills, confidence and stress, as well as patient-rated communication skills using the RCSAT. Residents' baseline self-assessed communication skills regarding abnormal mammograms were fair, confidence in their communication was minimal, and they found this communication stressful. Overall baseline communication skills, rated by patient-teachers using the RCSAT, were 3.62 on a 5-point scale (1 = poor to 5 = excellent). Analysis of post-OSCE debriefing comments yielded nine themes regarding effective radiology communication, as well as residents' reflections on the communication challenges they experience. The themes were integrated into subsequent RCSAT revisions. Residents' reflections were used to inform teaching workshops. Educational curricula on communication about difficult information can be implemented in radiology training programs. Radiology residents' performance can be assessed using a communication skills assessment tool during standardized patient-teacher encounters. Further research is necessary in this important domain.

The Spatial Assessment of the Current Seismic Hazard State for Hard Rock Underground Mines

Science.gov (United States)

Wesseloo, Johan

2018-06-01

Mining-induced seismic hazard assessment is an important component in the management of safety and financial risk in mines. As the seismic hazard is a response to the mining activity, it is non-stationary and variable both in space and time. This paper presents an approach for implementing a probabilistic seismic hazard assessment to assess the current hazard state of a mine. Each of the components of the probabilistic seismic hazard assessment is considered within the context of hard rock underground mines. The focus of this paper is the assessment of the in-mine hazard distribution and does not consider the hazard to nearby public or structures. A rating system and methodologies to present hazard maps, for the purpose of communicating to different stakeholders in the mine, i.e. mine managers, technical personnel and the work force, are developed. The approach allows one to update the assessment with relative ease and within short time periods as new data become available, enabling the monitoring of the spatial and temporal change in the seismic hazard.

Detailed debris flow hazard assessment in Andorra: A multidisciplinary approach

Science.gov (United States)

Hürlimann, Marcel; Copons, Ramon; Altimir, Joan

2006-08-01

In many mountainous areas, the rapid development of urbanisation and the limited space in the valley floors have created a need to construct buildings in zones potentially exposed to debris flow hazard. In these zones, a detailed and coherent hazard assessment is necessary to provide an adequate urban planning. This article presents a multidisciplinary procedure to evaluate the debris flow hazard at a local scale. Our four-step approach was successfully applied to five torrent catchments in the Principality of Andorra, located in the Pyrenees. The first step consisted of a comprehensive geomorphologic and geologic analysis providing an inventory map of the past debris flows, a magnitude-frequency relationship, and a geomorphologic-geologic map. These data were necessary to determine the potential initiation zones and volumes of future debris flows for each catchment. A susceptibility map and different scenarios were the principal outcome of the first step, as well as essential input data for the second step, the runout analysis. A one-dimensional numerical code was applied to analyse the scenarios previously defined. First, the critical channel sections in the fan area were evaluated, then the maximum runout of the debris flows on the fan was studied, and finally simplified intensity maps for each defined scenario were established. The third step of our hazard assessment was the hazard zonation and the compilation of all the results from the two previous steps in a final hazard map. The base of this hazard map was the hazard matrix, which combined the intensity of the debris flow with its probability of occurrence and determined a certain hazard degree. The fourth step referred to the hazard mitigation and included some recommendations for hazard reduction. In Andorra, this four-step approach is actually being applied to assess the debris flow hazard. The final hazard maps, at 1 : 2000 scale, provide an obligatory tool for local land use planning. Experience

The radiological hazard of plutonium isotopes and specific plutonium mixtures

International Nuclear Information System (INIS)

Heindel, G.; Clow, J.; Inkret, W.; Miller, G.

1995-11-01

The US Department of Energy defines the hazard categories of its nuclear facilities based upon the potential for accidents to have significant effects on specific populations and the environment. In this report, the authors consider the time dependence of hazard category 2 (significant on-site effects) for facilities with inventories of plutonium isotopes and specific weapons-grade and heat-source mixtures of plutonium isotopes. The authors also define relative hazard as the reciprocal of the hazard category 2 threshold value and determine its time dependence. The time dependence of both hazard category 2 thresholds and relative hazards are determined and plotted for 10,000 years to provide useful information for planning long-term storage or disposal facilities

Radiological assessment of decommissioned nuclear facilities

International Nuclear Information System (INIS)

Dickson, H.W.; Cottrell, W.D.

1976-01-01

A radiological survey of the former Middlesex Sampling Plant, Middlesex, New Jersey, has been completed. The surveyed property served as a uranium ore sampling plant during the 1940's and early 1950's. It was released for unrestricted use in 1967 following a radiological survey by the Atomic Energy Commission and is now a reserve training center for the U. S. Marine Sixth Motor Transport Battalion. The present survey was undertaken to determine whether the existing radiological status of the property is consistent with current health standards and radiation protection practices. The radiological survey included measurement of residual alpha, beta, and gamma contamination levels, radon and radon daughter concentrations in buildings, external gamma radiation levels on the site and on adjacent property, and radium concentrations in soil on the site and on adjacent property

Hazardous metals in yellow items used in RCAs

International Nuclear Information System (INIS)

Brown, K.F.; Rankin, W.N.

1992-01-01

Yellow items used in Radiologically Controlled Areas (RCAs) that could contain hazardous metals were identified. X-ray fluorescence analyses indicated that thirty of the fifty-two items do contain hazardous metals. It is important to minimize the hazardous metals put into the wastes. The authors recommend that the specifications for all yellow items stocked in Stores be changed to specify that they contain no hazardous metals

Radiological impact assessment in Malaysia using RESRAD computer code

International Nuclear Information System (INIS)

Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol; Razali Hamzah

1999-01-01

Radiological Impact Assessment (RIA) can be conducted in Malaysia by using the RESRAD computer code developed by Argonne National Laboratory, U.S.A. The code can do analysis to derive site specific guidelines for allowable residual concentrations of radionuclides in soil. Concepts of the RIA in the context of waste management concern in Malaysia, some regulatory information and assess status of data collection are shown. Appropriate use scenarios and site specific parameters are used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Case study have been conducted to fulfil Atomic Energy Licensing Board (AELB) requirements where for disposal purpose the operator must be required to carry out. a radiological impact assessment to all proposed disposals. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Results obtained from analyses show the RESRAD computer code is able to calculate doses, risks, and guideline values. Sensitivity analysis by the computer code shows that the parameters used as input are justified so as to improve confidence to the public and the AELB the results of the analysis. The computer code can also be used as an initial assessment to conduct screening assessment in order to determine a proper disposal site. (Author)

Earthquake hazard assessment and small earthquakes

International Nuclear Information System (INIS)

Reiter, L.

1987-01-01

The significance of small earthquakes and their treatment in nuclear power plant seismic hazard assessment is an issue which has received increased attention over the past few years. In probabilistic studies, sensitivity studies showed that the choice of the lower bound magnitude used in hazard calculations can have a larger than expected effect on the calculated hazard. Of particular interest is the fact that some of the difference in seismic hazard calculations between the Lawrence Livermore National Laboratory (LLNL) and Electric Power Research Institute (EPRI) studies can be attributed to this choice. The LLNL study assumed a lower bound magnitude of 3.75 while the EPRI study assumed a lower bound magnitude of 5.0. The magnitudes used were assumed to be body wave magnitudes or their equivalents. In deterministic studies recent ground motion recordings of small to moderate earthquakes at or near nuclear power plants have shown that the high frequencies of design response spectra may be exceeded. These exceedances became important issues in the licensing of the Summer and Perry nuclear power plants. At various times in the past particular concerns have been raised with respect to the hazard and damage potential of small to moderate earthquakes occurring at very shallow depths. In this paper a closer look is taken at these issues. Emphasis is given to the impact of lower bound magnitude on probabilistic hazard calculations and the historical record of damage from small to moderate earthquakes. Limited recommendations are made as to how these issues should be viewed

Assessment of radiological technologist health condition by Todai health index

Energy Technology Data Exchange (ETDEWEB)

Kim, Ham Gyum [Ansan College, Ansan (Korea, Republic of); Kim, Wha Sun [College of Medicine, Hanyang Univ., Seoul (Korea, Republic of)

2001-04-01

The purpose of this study was to examine the general health status of radiological technologists by using Todai Health Index(THI) that has been employed as a standard health assessment tool for a specific group. The subjects in this study were 800 radiological technologists who were working in clinics, hospitals and university hospitals in and around Seoul and in some provincial cities. A survey was conducted directly or by mail in June and July, 2001. And the response rate was 68%. Using THI, the following findings were acquired: 1. By gender, both male and female radiological technologists complained about multiple subjective symptom(I) the most, And the women made more significant complaint of eight items including irregular life. 2. By age group, the radiological technologists whose age ranged from 20 to 24 got higher marks in most of the items, including multiple subjective symptom(I) and symptoms related to eyes and skin. 3. For career, those who had worked for a year or less or for one to five years got higher marks in most of the items. 4. Concerning marital status, the unmarried people complained about many items more, and the married people's symptom was more associated with live scale(L). 5. By the type of medical institution, the radiological technologists in the university hospitals got higher marks in two items including aggressiveness(F), but those in the clinics complained about the others more. 6. Regarding a place of service, there were little differences between the radiological technologists in basement and on the ground.

Assessment of radiological technologist health condition by Todai health index

International Nuclear Information System (INIS)

Kim, Ham Gyum; Kim, Wha Sun

2001-01-01

The purpose of this study was to examine the general health status of radiological technologists by using Todai Health Index(THI) that has been employed as a standard health assessment tool for a specific group. The subjects in this study were 800 radiological technologists who were working in clinics, hospitals and university hospitals in and around Seoul and in some provincial cities. A survey was conducted directly or by mail in June and July, 2001. And the response rate was 68%. Using THI, the following findings were acquired: 1. By gender, both male and female radiological technologists complained about multiple subjective symptom(I) the most, And the women made more significant complaint of eight items including irregular life. 2. By age group, the radiological technologists whose age ranged from 20 to 24 got higher marks in most of the items, including multiple subjective symptom(I) and symptoms related to eyes and skin. 3. For career, those who had worked for a year or less or for one to five years got higher marks in most of the items. 4. Concerning marital status, the unmarried people complained about many items more, and the married people's symptom was more associated with live scale(L). 5. By the type of medical institution, the radiological technologists in the university hospitals got higher marks in two items including aggressiveness(F), but those in the clinics complained about the others more. 6. Regarding a place of service, there were little differences between the radiological technologists in basement and on the ground

Radiological Protection Act 1970

International Nuclear Information System (INIS)

1970-01-01

This Act provides for the establishment of a Radiological Protection Board to undertake research and advise on protection from radiation hazards. Its functions include provision of advice to Government departments with responsibilities in relation to protection of sectors of the community or the community as a whole against the hazards of ionizing radiation. The Act, which lays down that the Board shall replace certain departments concerned with radiation protection, repeals several Sections of the Radioactive Substances Act 1948 and the Science and Technology Act 1965. (NEA) [fr

Hazard assessment and risk management of offshore production chemicals

International Nuclear Information System (INIS)

Schobben, H.P.M.; Scholten, M.C.T.; Vik, E.A.; Bakke, S.

1994-01-01

There is a clear need for harmonization of the regulations with regard to the use and discharge of drilling and production chemicals in the North Sea. Therefore the CHARM (Chemical Hazard Assessment and Risk Management) model was developed. Both government (of several countries) and industry (E and P and chemical suppliers) participated in the project. The CHARM model is discussed and accepted by OSPARCON. The CHARM model consists of several modules. The model starts with a prescreening on the basis of hazardous properties like persistency, accumulation potential and the appearance on black lists. The core of the model.consists of modules for hazard assessment and risk analysis. Hazard assessment covers a general environmental evaluation of a chemical on the basis of intrinsic properties of that chemical. Risk analysis covers a more specific evaluation of the environmental impact from the use of a production chemical, or a combination of chemicals, under actual conditions. In the risk management module the user is guided to reduce the total risk of all chemicals used on a platform by the definition of measures in the most cost-effective way. The model calculates the environmental impact for the marine environment. Thereto three parts are distinguished: pelagic, benthic and food chain. Both hazard assessment and risk analysis are based on a proportional comparison of an estimated PEC with an estimated NEC. The PEC is estimated from the use, release, dilution and fate of the chemical and the NEC is estimated from the available toxicity data of the chemicals

Review of Natural Phenomena Hazard (NPH) Assessments for the DOE Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Snow, Robert L.; Ross, Steven B.

2011-09-15

The purpose of this review is to assess the need for updating Natural Phenomena Hazard (NPH) assessments for the DOE's Hanford Site, as required by DOE Order 420.1B Chapter IV, Natural Phenomena Hazards Mitigation, based on significant changes in state-of-the-art NPH assessment methodology or site-specific information. This review is an update and expansion to the September 2010 review of PNNL-19751, Review of Natural Phenomena Hazard (NPH) Assessments for the Hanford 200 Areas (Non-Seismic).

Quantitative physical models of volcanic phenomena for hazards assessment of critical infrastructures

Science.gov (United States)

Costa, Antonio

2016-04-01

Volcanic hazards may have destructive effects on economy, transport, and natural environments at both local and regional scale. Hazardous phenomena include pyroclastic density currents, tephra fall, gas emissions, lava flows, debris flows and avalanches, and lahars. Volcanic hazards assessment is based on available information to characterize potential volcanic sources in the region of interest and to determine whether specific volcanic phenomena might reach a given site. Volcanic hazards assessment is focussed on estimating the distances that volcanic phenomena could travel from potential sources and their intensity at the considered site. Epistemic and aleatory uncertainties strongly affect the resulting hazards assessment. Within the context of critical infrastructures, volcanic eruptions are rare natural events that can create severe hazards. In addition to being rare events, evidence of many past volcanic eruptions is poorly preserved in the geologic record. The models used for describing the impact of volcanic phenomena generally represent a range of model complexities, from simplified physics based conceptual models to highly coupled thermo fluid dynamical approaches. Modelling approaches represent a hierarchy of complexity, which reflects increasing requirements for well characterized data in order to produce a broader range of output information. In selecting models for the hazard analysis related to a specific phenomenon, questions that need to be answered by the models must be carefully considered. Independently of the model, the final hazards assessment strongly depends on input derived from detailed volcanological investigations, such as mapping and stratigraphic correlations. For each phenomenon, an overview of currently available approaches for the evaluation of future hazards will be presented with the aim to provide a foundation for future work in developing an international consensus on volcanic hazards assessment methods.

Assessment of the radiological impact of gamma and radon dose rates at former U mining sites in Tajikistan

International Nuclear Information System (INIS)

Lespukh, E.; Stegnar, P.; Yunusov, M.; Tilloboev, H.; Zyazev, G.; Kayukov, P.; Hosseini, A.; Strømman, G.; Salbu, B.

2013-01-01

An assessment of the radiological situation due to exposure to gamma radiation, radon ( 222 Rn) and thoron ( 220 Rn) was carried out at former uranium (U) mining and processing sites in Taboshar and at Digmai in Tajikistan. Gamma dose rate measurements were made using various field instruments. 222 Rn/ 220 Rn measurements were carried out with field instruments for instantaneous measurements and then discriminative 222 Rn/ 220 Rn solid state nuclear track detectors (SSNTD) were used for longer representative measurements. The detectors were exposed for an extended period of time in different outdoor and indoor public and residential environments at the selected U legacy sites. The results showed that gamma, 222 Rn and 220 Rn doses were in general low, which consequently implies a low to relatively low radiological risk. The radiation doses deriving from external radiation (gamma dose rate), indoor 222 Rn and 220 Rn with their short-lived progenies did not exceed national or international standards. At none of the sites investigated did the average individual annual effective doses exceed 10 mSv, the recommended threshold value for the general public. A radiation hazard could be associated with exceptional situations, such as elevated exposures to ionizing radiation at the Digmai tailings site and/or in industrial facilities, where gamma and 222 Rn/ 220 Rn dose rates could reach values of several 10 mSv/a. Current doses of ionizing radiation do not represent a hazard to the health of the resident public, with the exception of some specific situations. These issues should be adequately addressed to further reduce needless exposure of the resident public to ionizing radiation

Multi Hazard Assessment: The Azores Archipelagos (PT) case

Science.gov (United States)

Aifantopoulou, Dorothea; Boni, Giorgio; Cenci, Luca; Kaskara, Maria; Kontoes, Haris; Papoutsis, Ioannis; Paralikidis, Sideris; Psichogyiou, Christina; Solomos, Stavros; Squicciarino, Giuseppe; Tsouni, Alexia; Xerekakis, Themos

2016-04-01

The COPERNICUS EMS Risk & Recovery Mapping (RRM) activity offers services to support efficient design and implementation of mitigation measures and recovery planning based on EO data exploitation. The Azores Archipelagos case was realized in the context of the FWC 259811 Copernicus EMS RRM, and provides potential impact information for a number of natural disasters. The analysis identified population and assets at risk (infrastructures and environment). The risk assessment was based on hazard and vulnerability of structural elements, road network characteristics, etc. Integration of different hazards and risks was accounted in establishing the necessary first response/ first aid infrastructure. EO data (Pleiades and WV-2), were used to establish a detailed background information, common for the assessment of the whole of the risks. A qualitative Flood hazard level was established, through a "Flood Susceptibility Index" that accounts for upstream drainage area and local slope along the drainage network (Manfreda et al. 2014). Indicators, representing different vulnerability typologies, were accounted for. The risk was established through intersecting hazard and vulnerability (risk- specific lookup table). Probabilistic seismic hazards maps (PGA) were obtained by applying the Cornell (1968) methodology as implemented in CRISIS2007 (Ordaz et al. 2007). The approach relied on the identification of potential sources, the assessment of earthquake recurrence and magnitude distribution, the selection of ground motion model, and the mathematical model to calculate seismic hazard. Lava eruption areas and a volcanic activity related coefficient were established through available historical data. Lava flow paths and their convergence were estimated through applying a cellular, automata based, Lava Flow Hazard numerical model (Gestur Leó Gislason, 2013). The Landslide Hazard Index of NGI (Norwegian Geotechnical Institute) for heavy rainfall (100 year extreme monthly rainfall

Radiation monitoring systems and methodologies for radiological impact assessment

International Nuclear Information System (INIS)

Chaudhury, Probal

2016-01-01

Radioactive sources of various strengths are used in large number of applications in industry, healthcare, agriculture and research. Though all the sources are transported and used under regulatory control, there is always a possibility of some of the sources getting into the hands of committed antisocial non state actors. In addition to this, there is a possible threat of radioactive material being illegally brought into a country. These gives rise to an increase in the global radiological threat and security experts world over are concerned about the possibility of malicious use of radiation in the public domain. Radiation detection systems are installed at various entry and exit ports of some of the countries to detect illicit trafficking of radioactive materials. IAEA has recommended that all States should have a national response plan for nuclear security events to provide for an appropriate and coordinated response. Considering the requirement of radiological emergency preparedness, various radiation monitoring systems and methodologies have been developed. A few aerial radiation monitoring systems developed at Bhabha Atomic Research Centre (BARC) for radiological impact assessment are described here

Probabilistic Approaches for Multi-Hazard Risk Assessment of Structures and Systems

Science.gov (United States)

Kwag, Shinyoung

Performance assessment of structures, systems, and components for multi-hazard scenarios has received significant attention in recent years. However, the concept of multi-hazard analysis is quite broad in nature and the focus of existing literature varies across a wide range of problems. In some cases, such studies focus on hazards that either occur simultaneously or are closely correlated with each other. For example, seismically induced flooding or seismically induced fires. In other cases, multi-hazard studies relate to hazards that are not dependent or correlated but have strong likelihood of occurrence at different times during the lifetime of a structure. The current approaches for risk assessment need enhancement to account for multi-hazard risks. It must be able to account for uncertainty propagation in a systems-level analysis, consider correlation among events or failure modes, and allow integration of newly available information from continually evolving simulation models, experimental observations, and field measurements. This dissertation presents a detailed study that proposes enhancements by incorporating Bayesian networks and Bayesian updating within a performance-based probabilistic framework. The performance-based framework allows propagation of risk as well as uncertainties in the risk estimates within a systems analysis. Unlike conventional risk assessment techniques such as a fault-tree analysis, a Bayesian network can account for statistical dependencies and correlations among events/hazards. The proposed approach is extended to develop a risk-informed framework for quantitative validation and verification of high fidelity system-level simulation tools. Validation of such simulations can be quite formidable within the context of a multi-hazard risk assessment in nuclear power plants. The efficiency of this approach lies in identification of critical events, components, and systems that contribute to the overall risk. Validation of any event or

Radiological safety assessment of Thoron inhalation hazards during DDU handling at UMP, Trombay

International Nuclear Information System (INIS)

Shailesh, M.; Belhe, M.S.; Malti; Narayani, K.; Satpati, S.K.

2012-01-01

Uranium Extraction Division, Bhabha Atomic Research Centre, Mumbai has been producing nuclear grade uranium metal from Ammonium di-uranate received from IRE to meet the fuel requirement of research reactors of Bhabha Atomic Research Centre at Uranium Metal Plant (UMP) in Trombay. In UMP, uranium oxide powder (U 3 O 8 and UO 3 ) is first reduced to uranium dioxide in reduction reactor and is converted to uranium tetra fluoride in hydro fluorination reactor. After removing moisture and acid vapour in expulsion area, reduction of uranium tetrafluoride is carried out with magnesium in magnesio-thermic reduction (MTR) reactor, pure uranium metal ingot with magnesium fluoride slag is produced. Finally natural uranium ingot is separated from slag in ingot discharging area. However deeply depleted uranium (DDU) metal was produced from uranium oxide (reprocessed uranium) received from PREFRE, Tarapur, as a special campaign. External radiation hazards are not dominant during the processing of natural uranium in uranium metal Plant. However it was observed that during processing of DDU metal, external and internal hazards are significant because of daughter products of thoron. Inhalation dose due to thoron was found less during charging of UO 3 powder operation than ingot discharge operation because of pneumatic powder transport system used for charging operation. It is estimated that after introduction of new blower system in different powder handling operation areas, the potential effective inhalation dose due to thoron inhalation may get reduced by 60% - 80%

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

Energy Technology Data Exchange (ETDEWEB)

Dionne, B.J.; Morris, S. III; Baum, J.W. [and others

1998-03-01

The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique.

Multi scenario seismic hazard assessment for Egypt

Science.gov (United States)

Mostafa, Shaimaa Ismail; Abd el-aal, Abd el-aziz Khairy; El-Eraki, Mohamed Ahmed

2018-05-01

Egypt is located in the northeastern corner of Africa within a sensitive seismotectonic location. Earthquakes are concentrated along the active tectonic boundaries of African, Eurasian, and Arabian plates. The study area is characterized by northward increasing sediment thickness leading to more damage to structures in the north due to multiple reflections of seismic waves. Unfortunately, man-made constructions in Egypt were not designed to resist earthquake ground motions. So, it is important to evaluate the seismic hazard to reduce social and economic losses and preserve lives. The probabilistic seismic hazard assessment is used to evaluate the hazard using alternative seismotectonic models within a logic tree framework. Alternate seismotectonic models, magnitude-frequency relations, and various indigenous attenuation relationships were amended within a logic tree formulation to compute and develop the regional exposure on a set of hazard maps. Hazard contour maps are constructed for peak ground acceleration as well as 0.1-, 0.2-, 0.5-, 1-, and 2-s spectral periods for 100 and 475 years return periods for ground motion on rock. The results illustrate that Egypt is characterized by very low to high seismic activity grading from the west to the eastern part of the country. The uniform hazard spectra are estimated at some important cities distributed allover Egypt. The deaggregation of seismic hazard is estimated at some cities to identify the scenario events that contribute to a selected seismic hazard level. The results of this study can be used in seismic microzonation, risk mitigation, and earthquake engineering purposes.

Recent developments in the external hazard risk assessment in Ukraine

International Nuclear Information System (INIS)

2000-01-01

Ukrainian legislation prescribes safety analysis reports for all operating and future NPPs. Apart from main report they must include: safety analysis supplement; design basis accident analysis; beyond design basis accident analysis; probabilistic safety assessment (PSA); technical; substantiation of safety. Regulatory requirements to PSA contents cover the criteria for core damage frequency and large radioactive release frequency. Initiating events taken into account are internal events; internal hazards and external hazards. External hazards to be considered are seismic events, external fires, external floods, extreme ambient temperatures, aircraft crashes, etc. Current status of PSA development is related to operating WWER-440 and WWER-1000 NPPs and NPPs under construction. This presentation describes in detail the external hazard risk assessment for South Ukraine including methodology applied and expected future activities

Afghanistan Multi-Risk Assessment to Natural Hazards

Science.gov (United States)

Diermanse, Ferdinand; Daniell, James; Pollino, Maurizio; Glover, James; Bouwer, Laurens; de Bel, Mark; Schaefer, Andreas; Puglisi, Claudio; Winsemius, Hessel; Burzel, Andreas; Ammann, Walter; Aliparast, Mojtaba; Jongman, Brenden; Ranghieri, Federica; Fallesen, Ditte

2017-04-01

The geographical location of Afghanistan and years of environmental degradation in the country make Afghanistan highly prone to intense and recurring natural hazards such as flooding, earthquakes, snow avalanches, landslides, and droughts. These occur in addition to man-made disasters resulting in the frequent loss of live, livelihoods, and property. Since 1980, disasters caused by natural hazards have affected 9 million people and caused over 20,000 fatalities in Afghanistan. The creation, understanding and accessibility of hazard, exposure, vulnerability and risk information is key for effective management of disaster risk. This is especially true in Afghanistan, where reconstruction after recent natural disasters and military conflicts is on-going and will continue over the coming years. So far, there has been limited disaster risk information produced in Afghanistan, and information that does exist typically lacks standard methodology and does not have uniform geo-spatial coverage. There are currently no available risk assessment studies that cover all major natural hazards in Afghanistan, which can be used to assess the costs and benefits of different resilient reconstruction and disaster risk reduction strategies. As a result, the Government of Afghanistan has limited information regarding current and future disaster risk and the effectiveness of policy options on which to base their reconstruction and risk reduction decisions. To better understand natural hazard and disaster risk, the World Bank and Global Facility for Disaster Reduction and Recovery (GFDRR) are supporting the development of new fluvial flood, flash flood, drought, landslide, avalanche and seismic risk information in Afghanistan, as well as a first-order analysis of the costs and benefits of resilient reconstruction and risk reduction strategies undertaken by the authors. The hazard component is the combination of probability and magnitude of natural hazards. Hazard analyses were carried out

BNL ALARA Center's development of a computerized radiological assessment and design system (RADS)

International Nuclear Information System (INIS)

Dionne, B.J.; Masciulli, S.; Connelly, J.M.

1993-01-01

The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation of DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of good-practice documents will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called Radiological Assessment and Design System (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analyses, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative rating of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

Assessment of mixed hazardous and radioactive waste sites at Hanford

International Nuclear Information System (INIS)

McLaughlin, T.J.; Cramer, K.H.; Lamar, D.A.; Sherwood, D.R.; Stenner, R.D.; Schulze, W.B.

1987-10-01

The US Department of Energy and Pacific Northwest Laboratory recently completed a preliminary assessment of 685 inactive hazardous waste sites located on the Hanford Site. The preliminary assessment involved collecting historical data and individual site information, conducting site inspections, and establishing an environmental impact priority, using the Hazard Ranking System, for each of these 685 sites. This preliminary assessment was the first step in the remediation process required by the Comprehensive Environmental Response, Compensation and Liability Act. This paper presents the results of that preliminary assessment. 10 refs., 4 figs., 1 tab

National-Level Multi-Hazard Risk Assessments in Sub-Saharan Africa

Science.gov (United States)

Murnane, R. J.; Balog, S.; Fraser, S. A.; Jongman, B.; Van Ledden, M.; Phillips, E.; Simpson, A.

2017-12-01

National-level risk assessments can provide important baseline information for decision-making on risk management and risk financing strategies. In this study, multi-hazard risk assessments were undertaken for 9 countries in Sub-Saharan Africa: Cape Verde, Ethiopia, Kenya, Niger, Malawi, Mali, Mozambique, Senegal and Uganda. The assessment was part of the Building Disaster Resilience in Sub-Saharan Africa Program and aimed at supporting the development of multi-risk financing strategies to help African countries make informed decisions to mitigate the socio-economic, fiscal and financial impacts of disasters. The assessments considered hazards and exposures consistent with the years 2010 and 2050. We worked with multiple firms to develop the hazard, exposure and vulnerability data and the risk results. The hazards include: coastal flood, drought, earthquake, landslide, riverine flood, tropical cyclone wind and storm surge, and volcanoes. For hazards expected to vary with climate, the 2050 hazard is based on the IPCC RCP 6.0. Geolocated exposure data for 2010 and 2050 at a 15 arc second ( 0.5 km) resolution includes: structures as a function of seven development patterns; transportation networks including roads, bridges, tunnels and rail; critical facilities such as schools, hospitals, energy facilities and government buildings; crops; population; and, gross domestic product (GDP). The 2050 exposure values for population are based on the IPCC SSP 2. Values for other exposure data are a function of population change. Vulnerability was based on openly available vulnerability functions. Losses were based on replacement values (e.g., cost/m2 or cost/km). Risk results are provided in terms of annual average loss and a variety of return periods at the national and Admin 1 levels. Assessments of recent historical events are used to validate the model results. In the future, it would be useful to use hazard footprints of historical events for validation purposes. The

Measurement of natural radioactivity and assessment of radiation hazard indices in soil samples at Pengerang, Kota Tinggi, Johor

International Nuclear Information System (INIS)

Nur Nazihah Hassan; Khoo, K.S.

2013-01-01

Full-text: Pengerang area consists of a mix of private plantation, individual residential lots and state land, which is leased for agriculture related activities. The analysis was conducted to determine the specific activity of the initial value and the radiation hazard indices in the surrounding area in Pengerang. This area will be developed into a major downstream for oil and gas. The aims of this preliminary study were 1) to determine the specific activities of 238 U, 232 Th, 226 Ra and 40 K of soil samples at six selected areas by Gamma-ray spectrometry and 2) to calculate the radiation hazard indices. The specific activities (Bq/ kg) of the samples ranged from 7.08 ± 5.01 to 36.29 ± 25.72 Bq/ kg, 5.62 ± 3.98 to 34.53 ± 24.07 Bq/ kg, 4.75 ± 3.42 to 24.76 ± 17.66 Bq/ kg and 10.58 ± 7.51 to 101.25 ± 72.00 Bq/ kg for 238 U, 232 Th, 226 Ra and 40 K, respectively. These values were well within the range that reported by UNSCEAR. The study also examined the radiation hazard indices, the mean values obtained were 48.49 ± 28.06 Bq/ kg for Radium Equivalent Activity (Ra eq ), 0.34 Bq/ kg for Representative Level Index (Iγ), 21.83 nGy/ h for Absorbed dose rates (D), 0.27 mSv/y for Annual Effective Dose Rates (D eff ), 0.13 and 0.18 for External Hazards Index (H ex ) and Internal Hazard Index (H in ), respectively. These calculated hazard indices were used to estimate the potential radiological health risk in soil and the dose rates associated with it were well below their permissible limit. The overall findings show that no radiological threat to the health of the population in the study area. (author)

Measurement of natural radioactivity and assessment of radiation hazard indices in soil samples at Pengerang, Kota Tinggi, Johor

Science.gov (United States)

Hassan, Nur Nazihah; Khoo, Kok Siong

2014-02-01

Pengerang area consists of a mix of private plantation, individual residential lots and state land, which is leased for agriculture related activities. The analysis was conducted to determine the specific activity of the initial value and the radiation hazard indices in the surrounding area in Pengerang. This area will be developed into a major downstream for oil and gas. The aims of this preliminary study were 1) to determine the specific activities of 238U, 232Th, 226Ra and 40K of soil samples at six selected areas by Gamma-ray spectrometry and 2) to calculate the radiation hazard indices. The specific activities (Bq/kg) of the samples ranged from 7.08±5.01 to 36.29±25.72 Bq/kg, 5.62±3.98 to 34.53±24.07 Bq/kg, 4.75±3.42 to 24.76±17.66 Bq/kg and 10.58±7.51 to 101.25±72.00 Bq/kg for 238U, 232Th, 226Ra and 40K, respectively. These values were well within the range that reported by UNSCEAR. The study also examined the radiation hazard indices, the mean values obtained were 48.49±28.06 Bq/kg for Radium Equivalent Activity (Raeq), 0.34 Bq/kg for Representative Level Index (Iγ), 21.83 nGy/h for Absorbed dose rates (D), 0.27 mSv/y for Annual Effective Dose Rates (Deff), 0.13 and 0.18 for External Hazards Index (Hex) and Internal Hazard Index (Hin), respectively. These calculated hazard indices were used to estimate the potential radiological health risk in soil and the dose rates associated with it were well below their permissible limit. The overall findings show that no radiological threat to the health of the population in the study area.

Measurement of natural radioactivity and assessment of radiation hazard indices in soil samples at Pengerang, Kota Tinggi, Johor

International Nuclear Information System (INIS)

Hassan, Nur Nazihah; Khoo, Kok Siong

2014-01-01

Pengerang area consists of a mix of private plantation, individual residential lots and state land, which is leased for agriculture related activities. The analysis was conducted to determine the specific activity of the initial value and the radiation hazard indices in the surrounding area in Pengerang. This area will be developed into a major downstream for oil and gas. The aims of this preliminary study were 1) to determine the specific activities of 238 U, 232 Th, 226 Ra and 40 K of soil samples at six selected areas by Gamma-ray spectrometry and 2) to calculate the radiation hazard indices. The specific activities (Bq/kg) of the samples ranged from 7.08±5.01 to 36.29±25.72 Bq/kg, 5.62±3.98 to 34.53±24.07 Bq/kg, 4.75±3.42 to 24.76±17.66 Bq/kg and 10.58±7.51 to 101.25±72.00 Bq/kg for 238 U, 232 Th, 226 Ra and 40 K, respectively. These values were well within the range that reported by UNSCEAR. The study also examined the radiation hazard indices, the mean values obtained were 48.49±28.06 Bq/kg for Radium Equivalent Activity (Raeq), 0.34 Bq/kg for Representative Level Index (I γ ), 21.83 nGy/h for Absorbed dose rates (D), 0.27 mSv/y for Annual Effective Dose Rates (Deff), 0.13 and 0.18 for External Hazards Index (H ex ) and Internal Hazard Index (H in ), respectively. These calculated hazard indices were used to estimate the potential radiological health risk in soil and the dose rates associated with it were well below their permissible limit. The overall findings show that no radiological threat to the health of the population in the study area

Radiological assessment for the dumping of radioactive wastes in the oceans

International Nuclear Information System (INIS)

Templeton, W.L.

1993-06-01

Over the last three decades or so, a number of international meetings have been convened to treat the specific problem of radioactive waste disposal into the oceans. The first of these meetings was held in 1958 at the United Nations Conference on the Law of the Sea. Immediately following, the International Atomic Energy Agency (IAEA), in the Brynielsson Report, recommended measures for ensuring that disposal of radioactive waste into the sea would not result in unacceptable hazards to man (IAEA 1961). Since that time, major changes have occurred in the philosophy and recommendations of the International Commission on Radiological Protection that are crucial to the assessments of impacts arising from this practice. Knowledge of oceanographic processes has improved markedly, providing better understanding of the physical transport process and of the pathways by which radionuclides are transported from marine dumping and disposal sites back to man. Finally, radioecology has developed to the stage where predictions of radionuclide cycling pathways and rates are possible. The IAEA report of 1961 was revised in 1983 (IAEA 1983). The IAEA has published many documents (Safety Series and Technical Documents) covering relevant areas such as oceanographic models, bioaccumulation factors, sediment distribution coefficients, and effects of ionizing radiation on organisms

Application of the Coastal Hazard Wheel methodology for coastal multi-hazard assessment and management in the state of Djibouti

DEFF Research Database (Denmark)

Appelquist, Lars Rosendahl; Balstrøm, Thomas

2014-01-01

coastal classification system that incorporates the main static and dynamic parameters determining the characteristics of a coastal environment. The methodology provides information on the hazards of ecosystem disruption, gradual inundation, salt water intrusion, erosion and flooding and can be used...... to support management decisions at local, regional and national level, in areas with limited access to geophysical data. The assessment for Djibouti applies a geographic information system (GIS) to develop a range of national hazard maps along with relevant hazard statistics and is showcasing the procedure......This paper presents the application of a new methodology for coastal multi-hazard assessment and management in a changing global climate on the state of Djibouti. The methodology termed the Coastal Hazard Wheel (CHW) is developed for worldwide application and is based on a specially designed...

Bayesian network learning for natural hazard assessments

Science.gov (United States)

Vogel, Kristin

2016-04-01

Even though quite different in occurrence and consequences, from a modelling perspective many natural hazards share similar properties and challenges. Their complex nature as well as lacking knowledge about their driving forces and potential effects make their analysis demanding. On top of the uncertainty about the modelling framework, inaccurate or incomplete event observations and the intrinsic randomness of the natural phenomenon add up to different interacting layers of uncertainty, which require a careful handling. Thus, for reliable natural hazard assessments it is crucial not only to capture and quantify involved uncertainties, but also to express and communicate uncertainties in an intuitive way. Decision-makers, who often find it difficult to deal with uncertainties, might otherwise return to familiar (mostly deterministic) proceedings. In the scope of the DFG research training group „NatRiskChange" we apply the probabilistic framework of Bayesian networks for diverse natural hazard and vulnerability studies. The great potential of Bayesian networks was already shown in previous natural hazard assessments. Treating each model component as random variable, Bayesian networks aim at capturing the joint distribution of all considered variables. Hence, each conditional distribution of interest (e.g. the effect of precautionary measures on damage reduction) can be inferred. The (in-)dependencies between the considered variables can be learned purely data driven or be given by experts. Even a combination of both is possible. By translating the (in-)dependences into a graph structure, Bayesian networks provide direct insights into the workings of the system and allow to learn about the underlying processes. Besides numerous studies on the topic, learning Bayesian networks from real-world data remains challenging. In previous studies, e.g. on earthquake induced ground motion and flood damage assessments, we tackled the problems arising with continuous variables

Preliminary radiological assessments of near-surface low-level radioactive waste repositories

International Nuclear Information System (INIS)

Sumerling, T.J.; Nancarrow, D.J.

1988-08-01

This report summarises preliminary assessments of post-closure radiological impact of LLW repositories at four sites previously under investigation by UK Nirex Ltd. The objectives of the assessments were: to demonstrate a methodology for site specific assessments, to identify important information requirements for detailed assessments; to identify methodological and research requirements. Doses and risks due to groundwater pathways, human intrusion, gaseous release and natural environmental change are estimated. (author)

Harmonizing seismic hazard assessments for nuclear power plants

International Nuclear Information System (INIS)

Mallard, D.J.

1993-01-01

Even a cursory comparison between maps of global seismicity and NPP earthquake design levels reveals many inconsistencies. While, in part, this situation reflects the evolution in understanding of seismic hazards, mismatches can also be due to ongoing differences in the way the hazards are assessed and in local regulatory requirements. So far, formal international consensus has only been able to encompass broad principles, such as those recently recommended by the International Atomic Energy Agency, and even these can raise many technical issues, particularly relating to zones of diffuse seismicity. In the future, greater harmonisation in hazard assessments and, to some extent, in earthquake design levels could emerge through the more widespread use of probabilistic methods. International collaborative ventures and joint projects will be important for resolving anomalies in the existing databases and their interpretations, and for acquiring new data, but to achieve their ideal objectives, they will need to proceed in clearly defined stages. (author)

Y-12 National Security Complex Emergency Management Hazards Assessment (EMHA) Process; FINAL

International Nuclear Information System (INIS)

Bailiff, E.F.; Bolling, J.D.

2001-01-01

This document establishes requirements and standard methods for the development and maintenance of the Emergency Management Hazards Assessment (EMHA) process used by the lead and all event contractors at the Y-12 Complex for emergency planning and preparedness. The EMHA process provides the technical basis for the Y-12 emergency management program. The instructions provided in this document include methods and requirements for performing the following emergency management activities at Y-12: (1) hazards identification; (2) hazards survey, and (3) hazards assessment

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

Assessing radiological impacts (exposures and doses) associated with the mining and milling of radioactive ores

International Nuclear Information System (INIS)

Williams, G.A.

1990-01-01

The basic units and concepts applicable to radiological assessment are presented. Data relevant to the assessment of radiological exposures from the mining and milling phases of uranium and thorium ores are discussed. As a guide to the assessment of environmental exposures to members of the public, concepts such as the critical group are defined. Environmental transport and exposure pathways are presented in general terms, together with a discussion of the use of mathematical models. The dose assessment procedures defined in the 1987 Code of Practice are described. 13 refs., 2 tabs., 1 fig

Geomorphological hazards and environmental impact: Assessment and mapping

Science.gov (United States)

Panizza, Mario

In five sections the author develops the methods for the integration of geomorphological concepts into Environmental Impact and Mapping. The first section introduces the concepts of Impact and Risk through the relationships between Geomorphological Environment and Anthropical Element. The second section proposes a methodology for the determination of Geomorphological Hazard and the identification of Geomorphological Risk. The third section synthesizes the procedure for the compilation of a Geomorphological Hazards Map. The fourth section outlines the concepts of Geomorphological Resource Assessment for the analysis of the Environmental Impact. The fifth section considers the contribution of geomorphological studies and mapping in the procedure for Environmental Impact Assessment.

Role of radiology in occupational medicine

International Nuclear Information System (INIS)

Vehmas, T.

2004-01-01

This review discusses the contribution of radiology to occupational medicine as well as work-related problems in radiology dept.s. Research issues are emphasized. Radiology has been used especially when diagnosing occupational respiratory and locomotive system problems and solvent-induced encephalo- and hepatopathy. The aim of research in these areas is usually to characterize occupational diseases and to identify physico-chemical hazards in the work place by comparing between groups of workers and non-exposed controls. Radiological imaging allows an objective characterization of the disease, and it may clarify the pathogenesis of the process and provide a useful epidemiological tool. Advanced statistical methods are often needed to adjust analyses for confounding variables. As the diagnostic requirements are increasing, more sensitive and sophisticated radiological methods, such as high-resolution computed tomography, magnetic resonance imaging and magnetic resonance spectroscopy, may be required for the early recognition of occupational health risks. This necessitates good cooperation between occupational health units and well-equipped imaging dept.s. Considering occupational problems in radiology departments, the increasing use of digital radiology requires ergonomic measures to control and prevent locomotive problems caused by work with computers. Radiation protection measures are still worth concern, especially in interventional radiology

Assessment and classification of hazardous street trees in University ...

African Journals Online (AJOL)

The study was carried out to assessed and classified hazardous trees within the University of Ibadan (UI) campus, Oyo State, Nigeria. The study population was 25 municipal tree species comprising of 420 individual trees located along the major roads of the study area, which were considered hazardous to the community.

Hanford B Reactor Building Hazard Assessment Report

International Nuclear Information System (INIS)

Griffin, P. W.

1999-01-01

The 105-B Reactor (hereinafter referred to as B Reactor) is located in the 100 Area of the Hanford Site near Richland, Washington. The B Reactor is one of nine plutonium production reactors that were constructed in the 1940s during the Cold War Era. Construction of the B Reactor began June 7, 1943, and operation began on September 26, 1944. The Environmental Restoration Contractor was requested by RL to provide an assessment/characterization of the B Reactor building to determine and document the hazards that are present and could pose a threat to the environment and/or to individuals touring the building. This report documents the potential hazards, determines the feasibility of mitigating the hazards, and makes recommendations regarding areas where public tour access should not be permitted

Assessment of the radiological control at the IPEN radioisotope production facility

International Nuclear Information System (INIS)

Carneiro, Janete C.G.G.; Sanches, Matias P.; Rodrigues, Demerval L.; Campos, Daniela; Nogueira, Paulo R.; Damato, Sandra R.; Pecequilo, Brigitte R.

2014-01-01

The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Instituto de Pesquisas Energeticas e Nucleares, IPEN/SP, and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in charcoal and paper filters) at the workplace during radioisotope production were 131 I, 99m Tc and 99 Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m 3 ), the activities concentrations also remained below the maximum permissible values, excepting to 125 I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y -1 , below the ICRP 103 recommended limit of 20 mSv.y -1 for workers. (author)

Analysis and Assessment of Parameters Shaping Methane Hazard in Longwall Areas

Directory of Open Access Journals (Sweden)

Eugeniusz Krause

2013-01-01

Full Text Available Increasing coal production concentration and mining in coal seams of high methane content contribute to its growing emission to longwall areas. In this paper, analysis of survey data concerning the assessment of parameters that influence the level of methane hazard in mining areas is presented. The survey was conducted with experts on ventilation and methane hazard in coal mines. The parameters which influence methane hazard in longwall areas were assigned specific weights (numerical values. The summary will show which of the assessed parameters have a strong, or weak, influence on methane hazard in longwall areas close to coal seams of high methane content.

Radiological emergency assessment of local decision support system

International Nuclear Information System (INIS)

Breznik, B.; Kusar, A.; Boznar, M.Z.; Mlakar, P.

2003-01-01

Local decision support system has been developed based on the needs of Krsko Nuclear Power Plant for quick dose projection and it is one of important features required for proposal of intervention before actual release may occur. Radiological emergency assessment in the case of nuclear accident is based on plant status analysis, radiation monitoring data and on prediction of release of radioactive sources to the environment. There are possibilities to use automatic features to predict release source term and manual options for selection of release parameters. Advanced environmental modelling is used for assessment of atmospheric dispersion of radioactive contamination in the environment. (author)

Assessing Expertise in Radiology : Evaluating and Improving the Assessment of Knowledge and Image Interpretation Skill

NARCIS (Netherlands)

Ravesloot, C.J.

2016-01-01

Aim: Expert radiologists are excellent image interpreters. Unfortunately, image interpretation errors are frequent even among experienced radiologists and not much is known about which factors lead to expertise. Increasing assessment quality can improve radiological performance. Progress tests can

Radiological dose assessment of naturally occurring radioactive materials in concrete building materials

International Nuclear Information System (INIS)

Amran AB Majid; Aznan Fazli Ismail; Muhamad Samudi Yasir; Redzuwan Yahaya; Ismail Bahari

2013-01-01

Previous studies have shown that the natural radioactivity contained in building materials have significantly influenced the dose rates in dwelling. Exposure to natural radiation in building has been of concerned since almost 80 % of our daily live are spend indoor. Thus, the aim of the study is to assess the radiological risk associated by natural radioactivity in soil based building materials to dwellers. A total of 13 Portland cement, 46 sand and 43 gravel samples obtained from manufacturers or bought directly from local hardware stores in Peninsular of Malaysia were analysed for their radioactivity concentrations. The activity concentrations of 226 Ra, 232 Th and 40 K in the studied building materials samples were found to be in the range of 3.7-359.3, 2.0-370.8 and 10.3-1,949.5 Bq kg -1 respectively. The annual radiation dose rates (μSv year -1 ) received by dwellers were evaluated for 1 to 50 years of exposure using Resrad-Build Computer Code based on the activity concentration of 226 Ra, 232 Th and 40 K found in the studied building material samples. The rooms modelling were based on the changing parameters of concrete wall thickness and the room dimensions. The annual radiation dose rates to dwellers were found to increase annually over a period of 50 years. The concrete thicknesses were found to have significantly influenced the dose rates in building. The self-absorption occurred when the concrete thickness was thicker than 0.4 m. Results of this study shows that the dose rates received by the dwellers of the building are proportional to the size of the room. In general the study concludes that concrete building materials; Portland cements, sands, and gravels in Peninsular of Malaysia does not pose radiological hazard to the building dwellers. (author)

BNL ALARA center's development of a computerized Radiological Assessment and Design System (RADS)

International Nuclear Information System (INIS)

Dionne, B.J.; Connelly, J.M.

1993-01-01

The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation at DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of open-quotes good-practice documentsclose quotes will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called open-quotes Radiological Assessment and Design Systemclose quotes (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analysis, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative ratings of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

Assessment of volcanic hazards, vulnerability, risk and uncertainty (Invited)

Science.gov (United States)

Sparks, R. S.

2009-12-01

A volcanic hazard is any phenomenon that threatens communities . These hazards include volcanic events like pyroclastic flows, explosions, ash fall and lavas, and secondary effects such as lahars and landslides. Volcanic hazards are described by the physical characteristics of the phenomena, by the assessment of the areas that they are likely to affect and by the magnitude-dependent return period of events. Volcanic hazard maps are generated by mapping past volcanic events and by modelling the hazardous processes. Both these methods have their strengths and limitations and a robust map should use both approaches in combination. Past records, studied through stratigraphy, the distribution of deposits and age dating, are typically incomplete and may be biased. Very significant volcanic hazards, such as surge clouds and volcanic blasts, are not well-preserved in the geological record for example. Models of volcanic processes are very useful to help identify hazardous areas that do not have any geological evidence. They are, however, limited by simplifications and incomplete understanding of the physics. Many practical volcanic hazards mapping tools are also very empirical. Hazards maps are typically abstracted into hazards zones maps, which are some times called threat or risk maps. Their aim is to identify areas at high levels of threat and the boundaries between zones may take account of other factors such as roads, escape routes during evacuation, infrastructure. These boundaries may change with time due to new knowledge on the hazards or changes in volcanic activity levels. Alternatively they may remain static but implications of the zones may change as volcanic activity changes. Zone maps are used for planning purposes and for management of volcanic crises. Volcanic hazards maps are depictions of the likelihood of future volcanic phenomena affecting places and people. Volcanic phenomena are naturally variable, often complex and not fully understood. There are

Radiological assistance program: Region I. Part I

International Nuclear Information System (INIS)

Musolino, S.V.; Kuehner, A.V.; Hull, A.P.

1985-01-01

The purpose of the Radiological Assistance Program (RAP) is to make DOE resources available and provide emergency assistance to state and local agencies in order to control radiological hazards, protect the public health and safety, and minimize the loss of property. This plan is an integral part of a nationwide program of radiological assistance established by the US DOE, and is implemented on a regional basis. The Brookhaven Area Office (BHO) Radiological Assistance Program is applicable to DOE Region I, which consists of the New England States, New York, New Jersey, Pennsylvania, Delaware, Maryland and the District of Columbia. The BHO RAP-1 has been developed to: (a) ensure the availability of an effective radiological assistance capability to ensure the protection of persons and property; (b) provide guidelines to RAP-1 Team personnel for the evaluation of radiological incidents and implementation of corrective actions; (c) maintain liaison with other DOE installations, Federal, State and local organizations which may become involved in radiological assistance operations in Region I; and (d) encourage development of a local capability to cope with radiological incidents

Preliminary Hazards Analysis Plasma Hearth Process

International Nuclear Information System (INIS)

Aycock, M.; Coordes, D.; Russell, J.; TenBrook, W.; Yimbo, P.

1993-11-01

This Preliminary Hazards Analysis (PHA) for the Plasma Hearth Process (PHP) follows the requirements of United States Department of Energy (DOE) Order 5480.23 (DOE, 1992a), DOE Order 5480.21 (DOE, 1991d), DOE Order 5480.22 (DOE, 1992c), DOE Order 5481.1B (DOE, 1986), and the guidance provided in DOE Standards DOE-STD-1027-92 (DOE, 1992b). Consideration is given to ft proposed regulations published as 10 CFR 830 (DOE, 1993) and DOE Safety Guide SG 830.110 (DOE, 1992b). The purpose of performing a PRA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PRA then is followed by a Preliminary Safety Analysis Report (PSAR) performed during Title I and II design. This PSAR then leads to performance of the Final Safety Analysis Report performed during construction, testing, and acceptance and completed before routine operation. Radiological assessments indicate that a PHP facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous material assessments indicate that a PHP facility will be a Low Hazard facility having no significant impacts either onsite or offsite to personnel and the environment

The radiological accident in Yanango

International Nuclear Information System (INIS)

2000-01-01

The use of nuclear technologies has fostered new, more effective and efficient medical procedures and has substantially improved diagnostic and therapeutic capabilities. However, in order that the benefits of the use of ionizing radiation outweigh the potential hazards posed by this medium, it is important that radiation protection and safety standards be established to govern every aspect of the application of ionizing radiation. Adherence to these standards needs to be maintained through effective regulatory control, safe operational procedures and a safety culture that is shared by all. Occasionally, established safety procedures are violated and serious radiological consequences ensue. The radiological accident described in this report, which took place in Lilo, Georgia, was a result of such an infraction. Sealed radiation sources had been abandoned by a previous owner at a site without following established regulatory safety procedures, for example by transferring the sources to the new owner or treating them as spent material and conditioning them as waste. As a consequence, 11 individuals at the site were exposed for a long period of time to high doses of radiation which resulted inter alia in severe radiation induced skin injuries. Although at the time of the accident Georgia was not an IAEA Member State and was not a signatory of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, the IAEA still provided assistance to the Government of Georgia in assessing the radiological situation, while the World Health Organization (WHO) assisted in alleviating the medical consequences of the accident. The two organizations co-operated closely from the beginning, following the request for assistance by the Georgian Government. The IAEA conducted the radiological assessment and was responsible for preparing the report. The WHO and its collaborating centres within the Radiation Emergency Medical Preparedness and Assistance Network

Management of a radiological emergency. Organization and operation

International Nuclear Information System (INIS)

Dubiau, Ph.

2007-01-01

After a recall of potential radiological emergency situations and their associated risks, this article describes the organization in France of the crisis management and its operation at the national and international scale: 1 - Nuclear or radiological emergency situations and their associated risks: inventory of ionising radiation sources, accidental situations, hazards; 2 - crisis organization in situation of radiological or nuclear emergency: organization at the local scale, organization at the national scale; 3 - management of emergency situations: accident at a facility, action circle, radiological emergency situations outside nuclear facilities, international management of crisis, situations that do not require the implementation of an emergency plan. (J.S.)

CUEX methodology for assessing radiological impacts in the context of ICRP Recommendations

International Nuclear Information System (INIS)

Rohwer, P.S.; Kaye, S.V.; Struxness, E.G.

1975-01-01

The Cumulative Exposure Index (CUEX) methodology was developed to estimate and assess, in the context of International Commission on Radiological Protection (ICRP) Recommendations, the total radiation dose to man due to environmental releases of radioactivity from nuclear applications. Each CUEX, a time-integrated radionuclide concentration (e.g.μCi.h.cm -3 ), reflects the selected annual dose limit for the reference organ and the estimated total dose to that organ via all exposure modes for a specific exposure situation. To assess the radiological significance of an environmental release of radioactivity, calculated or measured radionuclide concentrations in a suitable environmental sampling medium are compared with CUEXs determined for that medium under comparable conditions. The models and computer codes used in the CUEX methodology to predict environmental transport and to estimate radiation dose have been thoroughly tested. These models and codes are identified and described briefly. Calculation of a CUEX is shown step by step. An application of the methodology to a hypothetical atmospheric release involving four radionuclides illustrates use of the CUEX computer code to assess the radiological significance of a release, and to determine the relative importance (i.e. percentage of the estimated total dose contributed) of each radionuclide and each mode of exposure. The data requirements of the system are shown to be extensive, but not excessive in view of the assessments and analyses provided by the CUEX code. (author)

The assessment of tornado missile hazard to nuclear power plants

International Nuclear Information System (INIS)

Goodman, J.; Koch, J.E.

1983-01-01

Numerical methods and computer codes for assessing tornado missile hazards to nuclear power plants are developed. Due to the uncertainty and randomness of tornado and tornado-generated missiles' characteristics, the damage probability of targets has a highly spread distribution. The proposed method is useful for assessing the risk of not providing protection to some nonsafety-related targets whose failure can create a hazard to the safe operation of nuclear power plants

Recommended radiological controls for tritium operations

International Nuclear Information System (INIS)

Mansfield, G.

1992-01-01

This informal report presents recommendations for an adequate radiological protection program for tritium operations. Topics include hazards analysis, facility design, personnel protection equipment, training, operational procedures, radiation monitoring, to include surface and airborne tritium contamination, and program management

A global probabilistic tsunami hazard assessment from earthquake sources

Science.gov (United States)

Davies, Gareth; Griffin, Jonathan; Lovholt, Finn; Glimsdal, Sylfest; Harbitz, Carl; Thio, Hong Kie; Lorito, Stefano; Basili, Roberto; Selva, Jacopo; Geist, Eric L.; Baptista, Maria Ana

2017-01-01

Large tsunamis occur infrequently but have the capacity to cause enormous numbers of casualties, damage to the built environment and critical infrastructure, and economic losses. A sound understanding of tsunami hazard is required to underpin management of these risks, and while tsunami hazard assessments are typically conducted at regional or local scales, globally consistent assessments are required to support international disaster risk reduction efforts, and can serve as a reference for local and regional studies. This study presents a global-scale probabilistic tsunami hazard assessment (PTHA), extending previous global-scale assessments based largely on scenario analysis. Only earthquake sources are considered, as they represent about 80% of the recorded damaging tsunami events. Globally extensive estimates of tsunami run-up height are derived at various exceedance rates, and the associated uncertainties are quantified. Epistemic uncertainties in the exceedance rates of large earthquakes often lead to large uncertainties in tsunami run-up. Deviations between modelled tsunami run-up and event observations are quantified, and found to be larger than suggested in previous studies. Accounting for these deviations in PTHA is important, as it leads to a pronounced increase in predicted tsunami run-up for a given exceedance rate.

Probabilistic Seismic Hazard Assessment for Iraq

Energy Technology Data Exchange (ETDEWEB)

Onur, Tuna [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gok, Rengin [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Abdulnaby, Wathiq [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Shakir, Ammar M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mahdi, Hanan [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Numan, Nazar M.S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Al-Shukri, Haydar [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chlaib, Hussein K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ameen, Taher H. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Abd, Najah A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-05-06

Probabilistic Seismic Hazard Assessments (PSHA) form the basis for most contemporary seismic provisions in building codes around the world. The current building code of Iraq was published in 1997. An update to this edition is in the process of being released. However, there are no national PSHA studies in Iraq for the new building code to refer to for seismic loading in terms of spectral accelerations. As an interim solution, the new draft building code was considering to refer to PSHA results produced in the late 1990s as part of the Global Seismic Hazard Assessment Program (GSHAP; Giardini et al., 1999). However these results are: a) more than 15 years outdated, b) PGA-based only, necessitating rough conversion factors to calculate spectral accelerations at 0.3s and 1.0s for seismic design, and c) at a probability level of 10% chance of exceedance in 50 years, not the 2% that the building code requires. Hence there is a pressing need for a new, updated PSHA for Iraq.

Assessment of radiological referral practice and effect of computer-based guidelines on radiological requests in two emergency departments

Energy Technology Data Exchange (ETDEWEB)

Carton, Matthieu; Auvert, Bertran; Guerini, Henri; Boulard, Jean-Christophe; Heautot, Jean-Francois; Landre, Marie-France; Beauchet, Alain; Sznajderi, Marc; Brun-Ney, Dominique; Chagnon, Sophie

2002-02-01

AIM: To assess medical emergency radiology referral practice compared with a set of French guidelines and to measure the efficiency of computer-based guidelines on unnecessary medical imaging. MATERIALS AND METHODS: All radiological requests were computerized in the medical emergency departments of two French teaching hospitals. During control periods, radiological requests were recorded but no action was taken. During intervention periods, reminder displays on screen indicated the appropriate recommendations. Three control and three intervention periods of 1 month each were conducted. The percentage of requests that did not conform to the guidelines and variation related to periods of control and intervention were measured. RESULTS: The proportion of requests that did not conform to the guidelines was 33{center_dot}2% when the guidelines were inactive and decreased to 26{center_dot}9% when the recommendations were active (P < 0{center_dot}0001). The three imaging examinations (chest radiographs, abdominal plain radiographs and CT of the brain) accounted for more than 80% of all requests; more than 50% of abdominal plain radiographs requests did not conform with recommendations while this percentage was respectively 24{center_dot}9% and 15{center_dot}8% for chest radiographs and computed tomography (CT) of the brain. Seven situations accounted for 70% of non-conforming radiological referrals; in these situations, junior practitioners' knowledge was inadequate. CONCLUSION: While the computer provided advice that was tailored to the needs of individual patients, concurrent with care, the effect of our intervention was weak. However, our study identified the few situations that were responsible for the majority of unnecessary radiological requests; we expect that this result could help clinicians and radiologists to develop more specific actions for these situations. Carton, M. et al. (2002). Clinical Radiology (2002)

Assessment of radiological referral practice and effect of computer-based guidelines on radiological requests in two emergency departments

International Nuclear Information System (INIS)

Carton, Matthieu; Auvert, Bertran; Guerini, Henri; Boulard, Jean-Christophe; Heautot, Jean-Francois; Landre, Marie-France; Beauchet, Alain; Sznajderi, Marc; Brun-Ney, Dominique; Chagnon, Sophie

2002-01-01

AIM: To assess medical emergency radiology referral practice compared with a set of French guidelines and to measure the efficiency of computer-based guidelines on unnecessary medical imaging. MATERIALS AND METHODS: All radiological requests were computerized in the medical emergency departments of two French teaching hospitals. During control periods, radiological requests were recorded but no action was taken. During intervention periods, reminder displays on screen indicated the appropriate recommendations. Three control and three intervention periods of 1 month each were conducted. The percentage of requests that did not conform to the guidelines and variation related to periods of control and intervention were measured. RESULTS: The proportion of requests that did not conform to the guidelines was 33·2% when the guidelines were inactive and decreased to 26·9% when the recommendations were active (P < 0·0001). The three imaging examinations (chest radiographs, abdominal plain radiographs and CT of the brain) accounted for more than 80% of all requests; more than 50% of abdominal plain radiographs requests did not conform with recommendations while this percentage was respectively 24·9% and 15·8% for chest radiographs and computed tomography (CT) of the brain. Seven situations accounted for 70% of non-conforming radiological referrals; in these situations, junior practitioners' knowledge was inadequate. CONCLUSION: While the computer provided advice that was tailored to the needs of individual patients, concurrent with care, the effect of our intervention was weak. However, our study identified the few situations that were responsible for the majority of unnecessary radiological requests; we expect that this result could help clinicians and radiologists to develop more specific actions for these situations. Carton, M. et al. (2002). Clinical Radiology (2002)

Radiological hazard assessment of extracorporeal shock wave lithotripsy devices

International Nuclear Information System (INIS)

Sprague, D.D.; Vermeere, W.R.

1987-01-01

With the recent introduction of ESWL to the clinical environment, a new health physics challenge has entered the medical consulting area. The x-ray imaging systems used in the devices are of a conventional design, but in an unusual configuration that is difficult to properly assess. The scope of this paper considers specific evaluation problems, and deals with methods developed during experience with 4 units in California. Pertinent regulations are also covered, along with a synopsis of data obtained and ALARA recommendations

Electrical Switchgear Building No. 5010-ESF Fire Hazards Technical Report

International Nuclear Information System (INIS)

N.M. Ruonavaara

2001-01-01

The purpose of this Fire Hazards Analysis Technical Report (hereinafter referred to as Technical Report) is to assess the risk from fire within individual fire areas to ascertain whether the U.S. Department of Energy (DOE) fire safety objectives are met. The objectives, identified in DOE Order 420.1, Change 2, Fire Safety, Section 4.2, establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: (1) The occurrence of a fire or related event; (2) A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of the employees, the public, and the environment; (3) Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards; (4) Property losses from a fire and related events exceeding defined limits established by DOE; and (5) Critical process controls and safety class systems being damaged as a result of a fire and related event

RCT: Module 2.11, Radiological Work Coverage, Course 8777

Energy Technology Data Exchange (ETDEWEB)

Hillmer, Kurt T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-07-20

Radiological work is usually approved and controlled by radiation protection personnel by using administrative and procedural controls, such as radiological work permits (RWPs). In addition, some jobs will require working in, or will have the potential for creating, very high radiation, contamination, or airborne radioactivity areas. Radiological control technicians (RCTs) providing job coverage have an integral role in controlling radiological hazards. This course will prepare the student with the skills necessary for RCT qualification by passing quizzes, tests, and the RCT Comprehensive Phase 1, Unit 2 Examination (TEST 27566) and will provide in-the-field skills.

Radiological impact assessment of arc welding supplies rutile

International Nuclear Information System (INIS)

Rozas Guinea, S.; Herranz Soler, M.; Perez Marin, C.; Idoeta Hermandorena, R.; Alegria gutierrez, N.; Nunez-Lagos Rogla, R.; Legarda Ibanez, F.

2013-01-01

Consumables for welding containing rutile, the coating of the electrode or the filling of tubular thread, are the most widely used and also the most radioactive since the rutile is a mineral containing traces of natural radionuclides, and is therefore considered Normal Occurring Radioactive Material (NORM). As these electrodes and wire are consumed, small particles, aerosols and gases are emitted to the atmosphere of work, and may be inhaled by the welder. Therefore, and also according to the current regulatory framework and work carried out previously by the author on the radiological impact of the process of manufacture and storage of coated rutile electrodes, the objectives are: 1Calcular the internal dose for inhalation during two types of welding, one with electrodes coated and the other with thread. 2 calculate the external dose due to the deposition of particles in the work environment, slag and the immersion of the soldering iron in the cloud of smoke. 3 to assess the radiological impact. (Author)

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

Energy Technology Data Exchange (ETDEWEB)

Dionne, B.J.; Morris, S.C. III; Baum, J.W. [and others

1998-01-01

The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report.

Radiology now. The ten day rule - principles and practice

Energy Technology Data Exchange (ETDEWEB)

Carmichael, J H.E. [Broadgreen Hospital, Liverpool (UK); Warrick, C K

1978-11-01

The ten day rule recommends that non-urgent diagnostic radiography of the abdomen in women of child-bearing capacity should be confined to the pre-ovulatory phase of the menstrual cycle. Arguments for and against this rule are reviewed. The attitudes and organization of radiographic practice in the UK differ from those in the USA. Assessment of the evidence for the hazards involved leads to the conclusion that the continued application of the ten day rule should be strongly recommended as an essential part of good radiological and radiographic practice.

Radiological assessment of 36Cl in the disposal of used CANDU fuel

International Nuclear Information System (INIS)

Johnson, L.H.; Goodwin, B.W.; Sheppard, S.C.; Tait, J.C.; Wuschke, D.M.; Davison, C.C.

1995-06-01

An assessment of the potential radiological impact of 36 Cl in the disposal of used CANDU fuel has been performed. The assessment was based on new data on chlorine impurity levels in used fuel. Data bases for the vault, geosphere, and biosphere models used in the EIS postclosure assessment case study (Goodwin et al. 1994) were modified to include the necessary 36 Cl data. The resulting safety analysis shows that estimated radiological risks from 36 Cl are forty times lower than from 129 I at 10 4 a; this, incorporation of 36 Cl into the models does not change the overall conclusions of the study of Goodwin et al. (1994a). For human intrusion scenarios, an analysis using the methodology of Wuschke (1992) showed that the maximum risk is unaffected by the inclusion of 36 Cl. (author). 51 refs., 5 tabs., 15 figs

Lateral sesamoid position in hallux valgus: correlation with the conventional radiological assessment.

Science.gov (United States)

Agrawal, Yuvraj; Desai, Aravind; Mehta, Jaysheel

2011-12-01

We aimed to quantify the severity of the hallux valgus based on the lateral sesamoid position and to establish a correlation of our simple assessment method with the conventional radiological assessments. We reviewed one hundred and twenty two dorso-plantar weight bearing radiographs of feet. The intermetatarsal and hallux valgus angles were measured by the conventional methods; and the position of lateral sesamoid in relation to first metatarsal neck was assessed by our new and simple method. Significant correlation was noted between intermetatarsal angle and lateral sesamoid position (Rho 0.74, p lateral sesamoid position and hallux valgus angle (Rho 0.56, p lateral sesamoid position is simple, less time consuming and has statistically significant correlation with that of the established conventional radiological measurements. Copyright © 2011 European Foot and Ankle Society. Published by Elsevier Ltd. All rights reserved.

Evaluation and assessment methodology, standards, and procedures manual of the United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Kerns, K.C.; Burson, Z.G.; Smith, J.M.; Blanchard, R.L.

2000-01-01

In the event of a major radiological emergency, the U.S. Federal Radiological Emergency Response Plan authorises the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC). The FRMAC is established to co-ordinate the Federal off-site monitoring and assessment activities, and is comprised of representatives from several Federal agencies and Department of Energy contractors who provide assistance to the state(s) and Lead Federal Agency. The Evaluation and Assessment (E and A) Division of the FRMAC is responsible for receiving, storing, and interpreting environmental surveillance data to estimate the potential health consequences to the population in the vicinity of the accident site. The E and A Division has commissioned the preparation of a methodology and procedures manual which will result in a consistent approach by Division members in carrying out their duties. The first edition of this manual is nearing completion. In this paper, a brief review of the structure of the FRMAC is presented, with emphasis on the E and A Division. The contents of the E and A manual are briefly described, as are future plans for its expansion. (author)

Assessment of the radiological control at the IPEN radioisotope production facility

Energy Technology Data Exchange (ETDEWEB)

Carneiro, J.C.G.G.; Sanches, M.P.; Rodrigues, D.L.; Campos, D.; Nogueira, P.R.; Damatto, S.R.; Pecequilo, B.R.S. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Nuclear and Energy Research Institute, IPEN/SP, Brazil and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in activated carbon cartridges and filter paper) at the workplace during radioisotope production were {sup 131}I, {sup 99m}Tc and {sup 99}Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m{sup 3} ), the activities concentrations also remained below the maximum admissible values, excepting to {sup 125}I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y{sup -1} , below the ICRP 103 recommended limit of 20 mSv.y{sup -1} for workers. (author)

Benchmark problems for radiological assessment codes. Final report

International Nuclear Information System (INIS)

Mills, M.; Vogt, D.; Mann, B.

1983-09-01

This report describes benchmark problems to test computer codes used in the radiological assessment of high-level waste repositories. The problems presented in this report will test two types of codes. The first type of code calculates the time-dependent heat generation and radionuclide inventory associated with a high-level waste package. Five problems have been specified for this code type. The second code type addressed in this report involves the calculation of radionuclide transport and dose-to-man. For these codes, a comprehensive problem and two subproblems have been designed to test the relevant capabilities of these codes for assessing a high-level waste repository setting

Long-term volcanic hazard assessment on El Hierro (Canary Islands)

Science.gov (United States)

Becerril, L.; Bartolini, S.; Sobradelo, R.; Martí, J.; Morales, J. M.; Galindo, I.

2014-07-01

Long-term hazard assessment, one of the bastions of risk-mitigation programs, is required for land-use planning and for developing emergency plans. To ensure quality and representative results, long-term volcanic hazard assessment requires several sequential steps to be completed, which include the compilation of geological and volcanological information, the characterisation of past eruptions, spatial and temporal probabilistic studies, and the simulation of different eruptive scenarios. Despite being a densely populated active volcanic region that receives millions of visitors per year, no systematic hazard assessment has ever been conducted on the Canary Islands. In this paper we focus our attention on El Hierro, the youngest of the Canary Islands and the most recently affected by an eruption. We analyse the past eruptive activity to determine the spatial and temporal probability, and likely style of a future eruption on the island, i.e. the where, when and how. By studying the past eruptive behaviour of the island and assuming that future eruptive patterns will be similar, we aim to identify the most likely volcanic scenarios and corresponding hazards, which include lava flows, pyroclastic fallout and pyroclastic density currents (PDCs). Finally, we estimate their probability of occurrence. The end result, through the combination of the most probable scenarios (lava flows, pyroclastic density currents and ashfall), is the first qualitative integrated volcanic hazard map of the island.

Assessment of hazards and risks for landscape protection planning in Sicily.

Science.gov (United States)

La Rosa, Daniele; Martinico, Francesco

2013-09-01

Landscape protection planning is a complex task that requires an integrated assessment and involves heterogeneous issues. These issues include not only the management of a considerable amount of data to describe landscape features but also the choice of appropriate tools to evaluate the hazards and risks. The landscape assessment phase can provide fundamental information for the definition of a Landscape Protection Plan, in which the selection of norms for protection or rehabilitation is strictly related to hazards, values and risks that are found. This paper describes a landscape assessment methodology conducted by using GIS, concerning landscape hazards, values and risk. Four hazard categories are introduced and assessed concerning urban sprawl and erosion: landscape transformations by new planned developments, intensification of urban sprawl patterns, loss of agriculture land and erosion. Landscape value is evaluated by using different thematic layers overlaid with GIS geoprocessing. The risk of loss of landscape value is evaluated, with reference to the potential occurrence of the previously assessed hazards. The case study is the Province of Enna (Sicily), where landscape protection is a relevant issue because of the importance of cultural and natural heritage. Results show that high value landscape features have a low risk of loss of landscape value. For this reason, landscape protection policies assume a relevant role in landscapes with low-medium values and they should be addressed to control the urban sprawl processes that are beginning in the area. Copyright © 2012 Elsevier Ltd. All rights reserved.

Assessing qualitative long-term volcanic hazards at Lanzarote Island (Canary Islands)

Science.gov (United States)

Becerril, Laura; Martí, Joan; Bartolini, Stefania; Geyer, Adelina

2017-07-01

Conducting long-term hazard assessment in active volcanic areas is of primary importance for land-use planning and defining emergency plans able to be applied in case of a crisis. A definition of scenario hazard maps helps to mitigate the consequences of future eruptions by anticipating the events that may occur. Lanzarote is an active volcanic island that has hosted the largest (> 1.5 km3 DRE) and longest (6 years) eruption, the Timanfaya eruption (1730-1736), on the Canary Islands in historical times (last 600 years). This eruption brought severe economic losses and forced local people to migrate. In spite of all these facts, no comprehensive hazard assessment or hazard maps have been developed for the island. In this work, we present an integrated long-term volcanic hazard evaluation using a systematic methodology that includes spatial analysis and simulations of the most probable eruptive scenarios.

Radioactivity and associated radiation hazards in ceramic raw materials and end products.

Science.gov (United States)

Viruthagiri, G; Rajamannan, B; Suresh Jawahar, K

2013-12-01

Studies have been planned to obtain activity and associated radiation hazards in ceramic raw materials (quartz, feldspar, clay, zircon, kaolin, grog, alumina bauxite, baddeleyite, masse, dolomite and red mud) and end products (ceramic brick, glazed ceramic wall and floor tiles) as the activity concentrations of uranium, thorium and potassium vary from material to material. The primordial radionuclides in ceramic raw materials and end products are one of the sources of radiation hazard in dwellings made of these materials. By the determination of the activity level in these materials, the indoor radiological hazard to human health can be assessed. This is an important precautionary measure whenever the dose rate is found to be above the recommended limits. The aim of this work was to measure the activity concentration of (226)Ra, (232)Th and (40)K in ceramic raw materials and end products. The activity of these materials has been measured using a gamma-ray spectrometry, which contains an NaI(Tl) detector connected to multichannel analyser (MCA). Radium equivalent activity, alpha-gamma indices and radiation hazard indices associated with the natural radionuclides are calculated to assess the radiological aspects of the use of the ceramic end products as decorative or covering materials in construction sector. Results obtained were examined in the light of the relevant international legislation and guidance and compared with the results of similar studies reported in different countries. The results suggest that the use of ceramic end product samples examined in the construction of dwellings, workplace and industrial buildings is unlikely to give rise to any significant radiation exposure to the occupants.

Radioactivity and associated radiation hazards in ceramic raw materials and end products

International Nuclear Information System (INIS)

Viruthagiri, G.; Rajamannan, B.; Suresh Jawahar, K.

2013-01-01

Studies have been planned to obtain activity and associated radiation hazards in ceramic raw materials (quartz, feldspar, clay, zircon, kaolin, grog, alumina bauxite, baddeleyite, masse, dolomite and red mud) and end products (ceramic brick, glazed ceramic wall and floor tiles) as the activity concentrations of uranium, thorium and potassium vary from material to material. The primordial radionuclides in ceramic raw materials and end products are one of the sources of radiation hazard in dwellings made of these materials. By the determination of the activity level in these materials, the indoor radiological hazard to human health can be assessed. This is an important precautionary measure whenever the dose rate is found to be above the recommended limits. The aim of this work was to measure the activity concentration of 226 Ra, 232 Th and 40 K in ceramic raw materials and end products. The activity of these materials has been measured using a gamma-ray spectrometry, which contains an NaI(Tl) detector connected to multichannel analyser (MCA). Radium equivalent activity, alpha-gamma indices and radiation hazard indices associated with the natural radionuclides are calculated to assess the radiological aspects of the use of the ceramic end products as decorative or covering materials in construction sector. Results obtained were examined in the light of the relevant international legislation and guidance and compared with the results of similar studies reported in different countries. The results suggest that the use of ceramic end product samples examined in the construction of dwellings, workplace and industrial buildings is unlikely to give rise to any significant radiation exposure to the occupants. (authors)

Depleted uranium residual radiological risk assessment for Kosovo sites

International Nuclear Information System (INIS)

Durante, Marco; Pugliese, Mariagabriella

2003-01-01

During the recent conflict in Yugoslavia, depleted uranium rounds were employed and were left in the battlefield. Health concern is related to the risk arising from contamination of areas in Kosovo with depleted uranium penetrators and dust. Although chemical toxicity is the most significant health risk related to uranium, radiation exposure has been allegedly related to cancers among veterans of the Balkan conflict. Uranium munitions are considered to be a source of radiological contamination of the environment. Based on measurements and estimates from the recent Balkan Task Force UNEP mission in Kosovo, we have estimated effective doses to resident populations using a well-established food-web mathematical model (RESRAD code). The UNEP mission did not find any evidence of widespread contamination in Kosovo. Rather than the actual measurements, we elected to use a desk assessment scenario (Reference Case) proposed by the UNEP group as the source term for computer simulations. Specific applications to two Kosovo sites (Planeja village and Vranovac hill) are described. Results of the simulations suggest that radiation doses from water-independent pathways are negligible (annual doses below 30 μSv). A small radiological risk is expected from contamination of the groundwater in conditions of effective leaching and low distribution coefficient of uranium metal. Under the assumptions of the Reference Case, significant radiological doses (>1 mSv/year) might be achieved after many years from the conflict through water-dependent pathways. Even in this worst-case scenario, DU radiological risk would be far overshadowed by its chemical toxicity

Instructional Vignettes in Publication and Journalism Ethics in Radiology Research: Assessment via a Survey of Radiology Trainees.

Science.gov (United States)

Rosenkrantz, Andrew B; Ginocchio, Luke A

2016-07-01

The aim of the present study was to assess the potential usefulness of written instructional vignettes relating to publication and journalism ethics in radiology via a survey of radiology trainees. A literature review was conducted to guide the development of vignettes, each describing a scenario relating to an ethical issue in research and publication, with subsequent commentary on the underlying ethical issue and potential approaches to its handling. Radiology trainees at a single institution were surveyed regarding the vignettes' perceived usefulness. A total of 21 vignettes were prepared, addressing institutional review board and human subjects protection, authorship issues, usage of previous work, manuscript review, and other miscellaneous topics. Of the solicited trainees, 24.7% (16/65) completed the survey. On average among the vignettes, 94.0% of the participants found the vignette helpful; 19.9 received prior formal instruction on the issue during medical training; 40.0% received prior informal guidance from a research mentor; and 42.0% indicated that the issue had arisen in their own or a peer's prior research experience. The most common previously experienced specific issue was authorship order (93.8%). Free-text responses were largely favorable regarding the value of the vignettes, although also indicated numerous challenges in properly handling the ethical issues: impact of hierarchy, pressure to publish, internal politics, reluctance to conduct sensitive conversations with colleagues, and variability in journal and professional society policies. Radiology trainees overall found the vignettes helpful, addressing commonly encountered topics for which formal and informal guidance were otherwise lacking. The vignettes are publicly available through the Association of University Radiologists (AUR) website and may foster greater insights by investigators into ethical aspects of the publication and journalism process, thus contributing to higher quality

CP-50 calibration facility radiological safety assessment document

International Nuclear Information System (INIS)

Chilton, M.W.; Hill, R.L.; Eubank, B.F.

1980-03-01

The CP-50 Calibration Facility Radiological Safety Assessment document, prepared at the request of the Nevada Operations Office of the US Department of Energy to satisfy provisions of ERDA Manual Chapter 0531, presents design features, systems controls, and procedures used in the operation of the calibration facility. Site and facility characteristics and routine and non-routine operations, including hypothetical incidents or accidents are discussed and design factors, source control systems, and radiation monitoring considerations are described

RADIOLOGY EDUCATION: A PILOT STUDY TO ASSESS KNOWLEDGE OF MEDICAL STUDENTS REGARDING IMAGING IN TRAUMA.

Science.gov (United States)

Siddiqui, Saad; Saeed, Muhammad Anwar; Shah, Noreen; Nadeem, Naila

2015-01-01

Trauma remains one of the most frequent presentations in emergency departments. Imaging has established role in setting of acute trauma with ability to identify potentially fatal conditions. Adequate knowledge of health professionals regarding trauma imaging is vital for improved healthcare. In this work we try to assess knowledge of medical students regarding imaging in trauma as well as identify most effective way of imparting radiology education. This cross-sectional pilot study was conducted at Aga Khan University Medical College & Khyber Girls Medical College, to assess knowledge of medical students regarding imaging protocols practiced in initial management of trauma patients. Only 40 & 20% respectively were able to identify radiographs included in trauma series. Very few had knowledge of correct indication for Focused abdominal sonography in trauma. Clinical radiology rotation was reported as best way of learning radiology. Change in curricula & restructuring of clinical radiology rotation structure is needed to improve knowledge regarding Trauma imaging.

Modelling human interactions in the assessment of man-made hazards

International Nuclear Information System (INIS)

Nitoi, M.; Farcasiu, M.; Apostol, M.

2016-01-01

The human reliability assessment tools are not currently capable to model adequately the human ability to adapt, to innovate and to manage under extreme situations. The paper presents the results obtained by ICN PSA team in the frame of FP7 Advanced Safety Assessment Methodologies: extended PSA (ASAMPSA_E) project regarding the investigation of conducting HRA in human-made hazards. The paper proposes to use a 4-steps methodology for the assessment of human interactions in the external events (Definition and modelling of human interactions; Quantification of human failure events; Recovery analysis; Review). The most relevant factors with respect to HRA for man-made hazards (response execution complexity; existence of procedures with respect to the scenario in question; time available for action; timing of cues; accessibility of equipment; harsh environmental conditions) are presented and discussed thoroughly. The challenges identified in relation to man-made hazards HRA are highlighted. (authors)

Malaysian experiences in radiological safety assessment on norm wastes

International Nuclear Information System (INIS)

Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol

2000-01-01

Radiological Impact Assessments (RIAs) on proposed disposal sites for NORM wastes were performed in Malaysia. Analysis results were used to derive site specific guidelines for allowable residual concentrations of radionuclides in soil, calculation of doses and risks. Appropriate use scenarios and site specific parameters were used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Disposals were performed to fulfil Atomic Energy Licensing Board of Malaysia (AELB) requirements for which the operator must carry out a radiological impact assessment. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Fatal cancer risk factor is 5x10 -2 per man.Sv. Radionuclides of main concern are radium-226 and radium-228 which are considered as toxic. Sensitivity and uncertainty analyses were performed to show that the parameters used as input into the computer model were justified so as to improve confidence of the public and the AELB in respect of the results of the analysis. Case study to determine a proposed near surface disposal site for treated oil sludge was described. (author)

A critical analysis of hazard resilience measures within sustainability assessment frameworks

International Nuclear Information System (INIS)

Matthews, Elizabeth C.; Sattler, Meredith; Friedland, Carol J.

2014-01-01

Today, numerous sustainability assessment frameworks (SAFs) exist to guide designers in achieving sustainable performance in the design of structures and communities. SAFs are beneficial in educating users and are useful tools for incorporating sustainability strategies into planning, design, and construction; however, there is currently a substantial gap in the ability of existing SAFs to incorporate hazard resistance and hazard mitigation in the broader context of sustainable design. This paper analyzes the incorporation of hazard resistant design and hazard mitigation strategies within SAFs via a multi-level analysis of eleven SAFs. The SAFs analyzed range in scale of application (i.e. building, site, community). Three levels of analysis are presented: (1) macro-level analysis comparing the number of measures strictly addressing resilience versus sustainability, (2) meso-level analysis of the coverage of types of hazards within SAFs (e.g. flood, fire), and (3) micro-level analysis of SAF measures connected to flood-related hazard resilience. The results demonstrate that hazard resistance and hazard mitigation do not figure prominently in the intent of SAFs and that weaknesses in resilience coverage exist that have the potential to lead to the design of structures and communities that are still highly vulnerable to the impacts of extreme events. - Highlights: • Sustainability assessment frameworks (SAFs) were analyzed for resilience coverage • Hazard resistance and mitigation do not figure prominently in the intent of SAFs • Approximately 75% of SAFs analyzed address three or fewer hazards • Lack of economic measures within SAFs could impact resilience and sustainability • Resilience measures for flood hazards are not consistently included in SAFs

A critical analysis of hazard resilience measures within sustainability assessment frameworks

Energy Technology Data Exchange (ETDEWEB)

Matthews, Elizabeth C., E-mail: echiso1@lsu.edu [Louisiana State University, Baton Rouge, LA (United States); Sattler, Meredith, E-mail: msattler@lsu.edu [School of Architecture, Louisiana State University, Baton Rouge, LA (United States); Friedland, Carol J., E-mail: friedland@lsu.edu [Bert S. Turner Department of Construction Management, Louisiana State University, Baton Rouge, LA (United States)

2014-11-15

Today, numerous sustainability assessment frameworks (SAFs) exist to guide designers in achieving sustainable performance in the design of structures and communities. SAFs are beneficial in educating users and are useful tools for incorporating sustainability strategies into planning, design, and construction; however, there is currently a substantial gap in the ability of existing SAFs to incorporate hazard resistance and hazard mitigation in the broader context of sustainable design. This paper analyzes the incorporation of hazard resistant design and hazard mitigation strategies within SAFs via a multi-level analysis of eleven SAFs. The SAFs analyzed range in scale of application (i.e. building, site, community). Three levels of analysis are presented: (1) macro-level analysis comparing the number of measures strictly addressing resilience versus sustainability, (2) meso-level analysis of the coverage of types of hazards within SAFs (e.g. flood, fire), and (3) micro-level analysis of SAF measures connected to flood-related hazard resilience. The results demonstrate that hazard resistance and hazard mitigation do not figure prominently in the intent of SAFs and that weaknesses in resilience coverage exist that have the potential to lead to the design of structures and communities that are still highly vulnerable to the impacts of extreme events. - Highlights: • Sustainability assessment frameworks (SAFs) were analyzed for resilience coverage • Hazard resistance and mitigation do not figure prominently in the intent of SAFs • Approximately 75% of SAFs analyzed address three or fewer hazards • Lack of economic measures within SAFs could impact resilience and sustainability • Resilience measures for flood hazards are not consistently included in SAFs.

Seismic hazard assessment of the Province of Murcia (SE Spain): analysis of source contribution to hazard

Science.gov (United States)

García-Mayordomo, J.; Gaspar-Escribano, J. M.; Benito, B.

2007-10-01

A probabilistic seismic hazard assessment of the Province of Murcia in terms of peak ground acceleration (PGA) and spectral accelerations [SA( T)] is presented in this paper. In contrast to most of the previous studies in the region, which were performed for PGA making use of intensity-to-PGA relationships, hazard is here calculated in terms of magnitude and using European spectral ground-motion models. Moreover, we have considered the most important faults in the region as specific seismic sources, and also comprehensively reviewed the earthquake catalogue. Hazard calculations are performed following the Probabilistic Seismic Hazard Assessment (PSHA) methodology using a logic tree, which accounts for three different seismic source zonings and three different ground-motion models. Hazard maps in terms of PGA and SA(0.1, 0.2, 0.5, 1.0 and 2.0 s) and coefficient of variation (COV) for the 475-year return period are shown. Subsequent analysis is focused on three sites of the province, namely, the cities of Murcia, Lorca and Cartagena, which are important industrial and tourism centres. Results at these sites have been analysed to evaluate the influence of the different input options. The most important factor affecting the results is the choice of the attenuation relationship, whereas the influence of the selected seismic source zonings appears strongly site dependant. Finally, we have performed an analysis of source contribution to hazard at each of these cities to provide preliminary guidance in devising specific risk scenarios. We have found that local source zones control the hazard for PGA and SA( T ≤ 1.0 s), although contribution from specific fault sources and long-distance north Algerian sources becomes significant from SA(0.5 s) onwards.

Preoperative radiological assessment of children with pectus excavatum

International Nuclear Information System (INIS)

Kilda, A.; Barauskas, V.; Basevicius, A.; Lukosevicius, S.

2005-01-01

Objective: The degree of the pediatric chest deformation that should be subjected to corrective surgical treatment or conservative treatment remains poorly defined as recognized. In the present study, using preoperative and postoperative radiological examination data, we aim to assess what degree of chest wall deformation changes statistically reliably after surgery. Materials and methods: Radiological chest examinations were performed for 88 children before and after remedial operations. Chest X-ray and CT scans were done to measure transversal chest width; sagittal left chest side depth, sagittal right chest side depth, sternovertebral distance, and vertebral body length. Derivative indices were also estimated: the Vertebral Index, the Frontosagittal Index, the Haller index, and the asymmetry index. Computerized assessment of data was used. For statistical analysis, the software 'STATISTICA 6.0' was used. Results: Postoperatively, the Vertebral Index increased approximately by 2.37±2.72; the Frontosagittal Index decreased by 4.60±4.34, and the Haller index value increased approximately up by 0.45±0.49. Statistically reliable deformation index difference before and after surgery was not detected when the Vertebral Index was below 26.2, p=0.08; the Frontosagittal Index was above 32.9, p=0.079; and the Haller Index was less than 3.12, p=0.098. Conclusions: Preoperative CT scanning, coupled with assessment of the chest wall shape and the deformation degree, would be necessary for pediatric patients. The following deformation indices are indications for surgical treatment: VI > 26, FSI 3.1. (author)

Assessment of the radiation risk from diagnostic radiology

International Nuclear Information System (INIS)

Streffer, C.; Mueller, W.U.

1995-01-01

In any assessment of radiation risks from diagnostic radiology the main concern is the possible induction of cancer. It now appears to be beyond all doubt that ionizing rays invite the development of cancer in humans. The radiation doses encountered in diagnostic radiology generally vary from 1 to 50 mSv. For this dose range, no measured values are available to ascertain cancer risks from ionizing rays. The effects of such doses must therefore be extrapolated from higher dose levels under consideration of given dose-effect relationships. All relevant figures for diagnostic X-ray measures are therefore mathematically determined approximate values. The stochastic radiation risk following non-homogeneous radiation exposure is assessed on the basis of the effective dose. This dose was originally introduced to ascertain the risk from radioactive substances incorporated at the working place. A secondary intention was to trigger further developmental processes in radiation protection. Due to the difficulties previously outlined and the uncertainties surrounding the determination and assessment of the effective dose from diagnostic X-ray procedures, this dose should merely be used for technological refinements and comaprisons of examination procedures. It appears unreasonable that the effective doses determined for the individual examinations are summed up to obtain a collective effective dose and to multiply this with a risk factor so as to give an approximation of the resulting deaths from cancer. A reasonable alternative is to inform patients subjected to X-ray examinations about the associated radiation dose and to estimate form this the magnitude of the probable radiation risk. (orig./MG) [de

Hazard assessment for small torrent catchments - lessons learned

Science.gov (United States)

Eisl, Julia; Huebl, Johannes

2013-04-01

The documentation of extreme events as a part of the integral risk management cycle is an important basis for the analysis and assessment of natural hazards. In July 2011 a flood event occurred in the Wölzer-valley in the province of Styria, Austria. For this event at the "Wölzerbach" a detailed event documentation was carried out, gathering data about rainfall, runoff and sediment transport as well as information on damaged objects, infrastructure or crops using various sources. The flood was triggered by heavy rainfalls in two tributaries of the Wölzer-river. Though a rain as well as a discharge gaging station exists for the Wölzer-river, the torrents affected by the high intensity rainfalls are ungaged. For these ungaged torrent catchments the common methods for hazard assessment were evaluated. The back-calculation of the rainfall event was done using a new approach for precipitation analysis. In torrent catchments especially small-scale and high-intensity rainfall events are mainly responsible for extreme events. Austria's weather surveillance radar is operated by the air traffic service "AustroControl". The usually available dataset is interpreted and shows divergences especially when it comes to high intensity rainfalls. For this study the raw data of the radar were requested and analysed. Further on the event was back-calculated with different rainfall-runoff models, hydraulic models and sediment transport models to obtain calibration parameters for future use in hazard assessment for this region. Since there are often problems with woody debris different scenarios were simulated. The calibrated and plausible results from the runoff models were used for the comparison with empirical approaches used in the practical sector. For the planning of mitigation measures of the Schöttl-torrent, which is one of the affected tributaries of the Wölzer-river, a physical scale model was used in addition to the insights of the event analysis to design a check dam

Radiologic sciences. Faculty needs assessment.

Science.gov (United States)

Powers, Kevin J

2005-01-01

A total of 326 programs are represented in the data collected. Based on the average number of full- and part-time faculty members reported per program, this survey represents more than 1500 faculty positions. Based on the forecast of retirement and career change for all faculty members, there will be a turnover of 700 to 800 positions over the next 5 to 10 years. Part-time/adjunct faculty vacancies are expected to create the greatest number of opportunities for technologists to make the transition to education, with approximately one third of current part-time/adjunct educators planning on leaving radiologic sciences education within 5 years. To encourage retention of part-time/adjunct educators, annual evaluations should be modified to recognize the important educational role these instructors play. There is a need to create enthusiasm and interest in education as a career pathway for radiologic technologists. Resources are needed that help radiologic technologists make the transition to teaching. Finally, the retention of educators must be emphasized. Program applicant trends indicate radiologic technology students are older, have prior postsecondary education experience or are making a career change. This data emphasizes the need for educators, both full time and part time, to understand the characteristics and needs of the adult learner. Adult learners bring a wealth of education, experience and life skills that create both opportunities and challenges in the classroom and clinical setting. All categories of respondents indicated that their current salaries were greater than those of program graduates in their firstjob. Of interest is that 1 in 5 (20%) of part-time/adjunct educators indicated the opposite--that program graduates earn more in their firstjob than educators earn. When asked about salaries if working full time in clinical practice, the majority of all groups indicated their salary would be about the same or would decrease. Only 20% of program

Principles and issues in radiological ecological risk assessment.

Science.gov (United States)

Jones, Daniel; Domotor, Stephen; Higley, Kathryn; Kocher, David; Bilyard, Gordon

2003-01-01

This paper provides a bridge between the fields of ecological risk assessment (ERA) and radioecology by presenting key biota dose assessment issues identified in the US Department of Energy's Graded Approach for Evaluating Radiation Doses to Aquatic and Terrestrial Biota in a manner consistent with the US Environmental Protection Agency's framework for ERA. Current radiological ERA methods and data are intended for use in protecting natural populations of biota, rather than individual members of a population. Potentially susceptible receptors include vertebrates and terrestrial plants. One must ensure that all media, radionuclides (including short-lived radioactive decay products), types of radiations (i.e., alpha particles, electrons, and photons), and pathways (i.e., internal and external contamination) are combined in each exposure scenario. The relative biological effectiveness of alpha particles with respect to deterministic effects must also be considered. Expected safe levels of exposure are available for the protection of natural populations of aquatic biota (10 mGy d(-1)) and terrestrial plants (10 mGy d(-1)) and animals (1 mGy d(-1)) and are appropriate for use in all radiological ERA tiers, provided that appropriate exposure assumptions are used. Caution must be exercised (and a thorough justification provided) if more restrictive limits are selected, to ensure that the supporting data are of high quality, reproducible, and clearly relevant to the protection of natural populations.

Quantitative rock-fall hazard and risk assessment for Yosemite Valley, California

Science.gov (United States)

Stock, G. M.; Luco, N.; Collins, B. D.; Harp, E.; Reichenbach, P.; Frankel, K. L.

2011-12-01

Rock falls are a considerable hazard in Yosemite Valley, California with more than 835 rock falls and other slope movements documented since 1857. Thus, rock falls pose potentially significant risk to the nearly four million annual visitors to Yosemite National Park. Building on earlier hazard assessment work by the U.S. Geological Survey, we performed a quantitative rock-fall hazard and risk assessment for Yosemite Valley. This work was aided by several new data sets, including precise Geographic Information System (GIS) maps of rock-fall deposits, airborne and terrestrial LiDAR-based point cloud data and digital elevation models, and numerical ages of talus deposits. Using Global Position Systems (GPS), we mapped the positions of over 500 boulders on the valley floor and measured their distance relative to the mapped base of talus. Statistical analyses of these data yielded an initial hazard zone that is based on the 90th percentile distance of rock-fall boulders beyond the talus edge. This distance was subsequently scaled (either inward or outward from the 90th percentile line) based on rock-fall frequency information derived from a combination of cosmogenic beryllium-10 exposure dating of boulders beyond the edge of the talus, and computer model simulations of rock-fall runout. The scaled distances provide the basis for a new hazard zone on the floor of Yosemite Valley. Once this zone was delineated, we assembled visitor, employee, and resident use data for each structure within the hazard zone to quantitatively assess risk exposure. Our results identify areas within the new hazard zone that may warrant more detailed study, for example rock-fall susceptibility, which can be assessed through examination of high-resolution photographs, structural measurements on the cliffs, and empirical calculations derived from LiDAR point cloud data. This hazard and risk information is used to inform placement of existing and potential future infrastructure in Yosemite Valley.

Health Risk Assessment on Hazardous Ingredients in Household Deodorizing Products

Directory of Open Access Journals (Sweden)

Minjin Lee

2018-04-01

Full Text Available The inhalation of a water aerosol from a humidifier containing disinfectants has led to serious lung injuries in Korea. To promote the safe use of products, the Korean government enacted regulations on the chemicals in various consumer products that could have adverse health effects. Given the concern over the potential health risks associated with the hazardous ingredients in deodorizing consumer products, 17 ingredients were analyzed and assessed according to their health risk on 3 groups by the application type in 47 deodorizing products. The risk assessment study followed a stepwise procedure (e.g., collecting toxicological information, hazard identification/exposure assessment, and screening and detailed assessment for inhalation and dermal routes. The worst-case scenario and maximum concentration determined by the product purpose and application type were used as the screening assessment. In a detailed assessment, the 75th exposure factor values were used to estimate the assumed reasonable exposure to ingredients. The exposed concentrations of seven ingredients were calculated. Due to limitation of toxicity information, butylated hydroxyl toluene for a consumer’s exposure via the dermal route only was conducted for a detailed assessment. This study showed that the assessed ingredients have no health risks at their maximum concentrations in deodorizing products. This approach can be used to establish guidelines for ingredients that may pose inhalation and dermal hazards.

Health Risk Assessment on Hazardous Ingredients in Household Deodorizing Products

Science.gov (United States)

Lee, Minjin; Kim, Joo-Hyon; Lee, Daeyeop; Kim, Jaewoo; Lim, Hyunwoo; Seo, Jungkwan; Park, Young-Kwon

2018-01-01

The inhalation of a water aerosol from a humidifier containing disinfectants has led to serious lung injuries in Korea. To promote the safe use of products, the Korean government enacted regulations on the chemicals in various consumer products that could have adverse health effects. Given the concern over the potential health risks associated with the hazardous ingredients in deodorizing consumer products, 17 ingredients were analyzed and assessed according to their health risk on 3 groups by the application type in 47 deodorizing products. The risk assessment study followed a stepwise procedure (e.g., collecting toxicological information, hazard identification/exposure assessment, and screening and detailed assessment for inhalation and dermal routes). The worst-case scenario and maximum concentration determined by the product purpose and application type were used as the screening assessment. In a detailed assessment, the 75th exposure factor values were used to estimate the assumed reasonable exposure to ingredients. The exposed concentrations of seven ingredients were calculated. Due to limitation of toxicity information, butylated hydroxyl toluene for a consumer’s exposure via the dermal route only was conducted for a detailed assessment. This study showed that the assessed ingredients have no health risks at their maximum concentrations in deodorizing products. This approach can be used to establish guidelines for ingredients that may pose inhalation and dermal hazards. PMID:29652814

Assessing qualitative long-term volcanic hazards at Lanzarote Island (Canary Islands

Directory of Open Access Journals (Sweden)

L. Becerril

2017-07-01

Full Text Available Conducting long-term hazard assessment in active volcanic areas is of primary importance for land-use planning and defining emergency plans able to be applied in case of a crisis. A definition of scenario hazard maps helps to mitigate the consequences of future eruptions by anticipating the events that may occur. Lanzarote is an active volcanic island that has hosted the largest (>  1.5 km3 DRE and longest (6 years eruption, the Timanfaya eruption (1730–1736, on the Canary Islands in historical times (last 600 years. This eruption brought severe economic losses and forced local people to migrate. In spite of all these facts, no comprehensive hazard assessment or hazard maps have been developed for the island. In this work, we present an integrated long-term volcanic hazard evaluation using a systematic methodology that includes spatial analysis and simulations of the most probable eruptive scenarios.

Medicine and ionizing rays: a help sheet in analysing risks in exo-buccal dental radiology

International Nuclear Information System (INIS)

Gauron, C.

2009-01-01

This document proposes a synthesis of useful knowledge for radioprotection in the case of exo-buccal dental radiology. In the first part, several aspects are considered: the concerned personnel, the course of treatment procedures, the hazards, the identification of the risk associated with ionizing radiation, the risk assessment and the determination of exposure levels, the strategy to control the risks (reduction of risks, technical measures concerning the installation or the personnel, teaching and information, prevention and medical monitoring), and risk control assessment

Measurement of natural radioactivity and assessment of radiation hazard indices in soil samples at Pengerang, Kota Tinggi, Johor

Energy Technology Data Exchange (ETDEWEB)

Hassan, Nur Nazihah; Khoo, Kok Siong [School of Applied Physics, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), 43600 Bangi, Selangor (Malaysia)

2014-02-12

Pengerang area consists of a mix of private plantation, individual residential lots and state land, which is leased for agriculture related activities. The analysis was conducted to determine the specific activity of the initial value and the radiation hazard indices in the surrounding area in Pengerang. This area will be developed into a major downstream for oil and gas. The aims of this preliminary study were 1) to determine the specific activities of {sup 238}U, {sup 232}Th, {sup 226}Ra and {sup 40}K of soil samples at six selected areas by Gamma-ray spectrometry and 2) to calculate the radiation hazard indices. The specific activities (Bq/kg) of the samples ranged from 7.08±5.01 to 36.29±25.72 Bq/kg, 5.62±3.98 to 34.53±24.07 Bq/kg, 4.75±3.42 to 24.76±17.66 Bq/kg and 10.58±7.51 to 101.25±72.00 Bq/kg for {sup 238}U, {sup 232}Th, {sup 226}Ra and {sup 40}K, respectively. These values were well within the range that reported by UNSCEAR. The study also examined the radiation hazard indices, the mean values obtained were 48.49±28.06 Bq/kg for Radium Equivalent Activity (Raeq), 0.34 Bq/kg for Representative Level Index (I{sub γ}), 21.83 nGy/h for Absorbed dose rates (D), 0.27 mSv/y for Annual Effective Dose Rates (Deff), 0.13 and 0.18 for External Hazards Index (H{sub ex}) and Internal Hazard Index (H{sub in}), respectively. These calculated hazard indices were used to estimate the potential radiological health risk in soil and the dose rates associated with it were well below their permissible limit. The overall findings show that no radiological threat to the health of the population in the study area.

Hazard Baseline Downgrade Effluent Treatment Facility

International Nuclear Information System (INIS)

Blanchard, A.

1998-01-01

This Hazard Baseline Downgrade reviews the Effluent Treatment Facility, in accordance with Department of Energy Order 5480.23, WSRC11Q Facility Safety Document Manual, DOE-STD-1027-92, and DOE-EM-STD-5502-94. It provides a baseline grouping based on the chemical and radiological hazards associated with the facility. The Determination of the baseline grouping for ETF will aid in establishing the appropriate set of standards for the facility

Elevation uncertainty in coastal inundation hazard assessments

Science.gov (United States)

Gesch, Dean B.; Cheval, Sorin

2012-01-01

Coastal inundation has been identified as an important natural hazard that affects densely populated and built-up areas (Subcommittee on Disaster Reduction, 2008). Inundation, or coastal flooding, can result from various physical processes, including storm surges, tsunamis, intense precipitation events, and extreme high tides. Such events cause quickly rising water levels. When rapidly rising water levels overwhelm flood defenses, especially in heavily populated areas, the potential of the hazard is realized and a natural disaster results. Two noteworthy recent examples of such natural disasters resulting from coastal inundation are the Hurricane Katrina storm surge in 2005 along the Gulf of Mexico coast in the United States, and the tsunami in northern Japan in 2011. Longer term, slowly varying processes such as land subsidence (Committee on Floodplain Mapping Technologies, 2007) and sea-level rise also can result in coastal inundation, although such conditions do not have the rapid water level rise associated with other flooding events. Geospatial data are a critical resource for conducting assessments of the potential impacts of coastal inundation, and geospatial representations of the topography in the form of elevation measurements are a primary source of information for identifying the natural and human components of the landscape that are at risk. Recently, the quantity and quality of elevation data available for the coastal zone have increased markedly, and this availability facilitates more detailed and comprehensive hazard impact assessments.

Seismic hazard assessment; Valutazione della pericolosita` sismica

Energy Technology Data Exchange (ETDEWEB)

Paciello, A. [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dip. Ambiente

1998-12-31

This paper presents a brief summary of the most commonly used methodologies for seismic hazard assessment. The interest is focused on the probabilistic approach, which can take into account the uncertainties of input data and provides results better comparable with those obtained from hazard analyses of other natural phenomena. Calculation methods, input data and treatment of variability are examined. Some examples of probabilistic seismic hazard maps are moreover presented. [Italiano] Questo lavoro presenta un breve sommario delle piu` comuni metodologie utilizzate per la valutazione della pericolosita` sismica di un sito. Una particolare attenzione e` rivolta all`approccio probabilistico, che permette di tener conto delle incertezze legate ai dati iniziali e fornisce risultati piu` facilmente confrontabili con quelli ottenuti da analisi di pericolosita` di altri fenomeni naturali. Vengono presi in esame i metodi di calcolo, i dati di base e il trattamento delle incertezze. Vengono inoltre presentati alcuni esempi di carte di pericolosita` sismica di tipo probabilistico.

A spatiotemporal multi-hazard exposure assessment based on property data

Science.gov (United States)

Fuchs, Sven; Keiler, Margreth; Zischg, Andreas

2016-04-01

The paper presents a nation-wide spatially explicit object-based assessment of buildings and citizens exposed to natural hazards in Austria, including river flooding, torrential flooding, and snow avalanches. The assessment was based on two different datasets, (a) hazard information providing input to the exposure of elements at risk, and (b) information on the building stock combined from different spatial data available on the national level. Hazard information was compiled from two different sources. For torrential flooding and snow avalanches available local-scale hazard maps were used, and for river flooding the results of the countrywide flood modelling eHORA were available. Information on the building stock contained information on the location and size of each building, as well as on the building category and the construction period. Additional information related to the individual floors, such as their height and net area, main purpose and configuration, was included for each property. Moreover, this dataset has an interface to the population register and allowed therefore retrieving the number of primary residents for each building. With the exception of sacral buildings, an economic module was used to compute the monetary value of buildings using (a) the information of the building register such as building type, number of storeys and utilisation, and (b) regionally averaged construction costs. It is shown that the repeatedly-stated assumption of increasing exposure due to continued population growth and related increase in assets has to be carefully evaluated by the local development of building stock. While some regions have shown a clearly above-average increase in assets, other regions were characterised by a below-average development. This mirrors the topography of the country, but also the different economic activities. While hotels and hostels are extraordinary prone to torrential flooding, commercial buildings as well as buildings used for

Curriculum Guidelines for Predoctoral Oral Radiology.

Science.gov (United States)

Journal of Dental Education, 1987

1987-01-01

The American Association of Dental Schools' guidelines for oral radiology curricula give an overview of the field and its interrelationships with other fields and outline the primary educational objectives, prerequisites, core content, specific behavioral objectives, sequencing, faculty, facilities, and occupational hazards to be considered in…

The Importance of Curriculum-Based Training and Assessment in Interventional Radiology

Energy Technology Data Exchange (ETDEWEB)

Belli, Anna-Maria, E-mail: anna.belli@stgeorges.nhs.uk [St. George’s Hospital, Department of Radiology (United Kingdom); Reekers, Jim A., E-mail: j.a.reekers@amc.uva.nl [Academic Medical Centre, Department of Radiology (Netherlands); Lee, Michael, E-mail: mlee@rcsi.ie [Beaumont Hospital, Department of Radiology (Ireland)

2013-10-30

Physician performance and outcomes are being scrutinised by health care providers to improve patient safety and cost efficiency. Patients are best served by physicians who have undergone appropriate specialist training and assessment and perform large numbers of cases to maintain their skills. The Cardiovascular and Interventional Radiological Society of Europe has put into place a curriculum for training in interventional radiology (IR) and a syllabus with an examination, the European Board of Interventional Radiology, providing evidence of attainment of an appropriate and satisfactory skill set for the safe practice of IR. This curriculum is appropriate for IR where there is a high volume of image-guided procedures in vascular and nonvascular organ systems with cross-use of minimally invasive techniques in patients with a variety of disease processes. Other specialties may require different, longer, and more focused training if their experience is “diluted” by the need to master a different skill set.

The Importance of Curriculum-Based Training and Assessment in Interventional Radiology

International Nuclear Information System (INIS)

Belli, Anna-Maria; Reekers, Jim A.; Lee, Michael

2014-01-01

Physician performance and outcomes are being scrutinised by health care providers to improve patient safety and cost efficiency. Patients are best served by physicians who have undergone appropriate specialist training and assessment and perform large numbers of cases to maintain their skills. The Cardiovascular and Interventional Radiological Society of Europe has put into place a curriculum for training in interventional radiology (IR) and a syllabus with an examination, the European Board of Interventional Radiology, providing evidence of attainment of an appropriate and satisfactory skill set for the safe practice of IR. This curriculum is appropriate for IR where there is a high volume of image-guided procedures in vascular and nonvascular organ systems with cross-use of minimally invasive techniques in patients with a variety of disease processes. Other specialties may require different, longer, and more focused training if their experience is “diluted” by the need to master a different skill set

Calculating the radiological parameters used in non-human biota dose assessment tools using ERICA Tool and site-specific data

Energy Technology Data Exchange (ETDEWEB)

Sotiropoulou, Maria [INRASTES, NCSR ' ' Demokritos' ' , Environmental Radioactivity Laboratory, Athens (Greece); Aristotle University of Thessaloniki, Atomic and Nuclear Physics Laboratory, Thessaloniki (Greece); Florou, Heleny [INRASTES, NCSR ' ' Demokritos' ' , Environmental Radioactivity Laboratory, Athens (Greece); Kitis, Georgios [Aristotle University of Thessaloniki, Atomic and Nuclear Physics Laboratory, Thessaloniki (Greece)

2017-11-15

The substantial complexity in ecosystem-radionuclide interactions is difficult to be represented in terms of radiological doses. Thus, radiological dose assessment tools use typical exposure situations for generalized organisms and ecosystems. In the present study, site-specific data and radioactivity measurements of terrestrial organisms (grass and herbivore mammals) and abiotic components (soil) are provided. The retrieved data are used in combination with the ERICA Assessment Tool for calculation of radiological parameters. The process of radionuclide transfer within ecosystem components is represented using concentration ratios (CRs), while for the calculation of dose rates the dose conversion coefficient (DCC) methodology is applied. Comparative assessments are performed between the generic and assessment-specific radiological parameters and between the resulting dose rates. Significant differences were observed between CRs calculated in this study and those reported in the literature for cesium and thorium, which can easily be explained. On the other hand, CRs calculated for radium are in very good agreement with those reported in the literature. The DCCs exhibited some small differences between the reference and the assessment-specific organism due to mass differences. The differences were observed for internal and external dose rates, but they were less pronounced for total dose rates which are typically used in the assessment of radiological impact. The results of the current work can serve as a basis for further studies of the radiological parameters in environments that have not been studied yet. (orig.)

Practical Implications for an Effective Radiology Residency Quality Improvement Program for Milestone Assessment.

Science.gov (United States)

Leddy, Rebecca; Lewis, Madelene; Ackerman, Susan; Hill, Jeanne; Thacker, Paul; Matheus, Maria; Tipnis, Sameer; Gordon, Leonie

2017-01-01

Utilization of a radiology resident-specific quality improvement (QI) program and curriculum based on the Accreditation Council for Graduate Medical Education (ACGME) milestones can enable a program's assessment of the systems-based practice component and prepare residents for QI implementation post graduation. This article outlines the development process, curriculum, QI committee formation, and resident QI project requirements of one institution's designated radiology resident QI program. A method of mapping the curriculum to the ACGME milestones and assessment of resident competence by postgraduate year level is provided. Sample projects, challenges to success, and lessons learned are also described. Survey data of current trainees and alumni about the program reveal that the majority of residents and alumni responders valued the QI curriculum and felt comfortable with principles and understanding of QI. The most highly valued aspect of the program was the utilization of a resident education committee. The majority of alumni responders felt the residency quality curriculum improved understanding of QI, assisted with preparation for the American Board of Radiology examination, and prepared them for QI in their careers. In addition to the survey results, outcomes of resident project completion and resident scholarly activity in QI are evidence of the success of this program. It is hoped that this description of our experiences with a radiology resident QI program, in accordance with the ACGME milestones, may facilitate the development of successful QI programs in other diagnostic radiology residencies. Copyright © 2017 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

Chest radiological findings in pakistani cement mill workers

International Nuclear Information System (INIS)

Meo, Sultan A.

2003-01-01

Chest radiological findings in Pakistani cement mill workers Even in the 21st century, in developing countries millions of people work daily in dusty environments. They are exposed to different types of health hazards namely, fumes, gases and dust, which are risk factors for developing occupational diseases. Therefore, the aim of this study was to perform chest radiology to determine the occupational hazards of cement dust on the lungs of cement mill workers. This study was carried out in the Department of Physiology, Faculty of Health and Medical Sciences, Hamdard University Karachi, Pakistan, during the period June to August 2000. In this study 50, apparently healthy volunteer male cement mill workers were randomly selected with an average of 13 years exposure with age ranging from 20-60 years. They were matched with 50, healthy male control subjects in terms of age, height, weight and socioeconomic status. Both groups met with exclusion criteria as per standard. Radiology was performed by Trophy radiology. Results: The present study demonstrated 12% of cases with interstitial lung disease and 2% of cases with pleural thickening and chronic bronchitis in cement mill workers. Conclusion: Exposure to cement dust causes interstitial lung disease, pleural thickening and chronic bronchitis in cement mill workers. (author)

Comparison of landslide hazard and risk assessment practices in Europe

Science.gov (United States)

Corominas, J.; Mavrouli, O.

2012-04-01

An overview is made of the landslide hazard and risk assessment practices that are officially promoted or applied in Europe by administration offices, geological surveys, and decision makers (recommendations, regulations and codes). The reported countries are: Andorra, Austria, France, Italy (selected river basins), Romania, Spain (Catalonia), Switzerland and United Kingdom. The objective here was to compare the different practices for hazard and risk evaluation with respect to the official policies, the methodologies used (qualitative and quantitative), the provided outputs and their contents, and the terminology and map symbols used. The main observations made are illustrated with examples and the possibility of harmonization of the policies and the application of common practices to bridge the existing gaps is discussed. Some of the conclusions reached include the following: zoning maps are legally binding for public administrators and land owners only in some cases and generally when referring to site-specific or local scales rather than regional or national ones; so far, information is mainly provided on landslide susceptibility and hazard and risk assessment is performed only in a few countries; there is a variation in the use of scales between countries; the classification criteria for landslide types and mechanisms present large diversity even within the same country (in some cases no landslide mechanisms are specified while in others there is an exhaustive list); the techniques to obtain input data for the landslide inventory and susceptibility maps vary from basic to sophisticated, resulting in various levels of data quality and quantity; the procedures followed for hazard and risk assessment include analytical procedures supported by computer simulation, weighted-indicators, expert judgment and field survey-based, or a combination of all; there is an important variation between hazard and risk matrices with respect to the used parameters, the thresholds

Estimating risk at a Superfund site contaminated with radiological and chemical wastes

International Nuclear Information System (INIS)

Temeshy, A.; Liedle, J.M.; Sims, L.M.; Efird, C.R.

1992-01-01

This paper describes the method and results for estimating carcinogenic and noncarcinogenic effects at a Superfund site that is radiologically and chemically contaminated. Risk to receptors from disposal of waste in soil and resulting contamination of groundwater, air, surface water, and sediment is quantified. Specific risk assessment components which are addressed are the exposure assessment, toxicity assessment, and the resulting risk characterization. In the exposure assessment, potential exposure pathways are identified using waste disposal inventory information for soil and modeled information for other media. Models are used to calculate future radionuclide concentrations in groundwater, soil, surface water and air. Chemical exposure concentrations are quantified using site characterization data. Models are used to determine concentrations of chemicals in surface water and in air. Toxicity parameters used to quantify the dose-response relationship associated with the carcinogenic contaminants are slope factors and with noncarcinogenic contaminants are reference doses. In the risk characterization step, results from the exposure assessment and toxicity assessment are summarized and integrated into quantitative risk estimates for carcinogens and hazard induces for noncarcinogens. Calculated risks for carcinogenic contaminants are compared with EPA's target risk range. At WAG 6, the risk from radionuclides and chemicals for an on-WAG homesteader exceeds EPA's target risk range. Hazard indices are compared to unity for noncarcinogenic contaminants. At WAG 6, the total pathway hazard index for the on-WAG homesteader exceeds unity

Combining heuristic and statistical techniques in landslide hazard assessments

Science.gov (United States)

Cepeda, Jose; Schwendtner, Barbara; Quan, Byron; Nadim, Farrokh; Diaz, Manuel; Molina, Giovanni

2014-05-01

As a contribution to the Global Assessment Report 2013 - GAR2013, coordinated by the United Nations International Strategy for Disaster Reduction - UNISDR, a drill-down exercise for landslide hazard assessment was carried out by entering the results of both heuristic and statistical techniques into a new but simple combination rule. The data available for this evaluation included landslide inventories, both historical and event-based. In addition to the application of a heuristic method used in the previous editions of GAR, the availability of inventories motivated the use of statistical methods. The heuristic technique is largely based on the Mora & Vahrson method, which estimates hazard as the product of susceptibility and triggering factors, where classes are weighted based on expert judgment and experience. Two statistical methods were also applied: the landslide index method, which estimates weights of the classes for the susceptibility and triggering factors based on the evidence provided by the density of landslides in each class of the factors; and the weights of evidence method, which extends the previous technique to include both positive and negative evidence of landslide occurrence in the estimation of weights for the classes. One key aspect during the hazard evaluation was the decision on the methodology to be chosen for the final assessment. Instead of opting for a single methodology, it was decided to combine the results of the three implemented techniques using a combination rule based on a normalization of the results of each method. The hazard evaluation was performed for both earthquake- and rainfall-induced landslides. The country chosen for the drill-down exercise was El Salvador. The results indicate that highest hazard levels are concentrated along the central volcanic chain and at the centre of the northern mountains.

Numerical Simulations as Tool to Predict Chemical and Radiological Hazardous Diffusion in Case of Nonconventional Events

Directory of Open Access Journals (Sweden)

J.-F. Ciparisse

2016-01-01

Full Text Available CFD (Computational Fluid Dynamics simulations are widely used nowadays to predict the behaviour of fluids in pure research and in industrial applications. This approach makes it possible to get quantitatively meaningful results, often in good agreement with the experimental ones. The aim of this paper is to show how CFD calculations can help to understand the time evolution of two possible CBRNe (Chemical-Biological-Radiological-Nuclear-explosive events: (1 hazardous dust mobilization due to the interaction between a jet of air and a metallic powder in case of a LOVA (Loss Of Vacuum Accidents that is one of the possible accidents that can occur in experimental nuclear fusion plants; (2 toxic gas release in atmosphere. The scenario analysed in the paper has consequences similar to those expected in case of a release of dangerous substances (chemical or radioactive in enclosed or open environment during nonconventional events (like accidents or man-made or natural disasters.

Assessment of vulnerability to storm induced flood hazard along diverse coastline settings

Directory of Open Access Journals (Sweden)

Valchev Nikolay

2016-01-01

Full Text Available European coasts suffer notably from hazards caused by low-probability and high-impact hydrometeorological events. The aim of the study is to assess in probabilistic terms the magnitude of storm‐induced flooding hazard along Varna regional coast (Bulgaria, western Black Sea and to identify susceptible coastal sectors (hotspots. The study is performed employing the Coastal Risk Assessment Framework (CRAF developed within EU FP7 RISC-KIT project. It constitutes a screening process that allows estimation of relevant hazard intensities, extents and potential receptors’ exposure vulnerability within predefined sectors. Total water level was the chief property considered for calculation of coastal flooding hazard. It was estimated using Holman model (for sandy beaches and EurOtop formulation (for artificial or rocky slopes. Resulting values were subjected to Extreme Value Analysis to establish that the best fitting distribution corresponds to Generalized Extreme Value distribution. Furthermore, hazard extents were modelled by means of bathtubbing or overwash estimation in order to form the flooding hazard indicator. Land use, social vulnerability, transport systems, utilities and business settings were considered as exposure indicators. Finally, potential risk was assessed by coastal indices following an index-based methodology, which combines hazard and exposure indicators into a single index, thereby providing base for comparison of coastal sectors’ vulnerability. The study found that the concentration of hotspots is highest in Varna Bay.

Plant habitability assessment for Point Lepreau Generating Station during a severe accident resulting from station blackout conditions

International Nuclear Information System (INIS)

Mullin, D.

2015-01-01

In response to the CNSC Fukushima Action Plan, the CANDU Owners Group (COG) developed a methodology for assessing nuclear power plant habitability under Joint Project 4426 and to determine if any improvement actions are necessary to provide a high degree of assurance that a severe accident can be managed from a human and organizational performance perspective. NB Power has applied the methodology considering a station black-out scenario (representative case), and assessed the effects of non-radiological hazards and radiological hazards in the context of operator dose relative to emergency dose limits. The paper will discuss the overall methodology, findings and recommendations. (author)

Plant habitability assessment for Point Lepreau Generating Station during a severe accident resulting from station blackout conditions

Energy Technology Data Exchange (ETDEWEB)

Mullin, D., E-mail: dmullin@nbpower.com [New Brunswick Power Corporation, Point Lepreau Generating Station, Lepreau, NB (Canada)

2015-07-01

In response to the CNSC Fukushima Action Plan, the CANDU Owners Group (COG) developed a methodology for assessing nuclear power plant habitability under Joint Project 4426 and to determine if any improvement actions are necessary to provide a high degree of assurance that a severe accident can be managed from a human and organizational performance perspective. NB Power has applied the methodology considering a station black-out scenario (representative case), and assessed the effects of non-radiological hazards and radiological hazards in the context of operator dose relative to emergency dose limits. The paper will discuss the overall methodology, findings and recommendations. (author)

Hazard Assessment on Chlorine Distribution Use of Chemical Transportation Risk Index

International Nuclear Information System (INIS)

Kim, Jeong Gon; Byun, Hun Soo

2014-01-01

Chlorine is one of the most produced and most used non-flammable chemical substances in the world even though its toxicity and high reactivity cause the ozone layer depletion. However, in modern life, it is impossible to live a good life without using Chlorine and its derivatives since they are being used as an typical ingredient in more than 40 percent of the manufactured goods including medicines, detergents, deodorant, fungicides, herbicides, insecticides, and plastic, etc. Even if Chlorine has been handled and distributed in various business (small and medium-sized businesses, water purification plants, distribution company, etc.), there have been few researches about its possible health hazard and transportation risks. Accordingly, the purpose of this paper is to make a detailed assessment of Chlorinerelated risks and to model an index of chemicals transportation risks that is adequate for domestic circumstances. The assessment of possible health hazard and transportation risks was made on 13 kinds of hazardous chemicals, including liquid chlorine. This research may be contributed to standardizing the risk assessment of Chlorine and other hazardous chemicals by using an index of transportation risks

Hazard Assessment on Chlorine Distribution Use of Chemical Transportation Risk Index

Energy Technology Data Exchange (ETDEWEB)

Kim, Jeong Gon [Hanwha Chemical Ulsan Site, Ulsan (Korea, Republic of); Byun, Hun Soo [Chonnam National University, Yeosu (Korea, Republic of)

2014-12-15

Chlorine is one of the most produced and most used non-flammable chemical substances in the world even though its toxicity and high reactivity cause the ozone layer depletion. However, in modern life, it is impossible to live a good life without using Chlorine and its derivatives since they are being used as an typical ingredient in more than 40 percent of the manufactured goods including medicines, detergents, deodorant, fungicides, herbicides, insecticides, and plastic, etc. Even if Chlorine has been handled and distributed in various business (small and medium-sized businesses, water purification plants, distribution company, etc.), there have been few researches about its possible health hazard and transportation risks. Accordingly, the purpose of this paper is to make a detailed assessment of Chlorinerelated risks and to model an index of chemicals transportation risks that is adequate for domestic circumstances. The assessment of possible health hazard and transportation risks was made on 13 kinds of hazardous chemicals, including liquid chlorine. This research may be contributed to standardizing the risk assessment of Chlorine and other hazardous chemicals by using an index of transportation risks.

Hazardous waste management in research laboratories

International Nuclear Information System (INIS)

Sundstrom, G.

1989-01-01

Hazardous waste management in research laboratories benefits from a fundamentally different approach to the hazardous waste determination from industry's. This paper introduces new, statue-based criteria for identifying hazardous wastes (such as radiological mixed wastes and waste oils) and links them to a forward-looking compliance of laboratories, the overall system integrates hazardous waste management activities with other environmental and hazard communication initiatives. It is generalizable to other waste generators, including industry. Although only the waste identification and classification aspects of the system are outlined in detail here, four other components are defined or supported, namely: routine and contingency practices; waste treatment/disposal option definition and selection; waste minimization, recycling, reuse, and substitution opportunities; and key interfaces with other systems, including pollution prevention

Long Aftershock Sequences within Continents and Implications for Earthquake Hazard Assessment

Science.gov (United States)

Stein, S. A.; Liu, M.

2014-12-01

Recent seismicity in the Tangshan region in North China has prompted concern about a repetition of the 1976 M7.8 earthquake that destroyed the city, killing more than 242,000 people. However, the decay of seismicity there implies that the recent earthquakes are probably aftershocks of the 1976 event. This 37-year sequence is an example of the phenomenon that aftershock sequences within continents are often significantly longer than the typical 10 years at plate boundaries. The long sequence of aftershocks in continents is consistent with a simple friction-based model predicting that the length of aftershock sequences varies inversely with the rate at which faults are loaded. Hence the slowly-deforming continents tend to have aftershock sequences significantly longer than at rapidly-loaded plate boundaries. This effect has two consequences for hazard assessment. First, within the heavily populated continents that are typically within plate interiors, assessments of earthquake hazards rely significantly on the assumption that the locations of small earthquakes shown by the short historical record reflect continuing deformation that will cause future large earthquakes. This assumption would lead to overestimation of the hazard in presently active areas and underestimation elsewhere, if some of these small events are aftershocks. Second, successful attempts to remove aftershocks from catalogs used for hazard assessment would underestimate the hazard, because much of the hazard is due to the aftershocks, and the declustering algorithms implicitly assume short aftershock sequences and thus do not remove long-duration ones.

Debris flows: behavior and hazard assessment

Science.gov (United States)

Iverson, Richard M.

2014-01-01

Debris flows are water-laden masses of soil and fragmented rock that rush down mountainsides, funnel into stream channels, entrain objects in their paths, and form lobate deposits when they spill onto valley floors. Because they have volumetric sediment concentrations that exceed 40 percent, maximum speeds that surpass 10 m/s, and sizes that can range up to ~109 m3, debris flows can denude slopes, bury floodplains, and devastate people and property. Computational models can accurately represent the physics of debris-flow initiation, motion and deposition by simulating evolution of flow mass and momentum while accounting for interactions of debris' solid and fluid constituents. The use of physically based models for hazard forecasting can be limited by imprecise knowledge of initial and boundary conditions and material properties, however. Therefore, empirical methods continue to play an important role in debris-flow hazard assessment.

Patients exposure assessment for radiographic procedures in diagnostic radiology

International Nuclear Information System (INIS)

Arandjic, D.; Ciraj-Bjelac, O.; Stankovic, K.; Lazarevic, Dj.; Ciraj-Bjelac, O.)

2007-01-01

In this work the results of dose assessment for the most frequent radiographic procedures in diagnostic radiology are shown. Entrance surface doses were assessed for 7 radiographic procedures. Three hospitals, six x-ray units in total, were enrolled in investigation. Patient doses were estimated based on results of x-ray tube output measurements. Finally, doses were compared with Diagnostic reference level. Higher dose values were observed for chest examinations. In comparison with results from other countries, doses from this procedure in Serbia are significantly higher. Estimated doses for other procedures were well below Diagnostic reference levels [sr

Quality assessment for radiological model parameters

International Nuclear Information System (INIS)

Funtowicz, S.O.

1989-01-01

A prototype framework for representing uncertainties in radiological model parameters is introduced. This follows earlier development in this journal of a corresponding framework for representing uncertainties in radiological data. Refinements and extensions to the earlier framework are needed in order to take account of the additional contextual factors consequent on using data entries to quantify model parameters. The parameter coding can in turn feed in to methods for evaluating uncertainties in calculated model outputs. (author)

Radiological assessment report for the University of Rochester Annex, 400 Elmwood Avenue, Rochester, New York, April-May 1984

International Nuclear Information System (INIS)

Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Flynn, K.F.

1984-12-01

In light of the results of the comprehensive radiological assessment of the annex and auxiliary facilities, the following conclusions can be made: There is no immediate hazard from the elevated levels of radioactivity detected; however, some of these levels are above criteria. The radon, thoron, actinon, long-lived particulates, and tritium in the air are all below criteria for unrestricted use. Some ductwork has been identified as being contaminated. All ductwork must, therefore, be considered potentially contaminated. Since several floor drains were found to exhibit elevated readings, and the samples had elevated concentrations of radionuclides, it must be concluded that the drain and sewer systems of the Annex are contaminated with radioactive material. Since the samples collected from the storm and sewer systems outside the building also had elevated concentrations of radionuclides, these systems are also considered contaminated with radioactive material. The grounds around the Annex have exhibited background concentrations of radionuclides. Two rooms, B-330 and B-332, were inaccessible for survey due to the presence of stored furniture and equipment. Therefore, no comment about their radiological status can be made. At the common baseboard for Room C-12 and C-16 and on the floor below the tile in Room C-40, contamination appeared to be masked by construction modifications. Other areas of the Annex must also be considered potentially contaminated where modifications may have masked the contamination

Mineralogical, geochemical and radiological characterisation of Selmo Formation in Batman area, Turkey.

Science.gov (United States)

Isik, Umit; Damla, Nevzat; Akkoca, Dicle Bal; Cevik, Uğur

2012-06-01

This work deals with the mineralogical, geochemical and radiological characterisations of Selmo Formation in Batman neighbourhood. The upper Miocene-Pliocene Selmo Formation is common in the centre of Batman and composed of carbonated sandy claystones and silty-sandy stone lenses. The common whole minerals of the samples are quartz, feldspars, calcite and dolomite. The clay minerals are smectite, illite, chlorite and mixed-layer clay (chlorite-smectite). The geochemical mean values of the samples are 51.7% SiO(2); 12.6% Al(2)O(3); 6.2% Fe(2)O(3); 3.6% MgO; 6.3% CaO; 1.1% Na(2)O; 1.7% K(2)O; 0.8% TiO(2); 0.2% P(2)O(5); 0.1% MnO; and 0.03% Cr(2)O(3). In addition, baseline maps for the concentrations of each radionuclide, the radium equivalent activity and the outdoor gamma dose rate distributions have been plotted for the study area. The mean activity concentrations of (226)Ra, (232)Th, (40)K and (137)Cs were determined to be 32, 24, 210 and 9 Bq kg(-1), respectively. The assessments of the radiological hazard indices, such as radium equivalent activity, absorbed dose rate in air, annual effective dose equivalent, excess lifetime cancer risk, external hazard index and internal hazard index, were calculated and compared with the internationally accepted reference values. This study shows that the concentrations of radioactivities in the measured samples were within the recommended safety limits and did not pose to be any significant source of radiation hazard.

Radiological assessment of 50 cases of incisive or maxillary neoplasia in the dog

International Nuclear Information System (INIS)

Frew, D.G.; Dobson, J.M.

1992-01-01

This paper reviews the radiological features of 50 canine incisive or maxillary tumours and discusses the value of radiological assessment in the diagnosis and staging of these tumours. The 50 tumours examined included 21 sarcomas, 15 carcinomas, three melanomas and an assortment of benign tumours of the oral cavity. There was not any site specificity for the different histological tumour types within the upper dental arcade, although fibrosarcomas had a tendency to be maxillary whereas the squamous cell carcinomas were equally distributed between the incisive and maxillary regions. Seventy-eight per cent of fibrosarcomas, 82 per cent of squamous cell carcinoma and all three melanomas examined showed radiological evidence of bone involvement. Radiographic changes were also seen in the benign tumours. The pattern of growth of tumours correlated with the radiological changes observed. Malignant tumours showed a tendency to irregular or aggressive bone loss whereas bone production predominated in the benign tumours

Probabilistic risk assessment framework for structural systems under multiple hazards using Bayesian statistics

Energy Technology Data Exchange (ETDEWEB)

Kwag, Shinyoung [North Carolina State University, Raleigh, NC 27695 (United States); Korea Atomic Energy Research Institute, Daejeon 305-353 (Korea, Republic of); Gupta, Abhinav, E-mail: agupta1@ncsu.edu [North Carolina State University, Raleigh, NC 27695 (United States)

2017-04-15

Highlights: • This study presents the development of Bayesian framework for probabilistic risk assessment (PRA) of structural systems under multiple hazards. • The concepts of Bayesian network and Bayesian inference are combined by mapping the traditionally used fault trees into a Bayesian network. • The proposed mapping allows for consideration of dependencies as well as correlations between events. • Incorporation of Bayesian inference permits a novel way for exploration of a scenario that is likely to result in a system level “vulnerability.” - Abstract: Conventional probabilistic risk assessment (PRA) methodologies (USNRC, 1983; IAEA, 1992; EPRI, 1994; Ellingwood, 2001) conduct risk assessment for different external hazards by considering each hazard separately and independent of each other. The risk metric for a specific hazard is evaluated by a convolution of the fragility and the hazard curves. The fragility curve for basic event is obtained by using empirical, experimental, and/or numerical simulation data for a particular hazard. Treating each hazard as an independently can be inappropriate in some cases as certain hazards are statistically correlated or dependent. Examples of such correlated events include but are not limited to flooding induced fire, seismically induced internal or external flooding, or even seismically induced fire. In the current practice, system level risk and consequence sequences are typically calculated using logic trees to express the causative relationship between events. In this paper, we present the results from a study on multi-hazard risk assessment that is conducted using a Bayesian network (BN) with Bayesian inference. The framework can consider statistical dependencies among risks from multiple hazards, allows updating by considering the newly available data/information at any level, and provide a novel way to explore alternative failure scenarios that may exist due to vulnerabilities.

Probabilistic risk assessment framework for structural systems under multiple hazards using Bayesian statistics

International Nuclear Information System (INIS)

Kwag, Shinyoung; Gupta, Abhinav

2017-01-01

Highlights: • This study presents the development of Bayesian framework for probabilistic risk assessment (PRA) of structural systems under multiple hazards. • The concepts of Bayesian network and Bayesian inference are combined by mapping the traditionally used fault trees into a Bayesian network. • The proposed mapping allows for consideration of dependencies as well as correlations between events. • Incorporation of Bayesian inference permits a novel way for exploration of a scenario that is likely to result in a system level “vulnerability.” - Abstract: Conventional probabilistic risk assessment (PRA) methodologies (USNRC, 1983; IAEA, 1992; EPRI, 1994; Ellingwood, 2001) conduct risk assessment for different external hazards by considering each hazard separately and independent of each other. The risk metric for a specific hazard is evaluated by a convolution of the fragility and the hazard curves. The fragility curve for basic event is obtained by using empirical, experimental, and/or numerical simulation data for a particular hazard. Treating each hazard as an independently can be inappropriate in some cases as certain hazards are statistically correlated or dependent. Examples of such correlated events include but are not limited to flooding induced fire, seismically induced internal or external flooding, or even seismically induced fire. In the current practice, system level risk and consequence sequences are typically calculated using logic trees to express the causative relationship between events. In this paper, we present the results from a study on multi-hazard risk assessment that is conducted using a Bayesian network (BN) with Bayesian inference. The framework can consider statistical dependencies among risks from multiple hazards, allows updating by considering the newly available data/information at any level, and provide a novel way to explore alternative failure scenarios that may exist due to vulnerabilities.

The Generalised Ecosystem Modelling Approach in Radiological Assessment

Energy Technology Data Exchange (ETDEWEB)

Klos, Richard

2008-03-15

An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments, SSI through its modelling team CLIMB commissioned the development of a new model in 2004, a project to produce an integrated model of radionuclides in the landscape. The generalised ecosystem modelling approach (GEMA) is the result. GEMA is a modular system of compartments representing the surface environment. It can be configured, through water and solid material fluxes, to represent local details in the range of ecosystem types found in the past, present and future Swedish landscapes. The approach is generic but fine tuning can be carried out using local details of the surface drainage system. The modular nature of the modelling approach means that GEMA modules can be linked to represent large scale surface drainage features over an extended domain in the landscape. System change can also be managed in GEMA, allowing a flexible and comprehensive model of the evolving landscape to be constructed. Environmental concentrations of radionuclides can be calculated and the GEMA dose pathway model provides a means of evaluating the radiological impact of radionuclide release to the surface environment. This document sets out the philosophy and details of GEMA and illustrates the functioning of the model with a range of examples featuring the recent CLIMB review of SKB's SR-Can assessment

The Generalised Ecosystem Modelling Approach in Radiological Assessment

International Nuclear Information System (INIS)

Klos, Richard

2008-03-01

An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments, SSI through its modelling team CLIMB commissioned the development of a new model in 2004, a project to produce an integrated model of radionuclides in the landscape. The generalised ecosystem modelling approach (GEMA) is the result. GEMA is a modular system of compartments representing the surface environment. It can be configured, through water and solid material fluxes, to represent local details in the range of ecosystem types found in the past, present and future Swedish landscapes. The approach is generic but fine tuning can be carried out using local details of the surface drainage system. The modular nature of the modelling approach means that GEMA modules can be linked to represent large scale surface drainage features over an extended domain in the landscape. System change can also be managed in GEMA, allowing a flexible and comprehensive model of the evolving landscape to be constructed. Environmental concentrations of radionuclides can be calculated and the GEMA dose pathway model provides a means of evaluating the radiological impact of radionuclide release to the surface environment. This document sets out the philosophy and details of GEMA and illustrates the functioning of the model with a range of examples featuring the recent CLIMB review of SKB's SR-Can assessment

Radiological risk assessment for an urban area: Focusing on a drinking water contamination

International Nuclear Information System (INIS)

Jeong, Hyo-Joon; Hwang, Won-Tae; Kim, Eun-Han; Han, Moon-Hee

2009-01-01

This paper specifically discusses a water quality modeling and health risk assessment for cesium-137 to assess the potential and actual effects on human health from drinking water contaminated by a radiological terrorist attack in the Seoul metropolitan area, Korea. With respect to the source term caused by a terrorist attack, it was assumed that 50 TBq of cesium-137 was introduced into the Paldang Lake which is a single water resource for the Seoul metropolitan area. EFDC (Environmental Fluid Dynamics Code) model was used to calculate the hydrodynamic and water quality for the model domain, Paldang Lake. Mortality risk and morbid risk coefficients caused by the ingestion of tap water were used to assess a human health risk due to cesium-137. The transport of cesium-137 in the Paldang water system was mainly dependent on the flow streamlines and the effect of the dilution from the other branches. The mortality and morbidity risks due to the drinking water contamination by cesium-137 were 4.77 x 10 -7 and 6.92 x 10 -7 , respectively. Accordingly, it is very important to take appropriate countermeasures when radiological terrorist attacks have occurred at water resources to prevent radiological risks by radionuclides.

National Waste Repository Novi Han operational safety analysis report. Safety assessment methodology

International Nuclear Information System (INIS)

2003-01-01

The scope of the safety assessment (SA), presented includes: waste management functions (acceptance, conditioning, storage, disposal), inventory (current and expected in the future), hazards (radiological and non-radiological) and normal and accidental modes. The stages in the development of the SA are: criteria selection, information collection, safety analysis and safety assessment documentation. After the review the facilities functions and the national and international requirements, the criteria for safety level assessment are set. As a result from the 2nd stage actual parameters of the facility, necessary for safety analysis are obtained.The methodology is selected on the base of the comparability of the results with the results of previous safety assessments and existing standards and requirements. The procedure and requirements for scenarios selection are described. A radiological hazard categorisation of the facilities is presented. Qualitative hazards and operability analysis is applied. The resulting list of events are subjected to procedure for prioritization by method of 'criticality analysis', so the estimation of the risk is given for each event. The events that fall into category of risk on the boundary of acceptability or are unacceptable are subjected to the next steps of the analysis. As a result the lists with scenarios for PSA and possible design scenarios are established. PSA logical modeling and quantitative calculations of accident sequences are presented

The reliability and validity of radiological assessment for patellar instability. A systematic review and meta-analysis

Energy Technology Data Exchange (ETDEWEB)

Smith, Toby O. [University of East Anglia, Faculty of Health, Norwich (United Kingdom); Davies, Leigh [Norfolk and Norwich University Hospital, Norwich (United Kingdom); Toms, Andoni P.; Donell, Simon T. [University of East Anglia, Faculty of Health, Norwich (United Kingdom); Norfolk and Norwich University Hospital, Norwich (United Kingdom); Hing, Caroline B. [St George' s Hospital, London (United Kingdom)

2011-04-15

To determine the discriminative validity and reliability of the evidence base using meta-analysis. A review of published sources using the databases AMED, CINHAL, EMBASE, MEDLINE, Scopus and the Cochrane Library, and for unpublished material was conducted. All studies assessing the reliability, validity, sensitivity or specificity of magnetic resonance imaging (MRI), computed tomography (CT) or ultrasound (US) of the patellofemoral joint of patients following patellar dislocation, subluxation or instability, were included. A meta-analysis was performed to assess the difference in radiological measurements between healthy controls and subjects with patellar instability in order to assess discrimination validity. A narrative assessment was used to evaluate the inter- and intra-observer reliability as well as the sensitivity and specificity of specific radiological measurements. A total of 27 studies were reviewed. The findings indicated that there was acceptable inter-observer and intra-observer reliability and validity for different methods of assessing patellar height and the sulcus angle with X-ray, MRI and CT methods, and the tibial tubercle-trochlear groove (TT-TG) assessed using CT. There was poor reliability or validity for the assessment of severity of trochlear dysplasia and the sulcus angle using US. There is insufficient evidence to determine the reliability, validity, sensitivity or specificity of tests such as the congruence angle, lateral patellar displacement, lateral patellar tilt, trochlear depth, boss height, the crossing sign or Wiberg patellar classification. A critical appraisal of the literature identified a number of recurrent methodological limitations. Further study is recommended to evaluate the reliability and validity of these radiological outcomes using well-designed radiological trials. (orig.)

The reliability and validity of radiological assessment for patellar instability. A systematic review and meta-analysis

International Nuclear Information System (INIS)

Smith, Toby O.; Davies, Leigh; Toms, Andoni P.; Donell, Simon T.; Hing, Caroline B.

2011-01-01

To determine the discriminative validity and reliability of the evidence base using meta-analysis. A review of published sources using the databases AMED, CINHAL, EMBASE, MEDLINE, Scopus and the Cochrane Library, and for unpublished material was conducted. All studies assessing the reliability, validity, sensitivity or specificity of magnetic resonance imaging (MRI), computed tomography (CT) or ultrasound (US) of the patellofemoral joint of patients following patellar dislocation, subluxation or instability, were included. A meta-analysis was performed to assess the difference in radiological measurements between healthy controls and subjects with patellar instability in order to assess discrimination validity. A narrative assessment was used to evaluate the inter- and intra-observer reliability as well as the sensitivity and specificity of specific radiological measurements. A total of 27 studies were reviewed. The findings indicated that there was acceptable inter-observer and intra-observer reliability and validity for different methods of assessing patellar height and the sulcus angle with X-ray, MRI and CT methods, and the tibial tubercle-trochlear groove (TT-TG) assessed using CT. There was poor reliability or validity for the assessment of severity of trochlear dysplasia and the sulcus angle using US. There is insufficient evidence to determine the reliability, validity, sensitivity or specificity of tests such as the congruence angle, lateral patellar displacement, lateral patellar tilt, trochlear depth, boss height, the crossing sign or Wiberg patellar classification. A critical appraisal of the literature identified a number of recurrent methodological limitations. Further study is recommended to evaluate the reliability and validity of these radiological outcomes using well-designed radiological trials. (orig.)

AECB workshop on seismic hazard assessment in southern Ontario

International Nuclear Information System (INIS)

Stepp, J.C.; Price, R.A.; Coppersmith, K.J.; Klimkiewicz, G.C.; McGuire, R.K.

1995-10-01

The purpose of the workshop was to review available geological and seismological data which could affect earthquake occurrence in southern Ontario and to develop a consensus on approaches that should be adopted for characterization of seismic hazard. The workshop was structured in technical sessions to focus presentations and discussions on four technical issues relevant to seismic hazard in southern Ontario, as follows: (1) The importance of geological and geophysical observations for the determination of seismic sources, (2) Methods and approaches which may be adopted for determining seismic sources based on integrated interpretations of geological and seismological information, (3) Methods and data which should be used for characterizing the seismicity parameters of seismic sources, and (4) Methods for assessment of vibratory ground motion hazard. The format of each session involved invited presentations of relevant data followed by open presentations by participants, a general discussion focusing on the relevance of the presented information for seismic hazard assessment in southern Ontario, then development of conclusions and recommendations. In the final session, the conclusions and recommendations were summarized and an open discussion was held to develop consensus. This report presents perspective summaries of the workshop technical sessions together with conclusions and recommendations prepared by the session chairs and the general chairman. 2 refs

Determination of Radiological Hazard Associated with the use of ...

African Journals Online (AJOL)

Journal of Applied Sciences and Environmental Management ... calculated to be 17.41nGyhr-1 with mean annual effective dose rate of 0.022mSvyr-1The values of the radiological indicators were found to be within the limits recommended for safety, indicating that the use of the sediment of the river as building material does ...

Integration of Probabilistic Exposure Assessment and Probabilistic Hazard Characterization

NARCIS (Netherlands)

Voet, van der H.; Slob, W.

2007-01-01

A method is proposed for integrated probabilistic risk assessment where exposure assessment and hazard characterization are both included in a probabilistic way. The aim is to specify the probability that a random individual from a defined (sub)population will have an exposure high enough to cause a

Mine aftershocks and implications for seismic hazard assessment

CSIR Research Space (South Africa)

Kgarume, T

2010-11-01

Full Text Available A methodology of assessing the seismic hazard associated with aftershocks is developed by performing statistical and deterministic analysis of seismic data from two South African deep-level gold mines. A method employing stacking of aftershocks...