The results of artificial radionuclides monitoring in the Baltic sea

International Nuclear Information System (INIS)

Astrauskiene, N.; Lukinskiene, M; Zemaitiene, G.

1994-01-01

Long-term radionuclides volume activity (v.a.) monitoring (1976-1990) data showed that measurement results obtained in steady observation station give reliable information of the coastal area of the Baltic sea radioactive equilibrium between atmosphere and surface water was observed in the coastal zone. Chernobyl Power Plant accident influenced upon the Baltic sea coastal water by radionuclides 137 Cs and 144 Ce. Radionuclide 90 Sr volume activity was practically unchangerable. The mechanism of radionuclides fallout from atmosphere are various. lt can be illustrated by 137 Cs and 144 Ce a.v. structure field variations in open sea and coastal zone near Juodkrante. The Baltic sea inhomogeneous contamination by radionuclide 137 Cs in 1988-1990 leads to equalization of 137 Cs v.a. in the surface waters and it causes v.a. increase in coastal waters. (author)

Global Monitoring of the CTBT: Progress, Capabilities and Plans (Invited)

Science.gov (United States)

Zerbo, L.

2013-12-01

The Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), established in 1996, is tasked with building up the verification regime of the CTBT. The regime includes a global system for monitoring the earth, the oceans and the atmosphere for nuclear tests, and an on-site inspection (OSI) capability. More than 80% of the 337 facilities of the International Monitoring System (IMS) have been installed and are sending data to the International Data Centre (IDC) in Vienna, Austria for processing. These IMS data along with IDC processed and reviewed products are available to all States that have signed the Treaty. Concurrent with the build-up of the global monitoring networks, near-field geophysical methods are being developed and tested for OSIs. The monitoring system is currently operating in a provisional mode, as the Treaty has not yet entered into force. Progress in installing and operating the IMS and the IDC and in building up an OSI capability will be described. The capabilities of the monitoring networks have progressively improved as stations are added to the IMS and IDC processing techniques refined. Detection thresholds for seismic, hydroacoustic, infrasound and radionuclide events have been measured and in general are equal to or lower than the predictions used during the Treaty negotiations. The measurements have led to improved models and tools that allow more accurate predictions of future capabilities and network performance under any configuration. Unplanned tests of the monitoring network occurred when the DPRK announced nuclear tests in 2006, 2009, and 2013. All three tests were well above the detection threshold and easily detected and located by the seismic monitoring network. In addition, noble gas consistent with the nuclear tests in 2006 and 2013 (according to atmospheric transport models) was detected by stations in the network. On-site inspections of these tests were not conducted as the Treaty has not entered

Automated multi-radionuclide separation and analysis with combined detection capability

Science.gov (United States)

Plionis, Alexander Asterios

The radiological dispersal device (RDD) is a weapon of great concern to those agencies responsible for protecting the public from the modern age of terrorism. In order to effectively respond to an RDD event, these agencies need to possess the capability to rapidly identify the radiological agents involved in the incident and assess the uptake of each individual victim. Since medical treatment for internal radiation poisoning is radionuclide-specific, it is critical to identify and quantify the radiological uptake of each individual victim. This dissertation describes the development of automated analytical components that could be used to determine and quantify multiple radionuclides in human urine bioassays. This is accomplished through the use of extraction chromatography that is plumbed in-line with one of a variety of detection instruments. Flow scintillation analysis is used for 90Sr and 210Po determination, flow gamma analysis is used assess 60 Co and 137Cs, and inductively coupled plasma mass spectrometry is used to determine actinides. Detection limits for these analytes were determined for the appropriate technique and related to their implications for health physics.

Comprehensive Test Ban Treaty (CTBT) monitoring station operating regime influence on radionuclide detection sensitivity

International Nuclear Information System (INIS)

Williams, D.L.

1999-01-01

International Monitoring System (IMS) stations are being deployed worldwide in support of the Comprehensive [Nuclear] Test Ban Treaty (CTBT). The highly sensitive radionuclide monitoring stations regularly sample airborne radionuclide particulates to determine whether fission products are present in the atmosphere that may be indicative of a nuclear weapons test. Standards have been set for these stations regarding their operation regime and the minimum detectable concentrations (MDCs) for specific radionuclides likely to be present after a nuclear weapons test. This study uses actual CTBT monitoring data to relate a subset of the specified operational standards with the listed MDC limits. It is determined that a relationship exists between the specified operational regime and the MDC values. Since the background radioactivity is largely a function of the radon and thoron progeny, longer decay operational regimes allow for a reduction in the background. For longer lived radionuclides, this corresponds to a reduction in MDC. (author)

The Navruz experiment. Cooperative monitoring for radionuclides and metals in Central Asia transboundary rivers

International Nuclear Information System (INIS)

Barber, D.S.; Betsill, J.D.; Mohagheghi, A.H.; Passell, H.D.; Yuldashev, B.; Salikhbaev, U.; Djuraev, A.; Vasiliev, I.; Solodukhin, V.

2005-01-01

In March of 2000, scientists from four nuclear physics research institutes in the Central Asia Republics of Kazakhstan, Kyrgyzstan, Tajikistan, and Uzbekistan, and the U.S. Sandia National Laboratories embarked on a three-year cooperative transboundary river monitoring experiment. The experiment, named Navruz (meaning 'new beginning'), uses standardized methods to monitor basic water quality parameters, radionuclides, and metals in the Syr Darya and Amu Darya rivers. Overall, the project addresses three main goals: (1) to help increase capabilities in Central Asian nations for sustainable water resources management; (2) to provide a scientific basis for supporting nuclear transparency and non-proliferation in the region; and (3) to help reduce the threat of conflict in Central Asia over water resources. Contamination of these rivers is a result of growing population, urbanization, agricultural uses, and radioactive and metals contamination from a legacy of uranium mining, industry, and other activities of the former Soviet Union. The project focuses on waterborne radionuclides and metals because of the importance of these contaminants to public health and political stability in Central Asia. Moreover, the method of enabling scientists from bordering countries to study a transboundary problem, can lead to a greater scientific understanding, consensus on necessary mitigation steps, and ultimately the political resolution of the issue. The project scope, approach, and preliminary results are presented. (author)

Rapid monitoring of gaseous radionuclides using a portable spectrometer

International Nuclear Information System (INIS)

Chung, C.; Tsai, C.H.

1995-01-01

A field gamma ray spectrometer, consisting of a portable high purity germanium detector, portable multichannel analyser, and a notebook computer, was used to conduct in situ rapid scanning of radioactive Ar, Kr and Xe isotopes in the air around a nuclear facility. The portable gamma ray spectrometer was calibrated using Ar, Kr, and Xe radioisotopes, activated in a research reactor and released in a sealed chamber. The unit was further tested inside the reactor containment to monitor the concentration of 41 Ar. In a typical one hour field measurement, the detection limits for some rare gas radionuclides corresponded to dose rates around 0.1 nSv.h -1 , which is far less than the dose rate induced by derived air concentrations imposed by the authority. The dose rate due to ground level concentrations of gaseous radionuclides dispersed from a source, such a nuclear facility or nuclear test, can be monitored in a short period using the portable unit. (Author)

Using radionuclide imaging for monitoring repairment of bone defect with tissue-engineered bone graft in rabbits

International Nuclear Information System (INIS)

Xia Changsuo; Ye Fagang; Zou Yunwen; Ji Shixiang; Wang Dengchun

2004-01-01

Objective: To observe the effect of tissue-engineered bone grafts in repairing bone defect in rabbits, and assess the value of radionuclide for monitoring the therapeutic effect of this approach. Methods: Bilateral radial defects of 15 mm in length in 24 rabbits were made. The tissue-engineered bone grafts (composite graft) contained bone marrow stromal cells (BMSCs) of rabbits and calcium phosphate cement (CPC) were grafted in left side defects, CPC only grafts (artificial bone graft) in right defects. After the operation, radionuclide was used to monitor the therapeutic effects at 4, 8 and 12 weeks. Results: 99 Tc m -methylene diphosphonic acid (MDP) radionuclide bone imaging indicated that there was more radionuclide accumulation in grafting region of composite than that of CPC. There was significant difference between 99 Tc m -MDP uptake of the region of interest (ROI) and scintillant counts of composite bone and the artificial bone (P<0.01). Conclusion: Tissue-engineered bone grafts is eligible for repairing radial bone defects, and radionuclide imaging may accurately monitor the revascularization and bone regeneration after the bone graft implantation. (authors)

Monitoring and characterization of radionuclide transport in the hydrogeologic system

International Nuclear Information System (INIS)

Phillips, S.J.; Raymond, J.R.

1975-01-01

The groundwater monitoring program provides information and data on groundwater quality required to evaluate the impact of waste disposal practices on the Hanford Reservation. The program includes: collection and analysis of groundwater samples on a routine basis; data processing, analysis and reporting; design, construction and maintenance of well sampling structures; and design and implementation of supporting research studies. Within the overall framework of the Groundwater Monitoring Program, the 300 Area and Wye Burial Ground Characterization Program was initiated to evaluate transport of radionuclides in the partially saturated zone above the water table and to provide site characterization at solid waste burial locations on the Reservation. Methods for collecting and analyzing program data include geophysical exploration by ground penetrating radar, refraction and reflection acoustics, magnetics, and metal detection; stratigraphic investigations by drilling and sample collection techniques; evaluation of transport phenomena by in situ psychrometric and gamma-neutron techniques; laboratory characterization of fluid and vapor transport-controlling mechanisms; and evaluation of biological radionuclide transport by organisms inhabiting contaminated areas

Internal Dosimetry Monitoring- Detection Limits for a Selected Set of Radionuclides and Their Translation Into Committed Effective Dose

International Nuclear Information System (INIS)

Brandl, A.; Hrnecek, E.; Steger, F.

2004-01-01

To harmonize the practice of internal dosimetry monitoring across the country, the Austrian Standards Institute is currently drafting a new set of standards which are concerned with occupational incorporation monitoring of individuals handling non-sealed radioactive material. This set of standards is expected to consist of three parts discussing the general necessity and frequency, the requirements for monitoring institutions, and the determination and rigorous calculation of committed effective dose after incorporation of radioactive material, respectively. Considerations of the requirements for routine monitoring laboratories have led to an evaluation of the detection limits for routine monitoring equipment. For a selected set of radionuclides, these detection limits are investigated in detail. The main emphasis is placed on the decay chains of naturally occurring radionuclides showing some significant potential for being out of equilibrium due to chemical processes in certain mining industries. The radionuclides considered in this paper are 226Ra, 228Ra, 228Th, 232Th, 234U, 235U, and 238U. Given the routine monitoring intervals of the Austrian Standard, these detection limits are translated into information on committed effective dose. This paper investigates whether routine monitoring equipment is sufficient to ensure compliance with EC directive 96/29/Euratom for this selected set of radionuclides. (Author) 9 refs

Estimation of radionuclide releases in atmosphere from Cernavoda NPP based on continuous gaseous effluent monitoring

International Nuclear Information System (INIS)

Bobric, E.; Murgoci, S.; Popescu, I.; Ibadula, R.

2001-01-01

Monitoring of gaseous effluents from Cernavoda NPP is performed to assess the environmental impact of the plant operation. The results of the monitoring program are used to evaluate the population doses in order to ensure that the emissions of radionuclides in air are below regulatory limits and radiation doses are maintained ALARA. It complements, but is independent from the Operational Environmental Monitoring Program for Cernavoda NPP. Gaseous effluent monitors provide continuous indication of the radioactivity content in atmospheric emissions. Except for noble gases, these monitors also collect samples for later detailed analysis in the station Health Physics Laboratory. This paper presents the main equipment and the results of the gaseous effluents monitoring program in order to assess the impact of Cernavoda NPP operation and to predict the future releases as function of radionuclides concentrations in CANDU systems, based on the identified trends.(author)

Incorporation monitoring, above all for naturally occuring radionuclides; Inkorporationsueberwachung, vor allem bei natuerlichen radioaktiven Stoffen

Energy Technology Data Exchange (ETDEWEB)

Breustedt, Bastian [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Inst. fuer Strahlenforschung; Buchholz, Werner [Bundesamt fuer Strahlenschutz, Oberschleissheim (Germany). FB Strahlenschutz und Gesundheit; Burow, Mechthild [Forschungszentrum Juelich GmbH (Germany). Geschaeftsbereich ' ' Sicherheit und Strahlenschutz' ' ; and others

2017-08-01

The contribution of the main topic deals with further development of ICRP-models and standardization of regulations in the field of incorporation monitoring. Natural radionuclides, medically used radionuclides and quality assurance, will be discussed. The planning and realization of a shielding chamber for a whole body counter is presented.

Optimization of monitoring sewage with radionuclide contaminants

International Nuclear Information System (INIS)

Egorov, V.N.

1991-01-01

Recommendations on optimization of monitoring contaminated sewage aimed at enviromental protection agxinst radioactive contamination at minimum cost are presented. The way of selecting water sampling technique depends on water composition stability and flow rate. Depending on the type of radionuclide distribution in the sewage one can estimate minimum frequency of sampling or number of samples sufficient for assuring reliability of the conclusion on the excess or non-excess of permissible radioactive contamination levels, as well as analysis assigned accuracy. By irregular contaminated sewage-discharge and possibility of short-term releases of different form and duration, sampling should be accomplished through automatic devices of continuons or periodic operation

Development of a computational system for monitoring data management in vivo of the radionuclides in human body

International Nuclear Information System (INIS)

Reis, Arlene A. dos; Lucena, Eder A. de; Dantas, Ana Leticia A.; Dantas, Bernardo M.

2014-01-01

The management of in vivo monitoring process of internal contamination by radionuclides in human beings request a set of steps ranging from the spectrum acquisition to reporting. The spectrum analysis is the identification and quantification of radioactive materials present in organs and individual's body tissues submitted to monitoring procedures. The Body Counter Unit of IRD performs in vivo measurements emitting radionuclide photons in the 10-3000 keV energy range, using NaI type scintillation detectors (Tl) 8” x 4” and 3” x 3” and as semiconductor detectors type HPGe. The measuring system uses the Canberra Genie 2000 software for the acquisition of spectra with 1024 channels related to their respective energies. The counting are distributed in the spectrum due to the energy of the photons emitted by radionuclides of interest. The SIGMIV program (System for Management of in vivo monitoring), developed in MS Visual Basic 2010 accesses the spectrum after it is converted into an EXCEL spreadsheet. This program uses a bank Data developed in MS-Access to store information associated with each measurement, as counting and calibration parameters. SIGMIV generates a report containing personal information, activity and radionuclides of interest present in the body, associated with respective uncertainties and minimum activity detectable. The program SIGMIV optimized monitoring procedures 'in vivo', showing that is flexible, reliable and easy to handle, thus becoming an important tool for development routine in In vivo Monitoring Laboratory of IRD

Natural radionuclides monitoring in Lombardia drinking water by liquid scintillation technique

International Nuclear Information System (INIS)

Forte, M.; Rusconi, R.; Bellinsona, S.; Sgorbati, G.

2002-01-01

Concern about total radionuclides content in water intended for human consumption has been brought to public attention by the recent Council Directive 98/83/EC, subsequently enforced through an Italian law (DL 31, February 2., 2001). Parameter values have been fixed for Tritium content and total indicative dose: the Directive points out that the total indicative dose must be evaluated excluding Tritium, 4 0K , 1 4C , Radon and its decay products, but including all other natural series radionuclides. Maximum concentration values for Radon are separately proposed in Commission Recommendation 2001/928/Euratom. Tritium determination follows a well established procedure, standardised by International Standard Organisation (ISO 9698, 1989). On the contrary, total indicative dose evaluation requires more specific and cumbersome procedures for the measurement of radioactivity content, with special regard to natural series radionuclides. The large number of possibly involved radionuclides and the good sensitivities required make the application of traditional analytical techniques unsuitable in view of a large scale monitoring program. World Health Organisation (WHO 1993 and 1996) guidelines for drinking water suggest performing an indirect evaluation of committed dose by measuring alpha and beta gross radioactivity and checking compliance to derived limit values; the proposed limit values are 0,1 Bq/l for gross alpha and 1 Bq/l for gross beta radioactivity. Nevertheless, it is desirable to identify single radionuclides contribution to alpha and beta activity in order to perform more accurate measurements of committed dose

Airborne radionuclides of concern and their measurement in monitoring a Comprehensive Test Ban Treaty

International Nuclear Information System (INIS)

Perkins, R.W.; Miley, H.S.; Hensley, W.K.; Abel, K.H.

1995-01-01

The U.S. Department of Energy (DOE) is conducting radioanalytical developmental programs with the goal of providing near-real-time analysis technology for airborne signature radionuclides which are indicative of a nuclear weapons test in any of the earth's environments. If a test were conducted in the atmosphere or above the atmosphere, then the full spectrum of fission and activation products, together with residues from the device would be dispersed in the atmosphere. However, if a nuclear test were conducted underground or under water, the emission could range from a major to a very minor vent, and the material released would likely consist mainly of noble gas radionuclides and the radioiodines. Since many of the noble gases decay to form particulate radionuclides, these may serve as the more sensitive signatures. For example, Ba-140 is a daughter of Xe-140 (13.6 s), and Cs-137 is a daughter of Xe-137 (3.82 min). Both of these have been observed in large amounts relative to other fission products in dynamic venting of U.S. underground nuclear detonations. Large amounts of radionuclides are produced from even a comparatively small nuclear detonation. For example, a 10-KT fission device will produce approximately a megacurie of Ba-140 and of several other radionuclides with half-lives of days to weeks. If such a device were detonated in the atmosphere at midlatitude, it would easily be observable at downwind monitoring sites during its first and subsequent circumnavigations of the earth. Efficient and practical methods for the near-real-time analysis of both particulate and gaseous radionuclides are important to an effective monitoring and attribution program in support of a Comprehensive Test Ban Treaty (CTBT); methods for this purpose are being pursued

Longtime radionuclide monitoring in the vicinity of Salaspils nuclear reactor

International Nuclear Information System (INIS)

Riekstina, D.; Berzins, J.; Krasta, T.; Skrypnik, O.; Alksnis, J.

2016-01-01

The research nuclear reactor in Salaspils was decommissioned in 1998. Now reactor is partially dismantled and its territory is used as a temporary storage of radioactivity contaminated materials and water. Environment radioactivity monitoring for presence of artificial radionuclides in the vicinity of Salaspils nuclear reactor is carried out since 1990. Data include Cs-137 concentration in soils, tritium concentration in ground water, as well as H-3, Cs-137, Co-60 concentration and gross beta-activity of reactors sewage and rainwater drainage. The systematic monitoring allowed to detect in December 2014 a leakage from the special wastewater basin and so to prevent a pollution of ground water outside reactors territory.

The use of algae in monitoring discharges of radionuclides. Experiences from the 1992 and 1993 monitoring programmes at the Swedish nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Snoeijs, P. [Uppsala Univ. (Sweden). Dept. of Ecological Botany; Simenstad, P. [Swedish Radiation Protection Inst., Stockholm (Sweden)

1995-01-01

All four Swedish nuclear power plants (Forsmark, Oskarshamn, Barsebaeck and Ringhals) use brackish water as coolant (Baltic Sea and Swedish west coast). Radionuclides are discharged together with the cooling water. The gamma spectra of monthly algal samples harvested in 1992 and 1993 close to the discharge points of these power plants were determined within the routine monitoring programmes. The main radionuclides detected in the algal samples were {sup 54}Mn, {sup 58}Co, {sup 60}Co and {sup 137}Cs. Most {sup 137}Cs in the samples from the northern Baltic Sea (Forsmark) still originated from the 1986 Chernobyl accident. Other radionuclides, notably {sup 51}Cr, {sup 65}Zn, {sup 95}Zr, {sup 95}Nb, {sup 110m}Ag, {sup 124}b, {sup 125}Sb and {sup 134}Cs, were regularly detected at s of the sites. Transfer factors from discharge to algae were generally in the order of 0.3-3 Bq kg{sup -1} per MBq discharge. For the major discharged radionuclides, significant linear relationships were in most cases found between discharges and concentrations in algal samples. Differences in transfer factors and regression coefficients were explained by location of the sampling sites and type of radionuclide. It is concluded that algal samples provide useful complements to water and sediment samples in the monitoring programmes since radionuclide concentrations are much higher in algal samples and proportional to the discharges. 21 refs, figs.

Limitation of radioactive discharges from NPP based on radionuclide specific monitoring

International Nuclear Information System (INIS)

Bucina, I.; Malatova, I.; Vidlakova, J.

1998-01-01

Monitoring of gaseous and liquid discharges from nuclear power plants based on particulate-iodine-gas measurements and gross beta or gamma plus tritium measurements is being improved by performing radionuclide specific measurements using semiconductor gamma and beta spectrometers and radiochemical methods. A new concept of regulatory effluent limits is being developed. The activities of all the relevant radionuclides discharged during a years, multiplied by the appropriate Sv/Bq conversion coefficient based on a standard multi-pathway model, are summed up, and the effective dose is compared with the new limit. Such limits should be laid down as the per capita collective commitment effective dose in the plant surroundings for atmospheric discharges, and as the committed effective dose to a critical group member for the hydrospheric releases

High resolution and simultaneous monitoring of airborne radionuclides

International Nuclear Information System (INIS)

Abe, T.; Yamaguchi, Y.; Muguntha Manikandan, N.; Komura, K.

2005-01-01

By using 11 extremely low background Ge detectors at Ogoya Underground Laboratory, it became possible to investigate temporal variations of airborne 212 Pb (T 1/2 =10.6 h) along with 210 Pb and 7 Be with order of magnitude higher time resolution. Then, we have measured airborne nuclides at three monitoring points, (1) roof of our laboratory (LLRL; 40 m ASL), (2) Shinshiku Plateau (640 m ASL) located about 8 km from LLRL as a comparison of vertical distribution, and (3) Hegura Island (10 m ASL) at about 50 km from Wajima located north of Noto Peninsula facing on the Sea of Japan (about 180 km to the north-northeast of LLRL), to investigate influence of Asian continent. Airborne nuclides were collected by high volume air samplers at intervals of a few hours at either two or three points simultaneously. In the same manner, high resolution monitoring was carried out also at the time of passage of typhoon and cold front. In this study, we observed drastic temporal variations of airborne radionuclides and correlations of multiple monitoring points. The results indicate that high resolution and simultaneous monitoring is very useful to understand dynamic state of variations of airborne nuclides due to short and long-term air-mass movement. (author)

Monitoring of radionuclides in the Baltic Sea in 1988

International Nuclear Information System (INIS)

Saxen, R.; Ikaeheimonen, T.K.; Ilus, E.

1989-12-01

Monitoring of radioactive substances in the Baltic Sea was continued within the framework of the Finnish national monitoring programme. Samples of sea water, bottom sediment and fish were collected for radionuclide analyses. All samples were analysed for gamma-emitting radionuclides and partly also for 90 Sr and transuranic elements. The activity concentrations of 137 Cs were about 120 Bq/m 3 in the surface water of the Bothnian Bay, 220-320 Bq/m 3 in the Bothnian Sea, 120-230 Bq/m 3 in the Gulf of Finland and 150-170 Bq/m 3 in the Baltic Proper. In the open Gulf of Finland and Bothnian Sea the 137 Cs concentrations of surface water were about 20 and 55 % of the maximum values in 1986. The total amounts of 137 Cs in bottom sediments ranged from 1700 to 16000 Bq/m 2 . In the Gulf of Bothnia and Gulf of Finland the total amounts of 137 Cs were about 5-6 times higher in 1988 than before the Chernobyl accident and 3 times higher in the northern Baltic Proper. The 137 Cs concentrations in Baltic herring ranged from 20 to 37 Bq/kg fresh weight and in pike from 38 to 160 Bq/kg fresh weight, the maximum values being in samples supplied from the Vaasa archipelago. The internal radiation dose to Finnish people caused by the consumption of Baltic Sea fish in 1988 was about 0.009mSv. (orig.)

Monitoring program for evaluating radionuclide emissions from incineration of low-level radioactive waste

International Nuclear Information System (INIS)

Wittmer, S.C.; Solomon, H.F.

1984-01-01

The implementation of an incineration program for low-level radioactive waste is a complex task, especially in the area of obtaining environmental permits. To provide assurance to the appropriate regulatory agencies involved with environmental permitting and others that an incineration program is properly conducted, emissions monitoring to identify radionuclides and their fate may be needed. An electronic spreadsheet software program Lotus 1-2-3 (Lotus Development Corporation) on an IBM Personal Computer has been used to perform data reduction for test results from such a monitoring program and to present them graphically to facilitate interpretation. The sampling technique includes: (1) the use of an EPA Method 5 stack sampling train modified to exclude the dry-catch filtration assembly with ethanolamine used to scrub incinerator gas at depressed temperatures and (2) a continuous composite liquid sampler for incinerator wet scrubber discharge to the sanitary sewer. Radionuclides in the samples are assayed using scintillation spectrometry

Radionuclides in foods

International Nuclear Information System (INIS)

1994-01-01

This report contains data on the levels of radionuclides in the UK foodchain. Most data derive from monitoring programmes that exist around nuclear sites, and in some cases date back to the 1960s. Some comparative data from site operator and government-run programmes are included. Data from monitoring undertaken after the Chernobyl accident are summarised. General monitoring of the foodchain for both artificial and natural radionuclides, and the results of relevant government-sponsored research are also described. The report includes basic information on radioactivity in the environment, radiation protection standards and describes what measures are taken to routinely monitor the foodchain and assess public risk. (Author)

Monitoring radionuclides in marine organisms

International Nuclear Information System (INIS)

Ishii, T.; Matsuba, M.; Kurosawa, M.; Koyanagi, T.

1990-01-01

Concentration of stable elements corresponding to important radionuclides was determined by inductively coupled plasma atomic emission spectrometry (ICP-AES) and inductively coupled plasma mass spectrometry (ICP-MS) for various marine organisms to find indicator organisms for environmental monitoring. Both analytical techniques indicated linearity over a range of concentrations covering 2-4 orders of magnitude. Detection limits of elements by ICP-MS were 10 or 100 times higher than those of ICP-AES, although the precision and accuracy of ICP-MS was slightly inferior to that of ICP-AES. For quantitative analysis of elements with medium mass numbers (chromium, manganese, iron, nickel, copper, zinc, etc.), matrix interferences in ICP-MS were caused mainly by overlaps of spectra from coexisting elements in biological samples. The presence of background ions from atmosphere, water, and argon plasma interfered with determination of some isotopes. Most elements of high mass number could not be determined by ICP-AES because of its poor detection limits, whereas ICP-MS indicated high sensitivity and low background for elements of interest. We used ICP-MS analysis to determine the specific accumulation of certain elements in organs or tissues of 30 marine organisms

Manual of bioassay procedures for radionuclides

International Nuclear Information System (INIS)

Pleskach, S.; Petkau, A.

1986-06-01

A monitoring program is described by which atomic radiation workers ar monitored for internal contamination with radionuclides in the workplace. The program involves analytical procedures for measuring alpha, beta and gamma activity in biological specimens, usually urine. Radionuclides are identified by their characteristic radiation using liquid scintillation counting, and alpha, beta and gamma spectrometry. Examples of calculating the minimum detectable activity for specific radionuclides are given and used to derive call-in-criteria in accordance with which the different groups of workers are monitored each month

Limitation of radioactive discharges from NPP based on radionuclide specific monitoring

Energy Technology Data Exchange (ETDEWEB)

Bucina, I; Malatova, I; Vidlakova, J [National Radaition Protection Institute, Prague (Czech Republic)

1996-12-31

Monitoring of nuclear power plants (NPP) discharges into atmosphere and hydrosphere based on particulate-iodine-gas (PIG) measurements and gross beta and gamma plus tritium measurements respectively is being improved by nuclide specific measurements employing semiconductor gamma and alpha spectrometry and radiochemical methods. In connection with the progress new concept of authorized effluent limits and the related regulations is being implemented in the Czech Republic. Activities of all principally contributing to the effective dose radionuclides discharges during a year multiplied by a Sv/Bq conversion coefficient based on a standard model are summed up and the effective dose is compared with the new limit. These limits should be authorized for discharges into atmosphere as per caput collective committed effective dose in the NPP surrounding or as its value multiplied by the number of surrounding segment providing thus committed effective dose to member of a vital critical group and into the hydrosphere as committed effective dose to the critical group member. The criteria for obligatory evaluation of the specific radionuclide contribution and the resulting requirements on minimum detectable activities for both the shorter and longer monitoring intervals are included in the new regulations. The PIG and gross activity measurement results will be compared with investigation levels only and no more used for limitation purposes. (authors).

Monitoring of Radionuclide Contamination in Food Samples in Malaysia due to Daiichi Reactor Accident in Fukushima, Japan

International Nuclear Information System (INIS)

Nurrul Assyikeen Mohd Jaffary; Wo, Y.M.; Abdul Kadir Ishak

2015-01-01

On March 11, 2011, a serious accident occurred in Daiichi nuclear reactor plant, Fukushima, Japan which caused radioactive materials been released into the atmosphere in the form of aerosols and dust particles. Sea water around the plant was also found contaminated with high radioactivity readings. These radioactive materials could be transported by the winds and ocean current across international borders and cannot be controlled by human. Thus, a continuous monitoring activity of radionuclide content in the air and sea water needs to be conducted by the authorities. In addition to radioactivity monitoring, Malaysia should also control the entry of contaminated food in order to prevent radionuclide ingestion by human. The radionuclide 131 I, 134 Cs and 137 Cs were used as a measure of pollution levels and counted with gamma spectrometry using standard analysis method suggested by AOAC International. In this paper, details description of the role of Radiochemical and Environment Group, Nuclear Malaysia who is responsible in analyzing the radioactivity in the food samples due to Fukushima Daiichi, Japan accident was included. The radioactivity limit adopted and analysis results from this monitoring were discussed. (author)

Analysis of infrequent hydrologic events with regard to existing streamflow monitoring capabilities in White Oak Creek watershed

International Nuclear Information System (INIS)

Edgar, D.E.

1978-10-01

The quantity and concentration of radionuclides released to the environment by ORNL must be monitored continuously and accurately in order to ensure compliance with legal requirements established by Federal and state guidelines. Of the five streamflow monitoring stations located within White Oak Creek watershed, stations 3, 4, and 5 are of primary importance in quantifying the flux of water, sediment, and radionuclides through the drainage basin. Currently, the maximum measurable discharge at these three stations is 1.42 m 3 /sec (50 cfs), 0.54 m 3 /sec (19 cfs), and 4.25 m 3 /sec (150 cfs), respectively. Estimates of flood magnitude and frequency indicate that even small floods which are expected to recur often are significantly larger than the existing monitoring system can measure. Several independent studies have shown that most of the sediment transported from a watershed is carried by larger, less frequent streamflows which occur only a small percentage of the time. It also has been shown that certain radionuclides are transported in association with fluvial sediment. Thus, the flux of radionuclides, both in solution and associated with sediment, increases significantly during flood conditions. Estimates of peak discharges resulting from recent storms indicate that the drainage system has experienced variable flood conditions during the past few years for which no accurate and reliable records exist

Status of radionuclide monitoring stations in Australia

International Nuclear Information System (INIS)

Burns, P.A.

2001-01-01

The Australian Radiation Protection and Nuclear Safety Agency (ANSTO) first became involved in the monitoring of radionuclides in the environment in 1955 when assessing the effects on the Australian population of the radioactive releases associated with the atmospheric testing of nuclear weapons. (At that time ARPANSA was known as the Commonwealth X-ray and Radium Laboratory). The United Kingdom had tested weapons in Australia in 1952 and 1953 and in August 1954 entered into an agreement with the Australian Government to establish a test range at Maralinga in South Australia. The government established a Maralinga Safety Committee and through this Committee ARPANSA became involved in the surveillance of radioactive fallout over Australia. The primary function of this surveillance was to ensure that the nuclear trials would not adversely effect the health of the Australian population. A program was established to reliably assess the deposition of radioactive fallout over Australia so that exposure to the population could be estimated. This task was performed in conjunction with the Bureau of Meteorology and the Department of Supply. Measurements were made on daily samples of fallout dawn from 10 centres throughout Australia. A low level radiochemical facility was established in 1961 for the measurement of 90 Sr and 137 Cs in environmental samples so that the long term distribution of fallout could be tracked. In the 1960s the program was extended to measure fresh fission products reaching Australia from atmospheric testing in other countries, usually originating from test sites in the northern hemisphere. The sampling program that was established was designed so that it could be rapidly expanded when a new testing program started. At this time a permanent fallout monitoring network was established around Australia using high volume air samplers capable of sampling up to 10000 m 3 per week. Approximately six stations have been operated at any one time but the

Sensors and Automated Analyzers for Radionuclides

International Nuclear Information System (INIS)

Grate, Jay W.; Egorov, Oleg B.

2003-01-01

The production of nuclear weapons materials has generated large quantities of nuclear waste and significant environmental contamination. We have developed new, rapid, automated methods for determination of radionuclides using sequential injection methodologies to automate extraction chromatographic separations, with on-line flow-through scintillation counting for real time detection. This work has progressed in two main areas: radionuclide sensors for water monitoring and automated radiochemical analyzers for monitoring nuclear waste processing operations. Radionuclide sensors have been developed that collect and concentrate radionuclides in preconcentrating minicolumns with dual functionality: chemical selectivity for radionuclide capture and scintillation for signal output. These sensors can detect pertechnetate to below regulatory levels and have been engineered into a prototype for field testing. A fully automated process monitor has been developed for total technetium in nuclear waste streams. This instrument performs sample acidification, speciation adjustment, separation and detection in fifteen minutes or less

Soil and river sediments radionuclides monitoring at Aramar Experimental Center: an historical overview

International Nuclear Information System (INIS)

Segre, Nadia; Fagundes, Rosane Correa

2013-01-01

In order to evaluate possible effects to the environment resulting from the implementation of the Centro Tecnologico da Marinha - Centro Experimental Aramar (CTMSP-CEA) at Ipero in Sao Paulo state, Brazil, which came into operation in 1989, an Environmental Monitoring Program (PMA) was established in October, 1987. One of the aims of this program is to monitor the soil and river sediments radionuclides levels at CEA and beyond its boundary. The utilization of statistical tools to evaluate the results of radiometric environmental monitoring is a procedure required by National Nuclear Energy Commission (CNEN). The box plot is a simple statistical tool for displaying data. The central tendency and dispersion of the results as well as the observation of unusual results (outliers) in the dataset are easily visualized. Control chart is a graph that maps data and provides a picture of how a process is performing over time. A control chart always has a central line for the mean, an upper line for the upper control limit and a lower line for the lower control limit. Box plots and control charts were used to visualize the annual amount of natural uranium, lead-214, actinium-228 and lead-212 in soil and river sediment detected between 1987 and 2011, considering the measurements of all monitored places each year. This historical observation shows that, in average, the results obtained are below than the 1987-1988 levels (CEA's pre-operational) or below than the backgrounds radionuclides values. (author)

Soil and river sediments radionuclides monitoring at Aramar Experimental Center: an historical overview

Energy Technology Data Exchange (ETDEWEB)

Segre, Nadia; Fagundes, Rosane Correa, E-mail: nadia.segre@ctmsp.mar.mil.br [Centro Tecnologico da Marinha (CTM-SP/CEA/LARE), Ipero, SP (Brazil). Centro Experimental Aramar. Lab. Radioecologico; Moraes, Marco Antonio P.V. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2013-07-01

In order to evaluate possible effects to the environment resulting from the implementation of the Centro Tecnologico da Marinha - Centro Experimental Aramar (CTMSP-CEA) at Ipero in Sao Paulo state, Brazil, which came into operation in 1989, an Environmental Monitoring Program (PMA) was established in October, 1987. One of the aims of this program is to monitor the soil and river sediments radionuclides levels at CEA and beyond its boundary. The utilization of statistical tools to evaluate the results of radiometric environmental monitoring is a procedure required by National Nuclear Energy Commission (CNEN). The box plot is a simple statistical tool for displaying data. The central tendency and dispersion of the results as well as the observation of unusual results (outliers) in the dataset are easily visualized. Control chart is a graph that maps data and provides a picture of how a process is performing over time. A control chart always has a central line for the mean, an upper line for the upper control limit and a lower line for the lower control limit. Box plots and control charts were used to visualize the annual amount of natural uranium, lead-214, actinium-228 and lead-212 in soil and river sediment detected between 1987 and 2011, considering the measurements of all monitored places each year. This historical observation shows that, in average, the results obtained are below than the 1987-1988 levels (CEA's pre-operational) or below than the backgrounds radionuclides values. (author)

Environmental monitoring for radionuclides, chemicals, fish and wildlife at a US energy research facility: A case story

International Nuclear Information System (INIS)

Gray, R.H.

1989-09-01

Environmental monitoring has been an ongoing activity on the US Department of Energy's 560 m 2 Hanford Site in southeastern Washington, USA, for 45 years. Objectives are to detect and assess potential impacts of site operations on air, surface and ground water, foodstuffs, fish, wildlife, soils and vegetation. Data from monitoring efforts are used to calculate the overall radiological dose to humans working onsite or residing in nearby communities. In 1988, measured Hanford Site perimeter concentrations of airborne radionuclides were below applicable guidelines. Tritium and nitrate continued to be the most widespread constituents in onsite ground water. Concentrations of radionuclides and nonradiological water quality in the Columbia River were in compliance with applicable standards. Foodstuffs irrigated with river water downstream of the Site showed low levels of radionuclides that were similar to concentrations found in foodstuffs from control areas. Low levels of 90 Sr and 137 Cs in some onsite wildlife samples and concentrations of radionuclides in soils and vegetation from onsite and offsite locations were typical of those attributable to worldwide fallout. The calculated dose potentially received by a maximally exposed individual (i.e., based on hypothetical assumptions for all routes of exposure) in 1988 (0.08 mrem/yr) was similar to that calculated for 1985 through 1987. 31 refs., 3 figs

Monitoring of streams: macrozoobenthos and accumulation of heavy metals and radionuclides in bottom sediments

International Nuclear Information System (INIS)

Arbaciauskas, K.; Mackeviciene, G.; Striupkuviene, N.; Motiejunas, S; Kreslauskaite, R.

1998-01-01

To evaluate the environmental quality of streams in integrated monitoring sites (IMS) and agrostations (AS), the macrozoobenthos communities and accumulation of heavy metals and radionuclides in bottom sediments were studied during 1993-1996. Samples of macrozoobenthos were collected in stream biotopes which were recommended for monitoring. Community biodiversity was assessed by Shannon-Wiener and Simpson indices, and water quality of streams was estimated by Trent and Mean Chandler biotic indices. Heavy metal (Pb, Cd, Cu, Cr, Ni, Mn) concentrations and radionuclide ( 137 Cs, 134 Cs, 40 K, 90 Sr) activity were determined in sediments. Macrozoobenthos communities indicated that the studied streams were clean waters. The heavy metal concentrations in surficial sediments showed annual and seasonal changes and differences between monitoring sites. The Cu concentration in the soft turfy stream sediments at the Aukstaitija IMS was twice as high as that in sediments of other monitoring streams with hard sandy-gravel bottoms. During 1994-1996, the Ni concentration decreased, while levels of Cu, Cd and Cr were relatively stable. The Pb concentrations decreased in all IMS, while those in AS increased. The concentration of 137 Cs was relatively stable in agrostation streams. Compared to levels in 1993, an increase of 137 Cs activity was observed in sediments at the Dzuklija IMS during 1995-1996. 90 Sr activity fluctuated in the monitoring sites from 1.6 to 3.7 Bq/kg dry weight. (author)

Evaluation of strategies for monitoring and sampling airborne radionuclides in the workplace

International Nuclear Information System (INIS)

Boecker, B.B.; Hoover, M.D.; Newton, G.J.; Guilmette, R.A.; Scott, B.R.

1994-01-01

Protection of workers from intakes of airborne radioactive materials is receiving increased attention as part of the overall emphasis on minimisation of occupational radiation exposures. Because current guidance of the International Commission on Radiological Protection on protection from airborne radionuclides is based on annual limits on intake, ALI, and average annual air concentrations derived from these ALIs, increased effort is being devoted to monitoring exposure levels, directly or indirectly, in the workplace. Possible approaches include the use of fixed air samplers, continuous air monitors, and personal air samplers worn by individual workers. Periodic bioassay of these workers of whole-body counting, chest counting, or excreta analyses can provide useful information on the adequacy with which the above approaches are monitoring the workplace. Because each approach requires a major commitment of institutional resources, it is important that the overall monitoring plan reflect the relative value of these different approaches for the facility and processes being monitored. (Author)

40 CFR 141.26 - Monitoring frequency and compliance requirements for radionuclides in community water systems.

Science.gov (United States)

2010-07-01

... identified in the finished water. (iii) Annual monitoring for strontium-90 and tritium shall be conducted by... requirements for radionuclides in community water systems. 141.26 Section 141.26 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) NATIONAL PRIMARY DRINKING WATER...

Monitoring of Radionuclide Contamination in Food Samples in Malaysia due to Daiichi Reactor Accident in Fukushima, Japan

International Nuclear Information System (INIS)

Nurrul Assyikeen Mohd Jaffary; Abdul Kadir Ishak; Wo, Y.M.

2011-01-01

On March 11, 2011, a serious accident occurred in Daiichi nuclear reactor plant, Fukushima, Japan which caused radioactive materials been released into the atmosphere in the form of aerosols and dust particles. Sea water around the plant was also found contaminated with high radioactivity readings. These radioactive materials could be transported by the winds and ocean current across international borders and cannot be controlled by human. Besides a continuous monitoring activity of radionuclide content in the air and sea water that need to be conducted by the authorities, Malaysia should also control the entry of radionuclide through contaminated food ingestion by human. Radionuclide I-131, Cs-134 and Cs-137 were used as a counter-measure of pollution levels and counted with gamma spectrometry using standard analysis method suggested by AOAC International. In this paper, details description of the role of Radiochemical and Environment Group, Nuclear Malaysia who's responsible in analyzing the radioactivity in the food samples due to Fukushima Daiichi, Japan accident was included. Also discussed are the radioactivity limit adopted and analysis results from this monitoring. (author)

Monitoring intervals for the measurement of the radionuclides 125I and 129I in the thyroid gland

International Nuclear Information System (INIS)

Yera Simanca, Yoan; Lopez Bejerano, Gladys M.; Ramos Machado, Dayana; Acosta Rodriguez; Nancy

2014-01-01

This paper shows the monitoring intervals that can be implemented in the Internal Contamination Laboratory of the Center for Radiation Protection and Hygiene for direct measurement of the radionuclides 125 I and 129 I in the Thyroid gland. Two measuring systems were used, one of them uses a scintillation detector and the other one uses a Phoswich detector. Both detectors were situated inside of one shielding chamber of 2.5 x 2.5 x 2.5 m of dimension, cover with 15 cm of steel, 3 mm of lead, 1.8 mm of tin, and 1.5 mm of copper. For each system was calculated the minimum detectable activity and in function of it were determined the monitoring intervals. The results obtained showed that for the radionuclide 125 I all the evaluated intervals (120, 90, 60, 30, 14 and 7 days).can be implemented with both systems. For the case of the radionuclide 129 I it can only be implemented the intervals (120, 90, and 60 days) using the scintillation detector and all of them with the Phoswich detector. (author)

Monitoring Programme of Radionuclide Migration Through Food Chains at Low and Intermediate Level Radioactive Waste Repository in Trgoska Gora Mountain

International Nuclear Information System (INIS)

Schaller, A.; Lokner, V.; Kucar Dragicevic, S.; Subasic, D.; Barisic, D.

2001-01-01

Full text: Basic objective of the paper is to prepare a comprehensive programme of monitoring at the preferred site for low and intermediate level radioactive waste repository in the region of Trgovska Gora mountain. The programme is based on available information regarding hydrogeology, lithostratigraphy, tectonics, seismotectonics, geomorphology, meteorology, bioecology, demography and other site relevant disciplines. It is supposed to ensure (1) identification of the zero state at the broader region of the Trgovska gora mountain, and (2) to underline activities needed for monitoring of concentrations of expected radionuclides throughout possible pathways (particularly through food chains) that would migrate to the biosphere in the period after start of radioactive waste repository operation. Inventory of radionuclides contained in the radioactive waste to be disposed of at the site is naturally an important element of the programme structure. There should be identified those radionuclides which concentrations require to be monitored. Concentration measuring methods are proposed in the article. In addition, relevant aquatic and terrestrial organisms, serving as bioindicators, are identified. Types, quantities, frequency and methodology of sampling present an important part of the monitoring programme. Determination of monitoring sites for undertaking particular types of sampling (e.g. stream waters, stream sediment, detritus, ichtiofauna, groundwater, terrestrial organisms, honey, etc.), presenting an important aspect of a well-organised monitoring programme, is also included into this presentation. (author)

Field test facility for monitoring water/radionuclide transport through partially saturated geologic media: design, construction, and preliminary description

International Nuclear Information System (INIS)

Phillips, S.J.; Campbell, A.C.; Campbell, M.D.; Gee, G.W.; Hoober, H.H.; Schwarzmiller, K.O.

1979-11-01

Shallow land burial has been a common practice for disposing radioactive waste materials since the beginning of plutonium production operations. Accurate monitoring of radionuclide transport and factors causing transport within the burial sites is essential to minimizing risks associated with disposal. However, monitoring has not always been adequate. Consequently, the Department of Energy (DOE) has begun a program aimed at better assuring and evaluating containment of radioactive wastes at shallow land burial sites. This program includes a technological base for monitoring transport. As part of the DOE program, Pacific Northwest Laboratory (PNL) is developing geohydrologic monitoring systems to evaluate burial sites located in arid regions. For this project, a field test facility was designed and constructed to assess monitoring systems for near-surface disposal of radioactive waste and to provide information for evaluating site containment performance. The facility is an integrated network of monitoring devices and data collection instruments. This facility is used to measure water and radionuclide migration under field conditions typical of arid regions. Monitoring systems were developed to allow for measurement of both mass and energy balance. Work on the facility is ongoing. Continuing work includes emplacement of prototype monitoring instruments, data collection, and data synthesis. At least 2 years of field data are needed to fully evaluate monitoring information

Radiation monitoring for radionuclide release in water system resulted from nuclear power plant operation

International Nuclear Information System (INIS)

Vintsukevich, N.V.; Tomilin, Yu.A.

1983-01-01

Pre-operational investigation into environmental radioactivity in the vicinity of Yuzhno-Ukrainskaya NPP with reverse- direct flow cooling scheme of circulating water was conducted. Considering that reservoir-coolant of NPP will be connected constantly with water reservoirs located on the Yuzhnyj Bug river possibilities of radionuclide accumulation in different river components - 5ilt, algae, river water-were investigated. It was established that increase of pH and salt concentration in water of river undercurrent create the conditions for formation of radionuclide sedimentary forms, increase their accumulation in bottom sediments and aqquatic vegetation. The conclusion on the necessity of constant radiation monitoring for relase of liquid coastes of Yuzhno-Ukrainskaya NPP in the Yuzhnyj Bug river is drawn

Radionuclide monitoring in foodstuff: overview of the current implementation in the EU countries

International Nuclear Information System (INIS)

Borbala Mate; Katarzyna Sobiech-Matura; Timotheos Altzitzoglou

2015-01-01

The Member States (MS) of the European Union (EU) are obliged to monitor the radioactivity in the environment since the signature of the Euratom Treaty (Treaty establishing the European Atomic Energy Community). Numerous secondary legislations derived from the Treaty can be found stating restrictions and maximum permitted levels of radionuclides in foodstuff. But to that purpose, no common integrated measurement methods are used with well-defined measurands. The present work consists of two parts. First, the current European regulations in force were collected, and then the food monitoring results, provided by the MS, were analysed. (author)

Monitoring intervals for measurement of the radionuclides 125 I and 129I in thyroid glands

International Nuclear Information System (INIS)

Simanca, Yoan Yera; Bejerano, Gladys M. Lopez

2013-01-01

This work shows the monitoring interval, which can be implemented in the Laboratorio de Contaminacion Interna del Centro de Proteccion e Higiene de las Radiaciones, for direct measurement in the thyroid gland of radionuclides 125 I and 129 I . Were used two measuring systems, one employing a scintillating detector and the other detector Phoswich. Both detectors were placed inside a depth camera, 2.5 x 2.5 x 2.5m of dimension covered with 15 cm of steel, 3 mm lead, 1.8 mm tin and 1.5 mm of copper. Was calculated for each system, the minimum detectable activity, and based on this, the monitoring interval is determined. Was obtained, for 125 , all tested intervals, 120, 90,60,30 , 14, and 7 days may be implemented with both systems. In the case of the radionuclide 129 I, with the installation of scintillating detector can only be implemented the intervals 120, 90, and 60 days , and for installation with Phoswich, all evaluated

Radionuclide Sensors for Environmental Monitoring: From Flow Injection Solid-Phase Absorptiometry to Equilibration-Based Preconcentrating Minicolumn Sensors with Radiometric Detection

International Nuclear Information System (INIS)

Grate, Jay W.; Egorov, Oleg B.; O'Hara, Matthew J.; Devol, Timothy A.

2008-01-01

The development of in situ sensors for ultratrace detection applications in process control and environmental monitoring remains a significant challenge. Such sensors must meet difficult detection limit requirements while selectively detecting the analyte of interest in complex or otherwise challenging sample matrixes. Nowhere are these requirements more daunting than in the field of radionuclide sensing. The detection limit requirements can be extremely low. Nevertheless, a promising approach to radionuclide sensing based on preconcentrating minicolumn sensors has been developed. In addition, a method of operating such sensors, which we call equilibration-based sensing, has been developed that provides substantial preconcentration and a signal that is proportional to analyte concentration, while eliminating the need for reagents to regenerate the sorbent medium following each measurement. While this equilibration-based sensing method was developed for radionuclide sensing, it can be applied to nonradioactive species as well, given a suitable on-column detection system. By replacing costly sampling and laboratory analysis procedures, in situ sensors could have a significant impact on monitoring and long term stewardship applications. The aim of this review is to cover radionuclide sensors that combine some form of selective sorption with a radiometric detection method, and, as a primary aim, to comprehensively review preconcentrating minicolumn sensors for radionuclide detection. As a secondary aim, we will cover radionuclide sensors that combine sorption and scintillation in formats other than minicolumn sensors. We are particularly concerned with the detection of alpha- and beta-emitting radionuclides, which present particular challenges for measurements in liquid media

Biomedical research and application utilizing cyclotron produced radionuclides. Progress report, January 1 1977--December 31, 1977

International Nuclear Information System (INIS)

Laughlin, J.S.; Benua, R.S.; Tilbury, R.S.

1977-01-01

Progress is reported on cyclotron production of short-lived positron-emitting radionuclides ( 18 F, 15 O, 11 C, 13 N, 52 Fe, 38 K, 206 Bi, 73 Se, and 48 Cr) for use in the preparation labelled compounds for metabolic research in patients and animals. The chemical preparation of radiopharmaceuticals labelled with cyclotron-produced radionuclides for pancreas and tumor scanning is discussed. The imaging capabilities of a total organ kinetic imaging monitor (TOKIM) gamma camera system operated in the positron coincidence mode were improved with the addition of computerized iterative correction procedures

Monitoring of radionuclides in the Baltic Sea in 1989-1990

International Nuclear Information System (INIS)

Ilus, E.; Sjoeblom, K.L.; Ikaeheimonen, T.; Saxen, R.; Klemola, S.

1993-02-01

Monitoring of radioactive substances in the Baltic Sea continued within the framework of the Finnish national monitoring programme. Samples of sea water, bottom sediment and fish were collected for radionuclide analyses. All samples were analysed for gamma-emitting radionuclides and some also for 90 Sr and transuranic elements. The general levelling of Chernobyl derived 137 Cs and 134 Cs in the water mass of the Baltic Sea, which had started soon after the fallout situation, continued in 1989. The activity concentration of 137 Cs was about the same level (120-160 Bq/m 3 ) in surface water throughout the Baltic Sea area except in some coastal areas. The cesium concentrations had levelled vertically as well as horizontally. In 1990, the cesium concentrations of surface water decreased further in other sea areas, but not in the Bothnian Sea, where somewhat higher values were detected once more. In bottom sediments the total amounts of 137 Cs had clearly increased between 1988 and 1990 which indicates that fresh fallout was still settling on the bottom. No increase was found in the total amounts of 239 , 240 Pu. Small amounts of 60 Co were detected in the surface sediment of our sampling station in the Northern Baltic proper. 137 Cs concentrations in Baltic herring ranged from 17 to 32 Bq/kg fresh weight and pike from 22 to 290 Bq/kg fresh weight, the maximum values being in the samples supplied from the Vaasa archipelago. The internal radiation dose received by Finns from eating Baltic Sea fish was 0.01mSv both in 1989 and in 1990. (orig.)

Test plan for demonstration of Rapid Transuranic Monitoring Laboratory

International Nuclear Information System (INIS)

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.

1993-06-01

This plan describes tests to demonstrate the capability of the Rapid Transuranic Monitoring Laboratory (RTML) to monitor airborne alpha-emitting radionuclides and analyze soil, smear, and filter samples for alpha- and gamma-emitting radionuclides under field conditions. The RTML will be tested during June 1993 at a site adjacent to the Cold Test Pit at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. Measurement systems installed in the RTML that will be demonstrated include two large-area ionization chamber alpha spectrometers, an x-ray/gamma-ray spectrometer, and four alpha continuous air monitors. Test objectives, requirements for data quality, experimental apparatus and procedures, and safety and logistics issues are described

Predictive capabilities of a two-dimensional model in the ground water transport of radionuclides

International Nuclear Information System (INIS)

Gureghian, A.B.; Beskid, N.J.; Marmer, G.J.

1978-01-01

The discharge of low-level radioactive waste into tailings ponds is a potential source of ground water contamination. The estimation of the radiological hazards related to the ground water transport of radionuclides from tailings retention systems depends on reasonably accurate estimates of the movement of both water and solute. A two-dimensional mathematical model having predictive capability for ground water flow and solute transport has been developed. The flow equation has been solved under steady-state conditions and the mass transport equation under transient conditions. The simultaneous solution of both equations is achieved through the finite element technique using isoparametric elements, based on the Galerkin formulation. However, in contrast to the flow equation solution, the weighting functions used in the solution of the mass transport equation have a non-symmetric form. The predictive capability of the model is demonstrated using an idealized case based on analyses of field data obtained from the sites of operating uranium mills. The pH of the solution, which regulates the variation of the distribution coefficient (K/sub d/) in a particular site, appears to be the most important factor in the assessment of the rate of migration of the elements considered herein

Vadose zone monitoring plan using geophysical nuclear logging for radionuclides discharged to Hanford liquid waste disposal facilities

International Nuclear Information System (INIS)

Price, R.K.

1995-11-01

During plutonium production at Hanford, large quantities of hazardous and radioactive liquid effluent waste have been discharged to the subsurface (vadose zone). These discharges at over 330 liquid effluent disposal facilities (ie. cribs, ditches, and ponds) account for over 3,000,000 curies of radioactive waste released into the subsurface. It is estimated that 10% of the contaminants have reached the groundwater in many places. Continuing migration may further impact groundwater quality in the future. Through the RCRA Operational Monitoring Program, a Radionuclide Logging System (RLS) has been obtained by Hanford Technical Services (HTS) and enhanced to measure the distribution of contaminants and monitor radionuclide movement in existing groundwater and vadose zone boreholes. Approximately 100 wells are logged by HTS each year in this program. In some cases, movement has been observed years after discharges were terminated. A similar program is in place to monitor the vadose zone at the Tank Farms. This monitoring plan describes Hanford Programs for monitoring the movement of radioactive contamination in the vadose zone. Program background, drivers, and strategy are presented. The objective of this program is to ensure that DOE-RL is aware of any migration of contaminants in the vadose zone, such that groundwater can be protected and early actions can be taken as needed

Longtime radionuclide monitoring in the vicinity of Salaspils nuclear reactor; Dauerhaftes Monitoring der Radionuklide in Umgebung von Salaspils Kernreaktor

Energy Technology Data Exchange (ETDEWEB)

Riekstina, D.; Berzins, J.; Krasta, T. [Latvia Univ. (Latvia). Inst. of Solid State Physics; Skrypnik, O.; Alksnis, J. [Latvia Univ. (Latvia). Inst. of Chemical Physics

2016-07-01

The research nuclear reactor in Salaspils was decommissioned in 1998. Now reactor is partially dismantled and its territory is used as a temporary storage of radioactivity contaminated materials and water. Environment radioactivity monitoring for presence of artificial radionuclides in the vicinity of Salaspils nuclear reactor is carried out since 1990. Data include Cs-137 concentration in soils, tritium concentration in ground water, as well as H-3, Cs-137, Co-60 concentration and gross beta-activity of reactors sewage and rainwater drainage. The systematic monitoring allowed to detect in December 2014 a leakage from the special wastewater basin and so to prevent a pollution of ground water outside reactors territory.

Radionuclides in food

International Nuclear Information System (INIS)

Fernandez Gomez, Isis Maria

2008-01-01

The sources of the presence of radionuclides in food are presented: natural radiation and artificial radiation. The transfer of radionuclides through food chains, intakes of radionuclides to the body with its partners effective doses and typical consumption of basic foods of a rural adult population are exposed as main topics. Also the radiation doses from natural sources and exposure to man by ingestion of contaminated food with radionuclides of artificial origin are shown. The contribution of the food ingestion to the man exposure depends on: characteristics of radionuclide, natural conditions, farming practices and eating habits of the population. The principal international organizations in charge of setting guide levels for radionuclides in food are mentioned: standards, rules and the monitoring. It establishes that a guide is necessary for the food monitoring; the alone CODEX ALIMENTARIUS is applicable to emergency situations and the generic action levels proposed by the CODEX not satisfy all needs (no guiding international levels for planned or existing situations such as NORM). There are handled mainly socio-economic and political aspects. Among the actions to be taken are: to assure a public comprehensive information over the risk evaluation in food; to reinforce the collaboration among the different international organizations (WHO, IAEA, ICRP, EC) in relation with the food of set; to give follow-up to the control of the drinkable water and NORM's presence in the food. In addition, it is possible to create the necessary mechanisms to reduce the number of irrelevant measures and bureaucratic useless steps (certificates); to promote the exchange between the different institutions involved in the topic of the food, with relation to the acquired experiences and learned lessons. Likewise, it might examine the possibility of a multidisciplinary approximation (radioactive and not radioactive pollutants); to elaborate a technical guide to assure the

Monitoring of the radionuclides in the air of the Czech Republic

International Nuclear Information System (INIS)

Rulik, Petr; Skrkal, Jan; Hoelgye, Zoltan; Schlesingerova, Eva; Michalek, Vaclav; Mala, Helena; Beckova, Vera; Svetlik, Ivo

2008-01-01

The Radiation Monitoring Network (RMN) of the Czech Republic consists of several subnetworks among them of a subnetwork of 10 Monitoring Sintes of Air Contamination equipped with aerosol samplers with throughput up to 900 m 3 /h and a subnetwork of 4 laboratories, which analyse the samples. The aerosol samplers work continuously usually with one-week sampling periods in normal situation. Activities in all aerosol samples are measured by semiconductor gamma-spectrometry to determine man-made 137 Cs and natural 7 Be, 22 Na, 210 Pb and 40 K. The natural radionuclides are evaluated mainly in order tu QA/AC of individual laboratories. After the gamma spectrometric analysis the radiochemical separation followed by alpha spectrometry or beta measurement is used for determination or 90 Sr, 238 Pu and 239,240 Pu in the quarterly combined filters from the monitoring site in Prague. Continuous collection of the air for the determination activity concentrations of 85 Kr and 14 C and collection of the precipitation for assessment of activity concentrations of 3 H in monthly samples is performed in monitoring site of Prague, too. Results of long-time observation of radionuclides together with statistical analysis of the data are given in the paper. At present the values of 137 Cs activity concentrations range approximately form tenths to units of μBq/m 3 . The activity concentrations of 7 Be show typical seasonal variations with the mean value about 3000 μBq/m 3 . The mean value of 210 Pb activity concentration is about 500 μBq/m 3 and 22 Na 0.3 μBq/m 3 . The activities of 239,240 Pu are on the level of nBq/m 3 , of 238 Pu on the level of tenths of nBq/m 3 but often under the detection limit (MDA=0.3 nBq/m 3 ). The activities of 90 Sr are on the level of 0.1μBq/m 3 . The activity concentrations of 85 Kr have been in the range form 1 to 2 Bq/m3 in the last 10 years and activity concentrations of 3 H in precipitation about 2 Bq/litre. (author)

Building of effluence and environment monitoring capability of uranium mining and metallurgy in China

International Nuclear Information System (INIS)

Li Xianjie; Hu Penghua; Duan Jianchen; Xue Jianxin

2014-01-01

The status of effluence and environmental monitoring capability of nine uranium mining and metallurgy corporations in operation in China was investigated and analyzed. The results show that there exist some problems in all corporations such as imperfect monitoring plan, ineligible analyst, aging equipment, insufficient analysis capacity, lack of good detection limit. In order to solve the problems, several steps have been taken by Department of Safety and Environment Protection and Department of Geology and Mining (CNNC) in three years, including establishing three-level monitoring sys- tem, equipping corresponding monitoring instrument, holding three training classes, enhancing the analyst capacity, publishing the model for effluence and environment monitoring capability of uranium mining and metallurgy and carrying out comparison on monitoring of U and Ra in water, which greatly improved effluence and environment monitoring capability of uranium mining and metallurgy. (authors)

Final Technical Report: Development of Post-Installation Monitoring Capabilities

Energy Technology Data Exchange (ETDEWEB)

Polagye, Brian [University of Washington

2014-03-31

The development of approaches to harness marine and hydrokinetic energy at large-scale is predicated on the compatibility of these generation technologies with the marine environment. At present, aspects of this compatibility are uncertain. Demonstration projects provide an opportunity to address these uncertainties in a way that moves the entire industry forward. However, the monitoring capabilities to realize these advances are often under-developed in comparison to the marine and hydrokinetic energy technologies being studied. Public Utility District No. 1 of Snohomish County has proposed to deploy two 6-meter diameter tidal turbines manufactured by OpenHydro in northern Admiralty Inlet, Puget Sound, Washington. The goal of this deployment is to provide information about the environmental, technical, and economic performance of such turbines that can advance the development of larger-scale tidal energy projects, both in the United States and internationally. The objective of this particular project was to develop environmental monitoring plans in collaboration with resource agencies, while simultaneously advancing the capabilities of monitoring technologies to the point that they could be realistically implemented as part of these plans. In this, the District was joined by researchers at the Northwest National Marine Renewable Energy Center at the University of Washington, Sea Mammal Research Unit, LLC, H.T. Harvey & Associates, and Pacific Northwest National Laboratory. Over a two year period, the project team successfully developed four environmental monitoring and mitigation plans that were adopted as a condition of the operating license for the demonstration project that issued by the Federal Energy Regulatory Commission in March 2014. These plans address nearturbine interactions with marine animals, the sound produced by the turbines, marine mammal behavioral changes associated with the turbines, and changes to benthic habitat associated with colonization

Mass spectrometry of long-lived radionuclides

International Nuclear Information System (INIS)

Becker, Johanna Sabine.

2003-01-01

The capability of determining element concentrations at the trace and ultratrace level and isotope ratios is a main feature of inorganic mass spectrometry. The precise and accurate determination of isotope ratios of long-lived natural and artificial radionuclides is required, e.g. for their environmental monitoring and health control, for studying radionuclide migration, for age dating, for determining isotope ratios of radiogenic elements in the nuclear industry, for quality assurance and determination of the burn-up of fuel material in a nuclear power plant, for reprocessing plants, nuclear material accounting and radioactive waste control. Inorganic mass spectrometry, especially inductively coupled plasma mass spectrometry (ICP-MS) as the most important inorganic mass spectrometric technique today, possesses excellent sensitivity, precision and good accuracy for isotope ratio measurements and practically no restriction with respect to the ionization potential of the element investigated--therefore, thermal ionization mass spectrometry (TIMS), which has been used as the dominant analytical technique for precise isotope ratio measurements of long-lived radionuclides for many decades, is being replaced increasingly by ICP-MS. In the last few years instrumental progress in improving figures of merit for the determination of isotope ratio measurements of long-lived radionuclides in ICP-MS has been achieved by the application of a multiple ion collector device (MC-ICP-MS) and the introduction of the collision cell interface in order to dissociate disturbing argon-based molecular ions, to reduce the kinetic energy of ions and neutralize the disturbing noble gas ions (e.g. of 129 Xe + for the determination of 129 I). The review describes the state of the art and the progress of different inorganic mass spectrometric techniques such as ICP-MS, laser ablation ICP-MS vs. TIMS, glow discharge mass spectrometry, secondary ion mass spectrometry, resonance ionization mass

Monitoring and Evaluation of Cultivated Land Irrigation Guarantee Capability with Remote Sensing

Science.gov (United States)

Zhang, C., Sr.; Huang, J.; Li, L.; Wang, H.; Zhu, D.

2015-12-01

Abstract: Cultivated Land Quality Grade monitoring and evaluation is an important way to improve the land production capability and ensure the country food safety. Irrigation guarantee capability is one of important aspects in the cultivated land quality monitoring and evaluation. In the current cultivated land quality monitoring processing based on field survey, the irrigation rate need much human resources investment in long investigation process. This study choses Beijing-Tianjin-Hebei as study region, taking the 1 km × 1 km grid size of cultivated land unit with a winter wheat-summer maize double cropping system as study object. A new irrigation capacity evaluation index based on the ratio of the annual irrigation requirement retrieved from MODIS data and the actual quantity of irrigation was proposed. With the years of monitoring results the irrigation guarantee capability of study area was evaluated comprehensively. The change trend of the irrigation guarantee capability index (IGCI) with the agricultural drought disaster area in rural statistical yearbook of Beijing-Tianjin-Hebei area was generally consistent. The average of IGCI value, the probability of irrigation-guaranteed year and the weighted average which controlled by the irrigation demand index were used and compared in this paper. The experiment results indicate that the classification result from the present method was close to that from irrigation probability in the gradation on agriculture land quality in 2012, with overlap of 73% similar units. The method of monitoring and evaluation of cultivated land IGCI proposed in this paper has a potential in cultivated land quality level monitoring and evaluation in China. Key words: remote sensing, evapotranspiration, MODIS cultivated land quality, irrigation guarantee capability Authors: Chao Zhang, Jianxi Huang, Li Li, Hongshuo Wang, Dehai Zhu China Agricultural University zhangchaobj@gmail.com

Rest and exercise radionuclide ventriculography in the ambulatory monitoring of patients with valvular heart disease

Energy Technology Data Exchange (ETDEWEB)

Raichlen, J.S.; Brest, A.N.

1988-01-01

Radionuclide angiography serves as a valuable adjunct in the noninvasive evaluation and monitoring of patients with valvular heart disease. Although estimations of regurgitant fractions and the differences between left and right ventricular stroke volumes can be made, the limitations of the techniques do not enable adequate quantitation of the severity of valvular insufficiency to warrant routine use in ambulatory management. The importance of radionuclide ventriculography, however, lies in its ability to examine global ventricular function both at rest and with exercise, thus enabling assessment of the functional reserve of the left and right ventricles. Such data are of considerable value in determining the need for invasive evaluation and the timing of valve replacement in patients with valvular heart disease. 41 references.

Rest and exercise radionuclide ventriculography in the ambulatory monitoring of patients with valvular heart disease

International Nuclear Information System (INIS)

Raichlen, J.S.; Brest, A.N.

1988-01-01

Radionuclide angiography serves as a valuable adjunct in the noninvasive evaluation and monitoring of patients with valvular heart disease. Although estimations of regurgitant fractions and the differences between left and right ventricular stroke volumes can be made, the limitations of the techniques do not enable adequate quantitation of the severity of valvular insufficiency to warrant routine use in ambulatory management. The importance of radionuclide ventriculography, however, lies in its ability to examine global ventricular function both at rest and with exercise, thus enabling assessment of the functional reserve of the left and right ventricles. Such data are of considerable value in determining the need for invasive evaluation and the timing of valve replacement in patients with valvular heart disease. 41 references

Transfer of radionuclides into human milk

International Nuclear Information System (INIS)

Steiner, M.; Wirth, E.

1998-01-01

Up until now the potential radiation exposure to breast-fed babies due to contaminated human milk has not been taken into account, when deriving international limit values and reference levels for radionuclides in foodstuffs, in air at monitored work places or for exposures in the medical field. It was the aim of the research project 'Transfer of radionuclides into human milk' to quantify the transfer of incorporated radionuclides into mother's milk, and develop simple models to estimate the radiation exposure of babies through the ingestion of human milk. The study focused on considerations of the radiation exposure due to the ingestion of contaminated foodstuffs by the mother, the inhalation of radionuclides at monitored work places, and the administration of radiopharmaceuticals to breast-feeding mothers. The blocking of infant thyroid glands by stable iodine in the case of accidental releases of radioiodine was considered as well. (orig.) [de

Transport of radionuclides from the LAMPF lagoons

International Nuclear Information System (INIS)

Ferenbaugh, R.W.; Purtymun, W.D.

1985-01-01

Monitoring of the discharge water from the Los Alamos Meson Physics Facility lagoons continued during June and December of 1983. The list of radionuclides being monitoring includes 7 Be, 57 Co, 134 Cs, 3 H, 54 Mn, 22 Na, and 83 Rb. The sampling locations and the data obtained to date are presented. Movement of radionuclides around the lagoons has been described in a previous report. 1 reference, 1 table

Organic liquid scintillation detectors for on-the-fly neutron/gamma alarming and radionuclide identification in a pedestrian radiation portal monitor

Science.gov (United States)

Paff, Marc Gerrit; Ruch, Marc L.; Poitrasson-Riviere, Alexis; Sagadevan, Athena; Clarke, Shaun D.; Pozzi, Sara

2015-07-01

We present new experimental results from a radiation portal monitor based on the use of organic liquid scintillators. The system was tested as part of a 3He-free radiation portal monitor testing campaign at the European Commission's Joint Research Centre in Ispra, Italy, in February 2014. The radiation portal monitor was subjected to a wide range of test conditions described in ANSI N42.35, including a variety of gamma-ray sources and a 20,000 n/s 252Cf source. A false alarm test tested whether radiation portal monitors ever alarmed in the presence of only natural background. The University of Michigan Detection for Nuclear Nonproliferation Group's system triggered zero false alarms in 2739 trials. It consistently alarmed on a variety of gamma-ray sources travelling at 1.2 m/s at a 70 cm source to detector distance. The neutron source was detected at speeds up to 3 m/s and in configurations with up to 8 cm of high density polyethylene shielding. The success of on-the-fly radionuclide identification varied with the gamma-ray source measured as well as with which of two radionuclide identification methods was used. Both methods used a least squares comparison between the measured pulse height distributions to library spectra to pick the best match. The methods varied in how the pulse height distributions were modified prior to the least squares comparison. Correct identification rates were as high as 100% for highly enriched uranium, but as low as 50% for 241Am. Both radionuclide identification algorithms produced mixed results, but the concept of using liquid scintillation detectors for gamma-ray and neutron alarming in radiation portal monitor was validated.

Monitoring of radionuclides in the environs of the Finnish nuclear power stations in 1988

International Nuclear Information System (INIS)

Klemola, S.; Ilus, E.; Sjoeblom, K.L.; Arvela, H.; Blomqvist, L.

1991-03-01

Monitoring of radionuclides around Finnish nuclear power plants continued in 1988 with the regular programmes. About 1000 samples were analysed from both terrestrial and aquatic environments.The dominant artificial radioactive substances in the vicinity of power plants were still the fallout nuclides from the Chernobyl accident, but the concentrations in all the objects monitored are lower than in the previous year. Trace amounts of activation products originating from the airborne releases of local power plants were detected in some air and deposition samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms. However, their contribution to the radiation doses received by the the public was very small. (orig.)

Chernobyl'-92. Reports of the 3. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 1. Radiation monitoring. Migration of radionuclides in natural environment. Part 1

International Nuclear Information System (INIS)

Senin, E.V.

1992-01-01

Section Radiation monitoring comprises: atlas of area radioactive contamination as a result of the Chernobyl' nuclear power station accident, state of computerized radiation control system, hydrological monitoring, radiation situation in different areas, problems of radioactive monitoring and protection of water objects, methods for determining radionuclides content, radiochemical mechanisms of radionuclide migration mobility of the Chernobyl' effluents, the results of investigations into migration of radionuclides in soils, landscapes, bottom depositions, in the soil-plant chain

A waste characterization monitor for low-level radioactive waste management

International Nuclear Information System (INIS)

Davey, E.C.; Csullog, G.W.; Kupca, S.; Hippola, K.B.

1985-06-01

The exploitation of nuclear processes and technology for the benefit of Canadians results in the routine generation of approximately 12 000 m 3 of solid low-level radioactive waste annually. To protect the public and the environment, this waste must be isolated for the duration of its potential hazard. In Canada, current planning foresees the development and use of a range of storage and disposal facilities exhibiting differing containment capabilities. To demonstrate adequate isolation safety and to minimize overall costs, the radionuclide content of waste items must be quantified so that the radiological hazards of each waste item can be matched to the isolation capabilities of specific containment facilities. This paper describes a non-invasive, waste characterization monitor that is capable of quantifying the radionuclide content of low-level waste packages to the 9 Bq/g (250 pCi/g) level. The assay technique is based on passive gamma-ray spectroscopy where the concentration of gamma-ray emitting radionuclides in a waste item can be estimated from the analysis of the gamma-ray spectra of the item and calibrated standards

Natural and anthropogenic radionuclide activity concentrations in the New Zealand diet

International Nuclear Information System (INIS)

Pearson, Andrew J.; Gaw, Sally; Hermanspahn, Nikolaus; Glover, Chris N.

2016-01-01

To support New Zealand's food safety monitoring regime, a survey was undertaken to establish radionuclide activity concentrations across the New Zealand diet. This survey was undertaken to better understand the radioactivity content of the modern diet and also to assess the suitability of the current use of milk as a sentinel for dietary radionuclide trends. Thirteen radionuclides were analysed in 40 common food commodities, including animal products, fruits, vegetables, cereal grains and seafood. Activity was detected for 137 Caesium, 90 Strontium and 131 Iodine. No other anthropogenic radionuclides were detected. Activity concentrations of the three natural radionuclides of Uranium and the daughter radionuclide 210 Polonium were detected in the majority of food sampled, with a large variation in magnitude. The maximum activity concentrations were detected in shellfish for all these radionuclides. Based on the established activity concentrations and ranges, the New Zealand diet contains activity concentrations of anthropogenic radionuclides far below the Codex Alimentarius guideline levels. Activity concentrations obtained for milk support its continued use as a sentinel for monitoring fallout radionuclides in terrestrial agriculture. The significant levels of natural and anthropogenic radionuclide activity concentrations detected in finfish and molluscs support undertaking further research to identify a suitable sentinel for New Zealand seafood monitoring. - Highlights: • A radionuclide monitoring program was undertaken across the New Zealand food supply. • 40 food types were analysed for 13 radionuclides. • 137 Cs was present in 15% of foods (range: 0.05–0.44Bq/kg). • Anthropogenic radionuclides displayed compliance with international limits. • 210 Po, 234 U and 238 U were present in most foods with large ranges of activities.

Natural and anthropogenic radionuclide activity concentrations in the New Zealand diet.

Science.gov (United States)

Pearson, Andrew J; Gaw, Sally; Hermanspahn, Nikolaus; Glover, Chris N

2016-01-01

To support New Zealand's food safety monitoring regime, a survey was undertaken to establish radionuclide activity concentrations across the New Zealand diet. This survey was undertaken to better understand the radioactivity content of the modern diet and also to assess the suitability of the current use of milk as a sentinel for dietary radionuclide trends. Thirteen radionuclides were analysed in 40 common food commodities, including animal products, fruits, vegetables, cereal grains and seafood. Activity was detected for (137)Caesium, (90)Strontium and (131)Iodine. No other anthropogenic radionuclides were detected. Activity concentrations of the three natural radionuclides of Uranium and the daughter radionuclide (210)Polonium were detected in the majority of food sampled, with a large variation in magnitude. The maximum activity concentrations were detected in shellfish for all these radionuclides. Based on the established activity concentrations and ranges, the New Zealand diet contains activity concentrations of anthropogenic radionuclides far below the Codex Alimentarius guideline levels. Activity concentrations obtained for milk support its continued use as a sentinel for monitoring fallout radionuclides in terrestrial agriculture. The significant levels of natural and anthropogenic radionuclide activity concentrations detected in finfish and molluscs support undertaking further research to identify a suitable sentinel for New Zealand seafood monitoring. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

Radionuclide scanning

International Nuclear Information System (INIS)

Shapiro, B.

1986-01-01

Radionuclide scanning is the production of images of normal and diseased tissues and organs by means of the gamma-ray emissions from radiopharmaceutical agents having specific distributions in the body. The gamma rays are detected at the body surface by a variety of instruments that convert the invisible rays into visible patterns representing the distribution of the radionuclide in the body. The patterns, or images, obtained can be interpreted to provide or to aid diagnoses, to follow the course of disease, and to monitor the management of various illnesses. Scanning is a sensitive technique, but its specificity may be low when interpreted alone. To be used most successfully, radionuclide scanning must be interpreted in conjunction with other techniques, such as bone radiographs with bone scans, chest radiographs with lung scans, and ultrasonic studies with thyroid scans. Interpretation is also enhanced by providing pertinent clinical information because the distribution of radiopharmaceutical agents can be altered by drugs and by various procedures besides physiologic and pathologic conditions. Discussion of the patient with the radionuclide scanning specialist prior to the study and review of the results with that specialist after the study are beneficial

Support and Maintenance of the International Monitoring System network

Science.gov (United States)

Pereira, Jose; Bazarragchaa, Sergelen; Kilgour, Owen; Pretorius, Jacques; Werzi, Robert; Beziat, Guillaume; Hamani, Wacel; Mohammad, Walid; Brely, Natalie

2014-05-01

The Monitoring Facilities Support Section of the Provisional Technical Secretariat (PTS) has as its main task to ensure optimal support and maintenance of an array of 321 monitoring stations and 16 radionuclide laboratories distributed worldwide. Raw seismic, infrasonic, hydroacoustic and radionuclide data from these facilities constitutes the basic product delivered by the International Monitoring System (IMS). In the process of maintaining such a wide array of stations of different technologies, the Support Section contributes to ensuring station mission capability. Mission capable data availability according to the IMS requirements should be at least 98% annually (no more than 7 days down time per year per waveform stations - 14 continuous for radionuclide stations) for continuous data sending stations. In this presentation, we will present our case regarding our intervention at stations to address equipment supportability and maintainability, as these are particularly large activities requiring the removal of a substantial part of the station equipment and installation of new equipment. The objective is always to plan these activities while minimizing downtime and continuing to meet all IMS requirements, including those of data availability mentioned above. We postulate that these objectives are better achieved by planning and making use of preventive maintenance, as opposed to "run-to-failure" with associated corrective maintenance. We use two recently upgraded Infrasound Stations (IS39 Palau and IS52 BIOT) as a case study and establish a comparison between these results and several other stations where corrective maintenance was performed, to demonstrate our hypothesis.

Consultative committee on ionizing radiation: Impact on radionuclide metrology

International Nuclear Information System (INIS)

Karam, L.R.; Ratel, G.

2016-01-01

In response to the CIPM MRA, and to improve radioactivity measurements in the face of advancing technologies, the CIPM's consultative committee on ionizing radiation developed a strategic approach to the realization and validation of measurement traceability for radionuclide metrology. As a consequence, measurement institutions throughout the world have devoted no small effort to establish radionuclide metrology capabilities, supported by active quality management systems and validated through prioritized participation in international comparisons, providing a varied stakeholder community with measurement confidence. - Highlights: • Influence of CIPM MRA on radionuclide metrology at laboratories around the world. • CCRI strategy: to be the “undisputed hub for ionizing radiation global metrology.” • CCRI Strategic Plan stresses importance of measurement confidence for stakeholder. • NMIs increasing role in radionuclide metrology by designating institutions (DIs). • NMIs and DIs establish quality systems; validate capabilities through comparisons.

Satellite-based Tropical Cyclone Monitoring Capabilities

Science.gov (United States)

Hawkins, J.; Richardson, K.; Surratt, M.; Yang, S.; Lee, T. F.; Sampson, C. R.; Solbrig, J.; Kuciauskas, A. P.; Miller, S. D.; Kent, J.

2012-12-01

Satellite remote sensing capabilities to monitor tropical cyclone (TC) location, structure, and intensity have evolved by utilizing a combination of operational and research and development (R&D) sensors. The microwave imagers from the operational Defense Meteorological Satellite Program [Special Sensor Microwave/Imager (SSM/I) and the Special Sensor Microwave Imager Sounder (SSMIS)] form the "base" for structure observations due to their ability to view through upper-level clouds, modest size swaths and ability to capture most storm structure features. The NASA TRMM microwave imager and precipitation radar continue their 15+ yearlong missions in serving the TC warning and research communities. The cessation of NASA's QuikSCAT satellite after more than a decade of service is sorely missed, but India's OceanSat-2 scatterometer is now providing crucial ocean surface wind vectors in addition to the Navy's WindSat ocean surface wind vector retrievals. Another Advanced Scatterometer (ASCAT) onboard EUMETSAT's MetOp-2 satellite is slated for launch soon. Passive microwave imagery has received a much needed boost with the launch of the French/Indian Megha Tropiques imager in September 2011, basically greatly supplementing the very successful NASA TRMM pathfinder with a larger swath and more frequent temporal sampling. While initial data issues have delayed data utilization, current news indicates this data will be available in 2013. Future NASA Global Precipitation Mission (GPM) sensors starting in 2014 will provide enhanced capabilities. Also, the inclusion of the new microwave sounder data from the NPP ATMS (Oct 2011) will assist in mapping TC convective structures. The National Polar orbiting Partnership (NPP) program's VIIRS sensor includes a day night band (DNB) with the capability to view TC cloud structure at night when sufficient lunar illumination exits. Examples highlighting this new capability will be discussed in concert with additional data fusion efforts.

Maximum values and classifications of radionuclides

International Nuclear Information System (INIS)

1993-01-01

The primary means of controlling the use of radiation are safety license procedure and the monitoring of radiation exposure and working conditions at places of radiation use. In Section 17 of the Finnish Radiation Act (592/91) certain operations are exempted from the safety license. The exemption limits for the licensing of radioactive materials, the radiotoxicity classification of radionuclides related to such exemption limits, the annual limits on intake of radionuclides to be followed when monitoring internal radiation dose, as well as concentration limits in the breathing air are specified in the guide. Also the surface contamination limits which must be followed when monitoring working conditions at places of radiation use are presented. (4 refs., 6 tabs.)

Environmental radionuclide monitoring of Canadian harbours: a decade of analyses in support of due diligence activities by the Royal Canadian Navy.

Science.gov (United States)

Kelly, David G; Mattson, Kristine M; McDonald, Curtis; Nielsen, Kathy S; Weir, Ron D

2014-12-01

The Royal Canadian Navy has conducted a comprehensive programme of safety, security and environmental monitoring since the first visits of nuclear powered and nuclear capable vessels (NPV/NCVs) to Canadian harbours in the late 1960s. The outcomes of baseline monitoring and vessel visit sampling for the period 2003-2012 are described for vessel visits to Halifax (NS), Esquimalt (BC) and Nanoose (BC). Data were obtained by gamma-ray spectroscopy using high purity germanium detectors. No evidence was found for the release of radioactive fission or activation products by NCV/NPVs during the study period, although anthropogenically produced radionuclides were observed as part of the study's baseline monitoring. Background activities of Cs-137 can be observed in sediments from all three locations which are derived from well-documented radioactivity releases. The detection of I-131 in aquatic plants is consistently observed in Halifax at activities as high as 15,000 Bq kg(-1) dry weight. These data are tentatively assigned to the release of medical I-131, followed by bioaccumulation from seawater. I-131 was also observed in aquatic plants samples from Esquimalt (33 Bq kg(-1)) and Nanoose (20 Bq kg(-1)) for a single sampling following the Fukushima Daiichi accident. Crown Copyright © 2014. Published by Elsevier Ltd. All rights reserved.

Assessing COSMO-SkyMed capability for crops identification and monitoring

Science.gov (United States)

Guarini, R.; Dini, L.

2015-12-01

In the last decade, it has been possible to better understand the impact of agricultural human practices on the global environmental change at different spatial (from local to global) and time (from seasonal to decadal) scales. This has been achieved thanks to: big dataset continuously acquired by Earth Observation (EO) satellites; the improved capabilities of remote sensing techniques in extracting valuable information from the EO datasets; the new EO data policy which allowed unrestricted data usage; the net technologies which allowed to quickly and easily share national, international and market-derived information; an increasingly performing computing technology which allows to massively process large amount of data easier and at decreasing costs. To better understand the environmental impacts of agriculture and to monitor the consequences of human agricultural activities on the biosphere, scientists require to better identify crops and monitor crop conditions over time and space. Traditionally, NDVI time series maps derived from optical sensors have been used to this aim. As well-known this important source of information is conditioned by cloud cover. Unlike passive systems, synthetic aperture radar (SAR) ones are almost insensitive to atmospheric influences; thus, they are especially suitable for crop identification and condition monitoring. Among the other SAR systems currently in orbit, the Italian Space Agency (ASI) COSMO Sky-Med® (CSK®) constellation (X-band, frequency 9.6 GHz, wavelength 3.1 cm), especially for its peculiar high revisit capability (up to four images in 16 days with same acquisition geometry) seems to be particular suitable for providing information in addition and/or in alternative to other optical EO systems. To assess the capability of the CSK® constellation in identifying crops and in monitoring crops condition in 2013 ASI started the "AGRICIDOT" project. Some of the main project achievements will be presented at the congress.

Development of the Arctic radionuclide monitoring station

International Nuclear Information System (INIS)

King, S.E.; Phillips, G.W.; Aakenes, U.R.

1996-01-01

In recent years, the world has learned about the dumping of nuclear reactors and other waste into the Arctic seas by the former Soviet Union. Most of the information on the present levels of radioactivity in the region has been obtained by oceanographic expeditions conducted during the brief Arctic summers. Year-round monitoring of the movement of radio-activity during dynamic seasonal and episodic chances is hampered by the difficulties caused by sea ice, logistics and communication constraints associated with deployment and maintenance of monitoring equipment in this remote region. We have designed an autonomous station to measure the benthic gamma-ray emitting radioactivity for periods of at least one year. The station is capable of detecting a 30 Bq/m 3 increase in the 137 Cs activity in a 24 hour period. After a year-long deployment, the station releases its anchor and rises to the surface to transmit the accumulated spectra and oceanographic data via an Argos satellite link. The design and performance characteristics of the prototype station will be discussed

Development of the Arctic radionuclide monitoring station

Science.gov (United States)

King, S. E.; Aakenes, U. R.; McCoy, K.; Phillips, G. W.

1997-06-01

The world has learned about the dumping of nuclear reactors and other waste into the Arctic seas by the former Soviet Union. Most of the information on the present levels of radioactivity in the region has been obtained by oceanographic expeditions conducted during the brief Arctic summers. Year-round monitoring of the movement of radioactivity during dynamic seasonal and episodic changes is hampered by the difficulties caused by sea ice, logistics and communication constraints associated with deployment and maintenance of monitoring equipment in this remote region. The authors have designed an autonomous station to measure the benthic gamma-ray emitting radioactivity for periods of at least one year. The station is capable of detecting a 30 Bq/m/sup 3/ increase in the /sup 137/Cs activity in a 24 hour period. After a year-long deployment, the station releases its anchor and rises to the surface to transmit the accumulated spectra and oceanographic data via an Argos satellite link. The design and performance characteristics of the prototype station are discussed.

The response of the radionuclide monitoring programme for agricultural products in Great Britain to the accident at Chernobyl

International Nuclear Information System (INIS)

Morris, J.A.

1986-01-01

The overall objective of the radiation monitoring and control programme of the Ministry of Agriculture, Fisheries and Food in Great Britain is to ensure the safety of foodstuffs. The particular responsibility of my department within the Ministry is the analysis of agricultural products for the presence of radionuclides entering the human food chain from atmospheric releases. The Ministry also has a laboratory which monitors the marine environment. This presentation describes the surveillance programme for agricultural foodstuffs and show how it was used to monitor the deposition from the Chernobyl accident, and shows some of the monitoring data obtained and indicate how the information was used in formulating protective measures. It also mentions future plans

The response of the radionuclide monitoring programme for agricultural products in Great Britain to the accident at Chernobyl

Energy Technology Data Exchange (ETDEWEB)

Morris, J A [Central Veterinary Laboratory, Weybridge, Surrey (United Kingdom)

1986-07-01

The overall objective of the radiation monitoring and control programme of the Ministry of Agriculture, Fisheries and Food in Great Britain is to ensure the safety of foodstuffs. The particular responsibility of my department within the Ministry is the analysis of agricultural products for the presence of radionuclides entering the human food chain from atmospheric releases. The Ministry also has a laboratory which monitors the marine environment. This presentation describes the surveillance programme for agricultural foodstuffs and show how it was used to monitor the deposition from the Chernobyl accident, and shows some of the monitoring data obtained and indicate how the information was used in formulating protective measures. It also mentions future plans.

Report of the consultant's meeting on monitoring accidentally released radionuclides in the environment

International Nuclear Information System (INIS)

2001-01-01

At an earlier Research Co-ordination Meeting (12-16 August 1991, VIC, Vienna) for the IAEA Programme on 'Rapid Instrumental and Separation Methods for Monitoring Radionuclides in Food and Environmental Samples', it was recognized that a network of analytical laboratories with specially qualified scientists is needed which will provide a timely coordinated response to any future requests for assistance from Member States. The experience gained from the International Chernobyl Project revealed that there is a need for such a closely linked group when the Member State lacks sufficient technical resource to independently perform an assessment of environmental contamination following an accidental release of radioactivity. The existence of such a network of laboratories would help to assure responsible government representatives and the general public that the Agency has additional available resources including specialized experts to perform assessments on which to base required actions for many accident scenarios and their radiological consequences. The purpose of the present Consultants' Meeting is to discuss the organization and scope of the proposed network of analytical laboratories. The Consultants should discuss the matrices and nuclides of interest at various time frames of an accidental release of radioactivity. It is also intended that the Consultants should discuss the laboratories from their experience which would have the specialized expertise needed, in both terrestrial and aquatic sample collection and analysis. Finally, it is intended that the Consultants should discuss whether it would be desirable for the Agency to produce a technical document based on the achievements of the Agency programme on 'Rapid Instrumental and Separation Methods for Monitoring Radionuclides in Food and Environmental Samples'. A Guide Book was considered essential by the participants of this Co-ordinated Research Programme because it would be a succinct form and on a common

Monitoring of radionuclides in the environment - is chemistry still needed?

International Nuclear Information System (INIS)

Cooper, E.L.

1989-01-01

Improvements in gamma spectrometry have led to a decline in the use of radiochemical methods by environmental laboratories. Radiochemical methods are still required for radioisotopes which do not emit gamma rays (e.g. 89,90 Sr, 239,240 Pu, etc.); however, as the levels of these radioisotopes from weapons fallout declined in the 1970's and 1980's, the interest in them also declined. The changes which had occurred in analytical methodology became apparent after the Chernobyl accident when all the early measurements were obtained by gamma spectrometry and information on Sr isotopes and actinides only began to emerge some weeks later. The role of chemistry in monitoring begins with sampling because of speciation and matrix effects and extends through the radiochemical analysis. In some cases it may be necessary to determine speciation because of differences in dose conversion factors or environmental behavior. There is a need to improve radiochemical procedures and the IAEA has established in dose conversion factors or environmental behavior. There is a need to improve radiochemical procedures and the IAEA has established a new coordinated research program on rapid methods. Clearly, there still are chemical aspects to monitoring radionuclides in the environment, and these are discussed

Monitoring of processes with gamma-rays of neutron capture and short-living radionuclides

International Nuclear Information System (INIS)

Aripov, G.A.; Kurbanov, B.I.; Allamuratova, G.

2004-01-01

Element content is a fundamental parameter of a substance, on which all its properties, and also character of physical, chemical, biological, technological and ecological processes depend. Therefore monitoring of element content (in the course of technological process - on line; in natural conditions - in site; or in living organisms - in vivo) becomes necessary for investigation of aforementioned processes. This problem can be successfully solved by using the methods of prompt gamma activation analysis (PGAA) and instrumental neutron activation analysis (INAA) on short-living radionuclides. These methods don't depend on type of substance (biological, geological, technological etc.), since the content is determined by gamma radiation of nuclei, and allows to meet such a serious requirement like the necessity of achieving minimal irradiation of the object and its minimal residual activity. In this work minimal determinable concentrations of various elements are estimated (based on experimental data) by the method of PGAA using radionuclide 252 Cf - source of neutrons with the yield of the oil of 10 8 neutron/sec on the experimental device with preliminary focusing of neutrons /1/, and also data of determination of elements by their isotopes with maximum time efficiency /2,3/ by the method of INAA. (author)

Chernobyl'-92. Reports of the 3. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 1. Radiation monitoring. Migration of radionuclides in environment. Part 2

International Nuclear Information System (INIS)

Senin, E.V.

1992-01-01

Section Radiation monitoring comprises: atlas of area radioactive contamination as a result of the Chernobyl' NPP accident, state of automated radiation monitoring control system, hydrological monitoring, radiation situation in different areas, problems of radiation monitoring and protection of water objects, methods for determining radionuclidescontents, radiochemical mechanisms of radionuclide migration mobility in the Chernobyl' effluents, the results of investigations into migration of radionuclides in soils, landscapes, bottom depositions, in the soil-plant chain

Design of environment monitoring system to evaluate radionuclide release from subsystem on PWR nuclear power accident

International Nuclear Information System (INIS)

Sri Kuntjoro; Sugiyanto; Pande Made Udiyani; Jupiter Sitorus Pane

2012-01-01

Nuclear Power Plan (NPP) as a renewable energy source is selected as an alternative, because it has many advantages that is environmentally friendly, fuel supply which is independent of the season, and the price that can compete with other power plants. However, the existence of some public skepticism about nuclear radiation safety, the government must be convinced about the operation of nuclear power plants are safe and secure. Research on the design of environment monitoring system for evaluation of radionuclide release from the reactor subsystems and the environment due to accidents at power reactors has been done. The study was conducted by calculating the distribution of radionuclide release into the reactor subsystem and the environment and also to build the environment radiation monitoring system. Environmental monitoring system consists of a radiation counter, early warning systems, meteorological measurement systems, GPS systems and GIS. Radiation monitoring system used to record the data of radiation, meteorological measurement system used to record data of wind and speed direction, while the GPS system is used to determine position of data measurements. The data is then transmitted to a data acquisition system and then to be transmitted to the control center. Collection and transmission of data is done via SMS formatting using a modem device that is placed in the control center. The control center receives measurement data from various places. In this case the control center has a function as an SMS Gateway. This system can visualize for different measurement locations. Furthermore, radiation data and position data to be integrated with digital maps. System integration is then visualized in a personal computer. To position of measurements directly visualized on the map and also look for the data displayed on a monitor as a red or green circle colour. That colour indicated as a safe limit of radiation monitor. When the cycle colour is red, the system will

Monitoring radionuclides in subsurface drinking water sources near unconventional drilling operations: a pilot study

International Nuclear Information System (INIS)

Nelson, Andrew W.; Knight, Andrew W.; Eitrheim, Eric S.; Schultz, Michael K.

2015-01-01

Unconventional drilling (the combination of hydraulic fracturing and horizontal drilling) to extract oil and natural gas is expanding rapidly around the world. The rate of expansion challenges scientists and regulators to assess the risks of the new technologies on drinking water resources. One concern is the potential for subsurface drinking water resource contamination by naturally occurring radioactive materials co-extracted during unconventional drilling activities. Given the rate of expansion, opportunities to test drinking water resources in the pre- and post-fracturing setting are rare. This pilot study investigated the levels of natural uranium, lead-210, and polonium-210 in private drinking wells within 2000 m of a large-volume hydraulic fracturing operation – before and approximately one-year following the fracturing activities. Observed radionuclide concentrations in well waters tested did not exceed maximum contaminant levels recommended by state and federal agencies. No statistically-significant differences in radionuclide concentrations were observed in well-water samples collected before and after the hydraulic fracturing activities. Expanded monitoring of private drinking wells before and after hydraulic fracturing activities is needed to develop understanding of the potential for drinking water resource contamination from unconventional drilling and gas extraction activities. - Highlights: • Natural radionuclides in ground water near unconventional drilling operations were investigated. • Natural uranium ( nat U), lead-210 ( 210 Pb), and polonium-210 ( 210 Po) levels are described. • No statistically significant increases in natural radioactivity post-drilling were observed

Krypton and Xenon Radionuclides Monitoring in the Northwest Region of Russia

Science.gov (United States)

Dubasov, Yuri V.; Okunev, Nikolay S.

2010-05-01

Monitoring of Xe and Kr radionuclides was conducted from August 2006 to 30 July 2008 within the framework of ISTC Project #2133. Cherepovets City in Vologda Province and St. Petersburg were chosen as monitoring locations. Kr-Xe concentrate samples were obtained as a result of processing of several thousand m3 of atmospheric air. New results of 85Kr monitoring show, that for last 15 years, the 85Kr volumetric activity in the atmospheric air of the northwest region of Russia has increased approximately 50% and has achieved a level of 1.5 Bq/m3. This value correlates well with similar data for Western Europe and Japan. The xenon fraction (80-160 cm3 under STP) is adsorbed on charcoal in the ampoule, which is measured in the well of HPGe gamma detector. Minimum detectable concentration (MDC) of 133Xe for this technique is 0.008 mBq/m3, and it is the most sensitive method used today. The 133Xe concentration in the atmospheric air of Cherepovets City varied in the monitoring period ranging from 0.09 to 2.5 mBq/m3. During the period of March 2007-30 July 2008, 133Xe activity concentration in the atmospheric air of St. Petersburg changed from background values (0.2-0.3 mBq/m3) to 185 mBq/m3 and for approximately 20% of the samples 135Xe was also measured with the 135Xe/133Xe activity ratio varied within the range of 0.03-3.5.

Monitoring of radionuclides in carbon steel blooms produced by EAF process

Directory of Open Access Journals (Sweden)

Sofilić T.

2011-01-01

Full Text Available Because natural and artificial isotopes in steel might originate from steel scrap or from the residue of the material that was used in the technological process, thus monitoring especially artificial radionuclides 60Co, 137Cs and 192Ir deserve special attention. The analysis by g-spectrometry has been applied to determine the presence of natural isotopes 40K, 226Ra, 232Th and 238U as well as of the artificial isotope 60Co, 137Cs and 192Ir and their activity in the produced steel round blooms in the Steel Mill of CMC Sisak d.o.o. At the same time the content of radionuclides in the other materials (ferroalloys, bauxite, fluorite, lime, coke, graphite electrodes, refractory blocks used in the same steel making process was investigated. The measured values regarding the presence of individual isotopes and their activity in steel were as follows: 40K all values were less than 1.6 Bqkg-1; 232Th all activities values were less than 0.02 Bqkg-1; 226Ra all activities values were less than 0.01 Bqkg-1; 238U all activities values were less than 1.10 Bqkg-1; 60Co all activities values were less than 0.02 Bqkg-1; 192Ir all activities values were less than 0.02 Bqkg-1 and 137Cs all activities values were less than 0.30 Bqkg-1.

Transfer of fallout radionuclides derived from Fukushima NPP accident: 1 year study on transfer of radionuclides through hydrological processes

Science.gov (United States)

Onda, Yuichi; Kato, Hiroaki; Patin, Jeremy; Yoshimura, Kazuya; Tsujimura, Maki; Wakahara, Taeko; Fukushima, Takehiko

2013-04-01

Previous experiences such as Chernobyl Nuclear Power Plant accident have confirmed that fallout radionuclides on the ground surface migrate through natural environment including soils and rivers. Therefore, in order to estimate future changes in radionuclide deposition, migration process of radionuclides in forests, soils, ground water, rivers should be monitored. However, such comprehensive studies on migration through forests, soils, ground water and rivers have not been conducted so far. Here, we present the following comprehensive investigation was conducted to confirm migration of radionuclides through natural environment including soils and rivers. 1)Study on depth distribution of radiocaesium in soils within forests, fields, and grassland 2)Confirmation of radionuclide distribution and investigation on migration in forests 3)Study on radionuclide migration due to soil erosion under different land use 4)Measurement of radionuclides entrained from natural environment including forests and soils 5)Investigation on radionuclide migration through soil water, ground water, stream water, spring water under different land use 6)Study on paddy-to-river transfer of radionuclides through suspended sediments 7)Study on river-to-ocean transfer of radionuclides via suspended sediments 8)Confirmation of radionuclide deposition in ponds and reservoirs

Use of dual-head gamma camera in radionuclide internal contamination monitoring on radiation workers from a nuclear medicine department

International Nuclear Information System (INIS)

Rodriguez-Laguna, A.; Brandan, M.E.

2008-01-01

As a part of an internal dosimetry program that is performed at the Mexican National Institute of Cancerology - Nuclear Medicine Department, in the present work we suggest a procedure for the routinely monitoring of internal contamination on radiation workers and nuclear medicine staff. The procedure is based on the identification and quantification of contaminating radionuclides in human body by using a dual-head whole-body gamma camera. The results have shown that the procedures described in this study can be used to implement a method to quantify minimal accumulated activity in the main human organs to evaluate internal contamination with radionuclides. The high sensitivity of the uncollimated gamma camera is advantageous for the routinely detection and identification of small activities of internal contamination. But, the null spatial resolution makes impossible the definition of contaminated region of interest. Then, the use of collimators is necessary to the quantification of incorporated radionuclides activities in the main human organs and for the internal doses assessment. (author)

Optimization of monitoring sewage with radionuclide contaminants. Optimizatsiya kontroya stochnykh vod, zagryaznennykh radionuklidami

Energy Technology Data Exchange (ETDEWEB)

Egorov, V N [Vsesoyuznyj Nauchno-Issledovatel' skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation)

1991-03-01

Recommendations on optimization of monitoring contaminated sewage aimed at enviromental protection agxinst radioactive contamination at minimum cost are presented. The way of selecting water sampling technique depends on water composition stability and flow rate. Depending on the type of radionuclide distribution in the sewage one can estimate minimum frequency of sampling or number of samples sufficient for assuring reliability of the conclusion on the excess or non-excess of permissible radioactive contamination levels, as well as analysis assigned accuracy. By irregular contaminated sewage-discharge and possibility of short-term releases of different form and duration, sampling should be accomplished through automatic devices of continuons or periodic operation.

Gastroesophageal reflux in children: radionuclide gastroesophagography

International Nuclear Information System (INIS)

Blumhagen, J.D.; Rudd, T.G.; Christie, D.L.

1980-01-01

Sixty-five symptomatic infants and children underwent radionuclide gastroesophagography, acid reflux testing, and barium esophagography with water-siphon testing to evaluate the clinical efficacy of the scintigraphic technique in detecting gastroesophageal reflux. After ingesting /sup 99m/Tc sulfur colloid in fruit juice, patients rested beneath the gamma camera for 30 to 60 min while esophageal activity was monitored continuously. By using the acid reflux test as a standard of comparison, the senstivity of radionuclide gastroesophagography was 75%. Because of its physiologic nature, low radiation exposure, and convenience, radionuclide gastroesophagography warrants further evaluation as a screening test for gastroesophageal reflux

Radionuclides in ground-level air

International Nuclear Information System (INIS)

Sinkko, K.

1987-01-01

In the air surveillance programme the concentrations of artificial radionuclides are monitored in the air close to the ground to obtain the necessary basic data for estimating the exposure of the Finnish population to fall-out radionuclides and also to detect atmospheric traces of radioactive materials caused by their use or production. Airborne dust is collected on filters with high-volume air samplers and the concentrations of gamma-emitting radionuclides in the air are evaluated. In the first quarter of 1986 only long-lived cesium, caused by earlier atmospheric nuclear explosions was detected. The concentrations of cesium were very low. In January and March a small amount of short-lived, fresh fission and activation products were also observed

The radionuclide migration model in river system

International Nuclear Information System (INIS)

Zhukova, O.M.; Shiryaeva, N.M.; Myshkina, M.K.; Shagalova, Eh.D.; Denisova, V.V.; Skurat, V.V.

2001-01-01

It was propose the model of radionuclide migration in river system based on principle of the compartmental model at hydraulically stationary and chemically equilibrium conditions of interaction of radionuclides in system water-dredge, water-sediments. Different conditions of radioactive contamination entry in river system were considered. The model was verified on the data of radiation monitoring of Iput' river

2006 LANL Radionuclide Air Emissions Report

Energy Technology Data Exchange (ETDEWEB)

David P. Fuehne

2007-06-30

This report describes the impacts from emissions of radionuclides at Los Alamos National Laboratory (LANL) for calendar year 2006. This report fulfills the requirements established by the Radionuclide National Emissions Standards for Hazardous Air Pollutants (Rad-NESHAP). This report is prepared by LANL's Rad-NESHAP compliance team, part of the Environmental Protection Division. The information in this report is required under the Clean Air Act and is being reported to the U.S. Environmental Protection Agency (EPA). The highest effective dose equivalent (EDE) to an off-site member of the public was calculated using procedures specified by the EPA and described in this report. LANL's EDE was 0.47 mrem for 2006. The annual limit established by the EPA is 10 mrem per year. During calendar year 2006, LANL continuously monitored radionuclide emissions at 28 release points, or stacks. The Laboratory estimates emissions from an additional 58 release points using radionuclide usage source terms. Also, LANL uses a network of air samplers around the Laboratory perimeter to monitor ambient airborne levels of radionuclides. To provide data for dispersion modeling and dose assessment, LANL maintains and operates meteorological monitoring systems. From these measurement systems, a comprehensive evaluation is conducted to calculate the EDE for the Laboratory. The EDE is evaluated as any member of the public at any off-site location where there is a residence, school, business, or office. In 2006, this location was the Los Alamos Airport Terminal. The majority of this dose is due to ambient air sampling of plutonium emitted from 2006 clean-up activities at an environmental restoration site (73-002-99; ash pile). Doses reported to the EPA for the past 10 years are shown in Table E1.

Radiation monitoring system in medical facilities

International Nuclear Information System (INIS)

Matsuno, Kiyoshi

1981-01-01

(1) RI selective liquid effluent monitor is, in many cases, used at medical facilities to obtain data for density of radioactivity of six radionuclides. In comparison with the conventional gross measuring systems, over-evaluation is less, and the monitor is more practical. (2) Preventive monitor for loss of radium needle is a system which prevents missing of radium needle at a flush-toilet in radium treatment wards, and this monitor is capable of sensing a drop-off of radium needle of 0.5 mCi (minimum). (3) Short-lived positron gas measuring device belongs to a BABY CYCLOTRON installed in a hospital, and this device is used to measure density of radioactivity, radioactive impurity and chemical impurity of produced radioactive gas. (author)

The Navruz Project: Transboundary Monitoring for Radionuclides and Metals in Central Asia Rivers. Sampling and Analysis Plan and Operational Manual

International Nuclear Information System (INIS)

Passell, Howard D.; Barber, David S.; Betsill, J. David; Littlfield, Adriane C.; Mohagheghi, Amir H.; Shanks, Sonoya T.; Yuldashev, Bekhzad; Salikhbaev, Umar; Radyuk, Raisa; Djuraev, Akram; Djuraev, Amwar; Vasilev, Ivan; Tolongutov, Bajgabyl; Valentina, Alekhina; Solodukhin, Vladimir; Pozniak, Victor

2002-01-01

The transboundary nature of water resources demands a transboundary approach to their monitoring and management. However, transboundary water projects raise a challenging set of problems related to communication issues, and standardization of sampling, analysis and data management methods. This manual addresses those challenges and provides the information and guidance needed to perform the Navruz Project, a cooperative, transboundary, river monitoring project involving rivers and institutions in Kazakhstan, Kyrgyzstan, Tajikistan, and Uzbekistan facilitated by Sandia National Laboratories in the U.S. The Navruz Project focuses on waterborne radionuclides and metals because of their importance to public health and nuclear materials proliferation concerns in the region. This manual provides guidelines for participants on sample and data collection, field equipment operations and procedures, sample handling, laboratory analysis, and data management. Also included are descriptions of rivers, sampling sites and parameters on which data are collected. Data obtained in this project are shared among all participating countries and the public through an internet web site, and are available for use in further studies and in regional transboundary water resource management efforts. Overall, the project addresses three main goals: to help increase capabilities in Central Asian nations for sustainable water resources management; to provide a scientific basis for supporting nuclear transparency and non-proliferation in the region; and to help reduce the threat of conflict in Central Asia over water resources, proliferation concerns, or other factors.

The Navruz Project: Transboundary Monitoring for Radionuclides and Metals in Central Asia Rivers. Sampling and Analysis Plan and Operational Manual

Energy Technology Data Exchange (ETDEWEB)

Passell, Howard D.; Barber, David S.; Betsill, J. David; Littlfield, Adriane C.; Mohagheghi, Amir H.; Shanks, Sonoya T.; Yuldashev, Bekhzad; Salikhbaev, Umar; Radyuk, Raisa; Djuraev, Akram; Djuraev, Amwar; Vasilev, Ivan; Tolongutov, Bajgabyl; Valentina, Alekhina; Solodukhin, Vladimir; Pozniak, Victor

2002-04-02

The transboundary nature of water resources demands a transboundary approach to their monitoring and management. However, transboundary water projects raise a challenging set of problems related to communication issues, and standardization of sampling, analysis and data management methods. This manual addresses those challenges and provides the information and guidance needed to perform the Navruz Project, a cooperative, transboundary, river monitoring project involving rivers and institutions in Kazakhstan, Kyrgyzstan, Tajikistan, and Uzbekistan facilitated by Sandia National Laboratories in the U.S. The Navruz Project focuses on waterborne radionuclides and metals because of their importance to public health and nuclear materials proliferation concerns in the region. This manual provides guidelines for participants on sample and data collection, field equipment operations and procedures, sample handling, laboratory analysis, and data management. Also included are descriptions of rivers, sampling sites and parameters on which data are collected. Data obtained in this project are shared among all participating countries and the public through an internet web site, and are available for use in further studies and in regional transboundary water resource management efforts. Overall, the project addresses three main goals: to help increase capabilities in Central Asian nations for sustainable water resources management; to provide a scientific basis for supporting nuclear transparency and non-proliferation in the region; and to help reduce the threat of conflict in Central Asia over water resources, proliferation concerns, or other factors.

Monitoring of Radio-nuclides in the Vicinities of Finnish Nuclear Power Plants in 2002-2004

International Nuclear Information System (INIS)

Ilus, E.; Klemola, S.; Vartti, V.-P.; Mattila, J.; Ikaeheimonen, T.K.

2000-03-01

The monitoring of radioactive substances round Finnish nuclear power plants continued in 2002-2004 in accordance with the regular environmental monitoring programmes. Altogether, some 1000 samples are analysed annually from the terrestrial and aquatic environs of the two power plants. Trace amounts of activation products originating from airborne releases from the local power plants were detected in several air and deposition samples taken from the close vicinities of the power plants. At Loviisa, observations were made in two; at Olkiluoto in three aerosol samples during the reporting period. Except for the naturally occurring beryllium-7, the concentrations of all radionuclides in the air samples were very low; from few microbequerels to few tens of microbequerels per cubic metre. A similar pattern was tenable for the deposition samples as well. The activity concentrations of cobalt-60 of local origin were at their highest 0.3 bequerels per square metre in one sample taken from Loviisa and in one sample taken from Olkiluoto. No traces of local discharge nuclides were detected in foodstuffs, drinking water or garden products. In mushrooms and wild berries picked up in 2004 from the Loviisa area, only Chernobyl-derived caesium isotopes and natural potassium-40 were detected. Local discharge nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments, which effectively accumulate radioactive substances. Besides tritium originating from local discharges, the most significant artificial radionuclide in the samples taken from the aquatic environs of the power plants was still caesium-137 originating from the Chernobyl accident (potassium-40 is a naturally occurring radionuclide). Elevated tritium concentrations were more frequent in the water samples from Loviisa. In indicator organisms and sinking matter, the observed concentrations of local discharge nuclides were generally somewhat higher and

First retrieval of hourly atmospheric radionuclides just after the Fukushima accident by analyzing filter-tapes of operational air pollution monitoring stations.

Science.gov (United States)

Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

2014-10-22

No observed data have been found in the Fukushima Prefecture (FP) for the time-series of atmospheric radionuclides concentrations just after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident. Accordingly, current estimates of internal radiation doses from inhalation, and atmospheric radionuclide concentrations by atmospheric transport models are highly uncertain. Here, we present a new method for retrieving the hourly atmospheric (137)Cs concentrations by measuring the radioactivity of suspended particulate matter (SPM) collected on filter tapes in SPM monitors which were operated even after the accident. This new dataset focused on the period of March 12-23, 2011 just after the accident, when massive radioactive materials were released from the FD1NPP to the atmosphere. Overall, 40 sites of the more than 400 sites in the air quality monitoring stations in eastern Japan were studied. For the first time, we show the spatio-temporal variation of atmospheric (137)Cs concentrations in the FP and the Tokyo Metropolitan Area (TMA) located more than 170 km southwest of the FD1NPP. The comprehensive dataset revealed how the polluted air masses were transported to the FP and TMA, and can be used to re-evaluate internal exposure, time-series radionuclides release rates, and atmospheric transport models.

First retrieval of hourly atmospheric radionuclides just after the Fukushima accident by analyzing filter-tapes of operational air pollution monitoring stations

Science.gov (United States)

Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

2014-01-01

No observed data have been found in the Fukushima Prefecture (FP) for the time-series of atmospheric radionuclides concentrations just after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident. Accordingly, current estimates of internal radiation doses from inhalation, and atmospheric radionuclide concentrations by atmospheric transport models are highly uncertain. Here, we present a new method for retrieving the hourly atmospheric 137Cs concentrations by measuring the radioactivity of suspended particulate matter (SPM) collected on filter tapes in SPM monitors which were operated even after the accident. This new dataset focused on the period of March 12–23, 2011 just after the accident, when massive radioactive materials were released from the FD1NPP to the atmosphere. Overall, 40 sites of the more than 400 sites in the air quality monitoring stations in eastern Japan were studied. For the first time, we show the spatio-temporal variation of atmospheric 137Cs concentrations in the FP and the Tokyo Metropolitan Area (TMA) located more than 170 km southwest of the FD1NPP. The comprehensive dataset revealed how the polluted air masses were transported to the FP and TMA, and can be used to re-evaluate internal exposure, time-series radionuclides release rates, and atmospheric transport models. PMID:25335435

The behavior of radionuclides in the soils of Rocky Flats, Colorado

Energy Technology Data Exchange (ETDEWEB)

Litaor, M I [Tel-Hai Rodman Coll., Upper Galilee (Israel); Barth, G; Zika, E M; Litus, G; Moffitt, J; Daniels, H [Colorado Univ., Civil and Environmental Engineering Dept., Boulder, CO (United States)

1998-05-01

Radionuclide contamination of soils in Rocky Flats, Colorado, resulted from leaking drums of Pu-contaminated oil stored at an outdoor area. To evaluated the mechanisms of radionuclide transport from the contaminated soils to groundwater, an advanced monitoring system was installed across a toposequence. The impact of natural rain, snowmelt, and large-scale rain simulations on the mobility and distribution of the radionuclides in soil interstitial water was studied. The distribution of radionuclides during the monitoring period from 1993 to 1995 suggested that Pu-239 + 240 and Am-241 are largely immobile in semi-arid soils. Fractionation of Pu-239 + 240 and Am-241 to different particle sizes in the soil interstitial water suggested that most of the radionuclides (83-97%) were associated with suspended particles, whereas the level of radionuclides associated with colloidal (0.45 {mu}m > X > 1 nm) and nonfilterable (< 1 nm) fractions ranged from 1.5 to 15%. (author).

GHSI emergency radionuclide bioassay laboratory network - summary of the second exercise

International Nuclear Information System (INIS)

Li, Chunsheng; Ko, Raymond; Quayle, Debora; Sadi, Baki; Bartizel, Christine; Battisti, Paolo; Boettger, Axel; Bouvier, Celine; Paquet, Francois; CapoteCuellar, Antonio; Carr, Zhanat; Hammond, Derek; Hartmann, Martina; Heikkinen, Tarja; Jones, Robert L.; Kim, Eunjoo; Koga, Roberto; Kukhta, Boris; Mitchell, Lorna; Morhard, Ryan; Rulik, Petr; Sergei, Aleksanin; Sierra, Inmaculada; Oliveira Sousa, Wandersonde; Szabo, Gyula

2017-01-01

The Global Health Security Initiative (GHSI) established a laboratory network within the GHSI community to develop collective surge capacity for radionuclide bioassay in response to a radiological or nuclear emergency as a means of enhancing response capability, health outcomes and community resilience. GHSI partners conducted an exercise in collaboration with the WHO Radiation Emergency Medical Preparedness and Assistance Network and the IAEA Response and Assistance Network, to test the participating laboratories (18) for their capabilities in in vitro assay of biological samples, using a urine sample spiked with multiple high-risk radionuclides ( 90 Sr, 106 Ru, 137 Cs, and 239 Pu). Laboratories were required to submit their reports within 72 h following receipt of the sample, using a pre-formatted template, on the procedures, methods and techniques used to identify and quantify the radionuclides in the sample, as well as the bioassay results with a 95% confidence interval. All of the participating laboratories identified and measured all or some of the radionuclides in the sample. However, gaps were identified in both the procedures used to assay multiple radionuclides in one sample, as well as in the methods or techniques used to assay specific radionuclides in urine. Two-third of the participating laboratories had difficulties in determining all the radionuclides in the sample. Results from this exercise indicate that challenges remain with respect to ensuring that results are delivered in a timely, consistent and reliable manner to support medical interventions. Laboratories within the networks are encouraged to work together to develop and maintain collective capabilities and capacity for emergency bioassay, which is an important component of radiation emergency response. (authors)

Elimination of quarterly urinalysis of radiation workers based on detection capability of portal monitors for internal contamination

International Nuclear Information System (INIS)

Ramanuja, Jayalakshmi

2012-01-01

Covidien is a radiopharmaceutical manufacturing company in Missouri, USA. The facility produces radionuclides for diagnostic and therapeutic use. The radionuclides of interest, 123 I, 67 Ga, 99 Mo, 99m Tc, 201 Tl, 111 In, and 131 I are fairly short lived with the exception of 51 Cr. The operating license document for the company mandated quarterly urinalysis (bioassay) of all radiation workers in the facility. This was labor intensive and did not enhance the quality of radiation protection program. Nuclear Regulatory Commission (NRC) required a technical basis to prove that there was no compromise in the radiological safety and accurate dose assessment in the event of internal contamination of radiation workers if quarterly urinalysis was discontinued. Measurements in a phantom, gamma spectroscopy analysis, as well as calculations showed that there was no need to perform quarterly urinalysis and that portal monitors and other radiological controls were sufficient to detect any chronic or acute intake of radioactivity by radiation workers. Technical evaluation showed Portal monitors can detect an Effective Dose Equivalent of 0.1 mSv (10 mrem) in a year. NRC allowed revision of operating license document and operating procedures to discontinue quarterly urinalysis. (author)

SCORPIO-VVER core monitoring and surveillance system with advanced capabilities

International Nuclear Information System (INIS)

Molnar, J.; Vocka, R.

2010-01-01

In this work authors present 12 years of operation experience of core monitoring and surveillance system with advanced capabilities on nuclear power plants on 6 unit of VVER-440 type of reactors at two different NPPs. The original version of the SCORPIO (Surveillance of reactor CORe by PIcture On-line display) system was developed for the western type of PWR reactors. The first version of the SCORPIO-VVER Core Monitoring System for Dukovany NPP (VVER-440 type of reactor, Czech Republic) was developed in 1998. For SCORPIO-VVER implementation at Bohunice NPP in Slovakia (2001) the system was enhanced with startup module KRITEX.

A proposal to use chlorine-36 for monitoring the movement of radionuclides from nuclear explosions

International Nuclear Information System (INIS)

Phillips, F.M.; Davis, S.N.; Kubik, P.

1990-01-01

Chlorine-36 has been produced in large amounts by hundreds of nuclear explosions on the Nevada Test Site as well as 12 off-site explosions at eight locations in five states. Continued monitoring of the redistribution of radionuclides by subsurface water is of concern in most of the areas affected by the detonations. Chlorine-36 has the following advantages as a built-in tracer for this redistribution: its mobility is equal to or greater than water, its long half-life assures its continued usefulness over long periods, collection and storage of samples is simple, it is not subject to vapor transport at ordinary temperatures, its natural background is very low, and it does not form insoluble precipitates. Chlorine-36 from the Gnome event near Carlsbad, New Mexico, illustrates how 36 Cl can be used to help study the redistribution of radionuclides in the soil profile. Chlorine-36 is also potentially useful as a tracer to study movement of contaminants around large nuclear reactor complexes and near repositories for radioactive waste

Sorption of radionuclides from Pb-Bi melt. Report 1

International Nuclear Information System (INIS)

Konovalov, Eh.E.; Il'icheva, N.S.; Trifonova, O.E.

2015-01-01

Results of laboratory investigations of sorption and interfacial distribution of 54 Mn, 59 Fe, 60 Co, 106 Ru, 125 Sb, 137 Cs, 144 Ce, 154,155 Eu and 235,238 U radionuclides in the system Pb-Bi melt - steel surface are analyzed. It is shown that 106 Ru and 125 Sb are concentrated in Pb-Bi melt and other radionuclides with higher oxygen affinity are sorbed on oxide deposits on structural materials. Temperature dependences of sorption efficiency of radionuclides are studied. It is shown that there is sharp increase of this value for all radionuclides near the temperature range 350-400 deg C. Recommendations are given on the use of 106 Ru and 125 Sb as a reference for fuel element rupture detection system with radiometric monitoring of coolant melt samples and 137 Cs, 134 Cs, 134m Cs with radiometric monitoring of sorbing samples [ru

Benchmarking LWR codes capability to model radionuclide deposition within SFR containments: An analysis of the Na ABCOVE tests

International Nuclear Information System (INIS)

Herranz, Luis E.; Garcia, Monica; Morandi, Sonia

2013-01-01

Highlights: • Assessment of LWR codes capability to model aerosol deposition within SFR containments. • Original hypotheses proposed to partially accommodate drawbacks from Na oxidation reactions. • A defined methodology to derive a more accurate characterization of Na-based particles. • Key missing models in LWR codes for SFR applications are identified. - Abstract: Postulated BDBAs in SFRs might result in contaminated-coolant discharge at high temperature into the containment. A full scope safety analysis of this reactor type requires computation tools properly validated in all the related fields. Radionuclide transport, particularly within the containment, is one of those fields. This sets two major challenges: to have reliable codes available and to build up a sound data base. Development of SFR source term codes was abandoned in the 80's and few data are available at present. The ABCOVE experimental programme conducted in the 80's is still a reference in the field. Postulated BDBAs in SFRs might result in contaminated-coolant discharge at high temperature into the containment. A full scope safety analysis of this reactor type requires computation tools properly validated in all the related fields. Radionuclide deposition, particularly within the containment, is one of those fields. This sets two major challenges: to have reliable codes available and to build up a sound data base. Development of SFR source term codes was abandoned in the 80's and few data are available at present. The ABCOVE experimental programme conducted in the 80's is still a reference in the field. The present paper is aimed at assessing the current capability of LWR codes to model aerosol deposition within a SFR containment under BDBA conditions. Through a systematic application of the ASTEC, ECART and MELCOR codes to relevant ABCOVE tests, insights have been gained into drawbacks and capabilities of these computation tools. Hypotheses and approximations have been adopted so that

Field test facility for monitoring water/radionuclide transport through partially saturated geologic media: design, construction, and preliminary description. Appendix I. Engineering drawings

International Nuclear Information System (INIS)

Phillips, S.J.; Campbell, A.C.; Campbell, M.D.; Gee, G.W.; Hoober, H.H.; Schwarzmiller, K.O.

1979-11-01

The engineering plans for a test facility to monitor radionuclide transport in water through partially saturated geological media are included. Drawings for the experimental set-up excavation plan and details, lysimeter, pad, access caisson, and caisson details are presented

Direct internal dosimetry. A new way for routine incorporation monitoring of γ-emitting radionuclides

International Nuclear Information System (INIS)

Doerfel, H.

1996-01-01

The INDOS detector system offers the following advantages with respect to routine incorporation monitoring: The measurement is performed automatically and there is no need for trained staff. The measuring time is short and thus a relative large number of persons may be monitored with a relative high measuring frequency. First estimates of the individual effective dose equivalent rate are available immediately after the measurement. 1) The direct determination of the dose equivalent in principle is more precise than the conventional procedures for internal dosimetry, because (i) the retention of radionuclides in the body may be measured explicitly and (ii) the dependence of the dose equivalent on the body proportions is corrected implicitly. 2) The measuring procedure is comparable to the external dosimetry with respect to accuracy and lower limit of detection. Thus, the results of internal and external dosimetry can be summed up in an easy and reasonable manner. 3) The detector system can be installed in any building; it also can be installed as a mobile unit in a car or a container for long distance transportation by aircraft or train. 4) Last but not least, the cost for monitoring with INDOS is much lower than for the conventional monitoring procedures using whole body counters. (author)

Monitoring and characterization of radionuclide transport in the hydrogeologic system

International Nuclear Information System (INIS)

Phillips, S.J.; Raymond, J.R.

1975-01-01

Historical records pertaining to the 300 North and Wye Burial Grounds at the Hanford Reservation were reviewed as a prerequisite to determining programs for land reclamation. All available historical documents, agency communications, and engineering drawings related to the study areas were located, reviewed, and analyzed. An inventory of recorded location, type, and quantity of radionuclides and associated materials in each burial ground was completed and distributed to cooperating investigators. A geophysical survey of the 300 North Burial Ground was conducted as a basis for detecting the composition, size, distribution, and depth of buried objects and characterizing the sediments in which they are buried. Acoustic, radar, magnetic, and metal detection surveys were completed and their applicability evaluated; drilling techniques and equipment for recovering and characterizing sediments and radioactive contaminated material were developed. Drilling will also determine the amount and dimensional extent of radionuclide migration; sediment-fluid interaction and fluid migration through the unsaturated zone at the 300 North Burial Ground were characterized. A study to determine biological transport of radionuclides at the Wye Burial Ground was also initiated. This study involved a preliminary survey of present flora and fauna inhabiting the Wye Burial Ground site. Plant tissue was chemically and radiochemically analyzed to determine radionuclide migration and possible dose effects and population dynamics of burrowing animals that could potentially be exposed to buried waste materials were investigated

A computerized system for control and management of radionuclide inventory: application in nuclear medicine

International Nuclear Information System (INIS)

Hoory, S.; Levy, I.M.; Moskowitz, G.; Bandyopadhyay, D.; Vaugeois, J.C.

1982-01-01

An interactive computerized system for radioisotope management and instantaneous inventory is reported. The system is capable of handling operations such as filing, nuclear imaging and disposing of various radionuclides. All radiopharmaceutical transactions are achieved with the aid of a Prime 300 mini-computer of 192K words of high speed semi-conductor memory and over 120 mega bytes of disk storage. The system automatically corrects for the appropriate decay, monitors and updates the storage file after every subsequent study. The performed study is recorded in a special file, together with the time and data retrieved from the computer's real time clock at the time of the entry. The system provides an organized and complete bookkeeping of all records concerning radionuclide transactions. It is found to be simple, efficient, highly versatile, and drastically reduces the time of operation and errors in handling the radioisotope inventory. (author)

Innovative Strategy For Long Term Monitoring Of Metal And Radionuclide Plumes

International Nuclear Information System (INIS)

Eddy-Dilek, Carol; Millings, Margaret R.; Looney, Brian B.; Denham, Miles E.

2014-01-01

Many government and private industry sites that were once contaminated with radioactive and chemical wastes cannot be cleaned up enough to permit unrestricted human access. The sites will require long term management, in some cases indefinitely, leaving site owners with the challenge of protecting human health and environmental quality at these 'legacy' sites. Long-term monitoring of groundwater contamination is one of the largest projected costs in the life cycle of environmental management at the Savannah River Site, the larger DOE complex, and many large federal and private sites. There is a need to optimize the performance and manage the cost of long term surveillance and monitoring at their sites. Currently, SRNL is initiating a pilot field test using alternative protocols for long term monitoring of metals and radionuclides. A key component of the approach is that monitoring efforts are focused on measurement of low cost metrics related to hydrologic and chemical conditions that control contaminant migration. The strategy combines careful monitoring of hydrologic boundary conditions with measurement of master variables such as chemical surrogates along with a smaller number of standard well analyses. In plumes contaminated with metals, master variables control the chemistry of the groundwater system, and include redox variables (ORP, DO, chemicals), pH, specific conductivity, biological community (breakdown/decay products), and temperature. Significant changes in these variables will result in conditions whereby the plume may not be stable and therefore can be used to predict possible plume migration. Conversely, concentration measurements for all types of contaminants in groundwater are a lagging indicator plume movement - major changes contaminant concentrations indicate that contamination has migrated. An approach based on measurement of master variables and explicit monitoring of hydrologic boundary conditions combined with traditional metrics should lead

Innovative Strategy For Long Term Monitoring Of Metal And Radionuclide Plumes

Energy Technology Data Exchange (ETDEWEB)

Eddy-Dilek, Carol; Millings, Margaret R.; Looney, Brian B.; Denham, Miles E.

2014-01-08

Many government and private industry sites that were once contaminated with radioactive and chemical wastes cannot be cleaned up enough to permit unrestricted human access. The sites will require long term management, in some cases indefinitely, leaving site owners with the challenge of protecting human health and environmental quality at these "legacy" sites. Long-term monitoring of groundwater contamination is one of the largest projected costs in the life cycle of environmental management at the Savannah River Site, the larger DOE complex, and many large federal and private sites. There is a need to optimize the performance and manage the cost of long term surveillance and monitoring at their sites. Currently, SRNL is initiating a pilot field test using alternative protocols for long term monitoring of metals and radionuclides. A key component of the approach is that monitoring efforts are focused on measurement of low cost metrics related to hydrologic and chemical conditions that control contaminant migration. The strategy combines careful monitoring of hydrologic boundary conditions with measurement of master variables such as chemical surrogates along with a smaller number of standard well analyses. In plumes contaminated with metals, master variables control the chemistry of the groundwater system, and include redox variables (ORP, DO, chemicals), pH, specific conductivity, biological community (breakdown/decay products), and temperature. Significant changes in these variables will result in conditions whereby the plume may not be stable and therefore can be used to predict possible plume migration. Conversely, concentration measurements for all types of contaminants in groundwater are a lagging indicator plume movement - major changes contaminant concentrations indicate that contamination has migrated. An approach based on measurement of master variables and explicit monitoring of hydrologic boundary conditions combined with traditional metrics should lead

The repeatability of left ventricular volume assessment by a new ambulatory radionuclide monitoring system during head-up tilt

International Nuclear Information System (INIS)

Takase, Bonpei; Hosaka, Haruhiko; Kitamura, Katsuhiro

2001-01-01

The precise measurement of changes in left ventricular volume is important to elucidate the mechanisms of neurally mediated syncope. This study was conducted to determine whether or not a brand-new ambulatory radionuclide monitoring system (C-VEST system) can be clinically used to easily and precisely measure left ventricular volume and function in tilt testing. To assess the repeatability of the C-VEST system, 12 healthy volunteers (mean age 24±4 years old) underwent 20 minute head-up tilt testing and we measured the temporal changes in left ventricular volume and ejection fraction twice a day (first and second studies). To investigate the changes in the C-VEST measurements and the detector position in the first and second studies, tilt testing was performed with an 80-degree passive tilt, which is the same as the standard procedure used in diagnosing neurally mediated syncope. The coefficient of repeatability for both the C-VEST and detector position was well within the clinical range (coefficient of repeatability in left ventricular volume ranged from 1.7 to 2.8; coefficient of repeatability in the detector position ranged from 2.3 to 3.1). Precise evaluation of the left ventricular volume can be achieved by an ambulatory radionuclide monitoring system in tilt testing. (author)

Radionuclides in plants in urban areas

International Nuclear Information System (INIS)

Todorovic, D.; Ajtic, J.; Popovic, D.; Nikolic, J.

2009-01-01

The results of a long-term study (from 2002 to 2008) on the concentrations of natural ( 7 Be, 210 Pb, 40 K) and fission ( 137 Cs) radionuclides in leaves of higher plants (linden and chestnut) in an urban area (city of Belgrade) are presented. The activity of the radionuclides was determined on an HPGe detector by standard gamma spectrometry. The study is a part of the ongoing air quality monitoring programme in urban areas in the Republic of Serbia. (author) [sr

Radionuclides in house dust

CERN Document Server

Fry, F A; Green, N; Hammond, D J

1985-01-01

Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, alt...

Hybrid modeling approach to improve the forecasting capability for the gaseous radionuclide in a nuclear site

International Nuclear Information System (INIS)

Jeong, Hyojoon; Hwang, Wontae; Kim, Eunhan; Han, Moonhee

2012-01-01

Highlights: ► This study is to improve the reliability of air dispersion modeling. ► Tracer experiments assumed gaseous radionuclides were conducted at a nuclear site. ► The performance of a hybrid modeling combined ISC with ANFIS was investigated.. ► Hybrid modeling approach shows better performance rather than a single ISC model. - Abstract: Predicted air concentrations of radioactive materials are important for an environmental impact assessment for the public health. In this study, the performance of a hybrid modeling combined with the industrial source complex (ISC) model and an adaptive neuro-fuzzy inference system (ANFIS) for predicting tracer concentrations was investigated. Tracer dispersion experiments were performed to produce the field data assuming the accidental release of radioactive material. ANFIS was trained in order that the outputs of the ISC model are similar to the measured data. Judging from the higher correlation coefficients between the measured and the calculated ones, the hybrid modeling approach could be an appropriate technique for an improvement of the modeling capability to predict the air concentrations for radioactive materials.

Benchmarking LWR codes capability to model radionuclide deposition within SFR containments: An analysis of the Na ABCOVE tests

Energy Technology Data Exchange (ETDEWEB)

Herranz, Luis E., E-mail: luisen.herranz@ciemat.es [CIEMAT, Unit of Nuclear Safety Research, Av. Complutense, 40, 28040 Madrid (Spain); Garcia, Monica, E-mail: monica.gmartin@ciemat.es [CIEMAT, Unit of Nuclear Safety Research, Av. Complutense, 40, 28040 Madrid (Spain); Morandi, Sonia, E-mail: sonia.morandi@rse-web.it [Nuclear and Industrial Plant Safety Team, Power Generation System Department, RSE, via Rubattino 54, 20134 Milano (Italy)

2013-12-15

Highlights: • Assessment of LWR codes capability to model aerosol deposition within SFR containments. • Original hypotheses proposed to partially accommodate drawbacks from Na oxidation reactions. • A defined methodology to derive a more accurate characterization of Na-based particles. • Key missing models in LWR codes for SFR applications are identified. - Abstract: Postulated BDBAs in SFRs might result in contaminated-coolant discharge at high temperature into the containment. A full scope safety analysis of this reactor type requires computation tools properly validated in all the related fields. Radionuclide transport, particularly within the containment, is one of those fields. This sets two major challenges: to have reliable codes available and to build up a sound data base. Development of SFR source term codes was abandoned in the 80's and few data are available at present. The ABCOVE experimental programme conducted in the 80's is still a reference in the field. Postulated BDBAs in SFRs might result in contaminated-coolant discharge at high temperature into the containment. A full scope safety analysis of this reactor type requires computation tools properly validated in all the related fields. Radionuclide deposition, particularly within the containment, is one of those fields. This sets two major challenges: to have reliable codes available and to build up a sound data base. Development of SFR source term codes was abandoned in the 80's and few data are available at present. The ABCOVE experimental programme conducted in the 80's is still a reference in the field. The present paper is aimed at assessing the current capability of LWR codes to model aerosol deposition within a SFR containment under BDBA conditions. Through a systematic application of the ASTEC, ECART and MELCOR codes to relevant ABCOVE tests, insights have been gained into drawbacks and capabilities of these computation tools. Hypotheses and approximations have

Radionuclide Air Emissions Report for 2012

Energy Technology Data Exchange (ETDEWEB)

Wahl, Linnea [Ernest Orlando Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States)

2013-05-01

Berkeley Lab operates facilities where radionuclides are produced, handled, store d, and potentially emitted . These facilities are subject to the EPA radioactive air emission regulations in 40 CFR 61, Subpart H (EPA 1989a). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2012, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]) . These minor sources include d about 140 stack sources and no diffuse sources . T here were no unplanned airborne radionuclide emissions from Berkeley Lab operations . Emissions from minor sources were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building- specific and common parameters, Laboratory personnel applied the EPA -approved computer code s, CAP88-PC and COMPLY , to calculate doses to the maximally exposed individual (MEI) at any offsite point where there is a residence, school, business, or office. Because radionuclides are used at three noncontiguous locations (the main site, Berkeley West Bio center, and Joint BioEnergy Institute), three different MEIs were identified.

Choice of radionuclides for radioimmunotherapy

International Nuclear Information System (INIS)

DeNardo, S.J.; Jungerman, J.A.; DeNardo, G.L.; Lagunas-Solar, M.C.; Cole, W.C.; Meares, C.F.

1985-01-01

Innumerable questions need to be answered and obstacles overcome before radioimmunotherapy can be generally successful in cancer patients. Major developments have greatly enhanced the likelihood of success. The important development of appropriate radionuclides and radiochemistry for this therapy must be intimately linked with the biological and biochemical realities. All aspects must be considered, such as the specific nature of the antigenic target, the pharmacokinetics of the antibody fragment carrier, the capability of in vivo quantitation of tumor uptake and turnover time, as well as total body kinetics. With this knowledge, then, practical radiochemistry methods can be integrated with the suitable radionuclide choices, and production methods can be developed which will deliver effective and dependable products for patient therapy

Development of radionuclide parameter database on internal contamination in nuclear emergencies

International Nuclear Information System (INIS)

Zhao Li; Xu Cuihua; Li Wenhong; Su Xu

2010-01-01

Objective: To develop a radionuclide parameter database on internal contamination in nuclear emergencies. Methods: By researching the radionuclides composition discharged from different nuclear emergencies, the radionuclide parameters were achieved on physical decay, absorption and metabolism in the body from ICRP publications and some other publications. The database on internal contamination for nuclear incidents was developed by using MS Visual Studio 2005 C and MS Access programming language. Results: The radionuclide parameter database on internal contamination in nuclear emergency was established. Conclusions: The database may be very convenient for searching radionuclides and radionuclide parameter data discharged from different nuclear emergencies, which would be helpful to the monitoring and assessment and assessment of internal contamination in nuclear emergencies. (authors)

Proficiency testing for radionuclides

International Nuclear Information System (INIS)

Faanhof, A.; Kotze, O.; Louw, I.

2010-01-01

Proficiency testing in general is only useful when it suites a certain purpose. With regards to radionuclides basically three fields of interest can be identified: (I)Foodstuffs-Introduced in the early 1960's to monitor the fall-out of nuclear tests and eventually the pathway to foodstuffs fit for human consumption. The demand for analysis increased substantially after the Chernobyl accident. (II) Natural radioactivity-Associated with mining and mineral processing of uranium and thorium baring mineral resources throughout the world where the radionuclides from the natural uranium and thorium decay series are found to pose concern for professional and public exposure. (III) Artificial radioactivity-This category covers mostly the long-lived nuclides generated by nuclear fission of the fuel used in nuclear power plants, research reactors and nuclear bomb tests. All three categories require a specific approach for laboratories to test their ability to analyze specific radio nuclides of interest in a variety of matrices. In this lecture I will give a compiled overview of the required radioanalytical skills, analysis sensitivity needed and radionuclides of interest, with more specific emphasis on QAQC of water sources and the recommended monitoring approach. And provide information on available reference materials and organizations/institutes that provide regular exercises for participating laboratories. I will also briefly communicate on the advantages and disadvantages of ISO/IEC 17025 accreditation for test laboratories, which is these days a prerequisite in national and international trade especially where foodstuffs and mineral products are concerned.

Instant detection of incorporated radio-nuclides

International Nuclear Information System (INIS)

Dolgirev, E.I.; Porozov, N.V.

1978-01-01

A method is described for rapid estimation of radionuclides both in the whole human body and in individual human organs beginning from levels equal to 0.1-0.01 of the maxium permissible value of annual absorption by personnel. In post-accident radiation exposure surveys, the whole-body content of gamma-emitting nuclides is monitored by measuring the flow of gamma quanta by use of a gas-discharge counter cassette placed at a distance of 0.5 m from the subject. Relationships for determining radionuclides in the human body are presented

Radionuclide analysis of bush food

International Nuclear Information System (INIS)

Koperski, J.; Bywater, J.

1985-01-01

A model diet for an Aboriginal adult living entirely on bush foods collected from the Alligator Rivers Region of the Northern Territory has been established. Results of investigations of the specific activities of thorium-230, radium-226, lead-210 and polonium-210 in 123 samples of bush foods collected by Ranger Uranium Mines Pty Ltd during pre-production and production periods are presented. For all the investigated bush food items, excluding freshwater mussels (Velesunio angasi), no systematic differences were found between the specific activities of the radionuclides monitored in food items sampled during preproduction and production periods. Preliminary estimates of annual effective dose equivalent (DE) rates for stochastic effects on an adult living entirely on the model bush diet are presented. Of the four radionuclides monitored the major contributor to the effective DE rates appears to be lead-210 followed by radium-226. Among the selected nine components of the diet the major contributor to the effective DE rates appear to be mussels, water lilies and fish

Radionuclide analysis of bush food

Energy Technology Data Exchange (ETDEWEB)

Koperski, J; Bywater, J [Ranger Uranium Mines Proprietary Ltd., Chatswood (Australia)

1985-04-01

A model diet for an Aboriginal adult living entirely on bush foods collected from the Alligator Rivers Region of the Northern Territory has been established. Results of investigations of the specific activities of thorium-230, radium-226, lead-210 and polonium-210 in 123 samples of bush foods collected by Ranger Uranium Mines Pty. Ltd. during pre-production and production periods are presented. For all the investigated bush food items, excluding freshwater mussels (Velesunio angasi), no systematic differences were found between the specific activities of the radionuclides monitored in food items sampled during preproduction and production periods. Preliminary estimates of annual effective dose equivalent (DE) rates for stochastic effects on an adult living entirely on the model bush diet are presented. Of the four radionuclides monitored the major contributor to the effective DE rates appears to be lead-210 followed by radium-226. Among the selected nine components of the diet the major contributor to the effective DE rates appear to be mussels, water lilies and fish.

Developments in Bioremediation of Soils and Sediments Pollutedwith Metals and Radionuclides: 2. Field Research on Bioremediation of Metals and Radionuclides

Energy Technology Data Exchange (ETDEWEB)

Hazen, Terry C.; Tabak, Henry H.

2007-03-15

Bioremediation of metals and radionuclides has had manyfield tests, demonstrations, and full-scale implementations in recentyears. Field research in this area has occurred for many different metalsand radionuclides using a wide array of strategies. These strategies canbe generally characterized in six major categories: biotransformation,bioaccumulation/bisorption, biodegradation of chelators, volatilization,treatment trains, and natural attenuation. For all field applicationsthere are a number of critical biogeochemical issues that most beaddressed for the successful field application. Monitoring andcharacterization parameters that are enabling to bioremediation of metalsand radionuclides are presented here. For each of the strategies a casestudy is presented to demonstrate a field application that uses thisstrategy.

Comparison of two freshwater turtle species as monitors of radionuclide and chemical contamination: DNA damage and residue analysis

International Nuclear Information System (INIS)

Meyers-Schoene, L.; Shugart, L.R.; Beauchamp, J.J.; Walton, B.T.

1993-01-01

Two species of turtles that occupy different ecological niches were compared for their usefulness as monitors of freshwater ecosystems where both low-level radioactive and nonradioactive contaminants are present. The pond slider (Trachemys scripta) and common snapping turtle (Chelydra serpentina) were analyzed for the presence of 90 Sr, 137 Cs, 60 Co, and Hg, radionuclides and chemicals known to be present at the contaminated site, and single-strand breaks in liver DNA. The integrity of the DNA was examined by the alkaline unwinding assay, a technique that detects strand breaks as a biological marker of possible exposure to genotoxic agents. This measure of DNA damage was significantly increased in both species of turtles at the contaminated site compared with turtles of the same species at a reference site, and shows that contaminant-exposed populations were under more severe genotoxic stress than those at the reference site. The level of strand breaks observed at the contaminated site was high and in the range reported for other aquatic species exposed to deleterious concentrations of genotoxic agents such as chemicals and ionizing radiation. Statistically significantly higher concentrations of radionuclides and Hg were detected in the turtles from the contaminated area. Mercury concentrations were significantly higher in the more carnivorous snapping turtle compared with the slider; however, both species were effective monitors of the contaminants

A review of the behaviour of radionuclides in the environment around Dounreay

International Nuclear Information System (INIS)

MacKenzie, A.; Begg, F.; Scott, E.

1996-02-01

This study was commissioned by Her Majesty's Industrial Pollution Inspectorate of The Scottish Office Environment Department to review published literature on (1) radionuclide discharges from the Dounreay and Vulcan nuclear establishments, (2) environmental monitoring and modelling of the behaviour of radionuclides in the Dounreay environment, (3) local agricultural and fisheries practices and (4) radionuclide research studies carried out in this environment

Relative value of clinical variables, bicycle ergometry, rest radionuclide ventriculography and 24 hour ambulatory electrocardiographic monitoring at discharge to predict 1 year survival after myocardial infarction

NARCIS (Netherlands)

P.M. Fioretti (Paolo); R.W. Brower (Ronald); M.L. Simoons (Maarten); H.J. ten Katen (Harald); A. Beelen (Anita); T. Baardman (Taco); J. Lubsen (Jacob); P.G. Hugenholtz (Paul)

1986-01-01

textabstractThe relative value of predischarge clinical variables, bicycle ergometry, radionuclide ventriculography and 24 hour ambulatory electrocardiographic monitoring for predicting survival during the first year in 351 hospital survivors of acute myocardial infarction was assessed. Discriminant

Environmental auditing: Capabilities and management utility of recreation impact monitoring programs

Science.gov (United States)

Marion, J.L.

1995-01-01

A recreation impact monitoring system was developed and applied in 1984?1986 and in 1991 to all backcountry river-accessed campsites within Delaware Water Gap National Recreation Area, Pennsylvania and New Jersey. Results suggest that actions implemented by park managers in response to problems identified by the initial survey were highly effective in reducing resource degradation caused by camping. In particular, the elimination of some designated campsites and installation of anchored firegrates reduced the total area of disturbance by 50%. Firegrate installation provided a focal point that increased the concentration of camping activities, allowing peripheral areas to recover. As suggested by predictive models, additional resource degradation caused by increased camping intensities is more than offset by improvements in the condition of areas where use is eliminated. The capabilities and management utility of recreation impact monitoring programs, illustrated by the Delaware Water Gap monitoring program, are also presented and discussed.

Radionuclides in house dust

Energy Technology Data Exchange (ETDEWEB)

Fry, F A; Green, N; Dodd, N J; Hammond, D J

1985-04-01

Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate authorising Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, although radionuclides originating rom the BNFL site can be detected in house dust, this source of contamination is a negligible route of exposure for members of the public in West Cumbria. This report presents the results of the Board's study of house dust in twenty homes in Cumbria during the spring and summer of 1984. A more intensive investigation is being carried out by Imperial College. (author)

Cosmogenic Radionuclides as an Extension of the Neutron Monitor Era into the Past: Potential and Limitations

Science.gov (United States)

Beer, J.; McCracken, K. G.; Abreu, J.; Heikkilä, U.; Steinhilber, F.

2013-06-01

The cosmogenic radionuclides, 10Be, 14C and others, provide a record of the paleo-cosmic radiation that extends >10,000 years into the past. They are the only quantitative means at our disposal to study the heliosphere prior to the commencement of routine sunspot observations in the 17th century. The cosmogenic radionuclides are primarily produced by secondary neutrons generated by the galactic cosmic radiation, and can be regarded, in a sense, as providing an extrapolation of the neutron monitor era into the past. However, their characteristics are quite different from the man-made neutron monitor in several important respects: (1) they are sensitive to somewhat lower cosmic ray energies; (2) their temporal resolution is ˜1 to 2 years, being determined by the rapidity with which they are sequestered in ice, biological, or other archives; (3) the statistical precision for annual data is very poor (˜19%); however it is quite adequate (˜5% for 22-year averages) to study the large variations (±40%) that have occurred in the paleo-cosmic ray record in the past between grand solar minima and maxima. The data contains "noise" caused by local meteorological effects, and longer-term climate effects, and the use of principal component analysis to separate these "system" effects from production effects is outlined. The concentrations of 10Be decreased by a factor of two at the commencement of Holocene, the present-day "interglacial", due to a 100% increase in the ice accumulation rates in polar regions. The use of the 10Be flux to study heliospheric properties during the last glacial is discussed briefly.

Summary of intensive monitoring for radionuclides in fishery products after Fukushima accident and comparison to the results of long term monitoring program in Japan

Energy Technology Data Exchange (ETDEWEB)

Fujimoto, Ken; Morita, Takami; Shigenobu, Yuya; Takagi, Kaori; Miki, Shizuho; Kaeriyama, Hideki; Ambe, Daisuke; Ono, Tsuneo [National Research Institute of Fisheries Science, Fisheries Research Agency, 2-12-4, Fukuura, Kanazawa, Yokohama, Kanagawa 236-8648 (Japan)

2014-07-01

Monitoring of artificial radionuclides in fishery products started in late 1950's and has over half a century history in Japan. Fisheries Agency (FA), Fisheries Research Agency (FRA) and prefectural organizations have been conducting the monitoring. The intensive monitoring of radioactive material in fishery products started in the late of March 2011 immediately after the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident for the coastal area faced to the Pacific Ocean in the eastern area of Japan and for the offshore area. The purpose of this monitoring is to avoid the distribution of fishery products containing radioactive cesium in concentration over the Japanese standard limit (Cs-134+Cs-137: 100 Bq/kg). Japanese monitoring data are opened to public on the FA's and FRA's web page. In this study, we resume the results of intensive monitoring started in 2011 and show the temporal change of concentration of radioactive cesium in fishery product. In Fukushima Prefecture, the ratio of samples exceeding the Japanese standard limit shows a steadily decreasing trend from 53% at Mar.- Jun. 2011 to below 3% at Jul. - Sep. 2013. In other prefectures, the ratio was 6.5% at Mar.- Jun. 2011 and fell gradually, and it has been below to 1% at Jul. - Sep. 2013. In presentation, we show the results of monitoring conducted in the coastal area and deeper water around Japan from long gamma ray measurements with ashed samples by high purified germanium gamma spectrometry. (authors)

The basic principles for the assessment of occupational exposure due to intakes of radionuclides (The most important indirect methods used in the Protection and Safety Dept. for internal occupational exposure monitoring)

International Nuclear Information System (INIS)

Kharita, M. H.; Sakhita, K.

2009-05-01

This study shows the basic principles for the assessment of occupational exposure due to intakes of radionuclides in order to calculate the committed effective dose of each radionuclide separately. We also discussed when the routine monitoring of workers becomes useful and when the workplace monitoring is better than workers monitoring. In addition, this study contains the details of four indirect methods as they are validated in the protection and safety department, and their names are: Determination the concentration of total uranium by using fluorimetry technique, Determination the activity of two uranium isotopes 238 and 234, The activity of Polonium 210, and the activity of Radium 226 by using alpha spectrometry for urine samples collected from workers occupationally exposed to this isotope. (author)

Radiation protection aspects of the trafficking radionuclides contaminated metal scrap

International Nuclear Information System (INIS)

Prouza, Z.

1999-01-01

This paper covers the legal base of the release in the environment of radionuclides containing materials and the radiation protection aspects of trafficking in radionuclides contaminated materials. Materials, substance and objects containing radionuclides or contaminated by them may be released into the environment, if they do not exceed values authorized by SONS (State Office of Nuclear Safety). Legislative measures should be taken against illicit trafficking of the nuclear material in all the areas. The creation of a sophisticated system for the control and regulation of all important radionuclides released into the environment should be based on the radiation protection limits, constraints, reference and exemption levels which are introduced in the legislative documents; the strong supervision of producers and users of the sealed sources by SONS side, in addition to the requirements of the licensing process of their sources; a complete data-base and information exchange system related to illicit trafficking in contaminated material; in this system all the authorities with jurisdiction should be involved. The responsibilities of the persons involved in metal scrap trafficking should include arrangement of appropriate monitoring, rules for transport of the metal scrap, an adequate measuring system to monitor metal scrap including monitoring to prevent processing or smelting of the radioactive material, control measures, etc. All of the above items of legislation are an important challenge for the Czech Republic. (author)

Mathematical simulation of sediment and radionuclide transport in estuaries

International Nuclear Information System (INIS)

Onishi, Y.; Trent, D.S.

1982-11-01

The finite element model LFESCOT (Flow, Energy, Salinity, Sediment and Contaminant Transport Model) was synthesized under this study to simulate radionuclide transport in estuaries to obtain accurate radionuclide distributions which are affected by these factors: time variance, three-dimensional flow, temperature, salinity, and sediments. Because sediment transport and radionuclide adsorption/desorption depend strongly on sizes or types of sediments, FLESCOT simulates sediment and a sediment-sorbed radionuclide for the total of three sediment-size fractions (or sediment types) of both cohesive and noncohesive sediments. It also calculates changes of estuarine bed conditions, including bed elevation changes due to sediment erosion/deposition, and three-dimensional distributions of three bed sediment sizes and sediment-sorbed radionuclides within the bed. Although the model was synthesized for radionuclide transport, it is general enough to also handle other contaminants such as heavy metals, pesticides, or toxic chemicals. The model was checked for its capability for flow, water surface elevation change, salinity, sediment and radionuclide transport under various simple conditions first, confirming the general validity of the model's computational schemes. These tests also revealed that FLESCOT can use large aspect ratios of computational cells, which are necessary in handling long estuarine study areas. After these simple tests, FLESCOT was applied to the Hudson River estuary between Chelsea and the mouth of the river to examine how well the model can predict radionuclide transport through simulating tidally influenced three-dimensional flow, salinity, sediment and radionuclide movements with their interactions

Fault Injection and Monitoring Capability for a Fault-Tolerant Distributed Computation System

Science.gov (United States)

Torres-Pomales, Wilfredo; Yates, Amy M.; Malekpour, Mahyar R.

2010-01-01

The Configurable Fault-Injection and Monitoring System (CFIMS) is intended for the experimental characterization of effects caused by a variety of adverse conditions on a distributed computation system running flight control applications. A product of research collaboration between NASA Langley Research Center and Old Dominion University, the CFIMS is the main research tool for generating actual fault response data with which to develop and validate analytical performance models and design methodologies for the mitigation of fault effects in distributed flight control systems. Rather than a fixed design solution, the CFIMS is a flexible system that enables the systematic exploration of the problem space and can be adapted to meet the evolving needs of the research. The CFIMS has the capabilities of system-under-test (SUT) functional stimulus generation, fault injection and state monitoring, all of which are supported by a configuration capability for setting up the system as desired for a particular experiment. This report summarizes the work accomplished so far in the development of the CFIMS concept and documents the first design realization.

Monitoring of radionuclides in the vicinities of Finnish nuclear power plants in 1991-1992

Energy Technology Data Exchange (ETDEWEB)

Ikaeheimonen, T.K.; Klemola, S.; Ilus, E.; Sjoeblom, K.-L.

1995-06-01

Surveillance of radioactive substances around Finnish nuclear power plants continued in 1991-1992 according to regular monitoring programmes, in which about 1000 samples were analysed annually from terrestrial and aquatic environments of the two power plants. Trace amounts of activation products originating from the airborne releases of the local power plants were detected in several air, deposition and soil samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments. However, the concentrations were so low that they did not markedly increase the radiation burden in the environment. The dominant artificial radionuclides in the vicinity of the power plants remained the cesium isotopes, {sup 137}Cs and {sup 134}Cs, originating from the Chernobyl accident. (orig.) (21 figs., 40 tabs.).

CRRIS: a methodology for assessing the impact of airborne radionuclide releases

International Nuclear Information System (INIS)

Baes, C.F. III; Miller, C.W.

1983-01-01

The Computerized Radiological Risk Investigation System (CRRIS) consists of six fully integrated computer codes which calculate environmental transport and resulting doses and risks to individuals or populations exposed to atmospheric radionuclide releases. The individual codes may be used alone for various assessment applications or may be run as a system. This presentation provides an overview and introduction to this system of computer codes and their use in conducting nuclear assessments. Radionuclides are handled by CRRIS either in terms of the released radionuclides or in terms of exposure radionuclides which consist of both the released nuclides and all (or a subset of) the decay daughters that grow in during environmental transport. The capability of CRRIS to handle radionuclide chains is accomplished through PRIMUS which serves as a preprocessor by accessing a library of radionuclide decay data and sets up matricies of decay constants which are used by the other CRRIS codes in all calculations involving transport and decay. PRIMUS may also be run independently by the user to define the decay chains, radionuclide decay constants, and branching ratios

Laboratory and field studies related to the Radionuclide Migration Project: Progress report, October 1, 1985-September 30, 1986

International Nuclear Information System (INIS)

Thompson, J.L.

1987-08-01

In this report we describe the work done at Los Alamos in support of the Radionuclide Migration project during fiscal year 1986. We have continued to monitor the transport of tritium and 85 Kr from the Cambric explosion zone to the satellite well, which is pumped at 600 gal/min. Corresponding movement of cationic radionuclides such as 137 Cs and 90 Sr has not yet been observed after 12 yr of pumping, nor have we seen evidence that these strongly sorbing ions move in conjunction with colloids. We have analyzed more data from the Cheshire study site but have not resolved the uncertainties regarding the distribution and movement of radioactive materials at this location. Our attempts to improve our analytical capability for 36 Cl and 99 Tc have resulted in some progress. Similarly, we have increased our understanding of radionuclide transport phenomena such as channeling in fracture flow and anion exclusion in zeolites and clays. A sample exchange with Lawrence Livermore National Laboratory has helped us identify critical steps in our procedures for collecting and analyzing large-volume water samples. We have surveyed potential sites on Pahute Mesa at the Nevada Test Site for future radionuclide migration studies and conclude that there are none other than Cheshire presently available, and none are likely to be created in the near future. The Laboratory has engaged recently in radionuclide migration studies sponsored by our weapons program; we reviewed this work in an appendix to the annual report

Prediction of acute cardiac rejection using radionuclide techniques

International Nuclear Information System (INIS)

Novitzky, D.; Bonioszczuk, J.; Cooper, D.K.C.; Isaacs, S.; Rose, A.G.; Smith, J.A.; Uys, C.J.; Barnard, C.N.; Fraser, R.

1984-01-01

Radionuclide scanning of the donor left ventricle using technetium-99m-labelled red cells was used to monitor acute rejection after heterotopic heart transplantation and compared with histopathological evidence of rejection obtained at examination of an endomyocardial biopsy specimen. The ejection fraction and end-diastolic, end-systolic and stroke volumes were calculated at each examination; an equation was derived from these data to predict the degree of acute rejection, using histopathological examination of endomyocardial biopsy specimens as criteria of the presence and severity of rejection. A highly significant multiple correlation between radionuclide scanning parameters and endomyocardial biopsy was found. The advantages of non-invasive radionuclide scanning over the invasive procedure of endomyocardial biopsy are discussed

Waterborne Release Monitoring and Surveillance Programs at the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Blanchard, A.

1999-03-26

This report documents the liquid release environmental compliance programs currently in place at the Savannah river Site (SRS). Included are descriptions of stream monitoring programs, which measure chemical parameters and radionuclides in site streams and the Savannah river and test representative biological communities within the streams for chemical and radiological uptake. This report also explains the field sampling and analytical capabilities that are available at SRS during both normal and emergency conditions.

Waterborne Release Monitoring and Surveillance Programs at the Savannah River Site

International Nuclear Information System (INIS)

Blanchard, A.

1999-01-01

This report documents the liquid release environmental compliance programs currently in place at the Savannah river Site (SRS). Included are descriptions of stream monitoring programs, which measure chemical parameters and radionuclides in site streams and the Savannah river and test representative biological communities within the streams for chemical and radiological uptake. This report also explains the field sampling and analytical capabilities that are available at SRS during both normal and emergency conditions

AUTOMATED PROCESS MONITORING: APPLYING PROVEN AUTOMATION TECHNIQUES TO INTERNATIONAL SAFEGUARDS NEEDS

International Nuclear Information System (INIS)

O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Devol, Timothy A.; Egorov, Oleg; Clements, John P.

2008-01-01

Identification and quantification of specific alpha- and beta-emitting radionuclides in complex liquid matrices is highly challenging, and is typically accomplished through laborious wet chemical sample preparation and separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, gas proportional counting, alpha energy analysis, mass spectrometry). Analytical results may take days or weeks to report. Chains of custody and sample security measures may also complicate or slow the analytical process. When an industrial process-scale plant requires the monitoring of specific radionuclides as an indication of the composition of its feed stream or of plant performance, radiochemical measurements must be fast, accurate, and reliable. Scientists at Pacific Northwest National Laboratory have assembled a fully automated prototype Process Monitor instrument capable of a variety of tasks: automated sampling directly from a feed stream, sample digestion/analyte redox adjustment, chemical separations, radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results could be immediately transmitted to on- or off-site locations. The development of a rapid radiochemical Process Monitor for 99Tc in Hanford tank waste processing streams, capable of performing several measurements per hour, will be discussed in detail. More recently, the automated platform was modified to perform measurements of 90Sr in Hanford tank waste stimulant. The system exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

Statistical analysis of fallout radionuclides transfer to paddy-field rice

International Nuclear Information System (INIS)

Takahashi, T.; Morisawa, S.; Inoue, Y.

1996-01-01

Radionuclides released from nuclear facilities to atmosphere are transported through various pathways in biosphere and cause human exposure. Among these radionuclides transfer pathways, an ingestion of crops containing radionuclides is one of the dominant pathway for human exposure. For the safety assessment of nuclear facilities, it is important to understand the behavior of radionuclides in agricultural environment and to describe them in a mathematical model. In this paper, a statistical model is proposed for estimating the concentration of fallout radionuclides in paddy-field rice, the staple food for Japanese people. For describing behavior of fallout radionuclides in a paddy-field, a dynamic model and a statistical model have been proposed respectively. The model used in this study has been developed assuming that the amount of radionuclides transfer to brown rice (hulled rice) or polished rice through direct deposition of airborne radionuclides (the direct deposition pathway) and root uptake from a paddy soil (the root uptake pathway) are proportional to the deposition flux of radionuclides and concentration of radionuclides in paddy soil respectively. That is, the model has two independent variables; the deposition flux of radionuclides and the concentration of radionuclides in the paddy soil, and has single dependent variable; the concentration of radionuclides in brown rice or polished rice. The regression analysis is applied by using environmental monitoring data. Then the distribution of radionuclides between rice-bran (skin part of rice crop) and polished rice (core part) through both the direct deposition pathway and the root uptake pathway are evaluated by the model. (author)

Radionuclide concentrations in white sturgeon from the Columbia River

Energy Technology Data Exchange (ETDEWEB)

Dauble, D.D.; Price, K.R.; Poston, T.M.

1992-09-01

Although radioactive releases from the US Department of Energy`s Hanford Site have been monitored in the environment since the reactors began operating in 1945, recent information regarding historical releases of radionuclides has led to renewed interest in estimating human exposure to radionuclides at Hanford. Knowledge of the fate of radionuclides in some fish species may be important because of the potential for food-chain transfer to humans. White sturgeon (Acipenser transmontanus) were selected for study because they are long-lived, reside year-round in the Hanford Reach, are benthic, and are an important commercial and sport species in the Columbia River. They also have a greater potential for accumulating persistent radionuclides than shorter-lived species with pelagic and/or anadromous life histories. The purpose of our study was to summarize data on historical concentrations of industrial radionuclides in white sturgeon and to collect additional data on current body burdens in the Columbia River.

Radionuclide concentrations in white sturgeon from the Columbia River

Energy Technology Data Exchange (ETDEWEB)

Dauble, D.D.; Price, K.R.; Poston, T.M.

1992-09-01

Although radioactive releases from the US Department of Energy's Hanford Site have been monitored in the environment since the reactors began operating in 1945, recent information regarding historical releases of radionuclides has led to renewed interest in estimating human exposure to radionuclides at Hanford. Knowledge of the fate of radionuclides in some fish species may be important because of the potential for food-chain transfer to humans. White sturgeon (Acipenser transmontanus) were selected for study because they are long-lived, reside year-round in the Hanford Reach, are benthic, and are an important commercial and sport species in the Columbia River. They also have a greater potential for accumulating persistent radionuclides than shorter-lived species with pelagic and/or anadromous life histories. The purpose of our study was to summarize data on historical concentrations of industrial radionuclides in white sturgeon and to collect additional data on current body burdens in the Columbia River.

Radionuclide concentrations in white sturgeon from the Columbia River

International Nuclear Information System (INIS)

Dauble, D.D.; Price, K.R.; Poston, T.M.

1992-09-01

Although radioactive releases from the US Department of Energy's Hanford Site have been monitored in the environment since the reactors began operating in 1945, recent information regarding historical releases of radionuclides has led to renewed interest in estimating human exposure to radionuclides at Hanford. Knowledge of the fate of radionuclides in some fish species may be important because of the potential for food-chain transfer to humans. White sturgeon (Acipenser transmontanus) were selected for study because they are long-lived, reside year-round in the Hanford Reach, are benthic, and are an important commercial and sport species in the Columbia River. They also have a greater potential for accumulating persistent radionuclides than shorter-lived species with pelagic and/or anadromous life histories. The purpose of our study was to summarize data on historical concentrations of industrial radionuclides in white sturgeon and to collect additional data on current body burdens in the Columbia River

SCORPIO-VVER core monitoring and surveillance system with advanced capabilities

International Nuclear Information System (INIS)

Molnar, J.; Vocka, R.

2009-01-01

The SCORPIO-VVER system includes following features: 1) Validation of plant measurements and identification of sensor failures. 2) Optimum combination of measurements and calculations to obtain precise values of important parameters. 3) On-line 3D power distribution calculation with pin power reconstruction. 4) Limit checking and thermal margin calculation allowing for surveillance of VVER core limits such as DNBR, Sub-cooling margin, FdH and FQ peeking factors. 5) Integrated modules for monitoring fuel performance and coolant activity for identification of fuel failures. 6) Predictive capabilities and strategy planning, offering the possibility to check the consequences of operational manoeuvres in advance, prediction of critical parameters, etc. 7) Convenient monitoring of approach to criticality during reactor start-up. 8) Automated transition between cycles (fuel reload). The SCORPIO-VVER core monitoring system with its flexible and modular framework successfully responses to the plant operating needs and advances in nuclear fuel cycle strategies and fuel design. Modular framework allows for easy modifications of the system and implementation of new methods in physical modules. Even if the system is installed only on VVER-440 reactors, it could be adapted for VVER-1000 needs

Monitoring of radionuclides in the vicinities of Finnish nuclear power plants in 1993 and 1994

International Nuclear Information System (INIS)

Klemola, S.; Ilus, E.; Ikaeheimonen, T.K.

1998-08-01

Monitoring of radioactive substances around Finnish nuclear power plants continued in 1993-1994 in accordance with the regular programmes. Some 1000 samples are analysed annually from the terrestrial and aquatic environments of the two power plant sites. Trace amounts of activation products originating from airborne releases from the local power plants were detected in several air, deposition and soil samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments. However, the concentrations were so low that they did not significantly increase the radiation burden in the environment. The dominant artificial radionuclides in the vicinity of the power plants remained the cesium isotopes, especially 137 Cs but also 134 Cs, originating from the Chernobyl accident. (orig.)

Monitoring intakes of radionuclides by nuclear power plants workers in France: materials, methods and results

Energy Technology Data Exchange (ETDEWEB)

Gonin, M.; Le Guen, B.; Bailloeuil, C.; Gerondal, M. [Electricite De France (France)

2000-05-01

EDF (Electricite de France) owns 57 operating reactors distributed on 20 sites. Individual monitoring for intakes of radionuclides is done by whole body gamma countings and excretion bioassays. This monitoring concerns all EDF workers (about 20,000), and also subcontractor personnel (about 40,000 people per year). The aim of monitoring is to detect any intake above the recording level and to assess, as precisely as possible, internal doses. ICRP publications no.30 and 54 are used for internal dose calculations. Whole body countings (approximately 200,000 per year) are made by occupational health services on each nuclear site. The equipment consists of: 1. two whole body counters with two large NaI detectors, the approximate detection limit is 150 Bq in Co-60 for a 1-minute count. 2. one shielded chair with two smallers NaI detectors (one for thyroid and one for thoraco-abdominal region), specially designed for iodine contamination case, or casualties on stretchers. A special medical software program incorporates: 3. an operating system containing a module to ensure the quality control of measurements. 4. a measurement interpretation system with a screening histogram facility for activity alarm levels and spectrometry gamma analysis. 5. an administrative database for nationwide monitoring of all EDF and non-EDF workers. An EDF central radiotoxicology laboratory, located in the suburbs of Paris, analyses all the biological samples (about 8,000 per year, urines, faeces or nose blows) and centralises the results. At the occupational health service's request, the following analyses can be done: 1. tritium activity measurements (liquid scintillation) with a detection limit of 75 Bq per litre, 2. gamma spectrometry (HPGe detectors) on urines and faeces ash samples with a detection limit of 0.5 Bq per sample for one hours of counting. 3. alpha spectrometry (after chemical treatment) on urines and faeces ash samples with a lower detection limit of 0.2 mBq per sample

Monitoring intakes of radionuclides by nuclear power plants workers in France: materials, methods and results

International Nuclear Information System (INIS)

Gonin, M.; Le Guen, B.; Bailloeuil, C.; Gerondal, M.

2000-01-01

EDF (Electricite de France) owns 57 operating reactors distributed on 20 sites. Individual monitoring for intakes of radionuclides is done by whole body gamma countings and excretion bioassays. This monitoring concerns all EDF workers (about 20,000), and also subcontractor personnel (about 40,000 people per year). The aim of monitoring is to detect any intake above the recording level and to assess, as precisely as possible, internal doses. ICRP publications no.30 and 54 are used for internal dose calculations. Whole body countings (approximately 200,000 per year) are made by occupational health services on each nuclear site. The equipment consists of: 1. two whole body counters with two large NaI detectors, the approximate detection limit is 150 Bq in Co-60 for a 1-minute count. 2. one shielded chair with two smallers NaI detectors (one for thyroid and one for thoraco-abdominal region), specially designed for iodine contamination case, or casualties on stretchers. A special medical software program incorporates: 3. an operating system containing a module to ensure the quality control of measurements. 4. a measurement interpretation system with a screening histogram facility for activity alarm levels and spectrometry gamma analysis. 5. an administrative database for nationwide monitoring of all EDF and non-EDF workers. An EDF central radiotoxicology laboratory, located in the suburbs of Paris, analyses all the biological samples (about 8,000 per year, urines, faeces or nose blows) and centralises the results. At the occupational health service's request, the following analyses can be done: 1. tritium activity measurements (liquid scintillation) with a detection limit of 75 Bq per litre, 2. gamma spectrometry (HPGe detectors) on urines and faeces ash samples with a detection limit of 0.5 Bq per sample for one hours of counting. 3. alpha spectrometry (after chemical treatment) on urines and faeces ash samples with a lower detection limit of 0.2 mBq per sample for 72

Radionuclide transfer to meadow vegetation

International Nuclear Information System (INIS)

Goncharova, N.; Matsko, N.; Zhebrakova, I.; Montik, T.

1999-01-01

In the paper results of radioecological monitoring of natural plant populations in the 30 km zone of the Chernobyl Nuclear Power Plant (Polesky State Radioecological Reserve) during the period from 1987 to 1998 are presented. The level of radiation background in experimental areas varied from 0.1 to 30 mR/h that correspond to the total soil activity of 300-24000 kBq/m 2 (for May 1997). Monitoring was carried out including the radionuclide migration in natural plant complexes and transfer of 137 Cs between some plant organs. Refs. 3 (author)

Geotrap: radionuclide migration in geologic, heterogeneous media. Summary of accomplishments

International Nuclear Information System (INIS)

2002-01-01

GEOTRAP - the OECD/NEA Project on Radionuclide Migration in Geologic, Heterogeneous Media - was carried out in the context of site evaluation and safety assessment of deep repository systems for long-lived radioactive waste. The project was created in 1996 with the aim of developing an understanding of, and modelling capability for, potential radionuclide migration. This report provides an overview of the project's main findings and accomplishments over its five-year life. This summary should help make the valuable information collected and generated by the GEOTRAP project accessible to a wide readership both within and outside the radioactive waste community.It is a reflection of the careful attention paid by this community to the question of radionuclide transport. (authors)

RAPID AUTOMATED RADIOCHEMICAL ANALYZER FOR DETERMINATION OF TARGETED RADIONUCLIDES IN NUCLEAR PROCESS STREAMS

International Nuclear Information System (INIS)

O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Egorov, Oleg; Devol, Timothy A.

2008-01-01

Some industrial process-scale plants require the monitoring of specific radionuclides as an indication of the composition of their feed streams or as indicators of plant performance. In this process environment, radiochemical measurements must be fast, accurate, and reliable. Manual sampling, sample preparation, and analysis of process fluids are highly precise and accurate, but tend to be expensive and slow. Scientists at Pacific Northwest National Laboratory (PNNL) have assembled and characterized a fully automated prototype Process Monitor instrument which was originally designed to rapidly measure Tc-99 in the effluent streams of the Waste Treatment Plant at Hanford, WA. The system is capable of a variety of tasks: extraction of a precise volume of sample, sample digestion/analyte redox adjustment, column-based chemical separations, flow-through radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results can be immediately calculated and electronically reported. It is capable of performing a complete analytical cycle in less than 15 minutes. The system is highly modular and can be adapted to a variety of sample types and analytical requirements. It exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

Assessing the weather monitoring capabilities of cellular microwave link networks

Science.gov (United States)

Fencl, Martin; Vrzba, Miroslav; Rieckermann, Jörg; Bareš, Vojtěch

2016-04-01

Using of microwave links for rainfall monitoring was suggested already by (Atlas and Ulbrich, 1977). However, this technique attracted broader attention of scientific community only in the recent decade, with the extensive growth of cellular microwave link (CML) networks, which form the backbone of today's cellular telecommunication infrastructure. Several studies have already shown that CMLs can be conveniently used as weather sensors and have potential to provide near-ground path-integrated observations of rainfall but also humidity or fog. However, although research is still focusing on algorithms to improve the weather sensing capabilities (Fencl et al., 2015), it is not clear how to convince cellular operators to provide the power levels of their network. One step in this direction is to show in which regions or municipalities the networks are sufficiently dense to provide/develop good services. In this contribution we suggest a standardized approach to evaluate CML networks in terms of rainfall observation and to identify suitable regions for CML rainfall monitoring. We estimate precision of single CML based on its sensitivity to rainfall, i.e. as a function of frequency, polarization and path length. Capability of a network to capture rainfall spatial patterns is estimated from the CML coverage and path lengths considering that single CML provides path-integrated rain rates. We also search for suitable predictors for regions where no network topologies are available. We test our approach on several European networks and discuss the results. Our results show that CMLs are very dense in urban areas (> 1 CML/km2), but less in rural areas (online tool. In summary, our results demonstrate that CML represent promising environmental observation network, suitable especially for urban rainfall monitoring. The developed approach integrated into an open source online tool can be conveniently used e.g. by local operators or authorities to evaluate the suitability of

Direct methods for measuring radionuclides in the human body

International Nuclear Information System (INIS)

1996-01-01

Occupational exposure leading to intakes of internally incorporated radionuclides can occur as a result of various activities. This includes work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve exposure to enhanced levels of naturally occurring radionuclides. In 1987 the IAEA published a Safety Guide on basic principles for occupational radiation monitoring which set forth principles and objectives of a strategy for monitoring exposures of workers. Since drafting of the present Safety Practice commenced, the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) have been issued. On the basis of the principles laid down in the BSS, the 1987 Safety Guide is also being revised, and recommendations on the assessment of the occupational intake of radioactive materials are to be added. The present Safety Practice, which deals with direct measurement of radionuclides in the human body, is the first to be published in this area. Refs, figs, tabs

Serial exercise gated radionuclide ventriculograms (RVG) in monitoring doxorubicin cardiotoxicity

International Nuclear Information System (INIS)

Goldstein, H.A.; Lahoda, J.; Fox, L.

1985-01-01

The resting RVG (Radionuclide Ventriculograms) are demonstrated to be an effective monitor of the cardiotoxicity of doxorubicin. The exercise RVG has not been as well studied to see if it yields additional information or detects toxicity effects earlier. Sixteen patients receiving doxorubicin for chemotherapy had 2-6 serial exercise studies with intervals between studies of 1 month to 15 months. The patients exercised varying amounts with cardiac work indicated by their double products (HR x Sys. BP). Although all patients started with a normal resting LVEF (>50%), 5 of the 16 did not have a normal response (≥5% increase in LVEF) with initial exercise study. Of the 11 patients with an initially normal response to exercise, on at least one subsequent study, 3 had an abnormal response to exercise. On a later follow up study 1 of these 3 patients again had a normal response to exercise. Six of these 11 patients had had RVG evidence of cardiotoxicity. Four of these 6 patients had continually normal exercise responses, while 2 of these 5 patients had had an abnormal exercise response. An initial exercise RVG may be reasonable to detect unsuspected CAD in cancer victims. These patients are reported to be more sensitive to the toxic effects of doxorubicin. Follow up exercise RVGs do not contribute useful information, do not predict cardiotoxicity, and may be misleading

Research summary: characterization of radionuclide and moisture movement through arid region sediments

International Nuclear Information System (INIS)

Gee, G.W.; Jones, T.L.; Rai, D.

1981-09-01

This project has the task of understanding the movement of moisture and radionuclides under arid region conditions. This understanding will be used to maximize the isolation of low level waste from the environment. Specific objectives include: field monitoring of moisture and radionuclide transport at an arid region site; assessment of the interaction of radionuclides with unsaturated soils in arid regions; evaluation of radionuclide transport in unsaturated soils by appropriate mathematical models; and assessment of the importance of upward migration of radionuclides by evaporation and diffusion processes. The Burial Waste Test Facility (BWTF) located near Richland, Washington, on the Department of Energy (DOE) Hanford Site has been monitored for water content and radionuclide transport for the past two years. Tritium movement has been observed to depths of 7.6 m in both irrigated and nonirrigated lysimeters. Laboratory tests were conducted to determine how leachate from uranium tailings interacts with geologic materials. Acid leach tailings and tailings solution and geologic materials typical of mill site tailing pits were physically and chemically characterized. Investigation was made of the sorption characteristics of heavy metals and radionuclides on the geologic materials under low and neutral pH conditions. From solubility tests conducted at Pacific Northwest Laboratory, thermodynamic considerations predicted that for the Eh-pH range of natural aqueous environment, the dominant species of Pu is likely to be Pu(V) in relatively oxidizing environments and Pu(III) in reducing environments. Radionuclide transport through unsaturated media was investigated by using two solute transport models to describe the transport of tritium and strontium-85 in laboratory columns. A new approach was used to analyze radon emissions from uranium mill tailings

The use of Canadian monitoring networks to study the movement of airborne radionuclides on a global scale

International Nuclear Information System (INIS)

Bliss, L.T.; Johnson, S.; Mercier, J.F.; Stocki, T.J.; Ungar, R.K.

2008-01-01

The Radiation Protection Bureau of Health Canada operates a number of radiological monitoring networks for the purpose of detecting routine emissions from nuclear facilities and also of providing early warnings of major nuclear events which may have an impact on Canada. The vast quantity of data collected from these networks can contribute to a wide range of scientific studies on atmospheric transport processes and climate change effects. The potential for such studies can be greatly expanded through partnerships with other nations operating similar monitoring networks. We present a number of examples to illustrate the application of this information for a variety of environmental problems. To be consistent with the theme of this conference, we have considered only the measurements of radio-nuclides and radioactivity. However, archived air filters can equally well be used to study a wide range of trace metal contaminants and also certain persistent organic pollutants that remain stable on the air filter medium (author)(tk)

Monitoring of radionuclides in the vicinities of Finnish nuclear power plants in 1993 and 1994

Energy Technology Data Exchange (ETDEWEB)

Klemola, S.; Ilus, E.; Ikaeheimonen, T.K

1998-08-01

Monitoring of radioactive substances around Finnish nuclear power plants continued in 1993-1994 in accordance with the regular programmes. Some 1000 samples are analysed annually from the terrestrial and aquatic environments of the two power plant sites. Trace amounts of activation products originating from airborne releases from the local power plants were detected in several air, deposition and soil samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments. However, the concentrations were so low that they did not significantly increase the radiation burden in the environment. The dominant artificial radionuclides in the vicinity of the power plants remained the cesium isotopes, especially {sup 137}Cs but also {sup 134}Cs, originating from the Chernobyl accident. (orig.) 14 refs.

Internal exposure of populations to long-lived radionuclides released into the environment

International Nuclear Information System (INIS)

Balonov, M.I.

1997-01-01

This chapter discusses the events that led to the contamination of environments with the long-lived radionuclides of caesium, strontium and other elements, and to the internal exposure of populations living in contaminated areas. Among these events are radioactive releases into the river Techa from the Soviet nuclear weapons facility Mayak in 1949-1956, thermonuclear weapons test in the 1950s and 1960s, the Kyshtim and Windscale accidents in 1957, and the Chernobyl and Tomsk-7 accidents in 1986 and 1993, respectively. Methods of environmental monitoring and individual internal dose monitoring of inhabitants are described. These are based on measuring the content of radionuclides not only in the air, drinking water and local food products, but also in humans using whole-body counters and analysing excreta and autopsy samples. The dynamics of internal exposure of people of different ages to radionuclides of caesium, strontium and plutonium from the environment are considered. Examples of radionuclide distributions in the environment, and of individual/collective internal doses and related medical effects are presented. (Author)

Capabilities of infrared weld monitor

Energy Technology Data Exchange (ETDEWEB)

Sanders, P.G.; Keske, J.S.; Leong, K.H.; Kornecki, G.

1997-11-01

A non-obtrusive pre-aligned, solid-state device has been developed to monitor the primary infrared emissions during laser welding. The weld monitor output is a 100-1000 mV signal that depends on the beam power and weld characteristics. The DC level of this signal is related to weld penetration, while AC portions of the output can be correlated with surface irregularities and part misalignment or contamination. Changes in DC behavior are also noted for both full and deep penetration welds. Full penetration welds are signified by an abrupt reduction in the weld monitor output. Bead on plate welds were made on steel, aluminum, and magnesium with both a CW CO{sub 2} laser and a pulsed Nd:YAG laser to explore the relationships between the weld characteristics and the weld monitor output.

Agriculture products as source of radionuclides and some monitoring principles of agriculture near nuclear facilities

International Nuclear Information System (INIS)

Aleksakhin, R.M.; Korneev, N.A.; Panteleev, L.I.; Shukhovtsev, B.I.

1985-01-01

Migration of radionuclides into agriculture products in regions adjoining the nuclear facilities depends on a large number of factors. Among them is the complex of ecological conditions: meteorological factors, type of soils etc., as well as biological peculiarities of agriculture plants and animals. It is possible to control the radionuclide content administered to man's organism with agriculture products changing large branches of agriculture and varying within the range of seprate branches of industry, taking into account the most effective ways of radionuclide pathways

Developing role of short-lived radionuclides in nuclear medical practice. DOE symposium series; 56

International Nuclear Information System (INIS)

Paras, P.; Thiessen, J.W.

1985-01-01

The purpose was to define the developing role and state-of-the-art development of short-lived radionuclides (SLR's) in current nuclear medical practice. Special emphasis was placed on radionuclides with general-purpose labeling capabilities. The need for high-purity labeling-grade iodine-123 was emphasized in the program. Papers have been separately abstracted for the data base

Mathematical Basis and Test Cases for Colloid-Facilitated Radionuclide Transport Modeling in GDSA-PFLOTRAN

Energy Technology Data Exchange (ETDEWEB)

Reimus, Paul William [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-07-31

This report provides documentation of the mathematical basis for a colloid-facilitated radionuclide transport modeling capability that can be incorporated into GDSA-PFLOTRAN. It also provides numerous test cases against which the modeling capability can be benchmarked once the model is implemented numerically in GDSA-PFLOTRAN. The test cases were run using a 1-D numerical model developed by the author, and the inputs and outputs from the 1-D model are provided in an electronic spreadsheet supplement to this report so that all cases can be reproduced in GDSA-PFLOTRAN, and the outputs can be directly compared with the 1-D model. The cases include examples of all potential scenarios in which colloid-facilitated transport could result in the accelerated transport of a radionuclide relative to its transport in the absence of colloids. Although it cannot be claimed that all the model features that are described in the mathematical basis were rigorously exercised in the test cases, the goal was to test the features that matter the most for colloid-facilitated transport; i.e., slow desorption of radionuclides from colloids, slow filtration of colloids, and equilibrium radionuclide partitioning to colloids that is strongly favored over partitioning to immobile surfaces, resulting in a substantial fraction of radionuclide mass being associated with mobile colloids.

Monitoring of radionuclides in the environs of Finnish nuclear power plants in 1989-1990

International Nuclear Information System (INIS)

Ilus, E.; Sjoeblom, K-L.; Klemola, S.; Arvela, H.

1992-01-01

Surveillance of radioactive substances around Finnish nuclear power plants continued in 1989-1990 according to the regular monitoring programmes. About 1000 samples were analysed annually from both terrestrial and aquatic environments. The dominant artificial radionuclides in the vicinity of the power plants were still the cesium isotopes, 137 Cs and 134 Cs, originating from the Chernobyl accident. Owing to radioactive decay, other fallout nuclides with shorter half-lives disappeared from the environmental samples during the period in question. Trace amounts of activation products originating from the airborne releases of the local power plants were detected in some air and deposition samples. Discharged nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms and sinking matter collected from the Olkiluoto area in 1990. However, the concentrations were so low that they did not markedly raise the radiation burden in the environment. (orig.)

The use of 59Ni, 99Tc, and 236U to monitor the release of radionuclides from objects containing spent nuclear fuel dumped in the Kara Sea

International Nuclear Information System (INIS)

Mount, M.E.; Layton, D.W.; Hamilton, T.F.; Lynn, M.

1999-01-01

Between 1965 and 1981, five objects and six naval reactor pressure vessels (RPVs) from four former Soviet Union submarines and a special container from the icebreaker Lenin, all containing damaged spent nuclear fuel (SNF) were dumped in a variety of containments, at four sites in the Kara Sea. The International Atomic Energy Agency initiated the International Arctic Seas Assessment Project (IASAP) to study the possible health and environmental effects from disposal of these objects. One outcome of the IASAP was an estimation of the radionuclide inventory and their release rates from these objects. A follow-on concern is the ability to detect the radionuclides released into the water column. The work reported here is the feasibility of using the long-lived radionuclides 59 Ni, 99 Tc, and 236 U encased within these objects, to monitor the breakdown of the containments due to corrosion

Environmental radiation monitoring

International Nuclear Information System (INIS)

Watanabe, Isao

2011-01-01

The samples, pretreatment method, and measurement methods of 'Environmental radioactivity level by prefecture' of Ministry of Education, Culture, Sports, Science and Education (MEXT) is explained. It consists of 1), 'Environmental radioactivity level by prefecture' in normal period, 2) 'Strengthening of Monitoring of Environmental Radioactivity Level by Prefecture' of MEXT at emergency 3) strengthening of monitoring by Fukushima Daiichi nuclear accident, 4) radiation monitoring around the nuclear facility, 5) strengthening of monitoring by MEXT, and 6) quality of monitoring. The survey item and samples etc., of 'Environmental radioactivity level by prefecture', monitoring post, NaI (Tl) scintillation survey meter, sampling and pretreatment methods for radionuclide analysis in normal period, an example of germanium semiconductor detector, gamma ray spectrum of spaghetti from Italy by germanium semiconductor detector, flow chart of radionuclide analysis of fallout in normal period and emergency by germanium semiconductor detector, example of analytical method of radioactive strontium ( ion exchange method), outline of plutonium analytical method for emergency, sampling and pretreatment methods of radionuclides for strengthening, monitoring result around Fukushima Daiichi nuclear plant from June 23 to 24, 2011, change of air dose rate of monitoring post in Mito city from March 14 to 26, 2011, concentration of I-131 and Cs-137 in fallout in Hitachinaka city from March 19 to April 30, 2011, and change of concentration of I-131, Cs-134 and Cs-137 in tap water of Iitate village from March 20 to April 30, 2011, are illustrated. (S.Y.)

Radionuclide reporter gene imaging

Energy Technology Data Exchange (ETDEWEB)

Min, Jung Joon [School of Medicine, Chonnam National Univ., Gwangju (Korea, Republic of)

2004-04-01

Recent progress in the development of non-invasive imaging technologies continues to strengthen the role of molecular imaging biological research. These tools have been validated recently in variety of research models, and have been shown to provide continuous quantitative monitoring of the location(s), magnitude, and time-variation of gene expression. This article reviews the principles, characteristics, categories and the use of radionuclide reporter gene imaging technologies as they have been used in imaging cell trafficking, imaging gene therapy, imaging endogenous gene expression and imaging molecular interactions. The studies published to date demonstrate that reporter gene imaging technologies will help to accelerate model validation as well as allow for clinical monitoring of human diseases.

Radionuclide reporter gene imaging

International Nuclear Information System (INIS)

Min, Jung Joon

2004-01-01

Recent progress in the development of non-invasive imaging technologies continues to strengthen the role of molecular imaging biological research. These tools have been validated recently in variety of research models, and have been shown to provide continuous quantitative monitoring of the location(s), magnitude, and time-variation of gene expression. This article reviews the principles, characteristics, categories and the use of radionuclide reporter gene imaging technologies as they have been used in imaging cell trafficking, imaging gene therapy, imaging endogenous gene expression and imaging molecular interactions. The studies published to date demonstrate that reporter gene imaging technologies will help to accelerate model validation as well as allow for clinical monitoring of human diseases

Activity concentration of radionuclides in plants in the environment of western Ghats

International Nuclear Information System (INIS)

Manigandan, P. K.

2009-01-01

A field study on the transfer of primordial radionuclides 238 U, 232 Th, 40 K and fallout radionuclides 210 Po in different plant species in tropical forest of western Ghats environment is presented. Material and Methods: The Top storey, Second storey, Shrubs and epiphytic plant species were chosen and concentration of these radionuclides in plant and soil were measured by employing gamma ray spectrometer and alpha counter. Results: The concentration ratio shows the variation in different species while a wild plant Elaeocarpus oblongus and epiphytic plants indicated preferential uptake of these radionuclides. Conclusion: The dust trapped in the root system of. epiphytic plants could be used as bio indicator to monitor fallout radionuclides in the Western Ghats. The concentration of 232 Th and 40 K in leaves depends on the age of the leaves.

Real-time radionuclide identification in γ-emitter mixtures based on spiking neural network

International Nuclear Information System (INIS)

Bobin, C.; Bichler, O.; Lourenço, V.; Thiam, C.; Thévenin, M.

2016-01-01

Portal radiation monitors dedicated to the prevention of illegal traffic of nuclear materials at international borders need to deliver as fast as possible a radionuclide identification of a potential radiological threat. Spectrometry techniques applied to identify the radionuclides contributing to γ-emitter mixtures are usually performed using off-line spectrum analysis. As an alternative to these usual methods, a real-time processing based on an artificial neural network and Bayes’ rule is proposed for fast radionuclide identification. The validation of this real-time approach was carried out using γ-emitter spectra ( 241 Am, 133 Ba, 207 Bi, 60 Co, 137 Cs) obtained with a high-efficiency well-type NaI(Tl). The first tests showed that the proposed algorithm enables a fast identification of each γ-emitting radionuclide using the information given by the whole spectrum. Based on an iterative process, the on-line analysis only needs low-statistics spectra without energy calibration to identify the nature of a radiological threat. - Highlights: • A fast radionuclide identification algorithm applicable in spectroscopic portal monitors is presented. • The proposed algorithm combines a Bayesian sequential approach and a spiking neural network. • The algorithm was validated using the mixture of γ-emitter spectra provided by a well-type NaI(Tl) detector. • The radionuclide identification process is implemented using the whole γ-spectrum without energy calibration.

Radionuclide concentrations in underground waters of Mururoa and Fangataufa Atolls.

Science.gov (United States)

Mulsow, S; Coquery, M; Dovlete, C; Gastaud, J; Ikeuchi, Y; Pham, M K; Povinec, P P

1999-09-30

In 1997 an expedition to Mururoa and Fangataufa Atolls was carried out to sample underground waters from cavity-chimneys and carbonate monitoring wells. The aim of this study was to determine the prevailing concentration and distribution status of radionuclides. Elemental analysis of interstitial waters was carried out in the water fraction as well as in particles collected at 11 underground monitoring wells. 238Pu, 239,240Pu, 241Am, 137Cs, 90Sr, 3H, 125Sb, 155Eu and 60Co were analyzed in both fractions by alpha-, beta- and gamma-spectrometry. Measurements showed that at 60% of the sites, pH and Eh seemed to be related to tidal cycles; in contrast HTO was constant during the sampling time. Interstitial waters from carbonates and transition zones shared similar chemical composition that were not different from that of the surrounding seawater. Waters collected from basalt cavities left after nuclear tests, (Aristee and Ceto) have a different chemical signature characterized by a deficiency in Mg, K and SO4 as well as enrichment in Sr, Si, Al and Cl compared to the rest of the stations. Radionuclide concentrations present in both, water and particulate fractions, were significantly higher at Ceto and Aristee than at any other monitoring wells, except for Fuseau and Mitre monitoring wells (Fangataufa) where values similar to Ceto were found (e.g. 239,240Pu: > 20 mBq g-1). Considering that Pu isotopes showed high Kd values compared to non-sorbing radionuclides such as 3H, 90Sr and 137Cs it is very unlikely that migration from cavities to monitoring wells accounts for the concentration of Pu isotopes and Am at Fuseau 30 and Mitre 27. Perhaps the contact of lagoon waters with the well before sealing could be a possible source of the transuranics found at these sites. The 238Pu/239,240Pu ratios measured in the particles were similar to that of the lagoon (0.38), thus supporting this hypothesis. The fact that transuranics were found only in the particle fraction, in the

The monitoring of radioactivity in the environment

International Nuclear Information System (INIS)

1986-01-01

35 separately indexed lectures are discussed of this conference. The contents of the individual contributions cover the following areas: 1) Monitoring networks and guidelines; 2) Monitoring equipment and methods; 3) Development of models for radionuclide migration, and 4) Individual determination and analysis of radionuclides relevant to the environment. (PW) [de

Radionuclide toxicity

International Nuclear Information System (INIS)

Galle, P.

1982-01-01

The aim of this symposium was to review the radionuclide toxicity problems. Five topics were discussed: (1) natural and artificial radionuclides (origin, presence or emission in the environment, human irradiation); (2) environmental behaviour of radionuclides and transfer to man; (3) metabolism and toxicity of radionuclides (radioiodine, strontium, rare gas released from nuclear power plants, ruthenium-activation metals, rare earths, tritium, carbon 14, plutonium, americium, curium and einsteinium, neptunium, californium, uranium) cancerogenous effects of radon 222 and of its danghter products; (4) comparison of the hazards of various types of energy; (5) human epidemiology of radionuclide toxicity (bone cancer induction by radium, lung cancer induction by radon daughter products, liver cancer and leukaemia following the use of Thorotrast, thyroid cancer; other site of cancer induction by radionuclides) [fr

Considerations of selection suggested for internal contamination monitoring in Cuba

International Nuclear Information System (INIS)

Cruz S, R.; Lopez B, G.; Placeres V, C.; Arado L, J.; Jova S, L.

1996-01-01

A method for calculating effective risk of radionuclide intake and hypothetical annual dose that will receive a person who works with unsealed sources is proposed. Calculated committed dose equivalent and metabolic characteristic of radionuclides permit to select the type of monitoring 'in vivo' and/or 'in vitro'. The method was applied to 396 workers from 28 institutions, where 20 radionuclides in 124 different products for 266 applications are used. From this study 62% of the workers had to be monitored for internal contamination, meanly by 'in vitro' monitoring. In practices of Nuclear Medicine and other medical uses 75% of the workers had to be monitored. These results permitted to corroborate the criteria for internal contamination monitoring program carried out by Center for Hygiene and Radiation Protection and permitted to identify needs for control of radionuclides intakes. (authors).5 refs., 3 figs

Removal of natural radionuclides from drinking water from private wells in Finland

International Nuclear Information System (INIS)

Huikuri, Pia; Salonen, Laina; Turtiainen, Tuukka

1999-01-01

Removal of natural radionuclides is often necessary in Finland when household water is taken from a drilled well. Removal of radionuclides by various methods from Finnish groundwaters were studied in a EU-research project, TENAWA. The results indicated that radon can be removed very efficiently (up to 99%) by applying aeration or granular activated carbon (GAC) filtration. Uranium and radium were also removed (over 94%) by using strong base anion (SBA) and strong acid cation (SAC) resins. The capability of reverse osmosis (RO) equipment to remove radionuclides was over 90% for uranium, radium and polonium. The water quality analyses indicated that water quality remained mostly good during the water treatment. (au)

Pacific Northwest Laboratory facilities radionuclide inventory assessment CY 1992-1993

International Nuclear Information System (INIS)

Sula, M.J.; Jette, S.J.

1994-09-01

Assessments for evaluating compliance with airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAPs - U.S. Code of Federal Regulations, Title 40 Part 61, Subparts H and I) were performed for 33 buildings at the U.S. Department of Energy's (DOE) Pacific Northwest Laboratory on the Hanford Site, and for five buildings owned and operated by Battelle, Pacific Northwest Laboratories in Richland, Washington. The assessments were performed using building radionuclide inventory data obtained in 1992 and 1993. Results of the assessments are summarized in Table S.1 for DOE-PNL buildings and in Table S.2 for Battelle-owned buildings. Based on the radionuclide inventory assessments, four DOE-PNL buildings (one with two emission points) require continuous sampling for radionuclides per 40 CFR 61. None of the Battelle-owned buildings require continuous emission sampling

A portable ECG monitoring device with Bluetooth and Holter capabilities for telemedicine applications.

Science.gov (United States)

Lucani, Daniel; Cataldo, Giancarlos; Cruz, Julio; Villegas, Guillermo; Wong, Sara

2006-01-01

A prototype of a portable ECG-monitoring device has been developed for clinical and non-clinical environments as part of a telemedicine system to provide remote and continuous surveillance of patients. The device can acquire, store and/or transmit ECG signals to computer-based platforms or specially configured access points (AP) with Intranet/Internet capabilities in order to reach remote monitoring stations. Acquired data can be stored in a flash memory card in FAT16 format for later recovery, or transmitted via Bluetooth or USB to a local station or AP. This data acquisition module (DAM) operates in two modes: Holter and on-line transmission.

Development of a portable equipment for identification of radionuclides

International Nuclear Information System (INIS)

Farias, Marcos Santana; Carvalho, Paulo Victor R. de; Nedjah, Nadia; Mourelle, Luiza de Macedo

2014-01-01

The rapid and automatic identification of radionuclides present in a radioactive sample detected in the field, is information that helps in decision making. In areas of high traffic of people and materials, such as ports and airports as well as at major events, radiation monitoring, together with the identification of the radionuclide, it is advisable within protective standards to the public. The correct identification of radionuclides depends on the ability to determine whether specific peaks energy sources are present in the spectrum of gamma radiation sources. Radionuclides can be identified by these energy characteristics in the sense that the energy value associated with these peaks in the spectrum corresponds to the radiation sources present in the sample. There are many methods that can be used for automatic identification of radionuclides. Most of them are based on software algorithms for the detection of peaks in the energy spectrum. Processing time of these tasks can be very long for applications requiring quick responses, as in equipment portable. A dedicated digital hardware offers better performance for tasks with high processing demand like this. This work shows the development of a handle Portable radionuclides based on a digital hardware solution using a FPGA (Field Programmable Gate Array) for implementing a clustering algorithm for the detection of energy peaks. (author)

On-line detection of key radionuclides for fuel-rod failure in a pressurized water reactor.

Science.gov (United States)

Qin, Guoxiu; Chen, Xilin; Guo, Xiaoqing; Ni, Ning

2016-08-01

For early on-line detection of fuel rod failure, the key radionuclides useful in monitoring must leak easily from failing rods. Yield, half-life, and mass share of fission products that enter the primary coolant also need to be considered in on-line analyses. From all the nuclides that enter the primary coolant during fuel-rod failure, (135)Xe and (88)Kr were ultimately chosen as crucial for on-line monitoring of fuel-rod failure. A monitoring system for fuel-rod failure detection for pressurized water reactor (PWR) based on the LaBr3(Ce) detector was assembled and tested. The samples of coolant from the PWR were measured using the system as well as a HPGe γ-ray spectrometer. A comparison showed the method was feasible. Finally, the γ-ray spectra of primary coolant were measured under normal operations and during fuel-rod failure. The two peaks of (135)Xe (249.8keV) and (88)Kr (2392.1keV) were visible, confirming that the method is capable of monitoring fuel-rod failure on-line. Copyright © 2016 Elsevier Ltd. All rights reserved.

FTRANS, Radionuclide Flow in Groundwater and Fractured Rock

International Nuclear Information System (INIS)

Huyakorn, P.; Golis, M.J.

1987-01-01

1 - Description of program or function: FTRANS (Fractured flow and Transport of Radionuclides) is a two-dimensional finite-element code designed to simulate ground-water flow and transport of radioactive nuclides in a fractured porous return medium. FTRANS takes into account fluid interactions between the fractures and porous matrix blocks, advective-dispersive transport in the fractures and diffusion in the porous matrix blocks, and chain reactions of radionuclide components. It has the capability to model the fractured system using either the dual-porosity or the discrete- fracture modeling approach or a combination of both. FTRANS can be used to perform two-dimensional near-field or far-field predictive analyses of ground-water flow and to perform risk assessments of radionuclide transport from nuclear waste repository subsystems to the biosphere. 2 - Restrictions on the complexity of the problem: Although FTRANS does cannot account for deformation processes which can affect the flow capacity and velocity field

Monitoring of radionuclides in the terrestrial and aquatic environment of the nuclear power plant at Barsebaeck (Sweden) for the period 1984-1991

International Nuclear Information System (INIS)

Neumann, G.

1994-01-01

This report summarizes the main results from the environment monitoring sampling for the years 1984-1991 around the nuclear power plant at Barsebaeck, southern Sweden. The sampling are required according to the environment monitoring programme which has been decided upon by the Swedish Radiation Protection Inst. Terrestrial samples include cultivated plants, natural vegetation, milk, some other foods of animal origin and sludge. From the aquatic environment, samples of sea water, bottom sediments, benthic fauna, algae and fish are collected. This report accounts for all samples that have been measured during the period 1984-1991. The diagrams also include data from the years 1981-1983. The annual discharge to air and to water resulted during the years 1984-1991 in a dose commitment to a critical group which generally amounted to less than 2 micro-sievert (which equals 2 per cent of the maximum permitted, viz. one Norm release). The annual radiation dose outside the power plant has always been found less than 0.2% of that from the background radiation. Outside the plant, only very small quantities of radionuclides were detected which could be related to its operation. Radionuclides from the power plant have not with certainty been detected in cultivated plants, milk, and meat produced in the vicinity of the power plant. On the other hand small quantities of Co-60 and Zn-65 from the plant were detected in, for instance, some samples of eel and cod from stations close to the plant. In 1985 and 1989, special sediment sampling were carried out at 12 stations off Barsebaeck. One aim was to investigate whether any accumulation of radionuclides from Barsebaeck in bottom sediments had occurred during the period. There was no clear evidence of any such accumulation. 15 refs, 22 figs, 16 tabs

Pollen as indicator of radionuclide pollution

International Nuclear Information System (INIS)

Kirkham, M.B.; Corey, J.C.

1977-01-01

To assess hazards of radioactivity in the environment, agricultural scientists must identify plant and animal species which can be used as biological indicators of radionuclide contamination. In this experiments, the pollen-bee-honey system was chosen to study movement of radioactive elements in the plant-animal-man food chain. Pollen, bees, and honey were collected from different locations at a nuclear facility in South Carolina. They were analyzed for nine radionuclides and 22 stable elements. The results showed that pollen is a more sensitive indicator of pollution than bees or honey. If pollen-monitoring shows that an area has become polluted, hives and other sources of human and animal food should not be placed in the region until it is no longer contaminated. (author)

Methods of separating short half-life radionuclides from a mixture of radionuclides

International Nuclear Information System (INIS)

Bray, L.A.; Ryan, J.L.

1998-01-01

The present invention is a method of obtaining a radionuclide product selected from the group consisting of 223 Ra and 225 Ac, from a radionuclide ''cow'' of 227 Ac or 229 Th respectively. The method comprises the steps of (a) permitting ingrowth of at least one radionuclide daughter from said radionuclide ''cow'' forming an ingrown mixture; (b) insuring that the ingrown mixture is a nitric acid ingrown mixture; (c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the ''cow'' from at least one radionuclide daughter; (d) insuring that the at least one radionuclide daughter contains the radionuclide product; (e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and (f) recycling the at least one radionuclide daughter by adding it to the ''cow''. In one embodiment the radionuclide ''cow'' is the 227 Ac, the at least one daughter radionuclide is a 227 Th and the product radionuclide is the 223 Ra and the first nitrate form ion exchange column passes the 227 Ac and retains the 227 Th. In another embodiment the radionuclide ''cow'' is the 229 Th, the at least one daughter radionuclide is a 225 Ra and said product radionuclide is the 225 Ac and the 225 Ac and nitrate form ion exchange column retains the 229 Th and passes the 225 Ra/Ac. 8 figs

Effectiveness of direct and indirect radionuclide cystography in detecting vesicoureteral reflux

International Nuclear Information System (INIS)

Conway, J.J.; Kruglik, G.D.

1976-01-01

A modified of the direct radionuclide cystography technique to include filling, voiding, and postvoiding phases of the examination permitted a simulated comparison between direct and indirect radionuclide cystography. One hundred thirty-seven examples of reflux were documented with this technique. Of these, 96 instances of reflux (70 percent) were recorded during two or more phases and thus would have been detected by either technique. Twenty-nine examples (21 percent) were only detected during filling and thus would have been missed by the indirect radionuclide technique and by some roentgenographic techniques. Only 12 examples (9 percent) were detected during the voiding phase only. The modified direct method of radionuclide cystography, which continuously monitors the urinary tracts during filling, voiding, and postvoiding, is offered as the best current technique for assessing visicoureteral reflus

Improved radionuclide method for the diagnosis of gastroesophageal reflux and aspiration in children (milk scan)

International Nuclear Information System (INIS)

Heyman, S.; Kirkpatrick, J.A.; Winter, H.S.; Treves, S.

1979-01-01

A radionuclide study using technetium-99m-labelled milk feeding is described for the detection of gastroesophageal reflux and aspiration in children. A comparison of findings in 39 patients referred for both radiographic and radionuclide studies showed that barium studies were positive in 25.6% and radionuclide studies in 59% of cases, reflecting the sensitivity of the radionuclide technique. This technique is also physiological and allows prolonged patient monitoring. It is simple to perform and should prove useful in the evaluation of patients suspected of having gastroesophageal reflux and aspiration

Methods of separating short half-life radionuclides from a mixture of radionuclides

Science.gov (United States)

Bray, Lane A.; Ryan, Jack L.

1998-01-01

The present invention is a method of obtaining a radionuclide product selected from the group consisting of .sup.223 Ra and .sup.225 Ac, from a radionuclide "cow" of .sup.227 Ac or .sup.229 Th respectively. The method comprises the steps of a) permitting ingrowth of at least one radionuclide daughter from said radionuclide "cow" forming an ingrown mixture; b) insuring that the ingrown mixture is a nitric acid ingrown mixture; c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the "cow" from at least one radionuclide daughter; d) insuring that the at least one radionuclide daughter contains the radionuclide product; e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and f) recycling the at least one radionuclide daughter by adding it to the "cow". In one embodiment the radionuclide "cow" is the .sup.227 Ac, the at least one daughter radionuclide is a .sup.227 Th and the product radionuclide is the .sup.223 Ra and the first nitrate form ion exchange column passes the .sup.227 Ac and retains the .sup.227 Th. In another embodiment the radionuclide "cow"is the .sup.229 Th, the at least one daughter radionuclide is a .sup.225 Ra and said product radionuclide is the .sup.225 Ac and the .sup.225 Ac and nitrate form ion exchange column retains the .sup.229 Th and passes the .sup.225 Ra/Ac.

Capability of Raman lidar for monitoring the variation of atmospheric CO2 profile

International Nuclear Information System (INIS)

Zhao Peitao; Hu Shunxing; Su Jia; Cao Kaifa; Hu Huanling; Zhang Yinchao; Wang Lian; Zhao Yuefeng

2008-01-01

Lidar (Light detection and ranging) has special capabilities for remote sensing of many different behaviours of the atmosphere. One of the techniques which show a great deal of promise for several applications is Raman scattering. The detecting capability, including maximum operation range and minimum detectable gas concentration is one of the most significant parameters for lidar remote sensing of pollutants. In this paper, based on the new method for evaluating the capabilities of a Raman lidar system, we present an evaluation of detecting capability of Raman lidar for monitoring atmospheric CO 2 in Hefei. Numerical simulations about the influence of atmospheric conditions on lidar detecting capability were carried out, and a conclusion can be drawn that the maximum difference of the operation ranges caused by the weather conditions alone can reach about 0.4 to 0.5km with a measuring precision within 30ppmv. The range of minimum detectable concentration caused by the weather conditions alone can reach about 20 to 35 ppmv in vertical direction for 20000 shots at a distance of 1 km on the assumption that other parameters are kept constant. The other corresponding parameters under different conditions are also given. The capability of Raman lidar operated in vertical direction was found to be superior to that operated in horizontal direction. During practical measurement with the Raman lidar whose hardware components were fixed, aerosol scattering extinction effect would be a significant factor that influenced the capability of Raman lidar. This work may be a valuable reference for lidar system designing, measurement accuracy improving and data processing

Radionuclide distributions and migration mechanisms at shallow land burial sites

International Nuclear Information System (INIS)

Kirby, L.J.; Toste, A.P.; Thomas, C.W.; Rickard, W.H.; Nielson, H.L.; Campbell, R.M.; McShane, M.C.; Wilkerson, C.L.; Robertson, D.E.

1991-02-01

During the past several years, Pacific Northwest Laboratory (PNL) has conducted research at the Maxey Flats Disposal Site (MFDS) for the US Nuclear Regulatory Commission (NRC). This work has identified the spectrum of radionuclides present in the waste trenches, determined the processes that were occurring relative to degradation of radioactive material within the burial trenches, determined the chemical and physical characteristics of the trench leachates and the chemical forms of the leached radionuclides, determined the mobility of these radionuclides, investigated the subsurface and surface transport processes, determined the biological uptake by the native vegetation, developed strategies for environmental monitoring, and investigated other factors that influence the long-term fate of the radionuclide inventory at the disposal site. This report is a final summary of the research conducted by PNL and presents the results and discussions relative to the above investigative areas. 45 refs., 31 figs., 17 tabs

Present status and perspective of radiochemical analysis of radionuclides in Nordic countries

DEFF Research Database (Denmark)

Hou, Xiaolin; Olsson, Mattias; Togneri, Laura

2016-01-01

Radiochemical analysis plays a critical role in the determination of pure beta and alpha emitting radionuclides for environmental monitoring, radioecology, decommissioning, nuclear forensics and geological dating. A remarkable development on radiochemical analysis has been achieved in the past...... of radionuclides, especially in Nordic countries; some requirements from nuclear industries and research organizations, as well as perspectives on the development of radiochemical analysis are discussed....

Programmes and Systems for Source and Environmental Radiation Monitoring

International Nuclear Information System (INIS)

2010-01-01

The discharge of radionuclides to the atmosphere and aquatic environments is a legitimate practice in the nuclear and other industries, hospitals and research. Where appropriate, monitoring of the discharges and of relevant environmental media is an essential regulatory requirement in order to ensure appropriate radiation protection of the public. Such monitoring provides information on the actual amounts of radioactive material discharged and the radionuclide concentrations in the environment, and is needed to demonstrate compliance with authorized limits, to assess the radiation exposure of members of the public and to provide data to aid in the optimization of radiation protection. Uncontrolled releases of radionuclides to the atmosphere and aquatic environments may occur as a result of a nuclear or radiological accident. Again, monitoring at the source of the release and of the environment is necessary. In this case, monitoring is used both to assess the radiation exposure of members of the public and to determine the actions necessary for public protection, including longer term countermeasures. Source and environmental monitoring associated with the release of radionuclides to the environment is the subject of a number of IAEA Safety Standards, particularly IAEA Safety Standard RS-G-1.8 (Environmental and Source Monitoring for Purposes of Radiation Protection). This publication is intended to complement this Safety Guide and, by so doing, replaces Safety Series No. 41 (Objectives and Design of Environmental Monitoring Programmes for Radioactive Contaminants) and Safety Series No. 46 (Monitoring of Airborne and Liquid Radioactive Releases from Nuclear Facilities to the Environment). Like Safety Standard RS-G-1.8, this Safety Report deals with monitoring at the source and in the environment associated with authorized releases of radionuclides to the environment. It also deals with the general issues of emergency monitoring during and in the aftermath of an

The diffusion and deposition of the gaseous and solid alpha radionuclides/aerosols in air

International Nuclear Information System (INIS)

Danis, A.; Ciubotariu, M.; Oncescu, M.; Mocsy, I.

1999-01-01

The diffusion and deposition of gaseous and solids alpha radionuclides and aerosols in air are processes which implicate low element amounts and therefore their studies require the using of very accurate and sensitive analysis methods. The alpha track method meets these requirements. The used alpha radionuclides were: Rn-222, as gaseous radionuclide and its solid descendants genetically related as solid radionuclides and the descendants attached to different particles from air as alpha aerosols. All these radionuclides were obtained from a calibrated Ra-226 source. The source was included into an air tight device with a well known volume and used after 40 days when the Ra-226 and its alpha descendants were under radioactive equilibrium. The relative amount and activity of each decay product, at any duration, for any initial mass of Ra-226 parent radionuclide, were calculated using a programme for computation of the U-238 radioactive series gamma accumulation, UURASE, adapted for alpha accumulation as ALFAURASE programme. The radon, Rn-222, as well as the solid alpha radionuclides and aerosols were measured using a new alpha monitoring device with or without paper filter for solid radionuclides and aerosols stopping. The track detectors of CR-39 type were incorporated with these monitoring devices. In order to calibrate the CR-39 detectors, a radon intercomparison programme was established with the participation of the SSNTD group from the Institute of Nuclear Research ATOMKI, Debrecen, Hungary, Institute of Public Health, Cluj-Napoca and SSNTD research group from IFIN-HH. We have used for radon calibration a special experimental device and a Ra-226 source. Using an air tight diffusion and deposition device, coupled with the source device, the concentration of radon and solid alpha radionuclides and aerosols were determined using the alpha track method. The alpha monitoring devices were fixed vertically at different distances from the place of radon penetration into

Appraising city-scale pollution monitoring capabilities of multi-satellite datasets using portable pollutant monitors

Science.gov (United States)

Aliyu, Yahaya A.; Botai, Joel O.

2018-04-01

The retrieval characteristics for a city-scale satellite experiment was explored over a Nigerian city. The study evaluated carbon monoxide and aerosol contents in the city atmosphere. We utilized the MSA Altair 5× gas detector and CW-HAT200 particulate counter to investigate the city-scale monitoring capabilities of satellite pollution observing instruments; atmospheric infrared sounder (AIRS), measurement of pollution in the troposphere (MOPITT), moderate resolution imaging spectroradiometer (MODIS), multi-angle imaging spectroradiometer (MISR) and ozone monitoring instrument (OMI). To achieve this, we employed the Kriging interpolation technique to collocate the satellite pollutant estimations over 19 ground sample sites for the period of 2015-2016. The portable pollutant devices were validated using the WHO air filter sampling model. To determine the city-scale performance of the satellite datasets, performance indicators: correlation coefficient, model efficiency, reliability index and root mean square error, were adopted as measures. The comparative analysis revealed that MOPITT carbon monoxide (CO) and MODIS aerosol optical depth (AOD) estimates are the appropriate satellite measurements for ground equivalents in Zaria, Nigeria. Our findings were within the acceptable limits of similar studies that utilized reference stations. In conclusion, this study offers direction to Nigeria's air quality policy organizers about available alternative air pollution measurements for mitigating air quality effects within its limited resource environment.

Radionuclide metrology: traceability and response to a radiological accident

Energy Technology Data Exchange (ETDEWEB)

Tauhata, L.; Cruz, P.A.L. da; Silva, C.J. da; Delgado, J.U.; Oliveira, A.E. de; Oliveira, E.M. de; Poledna, R.; Loureiro, J. dos S.; Ferreira Filho, A.L.; Silva, R.L. da; Filho, O. L.T.; Santos, A.R.L. dos; Veras, E.V. de; Rangel, J. de A.; Quadros, A.L.L.; Araújo, M.T.F. de; Souza, P.S. de; Ruzzarim, A.; Conceição, D.A. da; Iwahara, A., E-mail: palcruz@ird.gov.br [Instituto de Radioproteção e Dosimetria (LNMRI/IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. Nacional de Metrologia das Radiações Ionizantes

2017-07-01

In the case of a radiological accident, there are characteristic phases: discovery and initial assistance with first aid; the triage and monitoring of the affected population; the release of the affected people; forward the victims to medical care; as well as the preparation of the report on the accident. In addition, studies and associated researches performed in the later period. Monitors, dosimeters and measuring systems should be calibrated by contaminating radionuclide standards. The radioactive sources used must be metrologically reliable. In Brazil, this function is performed by LNMRI/IRD/CNEN, designated by INMETRO, which Radionuclide Metrology Laboratory is responsible for the standardization and supply of radioactive sources in diverse geometries and matrices. This laboratory has a stock of radionuclide solutions with controlled environmental variables for the preparation of sources, which are calibrated and standardized by mean of primary and secondary systems. It is also responsible for the dissemination of standards and, in order to establish the metrological traceability of national standards, participates in international key-comparisons promoted by BIPM and regional metrology organizations. Internally, it promotes the National Comparison Programs for laboratories for the analysis of environmental samples and the traceability for producing centers of radiopharmaceuticals and Nuclear Medicine Services in the country. The paper presents the demand for {sup 137}Cs related to the radioactive accident in Goiania/Brazil and the significant results for the main radionuclides standardized by the Radionuclide Metrology Laboratory for international key-comparisons and national comparisons to provide metrological traceability. With the obtained results, the LNMRI of Brazil integrates the international metrology BIPM network and fulfills its function of supplying, with about a hundred of radioactive standards, the country's needs in different applications

Radionuclide metrology: traceability and response to a radiological accident

International Nuclear Information System (INIS)

Tauhata, L.; Cruz, P.A.L. da; Silva, C.J. da; Delgado, J.U.; Oliveira, A.E. de; Oliveira, E.M. de; Poledna, R.; Loureiro, J. dos S.; Ferreira Filho, A.L.; Silva, R.L. da; Filho, O. L.T.; Santos, A.R.L. dos; Veras, E.V. de; Rangel, J. de A.; Quadros, A.L.L.; Araújo, M.T.F. de; Souza, P.S. de; Ruzzarim, A.; Conceição, D.A. da; Iwahara, A.

2017-01-01

In the case of a radiological accident, there are characteristic phases: discovery and initial assistance with first aid; the triage and monitoring of the affected population; the release of the affected people; forward the victims to medical care; as well as the preparation of the report on the accident. In addition, studies and associated researches performed in the later period. Monitors, dosimeters and measuring systems should be calibrated by contaminating radionuclide standards. The radioactive sources used must be metrologically reliable. In Brazil, this function is performed by LNMRI/IRD/CNEN, designated by INMETRO, which Radionuclide Metrology Laboratory is responsible for the standardization and supply of radioactive sources in diverse geometries and matrices. This laboratory has a stock of radionuclide solutions with controlled environmental variables for the preparation of sources, which are calibrated and standardized by mean of primary and secondary systems. It is also responsible for the dissemination of standards and, in order to establish the metrological traceability of national standards, participates in international key-comparisons promoted by BIPM and regional metrology organizations. Internally, it promotes the National Comparison Programs for laboratories for the analysis of environmental samples and the traceability for producing centers of radiopharmaceuticals and Nuclear Medicine Services in the country. The paper presents the demand for 137 Cs related to the radioactive accident in Goiania/Brazil and the significant results for the main radionuclides standardized by the Radionuclide Metrology Laboratory for international key-comparisons and national comparisons to provide metrological traceability. With the obtained results, the LNMRI of Brazil integrates the international metrology BIPM network and fulfills its function of supplying, with about a hundred of radioactive standards, the country's needs in different applications

Sensor Alerting Capability

Science.gov (United States)

Henriksson, Jakob; Bermudez, Luis; Satapathy, Goutam

2013-04-01

There is a large amount of sensor data generated today by various sensors, from in-situ buoys to mobile underwater gliders. Providing sensor data to the users through standardized services, language and data model is the promise of OGC's Sensor Web Enablement (SWE) initiative. As the amount of data grows it is becoming difficult for data providers, planners and managers to ensure reliability of data and services and to monitor critical data changes. Intelligent Automation Inc. (IAI) is developing a net-centric alerting capability to address these issues. The capability is built on Sensor Observation Services (SOSs), which is used to collect and monitor sensor data. The alerts can be configured at the service level and at the sensor data level. For example it can alert for irregular data delivery events or a geo-temporal statistic of sensor data crossing a preset threshold. The capability provides multiple delivery mechanisms and protocols, including traditional techniques such as email and RSS. With this capability decision makers can monitor their assets and data streams, correct failures or be alerted about a coming phenomena.

Hydrologic transport of radionuclides from low-level waste burial grounds

International Nuclear Information System (INIS)

Duguid, J.O.

1979-01-01

The physical characteristics of the virgin site and of the disturbed site after burial drastically affect the transport of radionuclides from buried waste. The disturbance of the land surface during the waste burial operation causes changes in the local ground-water regimen. These changes can increase the water table elevation and cause the occurrence of perched water in burial trenches. The combination of these changes may lead to submersion of the waste and to increased radionuclide transport from the burial site in both surface and groundwater. Factors such as ion exchange can retard or in some cases, with competing ions, can also mobilize radionuclides and increase their discharge into ground and surface water. Because of complexing agents (organics) contained in the waste, increased mobility of some radionuclides can be expected. The chemical form of radionuclides in the water, the ground-water quality, and the chemistry of the geologic formation in which the waste is buried all influence the movement of radionuclides in the hydrologic system. For the assessment of the environmental impact of low-level waste burial, models capable of simulating both the chemical and the physical factors that affect hydrologic transport must be available. Several models for conducting such simulation are presently available. However, the input parameters used in these models are highly variable; and the accuracy of parameter measurement must be considered in evaluating the reliability of simulated results

The IMS radionuclide network of the CTBT

International Nuclear Information System (INIS)

Medici, Fausto

2001-01-01

A world-wide radionuclide network consisting of 80 stations is under establishment in the framework of the comprehensive nuclear test-ban treaty (CTBT). These monitoring stations are essential for the verification regime of the treaty and they will be able to monitor the airborne particulate as well as xenon isotopes that are produced by nuclear tests. The equipment, the operation and the locations of these stations are chosen in such a way to provide a very high confidence of the compliance of the treaty.

Methods and systems for detection of radionuclides

Science.gov (United States)

Coates, Jr., John T.; DeVol, Timothy A.

2010-05-25

Disclosed are materials and systems useful in determining the existence of radionuclides in an aqueous sample. The materials provide the dual function of both extraction and scintillation to the systems. The systems can be both portable and simple to use, and as such can beneficially be utilized to determine presence and optionally concentration of radionuclide contamination in an aqueous sample at any desired location and according to a relatively simple process without the necessity of complicated sample handling techniques. The disclosed systems include a one-step process, providing simultaneous extraction and detection capability, and a two-step process, providing a first extraction step that can be carried out in a remote field location, followed by a second detection step that can be carried out in a different location.

Operators guide: Atmospheric Release Advisory Capability (ARAC) site facility

International Nuclear Information System (INIS)

Lawver, B.S.

1977-01-01

In this report capabilities and services are described for the Atmospheric Release Advisory Capability (ARAC). The ARAC site system and its operating procedures and interactions with the ARAC central facility located at LLL is outlined. ARAC is designed to help officials at designated ERDA sites and other locations in estimating the effects of atmospheric releases of radionuclides or other hazardous materials by issuing real-time advisories to guide them in their planning

Operators guide: Atmospheric Release Advisory Capability (ARAC) site facility

International Nuclear Information System (INIS)

Cassaro, E.; Lomonaco, L.

1979-01-01

The Atmospheric Release Advisory Capability (ARAC) is designed to help officials at designated DOE sites and other locations in estimating the effects of atmospheric releases of radionuclides or other hazardous materials by issuing real-time advisories to guide them in their planning. This report outlines the capabilities and sources of ARAC, and in more detail describes an ARAC Site Facility, its operating procedures and interactions with the ARAC Central Facility (ACF) located at LLL

Ecological processes in the cycling of radionuclides within arctic ecosystems

International Nuclear Information System (INIS)

Hanson, W.C.

1986-01-01

Worldwide fallout radionuclides in arctic ecosystems was investigated ecologically by circumpolar nations during 1959-80. Several of the radionuclides are isotopes of elements which currently contribute to arctic haze; they thus serve as effective tracers of biogeochemical processes. Investigations demonstrated the effective concentration of several radionuclides, particularly strontium-90 (an alkaline earth metal) and cesium-137 (a light alkali metal) which are chemical analogs of calcium and potassium, two very important stable elements in biotic systems. Transfer of 137 Cs through the lichen-cariboureindeer-man food chain characteristic of circumpolar nations, resulted in body burdens in Inuit that were 20 to 200 times greater than those in human populations of temperature latitudes. Radiation exposures from 90 Sr, 137 Cs and other natural and worldwide fallout radionuclides, were two to three times greater than for most other world populations. These results demonstrate the concentration capabilities of arctic ecosystems for several groups of chemical elements that have counterparts in arctic haze. These elements, therefore, provide the basis for considering the ecological implications of current situations

Erosion of atmospherically deposited radionuclides as affected by soil disaggregation mechanisms

International Nuclear Information System (INIS)

Claval, D.; Garcia-Sanchez, L.; Real, J.; Rouxel, R.; Mauger, S.; Sellier, L.

2004-01-01

The interactions of soil disaggregation with radionuclide erosion were studied under controlled conditions in the laboratory on samples from a loamy silty-sandy soil. The fate of 134 Cs and 85 Sr was monitored on soil aggregates and on small plots, with time resolution ranging from minutes to hours after contamination. Analytical experiments reproducing disaggregation mechanisms on aggregates showed that disaggregation controls both erosion and sorption. Compared to differential swelling, air explosion mobilized the most by producing finer particles and increasing five-fold sorption. For all the mechanisms studied, a significant part of the contamination was still unsorbed on the aggregates after an hour. Global experiments on contaminated sloping plots submitted to artificial rainfalls showed radionuclide erosion fluctuations and their origin. Wet radionuclide deposition increased short-term erosion by 50% compared to dry deposition. A developed soil crust when contaminated decreased radionuclide erosion by a factor 2 compared to other initial soil states. These erosion fluctuations were more significant for 134 Cs than 85 Sr, known to have better affinity to soil matrix. These findings confirm the role of disaggregation on radionuclide erosion. Our data support a conceptual model of radionuclide erosion at the small plot scale in two steps: (1) radionuclide non-equilibrium sorption on mobile particles, resulting from simultaneous sorption and disaggregation during wet deposition and (2) later radionuclide transport by runoff with suspended matter

Radionuclide trap

International Nuclear Information System (INIS)

McGuire, J.C.

1978-01-01

The deposition of radionuclides manganese-54, cobalt-58 and cobalt-60 from liquid sodium coolant is controlled by providing surfaces of nickel or high nickel alloys to extract the radionuclides from the liquid sodium, and by providing surfaces of tungsten, molybdenum or tantalum to prevent or retard radionuclide deposition

Naturally occurring radionuclides in pasture soil, feed ingredients and milk of dairy cattle

Energy Technology Data Exchange (ETDEWEB)

Turtiainen, T.; Kostiainen, E.; Solatie, D. [STUK-Radiation and Nuclear Safety Authority (Finland)

2014-07-01

Naturally occurring radionuclides are generally considered being respective part of the environment and hence no statutory monitoring of their levels are required in food products. Therefore, limited data are available on the naturally occurring radionuclides in food. Dairy products constitute a significant portion of Finnish diet (400-500 g/d) and hence it is reasonable to study radionuclide levels in milk in more detail. Contrary to caesium, strontium and iodine, few transfer coefficients are available in the literature for naturally occurring radionuclide transfer to cow's milk. The renaissance of mining industry in Finland has raised a question among the public about the baseline values of naturally occurring radionuclides in Finnish agricultural products. The objective of this study was to investigate naturally occurring radionuclides in the components of dairy cattle diet and milk and calculate their transfer to milk. This information is needed for regulating the permitted discharges to the environment and for setting up monitoring programs if any unplanned discharges are released. In modern dairy farming, cattle are fed a precise diet in order to maximize milk production and quality and to achieve cost-effectiveness. Therefore, several different components are found in dairy cattle's diet and pasture grass concentrations are not sufficient for calculating radionuclide transfer to cow's milk. In this study, we carried out comprehensive sampling at four dairy farms each representing different areas of natural radiation background. The pasture soils were characterized and measured for natural radioactivity. Samples were taken from cattle's total diet (including e.g. pasture grass, water, silage, mineral forage) and milk. Document available in abstract form only. (authors)

Emission, transport, deposition, and re-suspension of radionuclides from Fukushima Dai-ichi Nuclear Power Plant in the atmosphere - Overview of 2-year investigations in Japan

Science.gov (United States)

Kita, Kazuyuki; Igarashi, Yasuhiro; Yoshida, Naohiro; Nakajima, Teruyuki

2013-04-01

Following a huge earthquake and tsunami in Eastern Japan on 11 March, 2011, the accident in Fukushima Dai-ichi Nuclear Power Plant (FDNPP) occurred to emit a large amount of artificial radionuclides to the environment. Soon after the FDNPP accident, many Japanese researchers, as well as researchers in other countries, started monitoring radionuclides in various environmental fields and/or model calculations to understand extent and magnitude of radioactive pollution. In this presentation, we overview these activities for the atmospheric radionuclides in Japan as followings: 1. Investigations to evaluate radionuclide emissions by explosions at FNDPP in March 2011 and to estimate the respiration dose of the radiation at this stage. 2. Investigations to evaluate atmospheric transport and deposition processes of atmospheric radionuclide to determine the extent of radionuclide pollution. -- Based on results of the regular and urgent monitoring results, as well as the mapping of the distribution of radionuclide s accumulated by the deposition to the ground, restoration of their time-dependent emission rates has been tried, and processes determining atmospheric concentration and deposition to the ground have been investigated by using the model calculations. 3. Monitoring of the atmospheric concentrations of radionuclide after the initial, surge phase of FNDPP accident. 4. Investigations to evaluate re-suspension of radionuclide from the ground, including the soil and the vegetation. -- Intensive monitoring of the atmospheric concentrations and deposition amount of radionuclide after the initial, surge phase of the accident enable us to evaluate emission history from FNDPP, atmospheric transport and deposition processes, chemical and physical characteristics of atmospheric radionuclide especially of radio cesium, and re-suspension processes which has become dominant process to supply radio cesium to the atmosphere recently.

U.S. DOE 2004 LANL Radionuclide Air Emissions

International Nuclear Information System (INIS)

K.W. Jacobson

2005-01-01

Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2004

Evaluation of a gamma monitor for survey of waste for shallow land burial

International Nuclear Information System (INIS)

Hoy, J.E.

1978-12-01

During an 8-month evaluation of the Gamma Waste Monitor, 54 reactor-area scrap casks and 8 shipments from the separations areas containing fission product activities were measured. It was concluded that a more accurate and detailed record of radionuclide burials can be obtained by using this monitor than by present methods of estimation. The monitor will significantly improve records and will provide a more reliable data base for evaluating long-term effects on the environment. Although the monitor can directly detect only gamma-emitting radionuclides, a method is proposed in this report for estimating the total radionuclide distribution by association with radionuclides that are detected. The monitor cannot assay transuranic waste and tritium. In many cases where the radionuclide emits two gamma rays of different energy, corrections for attenuation at other photon energies can be empirically derived from the spectrum. Complete details are included in the Appendix for operating the facility. Experimental data gathered during the evaluation period are contained in the body of this report

Dynamic modelling of radionuclide uptake by Fukushima coastal biota - Dynamic modelling of radionuclide uptake by marine biota: application to Fukushima assessment

Energy Technology Data Exchange (ETDEWEB)

Vives i Batlle, Jordi [Belgian Nuclear Research Centre, Boeretang 200, 2400 Mol (Belgium)

2014-07-01

Radiological assessments to non-human marine biota are usually carried out by assuming that the activity concentration in an organism is proportional to the activity concentration in an adjacent volume of water, via a concentration factor (CF). It is also assumed that radionuclides in the water are in isotopic equilibrium with the sediments via a sediment distribution coefficient (K{sub d}). These assumptions are not valid in accidental situations where the biota and the sediments react with a time delay to large variations of activity concentration in seawater. A simple dynamic model was developed to factorise the dynamics of radionuclide uptake and turnover in biota and sediments, as determined by a balance between the residence time of radionuclides in seawater/sediments and the biological half-life of elimination in the biota. The model calculates activity concentration of {sup 131}I, {sup 134}Cs, {sup 137}Cs and {sup 90}Sr in seabed sediment, fish, crustaceans, molluscs and macro-algae from surrounding activity concentrations in seawater, with which to derive internal and external dose rates. A central element of this new model is the inclusion of sediment processes in dynamic transfer modelling. The model is adapted to include depletion of radionuclides adsorbed onto suspended particulates (particle scavenging), molecular diffusion, pore water mixing and bioturbation (modelled effectively as a diffusive process) represented by a simple set of differential equations that is coupled with the biological uptake/turnover processes. In this way, the model is capable of reproducing activity concentration in sediment to give a more realistic calculation of the external dose to biota compared with the simpler approach based on CF and K{sub d} values used in previous assessments. The model is applied to the assessment of the radiological impact of the Fukushima accident on marine biota in the early phase of the accident. It is shown that previous assessment of the

Monitoring of Radionuclides in Ship Ballast Water Following the Fukushima Nuclear Accident

International Nuclear Information System (INIS)

Abdul Kadir Ishak; Wo, Y.M.; Muhamat Omar

2011-01-01

Ballast water is the waters taken into the ship compartment to provide stability. It is taken on board at the port before the voyage begins and discharged at the port of call (arrival) while loading cargoes. Ballast is primarily composed of water and is full of stones, sediment, and thousands of living species. The quantity of water taken depends on the size of the ship and it can reach up to 10,000 tonnes. As a well known fact, Daiichi nuclear plant in Fukushima had released radioactive contaminated water into its surrounding sea and being dispersed by currents and tides. Therefore, ships travel between Malaysia and Japan in particular those from the affected regions and travel to Malaysia without cargoes will have a risk of transporting back radioactive contaminated water from Japan and released it at local ports. Malaysian Marine Department with the cooperation of Malaysian Nuclear Agency have been analysing the concentrations of several radionuclides in the ship's ballast water and sediment. This is to ensure the effective dosage is safe to the crews and general public as well to fulfill the permissible limit of 1 mSv/yr gazetted by the authorities. It is also to monitor that the contaminated water is not discharged into our marine environment. (author)

Radionuclide cisternography

International Nuclear Information System (INIS)

Song, H.H.

1980-01-01

The purpose of this thesis is to show that radionuclide cisternography makes an essential contribution to the investigation of cerebrospinal fluid (CSF) dynamics, especially for the investigation of hydrocephalus. The technical details of radionuclide cisternography are discussed, followed by a description of the normal and abnormal radionuclide cisternograms. The dynamics of CFS by means of radionuclide cisternography were examined in 188 patients in whom some kind of hydrocephalus was suspected. This study included findings of anomalies associated with hydrocephalus in a number of cases, such as nasal liquorrhea, hygromas, leptomeningeal or porencephalic cysts. The investigation substantiates the value of radionuclide cisternography in the diagnosis of disturbances of CSF flow. The retrograde flow of radiopharmaceutical into the ventricular system (ventricular reflux) is an abnormal phenomenon indicating the presence of communicating hydrocephalus. (Auth.)

An experimental study on the application of radionuclide imaging in repair of the bone defect

Directory of Open Access Journals (Sweden)

Weimin Zhu

2011-08-01

Full Text Available The aim of our study was to validate the effect of radionuclide imaging in early monitoring of the bone’s reconstruction, the animal model of bone defect was made on the rabbits repaired with HA artificial bone. The ability of bone defect repair was evaluated by using radionuclide bone imaging at 2, 4, 8 and 12 weeks postoperatively. The results indicate that the experimental group stimulated more bone formation than that of the control group. The differences of the bone reconstruction ability were statistically significant (p<0.05. The nano-HA artificial has good bone conduction, and it can be used for the treatment of bone defects. Radionuclide imaging may be an effective and first choice method for the early monitoring of the bone’s reconstruction.

Proceedings of the 2011 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

International Nuclear Information System (INIS)

Wetovsky, Marvin A.; Patterson, Eileen F.; Sandoval, Marisa N.

2011-01-01

These proceedings contain papers prepared for the Monitoring Research Review 2011: Ground-Based Nuclear Explosion Monitoring Technologies, held 13-15 September, 2011 in Tucson, Arizona. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), National Science Foundation (NSF), and other invited sponsors. The scientific objectives of the research are to improve the United States' capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Proceedings of the 2011 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

Energy Technology Data Exchange (ETDEWEB)

Wetovsky, Marvin A. [Editor; Patterson, Eileen F. [Editor; Sandoval, Marisa N. [Editor

2011-09-13

These proceedings contain papers prepared for the Monitoring Research Review 2011: Ground-Based Nuclear Explosion Monitoring Technologies, held 13-15 September, 2011 in Tucson, Arizona. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), National Science Foundation (NSF), and other invited sponsors. The scientific objectives of the research are to improve the United States' capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Proceedings of the 30th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring

Energy Technology Data Exchange (ETDEWEB)

Wetovsky, Marv A [Los Alamos National Laboratory; Aguilar-chang, Julio [Los Alamos National Laboratory; Arrowsmith, Marie [Los Alamos National Laboratory; Arrowsmith, Stephen [Los Alamos National Laboratory; Baker, Diane [Los Alamos National Laboratory; Begnaud, Michael [Los Alamos National Laboratory; Harste, Hans [Los Alamos National Laboratory; Maceira, Monica [Los Alamos National Laboratory; Patton, Howard [Los Alamos National Laboratory; Phillips, Scott [Los Alamos National Laboratory; Randall, George [Los Alamos National Laboratory; Revelle, Douglas [Los Alamos National Laboratory; Rowe, Charlotte [Los Alamos National Laboratory; Stead, Richard [Los Alamos National Laboratory; Steck, Lee [Los Alamos National Laboratory; Whitaker, Rod [Los Alamos National Laboratory; Yang, Xiaoning [Los Alamos National Laboratory

2008-09-23

These proceedings contain papers prepared for the 30th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 23-25 September, 2008 in Portsmouth, Virginia. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States’ capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Proceedings of the 2010 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

Energy Technology Data Exchange (ETDEWEB)

Wetovsky, Marvin A [Editor; Patterson, Eileen F [Editor

2010-09-21

These proceedings contain papers prepared for the Monitoring Research Review 2010: Ground-Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2010 in Orlando, Florida,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, National Science Foundation (NSF), Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Proceedings of the 2009 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

Energy Technology Data Exchange (ETDEWEB)

Wetovsky, Marv A [Los Alamos National Laboratory; Aguilar - Chang, Julio [Los Alamos National Laboratory; Anderson, Dale [Los Alamos National Laboratory; Arrowsmith, Marie [Los Alamos National Laboratory; Arrowsmith, Stephen [Los Alamos National Laboratory; Baker, Diane [Los Alamos National Laboratory; Begnaud, Michael [Los Alamos National Laboratory; Harste, Hans [Los Alamos National Laboratory; Maceira, Monica [Los Alamos National Laboratory; Patton, Howard [Los Alamos National Laboratory; Phillips, Scott [Los Alamos National Laboratory; Randall, George [Los Alamos National Laboratory; Rowe, Charlotte [Los Alamos National Laboratory; Stead, Richard [Los Alamos National Laboratory; Steck, Lee [Los Alamos National Laboratory; Whitaker, Rod [Los Alamos National Laboratory; Yang, Xiaoning ( David ) [Los Alamos National Laboratory

2009-09-21

These proceedings contain papers prepared for the Monitoring Research Review 2009: Ground -Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2009 in Tucson, Arizona,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Test Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States’ capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Proceedings of the 2010 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

International Nuclear Information System (INIS)

Wetovsky, Marvin A.; Patterson, Eileen F.

2010-01-01

These proceedings contain papers prepared for the Monitoring Research Review 2010: Ground-Based Nuclear Explosion Monitoring Technologies, held 21-23 September, 2010 in Orlando, Florida,. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, National Science Foundation (NSF), Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Effects of culinary preparation on radionuclide levels in vegetable foodstuffs

Energy Technology Data Exchange (ETDEWEB)

Wilkins, B.T.; Bradley, E.J.; Dodd, N.J.

1987-01-01

Vegetables contaminated by fall-out from the Chernobyl nuclear reactor accident have been used to investigate how simple culinary methods can affect the levels of various radionuclides in the portion consumed by man. Only ..gamma.. ray emitting radionuclides were investigated. Those parts of vegetables normally considered inedible, for example coarse outer leaves, foliage or roots, can account for between 50% and 97% of the total radionuclide content. Washing of the edible parts of vegetables can reduce the levels still further, although the efficacy is dependent on both the radionuclide and the vegetable type. These normal domestic procedures can reduce intakes of recently deposited radionuclides on vegetables by about an order of magnitude. The results have implications for the scope of monitoring programmes that might follow any future accidental release. They also reinforce very strongly the requirement for measurements on edible parts rather than whole samples as a direct input to dose evaluation. These results further suggest that there is no need to revise the general assumptions made in accident consequence models regarding losses of activity between harvest and consumption. However, more rigorous assessments of dose should take account of vegetable type and probable means of preparation.

Radionuclides in coffee, cacao and chocolate in Serbia during 2006-2007

International Nuclear Information System (INIS)

Mraovic, T.; Jankovic-Mandic, Lj; Mraovic, T.)

2007-01-01

The object of this work was monitoring radioactivity in 88 products of coffee, cacao and chocolate in Serbia during 2006-2007. The each product contained legal criterion for radionuclide safety. (author) [sr

Hydrologic transport of radionuclides from low-level waste burial grounds

International Nuclear Information System (INIS)

Duguid, J.O.

1977-01-01

The physical characteristics of the virgin site and of the disturbed site after burial drastically affect the transport of radionuclides from buried waste. The disturbance of the land surface during the waste burial operation causes changes in the local ground-water regimen. These changes can increase the water table elevation and cause the occurrence of perched water in burial trenches. The combination of these changes may lead to submersion of the waste and to increased radionuclide transport from the burial site in both surface and ground water. Factors such as ion exchange can retard or in some cases, with competing ions, can also mobilize radionuclides and increase their discharge into ground and surface water. Because of complexing agents (organics) contained in the waste, increased mobility of some radionuclides can be expected. The chemical form of radionuclides in the water, the ground-water quality, and the chemistry of the geologic formation in which the waste is buried all influence the movement of radionuclides in the hydrologic system. For the assessment of the environmental impact of low-level waste burial, models capable of simulating both the chemical and the physical factors that affect hydrologic transport must be available. Several models for conducting such simulation are presently available. However,the input parameters used in these models are highly variable, and the accuracy of parameter measurement must be considered in evaluating the reliability of simulated results

Detection and localization capability of an urban seismic sinkhole monitoring network

Science.gov (United States)

Becker, Dirk; Dahm, Torsten; Schneider, Fabian

2017-04-01

Microseismic events linked to underground processes in sinkhole areas might serve as precursors to larger mass dislocation or rupture events which can cause felt ground shaking or even structural damage. To identify these weak and shallow events, a sensitive local seismic monitoring network is needed. In case of an urban environment the performance of local monitoring networks is severely compromised by the high anthropogenic noise level. We study the detection and localization capability of such a network, which is already partly installed in the urban area of the city of Hamburg, Germany, within the joint project SIMULTAN (http://www.gfz-potsdam.de/en/section/near-surface-geophysics/projects/simultan/). SIMULTAN aims to monitor a known sinkhole structure and gain a better understanding of the underlying processes. The current network consists of six surface stations installed in the basement of private houses and underground structures of a research facility (DESY - Deutsches Elektronen Synchrotron). During the started monitoring campaign since 2015, no microseismic events could be unambiguously attributed to the sinkholes. To estimate the detection and location capability of the network, we calculate synthetic waveforms based on the location and mechanism of former events in the area. These waveforms are combined with the recorded urban seismic noise at the station sites. As detection algorithms a simple STA/LTA trigger and a more sophisticated phase detector are used. While the STA/LTA detector delivers stable results and is able to detect events with a moment magnitude as low as 0.35 at a distance of 1.3km from the source even under the present high noise conditions the phase detector is more sensitive but also less stable. It should be stressed that due to the local near surface conditions of the wave propagation the detections are generally performed on S- or surface waves and not on P-waves, which have a significantly lower amplitude. Due to the often

Radionuclides concentration in foods in Peninsular Malaysia

International Nuclear Information System (INIS)

Zalina Laili; Muhamat Omar; Mohd Nahar Othman; Md Suhaimi Elias; Esther Philip, Mohd Zaidi Ibrahim; Faizal Azrin Abdul Razalim; Azmi Hassan

2006-01-01

The concentrations of natural radionuclides (U-238, Th-232, Ra-226, Ra-228 and K-40) and artificial radionuclides (Cs-137) in fresh, dried and cooked foodstuffs from 30 major towns in Peninsular Malaysia were determined by gamma spectrometry system and Instrumental Neutron Activation Analysis (INAA) technique. A total of 232 samples representing a typical Malaysian community diet were analysed. The results showed that most of the samples contained only natural radionuclides. The percentage of radionuclides detected in the samples were found about 2% for U-238, 9% for Th-232, 49% for Ra-226, 77% for Ra-228, 99% for K-40 and 15% for Cs-137. The radionuclide concentrations were in the ranges of <6.1 - 29.3, <2.0 - 55.8, <0.1 - 34.4, <0.1 - 41, <0.1- 2552.3 and < 0.1 - 6.6 Bq/Kg dry weight for U-238, Th-232, Ra-226, Ra-228 and K-40 and Cs-137 respectively. The study revealed that most of the foodstuffs did not contain U-238. Lentils were found to contain significant concentration of Th-232 (4 - 49 Bq/kg) and can be considered as thorium accumulators. The concentrations of Ra-226 and Ra-228 in leafy vegetables were higher than the fruit and root vegetables. These data can be used as a reference for future food radioactivity monitoring. As edible mushroom and fern had high concentrations of Cs-137, indicating their high ability to accumulate Cs-137, they could be used as indicator plants in the event of radioactive fall outs

Three-dimensional simulation of radionuclides dispersion in the stratified estuaries

International Nuclear Information System (INIS)

Koziy, L.; Margvelashvili, N.; Maderich, V.; Zheleznyak, M.

1999-01-01

THREE-dimensional model of TOXicants transport (THREETOX) was developed for assessment of potential and real emergency situations in the coastal area of seas and the inland water bodies. It includes the high resolution numerical hydrodynamic submodel, dynamic-thermodynamic ice submodel, submodels of suspended sediment and radionuclide transport. The results of two case studies are described. The first one concerns to two-year simulation of the Chernobyl origin radionuclide transport through Dnieper-Bug estuary into the Black sea. In the second case study the simulations were performed for the assessment of potential emergency situation caused by the radionuclide release from reactors and containers with the liquid radioactive wastes scuttled in the Novaya Zemlya fjords (Tsivolki, Stepovogo and Abrosimov). The presented results demonstrate the capability of THREETOX model to describe the wide spatial and temporal range of transport processes in the coastal area of seas. (author)

EOS7R: Radionuclide transport for TOUGH2

International Nuclear Information System (INIS)

Oldenburg, C.M.; Pruess, K.

1995-11-01

EOS7R provides radionuclide transport capability for TOUGH2. EOS7R extends the EOS7 module (water, brine, and optional air) to model water, brine, parent component, daughter component, and optional air and heat. The radionuclide components follow a first-order decay law, and may adsorb onto the solid grains. Volatilization of the decaying components is modeled by Henry's Law. The decaying components are normally referred to as radionuclides, but they may in fact by any trace components that decay, adsorb, and volatilize. The decay process need not be radioactive decay, but could be any process that follows a first-order decay law, such as biodegradation. EOS7R includes molecular diffusion for all components in gaseous and aqueous phases using a simplified binary diffusion model. When EOS7R is used with standard TOUGH2, transport occurs by advection and molecular diffusion in all phases. When EOS7R is coupled with the dispersion module T2DM, one obtains T2DMR, the radionuclide transport version of T2DM. T2DMR models advection, diffusion, and hydrodynamic dispersion in rectangular two-dimensional regions. Modeling of radionuclide transport requires input parameters specifying the half-life for first-order decay, distribution coefficients for each rock type for adsorption, and inverse Henry's constants for volatilization. Options can be specified in the input file to model decay in inactive grid blocks and to read from standard EOS7 INCON files. The authors present a number of example problems to demonstrate application and accuracy of TOUGH2/EOS7R. One-dimensional simulation results agree well with analytical solutions. For a two-dimensional salt-dome flow problem, the final distribution of daughter radionuclide component is complicated by the presence of weak recirculation caused by density effects due to salinity

Reports of 5. International scientific-practical conference 'Heavy metals and radionuclides in the environment'

International Nuclear Information System (INIS)

2008-01-01

To the collection, consisting of 3 chapters, are included more 185 reports of plenary and sectional meetings of the conference, reflecting biogeochemical problems of heavy metals and radionuclides, modeling of processes of their migration and accumulation in natural and anthropogenic landscapes; physiology-biochemical aspects of metabolism and the participation of heavy metals and radionuclides in ecology-tropic system; the sources of entering of heavy metals and radionuclides to the natural components, ecological regulation of their loadings and the organization of environment monitoring; new methods of defining of heavy metals and radionuclides in the natural objects; of top-soil and natural water polluted by heavy metals and radionuclides; bio indicational methods of evaluation the condition of natural and anthropogenic landscapes, the problems of heavy metals and radionuclides in the context of education of higher educational establishments. The materials are made for the specialists, who work in the sphere of protection of environment, biogeochemists, ecologists, hydro chemists, biologists, pedologists, scientists, teachers and students of educational institutions

Twenty-five years of environmental radionuclide concentrations near a nuclear power plant.

Science.gov (United States)

Harris, Charles; Kreeger, Danielle; Patrick, Ruth; Palms, John

2015-05-01

The areas in and along a 262-km length of the Susquehanna River in Pennsylvania were monitored for the presence of radioactive materials. This study began two months after the 1979 Three Mile Island (TMI) partial reactor meltdown; it spanned the next 25 y. Monitoring points included stations at the PPL Susquehanna and TMI nuclear power plants. Monthly gamma measurements document concentrations of radionuclides from natural and anthropogenic sources. During this study, various series of gamma-emitting radionuclide concentration measurements were made in many general categories of animals, plants, and other inorganic matter. Sampling began in 1979 before the first start-up of the PPL Susquehanna power plant. Although all species were not continuously monitored for the entire period, an extensive database was compiled. In 1986, the ongoing measurements detected fallout from the Chernobyl nuclear accident. These data may be used in support of dose or environmental transport calculations.

Dependence of alpha radionuclide diffusion and deposition on relative air humidity

International Nuclear Information System (INIS)

Danis, A.; Ciubotariu, M.; Oncescu, M.; Mocsy, I.; Tomulescu, V.

2000-01-01

The diffusion and deposition of the gaseous and solid alpha radionuclides/aerosols depend strongly on the relative air humidity. This dependence gets a great significance in the case of radon and their genetically related alpha radionuclides monitoring in the dwelling and working places for radioprotection purposes, particularly in establishing the equilibrium factor. For the gaseous and solid alpha radionuclides genetically related, Rn-222 and its solid alpha descendants including their aerosols obtained by radionuclide attachments to different particles present in air, the vertical gradient of volume concentrations was experimentally determined. The experiments were performed in: an airtight tubular laboratory chamber, a house cellar (Cluj-Napoca) and the entrance gallery of an abandoned mine (Avram Iancu, Bihor), in which the relative humidity was ranging from 65% up to 96%. For the laboratory chamber, these radionuclides were generated by a calibrated Ra-226 source, prepared at the Radionuclide Production Centre, IPNE-HH, Bucharest. The source was included into an air tight device with a well known volume and it was used only after 40 days, when the Ra-226 and its alpha descendants were under radioactive equilibrium. For the diffusion/deposition studies, this source was coupled with the airtight laboratory chamber. In the mine gallery and house cellar, the radon and its descendants were naturally and continuously generated by radium sources in soil and building materials. The alpha volume concentration determinations required the use of a very accurate and sensitive alpha measurement method. These requirements were met by the alpha track method. This method was used by us in the following conditions: the CR-39 plastic track detector (Page, England) for the detection of the alpha particles and the optical microscopy for the study of alpha tracks (Wild stereomicroscope M7S and a Karl Zeiss Jena binocular microscope). The volume concentrations of radon and the

Clinical advance in radionuclide imaging of pulmonary cancer

International Nuclear Information System (INIS)

Deng Zhiyong; Yang Lichun

2008-01-01

Radionuclide imaging of pulmonary cancer develops very rapidly in recent years. Its important value on the diagnosis, staging, monitoring recur and metastasis after treatment, and judging the curative effect and prognosis has been demonstrated. Clinicians pay more attention to it than before. This present article introduces the imaging principle, clinical use, good and bad points, progress situation of 67 Ga, 201 Tl, 99 Tc m , 18 F and their labelled compounds, which are more commonly used in clinical. And introduces the clinical progress of radionuclide imaging of pulmonary neoplasm concerning 99 Tc m -sestamibi ( 99 Tc m -MIBI), 99 Tc m -HL91 and 18 F-fluorodeoxyglucose ( 18 F-FDG) with emphasis. (authors)

Informal workshop on radionuclide laboratories. Issue 1

International Nuclear Information System (INIS)

2001-01-01

The network of radionuclide stations in the International Monitoring System (IMS) of the Comprehensive Test Ban Treaty (CTBT) will be comprised of 80 monitoring stations and 16 laboratories acting in support of the monitoring stations. The 16 radionuclide laboratories have been designated but there are issues to resolve in several areas: - Fee structure and payments to the laboratories from the PTS; - Agreement on Detailed requirements for certification of the laboratories; - Duties of the laboratory To help provide technical information in these and other areas an Informal Workshop was held on January 29th - February 2nd 2001 at Atomic Weapons Establishment (AWE) United Kingdom. It was agreed that a common fee structure would make for a more efficient operation if one could be agreed. One possible fee structure for payment to the laboratories was considered to be an annual fixed fee for service (estimated at $38,000) plus a charge for each individual analysis (estimated at $1,200). These estimated values were based on the laboratory replies to a questionnaire organised by the PTS in December 2000. An average of 40 samples/year/ laboratory was considered to be the number required to maintain support to the monitoring station network and also maintain the laboratory capability. Based on this number the overall cost, payable to the laboratories, of running a network of 16 radionuclide laboratories was estimated at $1.38M per year, when all 80 radionuclide stations are operational. The first proficiency test exercise had been carried out in November 2000 and was discussed. Overall the results were highly encouraging and any minor problems found were being addressed. The technical areas requiring further consideration were uncertainty values and cascade summing corrections. The basis for an ongoing programme of such exercises was discussed and agreed by participants. One recommendation that came out of this meeting was the desirability of using a common nuclear data

Radiation, radionuclides and bacteria: An in-perspective review.

Science.gov (United States)

Shukla, Arpit; Parmar, Paritosh; Saraf, Meenu

2017-12-01

There has been a significant surge in consumption of radionuclides for various academic and commercial purposes. Correspondingly, there has been a considerable amount of generation of radioactive waste. Bacteria and archaea, being earliest inhabitants on earth serve as model microorganisms on earth. These microbes have consistently proven their mettle by surviving extreme environments, even extreme ionizing radiations. Their ability to accept and undergo stable genetic mutations have led to development of recombinant mutants that are been exploited for remediation of various pollutants such as; heavy metals, hydrocarbons and even radioactive waste (radwaste). Thus, microbes have repeatedly presented themselves to be prime candidates suitable for remediation of radwaste. It is interesting to study the behind-the-scenes interactions these microbes possess when observed in presence of radionuclides. The emphasis is on the indigenous bacteria isolated from radionuclide containing environments as well as the five fundamental interaction mechanisms that have been studied extensively, namely; bioaccumulation, biotransformation, biosorption, biosolubilisation and bioprecipitation. Application of microbes exhibiting such mechanisms in remediation of radioactive waste depends largely on the individual capability of the species. Challenges pertaining to its potential bioremediation activity is also been briefly discussed. This review provides an insight into the various mechanisms bacteria uses to tolerate, survive and carry out processes that could potentially lead the eco-friendly approach for removal of radionuclides. Copyright © 2017 Elsevier Ltd. All rights reserved.

Proceedings of the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

Energy Technology Data Exchange (ETDEWEB)

Wetovsky, Marvin A. [Editor; Benson, Jody [Editor; Patterson, Eileen F. [Editor

2007-09-25

These proceedings contain papers prepared for the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 25-27 September, 2007 in Denver, Colorado. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Proceedings of the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

International Nuclear Information System (INIS)

Wetovsky, Marvin A.; Benson, Jody; Patterson, Eileen F.

2007-01-01

These proceedings contain papers prepared for the 29th Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies, held 25-27 September, 2007 in Denver, Colorado. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Air Force Technical Applications Center (AFTAC), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Representing Geospatial Environment Observation Capability Information: A Case Study of Managing Flood Monitoring Sensors in the Jinsha River Basin

Science.gov (United States)

Hu, Chuli; Guan, Qingfeng; Li, Jie; Wang, Ke; Chen, Nengcheng

2016-01-01

Sensor inquirers cannot understand comprehensive or accurate observation capability information because current observation capability modeling does not consider the union of multiple sensors nor the effect of geospatial environmental features on the observation capability of sensors. These limitations result in a failure to discover credible sensors or plan for their collaboration for environmental monitoring. The Geospatial Environmental Observation Capability (GEOC) is proposed in this study and can be used as an information basis for the reliable discovery and collaborative planning of multiple environmental sensors. A field-based GEOC (GEOCF) information representation model is built. Quintuple GEOCF feature components and two GEOCF operations are formulated based on the geospatial field conceptual framework. The proposed GEOCF markup language is used to formalize the proposed GEOCF. A prototype system called GEOCapabilityManager is developed, and a case study is conducted for flood observation in the lower reaches of the Jinsha River Basin. The applicability of the GEOCF is verified through the reliable discovery of flood monitoring sensors and planning for the collaboration of these sensors. PMID:27999247

Safety-net concept - an extra step in environmental monitoring

International Nuclear Information System (INIS)

Sage, L.E.; Kachur, M.; Shank, K.E.; Palms, J.

1990-01-01

In 1979, a monitoring program, designed by the Academy of Natural Sciences, was implemented at the Pennsylvania Power and Light Company nuclear station in rural Pennsylvania. The program had three objectives: (1) provide an independent level of public confidence concerning the ecological significance of radionuclides released to the environment; (2) understand the transport and fate of radionuclides in the environment; (3) develop monitoring methods that are responsive to cumulative radiation in the environment. This program focuses on biological receptors that concentrate radionuclides and increase detection sensitivity in all segments of the environment. The aquatic environment is monitored in the conventional manner by sampling fish tissues and in a less traditional manner by sampling the finer river sediments and periphytic diatoms. The terrestrial environment is monitored by sampling home vegetable gardens, forest vegetation, lichens, and game mammals. A primary goal is to establish ecological linkages, for example, between radionuclides, tree leaves, leaf litter, humus, and fungi. These linkages extend, through food, to game mammals, thence to humans. Eight years of experimental results are presented

Environmental radiation monitoring from the decommission of TRIGA

Energy Technology Data Exchange (ETDEWEB)

Choi, Geun Sik; Lee, Chang Woo

2000-03-01

Environmental radiation monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around TRIGA Research Reactor. The results of environmental radiation monitoring around TRIGA Research Reactor are the follows: The average level of environmental radiation measured by potable ERM and accumulated radiation dose by TLD was almost same level compared with thepast years. Gross {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. but only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. (author)

CRITICAL RADIONUCLIDE AND PATHWAY ANALYSIS FOR THE SAVANNAH RIVER SITE

Energy Technology Data Exchange (ETDEWEB)

Jannik, T.

2011-08-30

This report is an update to the analysis, Assessment of SRS Radiological Liquid and Airborne Contaminants and Pathways, that was performed in 1997. An electronic version of this large original report is included in the attached CD to this report. During the operational history (1954 to the present) of the Savannah River Site (SRS), many different radionuclides have been released to the environment from the various production facilities. However, as will be shown by this updated radiological critical contaminant/critical pathway analysis, only a small number of the released radionuclides have been significant contributors to potential doses and risks to offsite people. The analysis covers radiological releases to the atmosphere and to surface waters, the principal media that carry contaminants offsite. These releases potentially result in exposure to offsite people. The groundwater monitoring performed at the site shows that an estimated 5 to 10% of SRS has been contaminated by radionuclides, no evidence exists from the extensive monitoring performed that groundwater contaminated with these constituents has migrated off the site (SRS 2011). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people. In addition, in response to the Department of Energy's (DOE) Order 435.1, several Performance Assessments (WSRC 2008; LWO 2009; SRR 2010; SRR 2011) and a Comprehensive SRS Composite Analysis (SRNO 2010) have recently been completed at SRS. The critical radionuclides and pathways identified in these extensive reports are discussed and, where applicable, included in this analysis.

Rapid instrumental and separation methods for monitoring radionuclides in food and environmental samples. Final report on an IAEA co-ordinated research programme

International Nuclear Information System (INIS)

1995-01-01

The Co-ordinated Research Programme (CRP) on Rapid Instrumental and Separation Methods for Monitoring Radionuclides in Food and Environmental Samples was established by the Agency following a Consultants' Meeting on the same topic, which was held 5-9 September 1988 in Vienna. It was completed in 1992. At various times during its course it encompassed 15 participants from 14 countries. The scope of work and objectives of the CRP were established at the Consultants' Meeting. It was agreed that the CRP should focus on the development of rapid methods for the determination of radionuclides in food and environmental samples during the intermediate and late post-accident phases. The rapid methods developed during the course of the CRP were intended to permit a timely and accurate determination of radionuclides at concentrations at least one order of magnitude below those specified for Derived Intervention Levels (DILs) for food by the WHO/FAO and the IAEA. Research Co-ordination meetings were held in Warsaw, Poland in September 1989 and in Vienna, Austria in 1991. Reports of the meetings are available from the Agency on Request. This document comprises copies of final reports from the participants and selected contributions presented by the participants at the meetings. The contributions were selected on the basis of being able to stand alone, without further explanation. Where there was an overlap in the information presented by a participant at both meetings, the most complete contribution was selected

Rapid instrumental and separation methods for monitoring radionuclides in food and environmental samples. Final report on an IAEA co-ordinated research programme

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The Co-ordinated Research Programme (CRP) on Rapid Instrumental and Separation Methods for Monitoring Radionuclides in Food and Environmental Samples was established by the Agency following a Consultants' Meeting on the same topic, which was held 5-9 September 1988 in Vienna. It was completed in 1992. At various times during its course it encompassed 15 participants from 14 countries. The scope of work and objectives of the CRP were established at the Consultants' Meeting. It was agreed that the CRP should focus on the development of rapid methods for the determination of radionuclides in food and environmental samples during the intermediate and late post-accident phases. The rapid methods developed during the course of the CRP were intended to permit a timely and accurate determination of radionuclides at concentrations at least one order of magnitude below those specified for Derived Intervention Levels (DILs) for food by the WHO/FAO and the IAEA. Research Co-ordination meetings were held in Warsaw, Poland in September 1989 and in Vienna, Austria in 1991. Reports of the meetings are available from the Agency on Request. This document comprises copies of final reports from the participants and selected contributions presented by the participants at the meetings. The contributions were selected on the basis of being able to stand alone, without further explanation. Where there was an overlap in the information presented by a participant at both meetings, the most complete contribution was selected.

Removal of dissolved heavy metals and radionuclides by microbial spores

International Nuclear Information System (INIS)

Revis, N.W.; Hadden, C.T.; Edenborn, H.

1997-01-01

Microbial systems have been shown to remove specific heavy metals from contaminated aqueous waste to levels acceptable to EPA for environmental release. However, systems capable of removing a variety of heavy metals from aqueous waste to environmentally acceptable levels remain to be reported. The present studies were performed to determine the specificity of spores of the bacterium Bacillus megaterium for the adsorption of dissolved metals and radionuclides from aqueous waste. The spores effectively adsorbed eight heavy metals from a prepared metal mix and from a plating rinse waste to EPA acceptable levels for waste water. These results suggest that spores have multiple binding sites for the adsorption of heavy metals. Spores were also effective in adsorbing the radionuclides 85 strontium and 197 cesium. The presence of multiple sites in spores for the adsorption of heavy metals and radionuclides makes this biosorbent a good candidate for the treatment of aqueous wastes associated with the plating and nuclear industries. 17 refs., 4 tabs

Speciation analysis of radionuclides

International Nuclear Information System (INIS)

Salbu, B.

2010-01-01

Full text: Naturally occurring and artificially produced radionuclides in the environment can be present in different physico-chemical forms (i. e. radionuclide species) varying in size (nominal molecular mass), charge properties and valence, oxidation state, structure and morphology, density, complexing ability etc. Low molecular mass (LMM) species are believed to be mobile and potentially bioavailable, while high molecular mass (HMM) species such as colloids, polymers, pseudocolloids and particles are considered inert. Due to time dependent transformation processes such as mobilization of radionuclide species from solid phases or interactions of mobile and reactive radionuclide species with components in soils and sediments, however, the original distribution of radionuclides deposited in ecosystems will change over time and influence the ecosystem behaviour. To assess the environmental impact from radionuclide contamination, information on radionuclide species deposited, interactions within affected ecosystems and the time-dependent distribution of radionuclide species influencing mobility and biological uptake is essential. The development of speciation techniques to characterize radionuclide species in waters, soils and sediments should therefore be essential for improving the prediction power of impact and risk assessment models. The present paper reviews fractionation techniques which should be utilised for radionuclide speciation purposes. (author)

Rapid determination of long-lived artificial alpha radionuclides using time interval analysis

International Nuclear Information System (INIS)

Uezu, Yasuhiro; Koarashi, Jun; Sanada, Yukihisa; Hashimoto, Tetsuo

2003-01-01

It is important to monitor long lived alpha radionuclides as plutonium ( 238 Pu, 239+240 Pu) in the field of working area and environment of nuclear fuel cycle facilities, because it is well known that potential risks of cancer-causing from alpha radiation is higher than gamma radiations. Thus, these monitoring are required high sensitivity, high resolution and rapid determination in order to measure a very low-level concentration of plutonium isotopes. In such high sensitive monitoring, natural radionuclides, including radon ( 222 Rn or 220 Rn) and their progenies, should be eliminated as low as possible. In this situation, a sophisticated discrimination method between Pu and progenies of 222 Rn or 220 Rn using time interval analysis (TIA), which was able to subtract short-lived radionuclides using the time interval distributions calculation of successive alpha and beta decay events within millisecond or microsecond orders, was designed and developed. In this system, alpha rays from 214 Po, 216 Po and 212 Po are extractable. TIA measuring system composes of Silicon Surface Barrier Detector (SSD), an amplifier, an Analog to Digital Converter (ADC), a Multi-Channel Analyzer (MCA), a high-resolution timer (TIMER), a multi-parameter collector and a personal computer. In ADC, incidental alpha and beta pulses are sent to the MCA and the TIMER simultaneously. Pulses from them are synthesized by the multi-parameter collector. After measurement, natural radionuclides are subtracted. Airborne particles were collected on membrane filter for 60 minutes at 100 L/min. Small Pu particles were added on the surface of it. Alpha and beta rays were measured and natural radionuclides were subtracted within 5 times of 145 msec. by TIA. As a result of it, the hidden Pu in natural background could be recognized clearly. The lower limit of determination of 239 Pu is calculated as 6x10 -9 Bq/cm 3 . This level is satisfied with the derived air concentration (DAC) of 239 Pu (8x10 -9 Bq/cm 3

Effluent Treatment Facility tritium emissions monitoring

International Nuclear Information System (INIS)

Dunn, D.L.

1991-01-01

An Environmental Protection Agency (EPA) approved sampling and analysis protocol was developed and executed to verify atmospheric emissions compliance for the new Savannah River Site (SRS) F/H area Effluent Treatment Facility. Sampling equipment was fabricated, installed, and tested at stack monitoring points for filtrable particulate radionuclides, radioactive iodine, and tritium. The only detectable anthropogenic radionuclides released from Effluent Treatment Facility stacks during monitoring were iodine-129 and tritium oxide. This paper only examines the collection and analysis of tritium oxide

Effects of radionuclides on non-human biota and natural ecosystem

International Nuclear Information System (INIS)

Garnier-Laplace, J.; Adam, C.; Gilbin, R.; Denison, F.; Fortin, C.; Simon, O.

2004-01-01

The need for a system of radiological protection of the environment drives regulators to urge scientists on conceptualisation of methods to demonstrate that the environment is protected against radioactive contaminants. One of the major difficulties in the implementation of ecological risk assessment for radioactive pollutants is the lack of data for wildlife chronic internal exposure to alpha or beta emitters. Situations of such chronic internal exposure at low levels are likely to cause toxic responses distinct from those observed after acute exposure at high doses because of the bioaccumulation phenomena. Biochemical mechanisms can lead to a gradual accumulation of elements present at trace level in the external medium, inducing a highly localised deposit within tissues or cells. These highly localised accumulations of radionuclides, coupling radiological and chemical toxicities, particularly for heavy elements such as actinides, may give rise to particular biological responses of a cell group, capable of causing functional or structural abnormalities at higher hierarchical levels. The assessment of these bioaccumulation phenomena investigated within the ENVIRHOM programme launched two years ago at the Institute for Radioprotection and Nuclear Safety, is primordial with regard to internal exposure to radionuclides since they increase locally both the radionuclide concentration and the biological effect of the delivered dose. Gaps of knowledge within this field constitute a strong limitation to our capability to make a reasonable risk estimate. Internal doses cannot be accurately calculated and potentially associated biological effects at any organization level remain fairly unknown. As a result, derivation of ecologically relevant and knowledge-based predicted no-effect concentrations becomes a critical issue in ERA. The scope of this paper is to illustrate the relevance of the development of a greater depth of understanding of radionuclide fate and biological

Monitoring of radionuclides in the vicinities of Finnish nuclear power plants in 1999-2001

International Nuclear Information System (INIS)

Ikaeheimonen, T.K.; Klemola, S.; Illus, E.; Vartti, V.P.; Mattila, J.

2006-09-01

Monitoring of the radioactive substances around Finnish nuclear power plants continued in 1999-2001 in accordance with the regular environmental monitoring programmes. Altogether some 1000 samples are analysed annually from the terrestrial and aquatic environs of the two power plants. Trace amounts of activation products originating from airborne releases from the local power plants were detected in several air and deposition samples. At Loviisa, observations were made in five aerosol samples; at Olkiluoto in three samples during the reporting period. The concentrations were very low, being a few microbequerels per cubic metre. A similar pattern was tenable for the deposition samples, too. No traces of local discharge nuclides were detected in foodstuffs, drinking water or garden products. In mushrooms and wild berries picked from the Loviisa and Olkiluoto areas, only Chernobyl-derived cesium isotopes and natural 40 K were found. Local discharge nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter and sediments. The dominant artificial radionuclides in the vicinity of the power plants were still the caesium isotopes, especially 137 Cs, originating from the Chernobyl accident. In seawater, elevated 3 H concentrations were more frequent at Loviisa, but no traces of other discharge nuclides were detected. In indicator organisms and sinking matter the concentrations of local discharge nuclides were somewhat higher and their distribution range was wider in the sea area off Olkiluoto. Small amounts of 60 Co originating from the local power plant were detected in sediments at a distance of about 15 km from the Olkiluoto NPP. (orig.)

Quantitative radionuclide angiocardiography

International Nuclear Information System (INIS)

Scholz, P.M.; Rerych, S.K.; Moran, J.F.; Newman, G.E.; Douglas, J.M.; Sabiston, D.C. Jr.; Jones, R.H.

1980-01-01

This study introduces a new method for calculating actual left ventricular volumes and cardiac output from data recorded during a single transit of a radionuclide bolus through the heart, and describes in detail current radionuclide angiocardiography methodology. A group of 64 healthy adults with a wide age range were studied to define the normal range of hemodynamic parameters determined by the technique. Radionuclide angiocardiograms were performed in patients undergoing cardiac catherization to validate the measurements. In 33 patients studied by both techniques on the same day, a close correlation was documented for measurement of ejection fraction and end-diastolic volume. To validate the method of volumetric cardiac output calcuation, 33 simultaneous radionuclide and indocyanine green dye determinations of cardiac output were performed in 18 normal young adults. These independent comparisons of radionuclide measurements with two separate methods document that initial transit radionuclide angiocardiography accurately assesses left ventricular function

The effects of culinary preparation on radionuclide levels in vegetable foodstuffs

International Nuclear Information System (INIS)

Wilkins, B.T.; Bradley, E.J.; Dodd, N.J.

1987-01-01

Vegetables contaminated by fall-out from the Chernobyl nuclear reactor accident have been used to investigate how simple culinary methods can affect the levels of various radionuclides in the portion consumed by man. Only γ ray emitting radionuclides were investigated. Those parts of vegetables normally considered inedible, for example coarse outer leaves, foliage or roots, can account for between 50% and 97% of the total radionuclide content. Washing of the edible parts of vegetables can reduce the levels still further, although the efficacy is dependent on both the radionuclide and the vegetable type. These normal domestic procedures can reduce intakes of recently deposited radionuclides on vegetables by about an order of magnitude. The results have implications for the scope of monitoring programmes that might follow any future accidental release. They also reinforce very strongly the requirement for measurements on edible parts rather than whole samples as a direct input to dose evaluation. These results further suggest that there is no need to revise the general assumptions made in accident consequence models regarding losses of activity between harvest and consumption. However, more rigorous assessments of dose should take account of vegetable type and probable means of preparation. (author)

MEASUREMENT OF RADIONUCLIDES USING ION CHROMATOGRAPHY AND FLOW-CELL SCINTILLATION COUNTING WITH PULSE SHAPE DISCRIMINATION

International Nuclear Information System (INIS)

Fjeld, R. A.; DeVol, T.A.; Leyba, J.D.

2000-01-01

Radiological characterization and monitoring is an important component of environmental management activities throughout the Department of Energy complex. Gamma-ray spectroscopy is the technology most often used for the detection of radionuclides. However, radionuclides which cannot easily be detected by gamma-ray spectroscopy, such as pure beta emitters and transuranics, pose special problems because their quantification generally requires labor intensive radiochemical separations procedures that are time consuming and impractical for field applications. This project focused on a technology for measuring transuranics and pure beta emitters relatively quickly and has the potential of being field deployable. The technology combines ion exchange liquid chromatography and on-line alpha/beta pulse shape discriminating scintillation counting to produce simultaneous alpha and beta chromatograms. The basic instrumentation upon which the project was based was purchased in the early 1990's. In its original commercial form, the instrumentation was capable of separating select activation/fission products in ionic forms from relatively pure aqueous samples. We subsequently developed the capability of separating and detecting actinides (thorium, uranium, neptunium, plutonium, americium, and curium) in less than 30 minutes (Reboul, 1993) and realized that the potential time savings over traditional radiochemical methods for isolating some of these radionuclides was significant. However, at that time, the technique had only been used for radionuclide concentrations that were considerably above environmental levels and for aqueous samples of relatively high chemical purity. For the technique to be useful in environmental applications, development work was needed in lowering detection limits; to be useful in applications involving non-aqueous matrices such as soils and sludges or complex aqueous matrices such as those encountered in waste samples, development work was needed in

The Problem of Assessment for Radionuclide and Chemical Hazard to People Heredity and Health

International Nuclear Information System (INIS)

Suskov, Igor I.; Glouchtchenko, Alexandre I.

2003-01-01

In the 21th century the assessment of the hazard to human heredity and health from the radionuclide and chemical environmental pollution becomes of prime social importance since it is related to the problems of utilization of great amounts of radioactive and chemical wastes, spent nuclear fuel, weapon plutonium, nuclear reactors and emergency discharges of isotopes which in total is higher than 1 billion Ci. Long-term cytogenetic monitoring of nuclear and chemical plant workers, local human populations of radioactive waste areas and radionuclide polluted territories has revealed that the level and spectrum of induced chromosome aberrations in blood lymphocytes correlate with the type, dose and duration of exposure. There is very strong evidence that the yield of chromosome aberrations (Y) is related to the dose (D) by the equation: Y=Ao+aD+bD 2 . Therefore the radiation/radionuclide risk (R(D) ) will correspond to a absorbed dose and its aberrational/mutational consequences ('doubling dose' coefficient). Increased levels of chromosome aberrations in the human body very often precede the development of several syndromes: chronic fatigue, secondary immune deficiency, early aging, reproductive dysfunction, oncological diseases and etc. The increased levels of chromosome aberrations in blood lymphocytes can serve as objective bio indicators of radiation and chemical risk to human heredity and health. Thus, monitoring of chromosome and genome aberrations must be of strategical importance in the system of governmental service for minimization of radionuclide and chemical hazard to human heredity and health the necessity of organization of which has already matured. The above mentioned confirms the necessity of founding a European network for ecological-genetic monitoring with 'Internet' translation of information on radionuclide composition and chromosome aberration levels in people, inhabiting polluted areas

Microbial mediation of radionuclide transport -significance for the nuclear fuel waste management program

International Nuclear Information System (INIS)

Champ, D.R.

1984-08-01

The role that microbially catalyzed processes may play in determining, or altering, radionuclide migration is an unresolved question in the Nuclear Fuel Waste Management Program. This report documents the results of a review of the available information on the existence and biochemical capabilities of micro-organisms and the potential for their involvement in processes affecting the migration of radionuclides of interest. The potential was judged sufficient to warrant conducting experiments to assess their role. The outline of an experimental program to address the role of micro-organisms is presented

Radionuclide concentrations in agricultural products near the Hanford Site, 1982 through 1992

International Nuclear Information System (INIS)

Antonio, E.J.

1994-06-01

The Pacific Northwest Laboratory reviewed monitoring data for agricultural products collected from 1982 through 1992 near the Hanford Site to determine radionuclide concentration trends. While samples were collected and analyzed, and results reported annual in Hanford Site environmental reports, an 11-year data set was reviewed for this report to increase the ability to assess trends and potential Hanford effects. Products reviewed included milk, chicken, eggs, beef, vegetables, fruit, wine, wheat, and alfalfa. To determine which radionuclides were detected sufficiently often to permit analysis for trends and effects, each radionuclide concentration and its associated uncertainty were ratioed. Radionuclides were considered routinely detectable if more than 50% of the ratios were between zero and one. Data for these radionuclides were then analyzed statistically, using analyses of variance. The statistical analyses indicated the following: for the most part, there were no measurable effects for Hanford operations; radionuclide concentrations in all products reviewed remained relatively low when compared to concentrations that would result in a 1-mrem effective dose equivalent to an individual; radionuclide concentrations are decreasing in general; however, 90 Sr concentrations in all media and 129 I in milk increased from 1982 to 1986, then decreased gradually for the remainder of the review period. The 129 I concentrations may be correlated with processing of irradiated reactor fuel at the Plutonium-Uranium Extraction (PUREX) Plant

The ANTARES accelerator: a facility for environmental monitoring and materials characterisation

International Nuclear Information System (INIS)

Tuniz, C.

1997-01-01

An analytical facility for Accelerator Mass Spectrometry (AMS) and Ion Beam Analysis (IBA) has been under development since 1989 on the 8-MV tandem accelerator ANTARES at the Lucas Heights Science and Technology Centre. Three beamlines are presently dedicated to the AMS analysis of long-lived radionuclides and one is used for the study of multilayered semiconductor structures by heavy ion recoil spectrometry. Having accomplished the task of transforming the old nuclear physics accelerator from Rutgers University into a world-class analytical facility, ANSTO scientists are now promoting research projects based on the capability of the ANTARES instruments. New instruments are being constructed on the ANTARES accelerator for future programs in environmental monitoring, safeguards, nuclear waste disposal and applications in advanced materials. A new AMS beamline has been designed that is expected to be capable of measuring rare heavy radionuclides, such as 236 U, 229 , 230T h and 244 Pu, in natural samples with ultra-high sensitivity. A novel, heavy ion microprobe will allow IBA of surfaces with a spatial resolution of 10 μm for high-energy ions (20-100 MeV) from chlorine to iodine. These instruments are complementary to other advanced analytical tools developed by ANSTO, such as the synchrotron radiation beamline at the Australian National Beamline Facility

Adding navigation, artificial audition and vital sign monitoring capabilities to a telepresence mobile robot for remote home care applications.

Science.gov (United States)

Laniel, Sebastien; Letourneau, Dominic; Labbe, Mathieu; Grondin, Francois; Polgar, Janice; Michaud, Francois

2017-07-01

A telepresence mobile robot is a remote-controlled, wheeled device with wireless internet connectivity for bidirectional audio, video and data transmission. In health care, a telepresence robot could be used to have a clinician or a caregiver assist seniors in their homes without having to travel to these locations. Many mobile telepresence robotic platforms have recently been introduced on the market, bringing mobility to telecommunication and vital sign monitoring at reasonable costs. What is missing for making them effective remote telepresence systems for home care assistance are capabilities specifically needed to assist the remote operator in controlling the robot and perceiving the environment through the robot's sensors or, in other words, minimizing cognitive load and maximizing situation awareness. This paper describes our approach adding navigation, artificial audition and vital sign monitoring capabilities to a commercially available telepresence mobile robot. This requires the use of a robot control architecture to integrate the autonomous and teleoperation capabilities of the platform.

Design and development of a computer-based continuous monitor for the determination of the short-lived decay products of radon and thoron

Energy Technology Data Exchange (ETDEWEB)

Bigu, J [Department of Energy, Mines and Resources, Elliot Lake, Ontario (Canada). Elliot Lake Lab.; Raz, R; Golden, K; Dominguez, P [Alpha-NUCLEAR, Toronto, Ontario (Canada)

1984-08-15

A portable, rugged, monitor has been designed and built for measuring the short-lived decay products of radon and thoron. The monitor is computer-based and employs a continuous filter strip which can be advanced at programmable time intervals to allow unattended continuous operation with automatic sampling, analysis and recording of radiation levels. Radionuclide analysis is carried out by two silicon diffused-junction alpha-detectors and electronic circuitry with multichannel spectral analysis capabilities. Standard gross ..cap alpha..-count methods and ..cap alpha..-spectroscopy methods can easily be implemented. The built-in computer performs a variety of operations via a specially designed interface module, including control and data recording functions, and computations, program storage and display functions. Programs and data are stored in the built-in casette tape drive and the computer integrated CRT display and keyboard allow simple, prompted menu-type operation of standard software. Graphical presentation of ..cap alpha..-spectra can be shown on the computer CRT and printed when required on the computer built-in thermal printer. In addition, to implementing the specially developed radionuclide analysis software, the operator can interact and modify existing software, and program new ones, through BASIC language programming, or employ the computer in a totally unrelated, general purpose model. Although the monitor is ideally suited for environmental radon (thoron) daughter monitoring, it could also be used in the determination of other airborne radionuclides provided adequate analytical procedures are developed or included in the already existing computer software.

Design and development of a computer-based continuous monitor for the determination of the short-lived decay products of radon and thoron

International Nuclear Information System (INIS)

Bigu, J.

1984-01-01

A portable, rugged, monitor has been designed and built for measuring the short-lived decay products of radon and thoron. The monitor is computer-based and employs a continuous filter strip which can be advanced at programmable time intervals to allow unattended continuous operatin with automatic sampling, analysis and recording of radiation levels. Radionuclide analysis is carried out by two silicon diffused-junction alpha-detectors and electronic circuitry with multichannel spectral analysis capabilities. Standard gross α-count methods and α-spectroscopy methods can easily be implemented. The built-in computer performs a variety of operations via a specially designed interface module, including control and data recording functions, and computations, program storage and display functions. Programs and data are stored in the built-in casette tape drive and the computer integrated CRT display and keyboard allow simple, prompted menu-type operation of standard software. Graphical presentation of α-spectra can be shown on the computer CRT and printed when required on the computer built-in thermal printer. In addition, to implementing the specially developed radionuclide analysis software, the operator can interact and modify existing software, and program new ones, through BASIC language programming, or employ the computer in a totally unrelated, general purpose model. Although the monitor is ideally suited for environmental radon (thoron) daughter monitoring, it could also be used in the determination of other airborne radionuclides provided adequate analytical procedures are developed or included in the already existing computer software. (orig.)

Biological sampling for marine radioactivity monitoring

International Nuclear Information System (INIS)

Fowler, S.W.

1997-01-01

Strategies and methodologies for using marine organisms to monitor radioactivity in marine waters are presented. When the criteria for monitoring radioactivity is to determine routes of radionuclide transfer to man, the ''critical pathway'' approach is often applied. Alternatively, where information on ambient radionuclide levels and distributions is sought, the approach of selecting marine organisms as ''bioindicators'' of radioactivity is generally used. Whichever approach is applied, a great deal of knowledge is required about the physiology and ecology of the specific organism chosen. In addition, several criteria for qualifying as a bioindicator species are discussed; e.g., it must be a sedentary species which reflects the ambient radionuclide concentration at a given site, sufficiently long-lived to allow long-term temporal sampling, widely distributed to allow spatial comparisons, able to bioconcentrate the radionuclide to a relatively high degree, while showing a simple correlation between radionuclide content in its tissues with that in the surrounding waters. Useful hints on the appropriate species to use and the best way to collect and prepare organisms for radioanalysis are also given. It is concluded that benthic algae and bivalve molluscs generally offer the greatest potential for use as a ''bioindicator'' species in radionuclide biomonitoring programmes. Where knowledge on contribution to radiological dose is required, specific edible marine species should be the organisms of choice; however, both purposes can be served when the edible species chosen through critical pathway analysis is also an excellent bioaccumulator of the radionuclide of interest. (author)

High resolution simultaneous measurements of airborne radionuclides in the pan-Japan sea area

International Nuclear Information System (INIS)

Yamaguchi, Y.; Abe, T.; Murata, Y.M.; Manikandan, N.; Tanaka, K.; Komura, K.

2006-01-01

By the use of ultra low background Ge detectors at Ogoya Underground Laboratory (OUL), it became possible to detect extremely low levels of environmental radionuclides. In this study, we tried to measure high resolution simultaneous measurements of airborne radionuclides at three monitoring points, i.e., 1) Low Level Radioactivity Laboratory (LLRL 40m asl) in Nomi City as the regular monitoring point, 2) Hegura Island Located 50 km from Noto Peninsula in the Sea of Japan to investigate the influence of Asian continent or mainland of Japan, and 3) Shishiku Plateau (640m asl) located about 8 km from LLRL to know vertical difference. Pb-210 and Be-7 were measured nondestructively by ultra low background gamma spectrometry at OUL, Po-210 by alpha spectrometry using Si detectors after the chemical treatment. Various interesting results on the concentrations and variation patterns of airborne radionuclides were obtained, particularly, during drastic meteorological changes such as the passage of typhoon, snow fall and so on. We have been analyzing the influence of the arrival of yellow sand occurred in this spring. (author)

Environmental radiation monitoring from the decommission of TRIGA

Energy Technology Data Exchange (ETDEWEB)

Choi Geun Sik; Lee, Chang Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-02-01

Environmental Radiation Monitoring was carried out with measurement of environment radiation and environment radioactivity analysis around TRIGA Research Reactor. The results of environmental radiation monitoring around TRIGA Research Reactor are the follows: The average level of environmental radiation dose measured by potable ERM and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {beta} radioactivity in environmental samples showed a environmental level. v-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. 37 refs., 12 figs., 31 tabs. (Author)

Natural attenuation of metals and radionuclides: Report from a workshop held by Sandia National Laboratories

International Nuclear Information System (INIS)

Brady, P.V.; Borns, D.J.

1997-11-01

Natural attenuation is increasingly applied to remediate contaminated soils and ground waters. Roughly 25% of Superfund groundwater remedies in 1995 involved some type of monitored natural attenuation, compared to almost none 5 years ago. Remediation by natural attenuation (RNA) requires clear evidence that contaminant levels are decreasing sufficiently over time, a defensible explanation of the attenuation mechanism, long-term monitoring, and a contingency plan at the very least. Although the primary focus of implementation has to date been the biodegradation of organic contaminants, there is a wealth of scientific evidence that natural processes reduce the bioavailability of contaminant metals and radionuclides. Natural attenuation of metals and radionuclides is likely to revolve around sorption, solubility, biologic uptake and dilution controls over contaminant availability. Some of these processes can be applied to actively remediate sites. Others, such as phytoremediation, are likely to be ineffective. RNA of metals and radionuclides is likely to require specialized site characterization to construct contaminant and site-specific conceptual models of contaminant behavior. Ideally, conceptual models should be refined such that contaminant attenuation can be confidently predicted into the future. The technical approach to RNA of metals and radionuclides is explored here

Natural attenuation of metals and radionuclides: Report from a workshop held by Sandia National Laboratories

Energy Technology Data Exchange (ETDEWEB)

Brady, P.V.; Borns, D.J. [Sandia National Labs., Albuquerque, NM (United States). Geochemistry Dept.

1997-11-01

Natural attenuation is increasingly applied to remediate contaminated soils and ground waters. Roughly 25% of Superfund groundwater remedies in 1995 involved some type of monitored natural attenuation, compared to almost none 5 years ago. Remediation by natural attenuation (RNA) requires clear evidence that contaminant levels are decreasing sufficiently over time, a defensible explanation of the attenuation mechanism, long-term monitoring, and a contingency plan at the very least. Although the primary focus of implementation has to date been the biodegradation of organic contaminants, there is a wealth of scientific evidence that natural processes reduce the bioavailability of contaminant metals and radionuclides. Natural attenuation of metals and radionuclides is likely to revolve around sorption, solubility, biologic uptake and dilution controls over contaminant availability. Some of these processes can be applied to actively remediate sites. Others, such as phytoremediation, are likely to be ineffective. RNA of metals and radionuclides is likely to require specialized site characterization to construct contaminant and site-specific conceptual models of contaminant behavior. Ideally, conceptual models should be refined such that contaminant attenuation can be confidently predicted into the future. The technical approach to RNA of metals and radionuclides is explored here.

Methodology for Determining Increases in Radionuclide Inventories for the Effluent Treatment Facility Process

International Nuclear Information System (INIS)

Blanchard, A.

1998-01-01

A study is currently underway to determine if the Effluent Treatment Facility can be downgraded from a Hazard Category 3 facility to a Radiological Facility per DOE STD-1027-92. This technical report provides a methodology to determine and monitor increases in the radionuclide inventories of the ETF process columns. It also provides guidelines to ensure that other potential increases to the ETF radionuclide inventory are evaluated as required to ensure that the ETF remains a Radiological Facility

Cells at risk from bone-seeking radionuclides: a review

International Nuclear Information System (INIS)

Hashimoto, E.G.; Jee, W.S.S.

1976-01-01

Although it is possible that any cell within range of an α-emitting radionuclide ( 239 Pu and 226 Ra) residing at a bone surface might be transformed into a bone forming neoplastic cell, the three most likely candidates are the the osteoprogenitor cell, the osteoblast, and the reticular cell of the marrow. These cells all possess osteogenic capability, proliferative activity, and resemblance to bone tumor cells

International symposium on low level measurements of radionuclides in the environment, 2004

International Nuclear Information System (INIS)

2004-01-01

The International Symposium of Low-Level Measurements of Radionuclides in the Environment was held on April 19-23, 2004 in Guilin, China, and sponsored by the Chinese Nuclear Society. The articles are published in the form of abstracts, and the contents include: 1. special lectures; 2.Environmental Radioanalysis; 3. Concentration and migration of radionuclides; 4. Analysis with instrumentation and applications; 5. preparation of samples and trace in living beings; 6. Environment impact assessment and calculation of dose; 7. Decommissioning, monitoring in emergency condition and others

Comparison of radionuclide levels in soil, sagebrush, plant litter, cryptogams, and small mammals

International Nuclear Information System (INIS)

Landeen, D.S.

1994-09-01

Soil, sagebrush, plant litter, cryptogam, and small mammal samples were collected and analyzed for cesium-137, strontium-90, plutonium-238, plutonium 239/240, technetium-99, and iodine-129 from 1981 to 1986 at the US Department of Energy Hanford Site in southeastern Washington State as part of site characterization and environmental monitoring activities. Samples were collected on the 200 Areas Plateau, downwind from ongoing waste management activities. Plant litter, cryptogams, and small mammals are media that are not routinely utilized in monitoring or characterization efforts for determination of radionuclide concentrations. Studies at Hanford, other US Department of Energy sites, and in eastern Europe have indicated that plant litter and cryptogams may serve as effective ''natural'' monitors of air quality. Plant litter in this study consists of fallen leaves from sagebrush and ''cryptogams'' describes that portion of the soil crust composed of mosses, lichens, algae, and fungi. Comparisons of cesium-137 and strontium-90 concentrations in the soil, sagebrush, litter, and cryptogams revealed significantly higher (p<0.05) levels in plant litter and cryptogams. Technetium-99 values were the highest in sagebrush and litter. Plutonium-238 and 239/40 and iodine-129 concentrations never exceeded 0.8 pCi/gm in all media. No evidence of any significant amounts of any radionuclides being incorporated into the small mammal community was discovered. The data indicate that plant litter and cryptogams may be better, indicators of environmental quality than soil or vegetation samples. Augmenting a monitoring program with samples of litter and cryptogams may provide a more accurate representation of radionuclide environmental uptake and/or contamination levels in surrounding ecosystems. The results of this study may be applied directly to other radioecological monitoring conducted at other nuclear sites and to the monitoring of other pollutants

Humic substances in natural waters and their complexation with trace metals and radionuclides: a review

International Nuclear Information System (INIS)

Boggs, S. Jr.; Livermore, D.; Seitz, M.G.

1985-07-01

Dissolved humic substances (humic and fulvic acids) occur in surface waters and groundwaters in concentrations ranging from less than 1 mg(C)/L to more than 100 mg(C)/L. Humic substances are strong complexing agents for many trace metals in the environment and are also capable of forming stable soluble complexes or chelates with radionuclides. Concentrations of humic materials as low as 1 mg(C)/L can produce a detectable increase in the mobility of some actinide elements by forming soluble complexes that inhibit sorption of the radionuclides onto rock materials. The stability of trace metal- or radionuclide-organic complexes is commonly measured by an empirically determined conditional stability constant (K'), which is based on the ratio of complexed metal (radionuclide) in solution to the product concentration of uncomplexed metal and humic complexant. Larger values of stability constants indicate greater complex stability. The stability of radionuclide-organic complexes is affected both by concentration variables and envionmental factors. In general, complexing is favored by increased of radionuclide, increased pH, and decreased ionic strength. Actinide elements are generally most soluble in their higher oxidation states. Radionuclides can also form stable, insoluble complexes with humic materials that tend to reduce radionuclide mobility. These insoluble complexes may be radionuclide-humate colloids that subsequently precipitate from solution, or complexes of radionuclides and humic substances that sorb to clay minerals or other soil particulates strongly enough to immobilize the radionuclides. Colloid formation appears to be favored by increased radionuclide concentration and lowered pH; however, the conditions that favor formation of insoluble complexes that sorb to particulates are still poorly understood. 129 refs., 25 figs., 19 tabs

Radionuclide fixation mechanisms in rocks

International Nuclear Information System (INIS)

Nakashima, S.

1991-01-01

In the safety evaluation of the radioactive waste disposal in geological environment, the mass balance equation for radionuclide migration is given. The sorption of radionuclides by geological formations is conventionally represented by the retardation of the radionuclides as compared with water movement. In order to quantify the sorption of radionuclides by rocks and sediments, the distribution ratio is used. In order to study quantitatively the long term behavior of waste radionuclides in geological environment, besides the distribution ratio concept in short term, slower radionuclide retention reaction involving mineral transformation should be considered. The development of microspectroscopic method for long term reaction path modeling, the behavior of iron during granite and water interaction, the reduction precipitation of radionuclides, radionuclide migration pathways, and the representative scheme of radionuclide migration and fixation in rocks are discussed. (K.I.)

Twenty-five-year study of radionuclides in the Susquehanna river via periphyton biomonitors.

Science.gov (United States)

Patrick, Ruth; Palms, John; Kreeger, Danielle; Harris, Charles

2007-01-01

This 25-y study monitored aquatic and terrestrial gamma-ray-emitting radionuclide levels near a nuclear power plant. It is the only known, long-term environmental survey of its kind. It was conducted neither by a utility owner, nor by a government agency, but rather by a private, environmental research institution. Compared to dozens of other flora and fauna, periphyton was found to be the best indicator to biomonitor the Susquehanna River, which runs near PPL Susquehanna's nuclear plant. Sampling began in 1979 before the first plant start-up and continued for the next 24 years. Monitoring began two months after the Three Mile Island accident of 28 March 1979 and includes Three Mile Island area measurements. Ongoing measurements detected fallout from Chernobyl in 1986, as well as I not released from PPL Susquehanna. Although this paper concentrates on radionuclides found in periphyton, the scope of the entire environmental program includes a wide variety of aquatic and land-based plants, animals, and inorganic matter. Other species and matter studied were fish, mussels, snails, crayfish, insects, humus, mushrooms, lichens, squirrels, deer, cabbage, tomatoes, coarse and flocculated sediment, and more. Results show periphyton works well for detection of radionuclide activity, even in concentrations less than 100 Bq kg (picocuries per gram amounts). Data indicate that PPL Susquehanna's radionuclide releases have had no known environmental or human health impact.

MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) code description and User's Manual

International Nuclear Information System (INIS)

Avci, H.I.; Raghuram, S.; Baybutt, P.

1985-04-01

A new computer code called MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) has been developed to replace the CORRAL-2 computer code which was written for the Reactor Safety Study (WASH-1400). This report is a User's Manual for MATADOR. MATADOR is intended for use in system risk studies to analyze radionuclide transport and deposition in reactor containments. The principal output of the code is information on the timing and magnitude of radionuclide releases to the environment as a result of severely degraded core accidents. MATADOR considers the transport of radionuclides through the containment and their removal by natural deposition and by engineered safety systems such as sprays. It is capable of analyzing the behavior of radionuclides existing either as vapors or aerosols in the containment. The code requires input data on the source terms into the containment, the geometry of the containment, and thermal-hydraulic conditions in the containment

Marine biogeochemistry of radionuclides

International Nuclear Information System (INIS)

Fowler, S.W.

1997-01-01

Radionuclides entering the ocean from runoff, fallout, or deliberate release rapidly become involved in marine biogeochemical cycles. Sources, sinks and transport of radionuclides and analogue elements are discussed with emphasis placed on how these elements interact with marine organisms. Water, food and sediments are the source terms from which marine biota acquire radionuclides. Uptake from water occurs by surface adsorption, absorption across body surfaces, or a combination of both. Radionuclides ingested with food are either assimilated into tissue or excreted. The relative importance of the food and water pathway in uptake varies with the radionuclide and the conditions under which exposure occurs. Evidence suggests that, compared to the water and food pathways, bioavailability of sediment-bound radionuclides is low. Bioaccumulation processes are controlled by many environmental and intrinsic factors including exposure time, physical-chemical form of the radionuclide, salinity, temperature, competitive effects with other elements, organism size, physiology, life cycle and feeding habits. Once accumulated, radionuclides are transported actively by vertical and horizontal movements of organisms and passively by release of biogenic products, e.g., soluble excreta, feces, molts and eggs. Through feeding activities, particles containing radionuclides are ''packaged'' into larger aggregates which are redistributed upon release. Most radionuclides are not irreversibly bound to such particles but are remineralized as they sink and/or decompose. In the pelagic zones, sinking aggregates can further scavenge particle-reactive elements thus removing them from the surface layers and transporting them to depth. Evidence from both radiotracer experiments and in situ sediment trap studies is presented which illustrates the importance of biological scavenging in controlling the distribution of radionuclides in the water column. (author)

Regional survey of radionuclides in the marine environment of the French Mediterranean coast

Energy Technology Data Exchange (ETDEWEB)

Thebault, Herve; Arnaud, Mireille; Duffa, Celine; Charmasson, Sabine; Dimeglio, Yves [Institut de Radioprotection et de Surete Nucleaire/PRP-ENV/SESURE/LERCM/ARM c/o Ifremer, CS 20330 Zone Portuaire de Bregaillon, 83507 La Seyne sur Mer Cedex (France)

2014-07-01

The French Institute for Radioprotection and Nuclear Safety (IRSN) runs a continuous monitoring program of the marine environment as a mandatory task. For the French Mediterranean coast, this monitoring activity focuses on two bio-indicators species: the Mediterranean mussel (Mytilus galloprovincialis) and the red mullet (Mullus sp.) sampled on a regular basis from natural populations at ten locations along the coast. Radionuclides are measured using direct low-level gamma spectrometry as a routine technique. In addition to this long-lasting monitoring, a broad survey of radionuclide baseline levels is conducted on all compartments of the coastal zone: water, sediments and a large selection of fish species among those most currently fished and marketed. This extended data collection is necessary to fulfill the information requirements of the UE Marine Strategy Framework Directive (MSFD) and its implementation by member states. This information is also essential for impact assessment of any incident or accident, included from a remote source. Levels of less commonly measured radionuclides like {sup 3}H, {sup 14}C, {sup 90}Sr, {sup 210}Po and U, Pu isotopes are investigated. Fish sampling relies mostly on scientific stock assessment campaigns. Mussel sampling is complemented by transplanted mussels on 40 specific sites. This regional survey also focuses on two possibly impacted areas: the Rhone river mouth coastal zone, with inputs from nuclear power plants along the river and the Bay of Toulon sheltering Navy harbor of nuclear-powered sub-marines and aircraft-carrier. First results show that the activity levels of artificial radionuclides are very low for most bio-indicator species, in accordance with previous monitoring trends. {sup 137}Cs is the only artificial radionuclide regularly detected by gamma spectrometry in mussel and fish samples at a level below 1 Bg.kg{sup -1} of dry weight. Values of {sup 3}H (organically bound Tritium) in the same samples lies under

Radionuclides around nuclear sites in England and Wales

International Nuclear Information System (INIS)

Sanchez, A.L.; Horrill, A.D.; Singleton, D.L.; Leonard, D.R.P.

1996-01-01

Environmental releases of low levels of radioactivity can occur as a consequence of normal operations at nuclear facilities. In England and Wales, the impact of gaseous discharges on the terrestrial environment is monitored routinely by the site operators as well as by Food Science Division of the Ministry of Agriculture, Fisheries and Food. The terrestrial surveillance programme carried out by MAFF Food Science concentrates on agricultural produce to provide assessments of doses to members of the population derived from the consumption of terrestrial foodstuffs. We present here the results of a survey, undertaken in 1993 to supplement the monitoring data of MAFF, of artificial radioactive contamination around eighteen nuclear establishments in England and Wales. Grass and soil samples were used as indicators of environmental contamination at these sites for the radionuclides 137 Cs, 90 Sr, 239+240 Pu and 241 Am. When compared to estimated background radionuclide concentrations close to each site, these data reveal that four of the 18 sites have contributed measurable increases to both the 137 Cs and 239+240 Pu inventory within 500 m outside the boundary fence. Two additional sites showed slight increases above the expected background soil levels of 239+240 Pu

Radionuclide inventories for the F- and H-area seepage basin groundwater plumes

Energy Technology Data Exchange (ETDEWEB)

Hiergesell, Robert A [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Kubilius, Walter P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-05-01

Within the General Separations Areas (GSA) at the Savannah River Site (SRS), significant inventories of radionuclides exist within two major groundwater contamination plumes that are emanating from the F- and H-Area seepage basins. These radionuclides are moving slowly with groundwater migration, albeit more slowly due to interaction with the soil and aquifer matrix material. The purpose of this investigation is to quantify the activity of radionuclides associated with the pore water component of the groundwater plumes. The scope of this effort included evaluation of all groundwater sample analyses obtained from the wells that have been established by the Environmental Compliance & Area Completion Projects (EC&ACP) Department at SRS to monitor groundwater contamination emanating from the F- and H-Area Seepage Basins. Using this data, generalized groundwater plume maps for the radionuclides that occur in elevated concentrations (Am-241, Cm-243/244, Cs-137, I-129, Ni-63, Ra-226/228, Sr-90, Tc-99, U-233/234, U-235 and U-238) were generated and utilized to calculate both the volume of contaminated groundwater and the representative concentration of each radionuclide associated with different plume concentration zones.

An overview of measurements of radionuclides in foods of the Comunidad Valenciana (Spain)

Science.gov (United States)

Ballesteros, L.; Ortiz, J.; Gallardo, S.; Martorell, S.

2015-11-01

Environmental radioactivity monitoring includes the determination of radionuclides in foods since they are an important way of intake of radionuclides to the human organism. Moreover, knowledge of the levels of radionuclides in foodstuffs will inform about the environmental radioactivity background permitting to control possible contamination due to human activity, such as agriculture activity, nuclear power plants or other radioactive facilities. The Environmental Radioactivity Laboratory (LRA) at the Universitat Politècnica de València (UPV) performs measurements on representative foods from all over the Comunidad Valenciana (CV). Those measurements are part of several monitoring programs promoted by the Generalitat Valenciana. A total of 2200 samples of fruits, cereals, vegetables, milk, meat, eggs and fish coming from markets, agricultural cooperatives or small producers have been analyzed. A gamma-ray spectrometry analysis has been performed in all samples. It has been detected 40K in all samples, 7Be in some of them. Radiochemical separation of 90Sr has been carried out in some of the samples collected, mainly orange and lettuce. Samples of lettuce and chard collected following Fukushima Nuclear Power Plant (NPP) accident present activity concentration of 131I (0.10-1.51 Bq kg-1). In this paper, a review of the data obtained at the 1991-2013 period in the framework of the development of the Environmental monitoring program is presented.

Annual environmental monitoring report of the Lawrence Berkeley Laboratory, 1981

International Nuclear Information System (INIS)

Schleimer, G.E.

1982-06-01

Results for 1981 of the LBL Environmental Monitoring Program are given. Data include monitoring results for accelerator-produced radiation, airborne and waterborne radionuclides, and nonradioactive pollutants. Population doses resulting from LBL operations are given in terms of accelerator-produced and airborne radioactivities. Trends in the environmental impacts of LBL operations are discussed in terms of accelerator-produced, airborne, and waterborne radionuclides

Web system for dosimetric data management of internal monitoring programme at IPEN

International Nuclear Information System (INIS)

Lima, Vanesa R. de; Rodriguez Junior, Orlando; Todo, Alberto S.

2008-01-01

Full text: The internal monitoring programme are carried out for the occupationally exposed workers that develop activities in the radioisotope production plant, fuel cycle facilities, waste management installations, cyclotron and the reactor facility at Institute of Nuclear Energy and Research (IPEN). According to the National Nuclear Energy Commission (CNEN), Regulation NN-3.01, the dose of each worker should be maintained at least for a period of 30 years. With this purpose, an online system, called 'IntDosWeb', was developed with the objective of the management for data dosimetric of internal monitoring programme. The system IntDosWeb, based on free software, was developed in programming language PHP and environment database PostgreSQL. This system is to be available at the local net, Intranet. The database maintains information about identification of the worker that handles non-sealed radioactive sources, physical and chemical characteristics of the radionuclides, monitoring types, measurement data and the dose. This system is able to generate annual reports of the individuals and the historical dose. Several simulation cases have been put into effect to check the on-line software functional capabilities. The users can access the dosimetric information according to following database field: monitoring period, monitoring type, intake pattern, radionuclide type and monitoring data from a specific installation or from each worker. The system was tested in the routinely service of internal dosimetry at IPEN. The rastreability of the information made in the internal monitoring programme was a success and also guaranteeing the reliability and integrity of the stored information. The IntDosWeb was shown as a helpful tool for analysis of the committed effective dose in the radiation protection programme, besides obeying the legal demands of the Brazilian Regulatory Commission. (author)

Bio-inspired digital signal processing for fast radionuclide mixture identification

Science.gov (United States)

Thevenin, M.; Bichler, O.; Thiam, C.; Bobin, C.; Lourenço, V.

2015-05-01

Countries are trying to equip their public transportation infrastructure with fixed radiation portals and detectors to detect radiological threat. Current works usually focus on neutron detection, which could be useless in the case of dirty bomb that would not use fissile material. Another approach, such as gamma dose rate variation monitoring is a good indication of the presence of radionuclide. However, some legitimate products emit large quantities of natural gamma rays; environment also emits gamma rays naturally. They can lead to false detections. Moreover, such radio-activity could be used to hide a threat such as material to make a dirty bomb. Consequently, radionuclide identification is a requirement and is traditionally performed by gamma spectrometry using unique spectral signature of each radionuclide. These approaches require high-resolution detectors, sufficient integration time to get enough statistics and large computing capacities for data analysis. High-resolution detectors are fragile and costly, making them bad candidates for large scale homeland security applications. Plastic scintillator and NaI detectors fit with such applications but their resolution makes identification difficult, especially radionuclides mixes. This paper proposes an original signal processing strategy based on artificial spiking neural networks to enable fast radionuclide identification at low count rate and for mixture. It presents results obtained for different challenging mixtures of radionuclides using a NaI scintillator. Results show that a correct identification is performed with less than hundred counts and no false identification is reported, enabling quick identification of a moving threat in a public transportation. Further work will focus on using plastic scintillators.

Transport and accumulation of radionuclides in the marine sediment of Urazoko Bay

International Nuclear Information System (INIS)

Nagaya, Yutaka; Nakamura, Kiyoshi

1976-01-01

Concentrations of 60 Co and other radionuclides in surface sediment samples were investigated in and around Urazoko Bay, Fukui Prefecture, where a nuclear power plant has been operating since 1969 and the radioactive waste effluent has been released into the sea. The main source of 90 Sr and 137 Cs was recognized to be radioactive fallout from nuclear explosions, whereas 60 Co was considered to originate from the nuclear power reactor. For evaluating radioactive pollution characteristics of the sea bottom, the behaviour of 60 Co was investigated using the 137 Cs concentration as an indicator of the radionuclide sorption capability or accumulation capability of the sediment. No seasonal variation was observed in the distribution pattern of the 60 Co/ 137 Cs ratio and the retention of the heavy initial discharge in 1969 is considered to dominate the radionuclide level in the sediment. The 60 Co contamination in the sediment, expressed as the 60 Co/ 137 Cs ratio, in this narrow and semi-closed bay was found to vary according to a simple exponential function of the distance from the discharge outlet. It was found that the contamination is spreading out gradually from Urazoko Bay to outer regions. Also the correlation between the amount of discharged radioactive waste and the variation of the 60 Co level in the sediment was investigated. (auth.)

Comparative evaluation of several small mammal species as monitors of heavy metals, radionuclides, and selected organic compounds in the environment

International Nuclear Information System (INIS)

Talmage, S.S.; Walton, B.T.

1990-08-01

The primary purpose of this study was to evaluate which small mammal species are the best monitors of specific environmental contaminants. The evaluation is based on the published literature and on an analysis of small mammals trapped at several sites on the Oak Ridge National Laboratory (ORNL) Reservation in Oak Ridge, Tennessee. Studies on the uptake of heavy metals, radionuclides, and organic chemicals are reviewed in Chapter II to evaluate several small mammal species for their capacity to serve as sentinels for the presence, accumulation, and effects of various contaminants. Where several species were present at a site, a comparative evaluation was made and species are ranked for their capacity to serve as monitors of specific contaminants. Food chain accumulation and food habits of the species are used to establish a relationship with suitability as a biomonitor. Tissue-specific concentration factors were noted in order to establish target tissues. Life histories, habitat, and food habits are reviewed in order to make generalizations concerning the ability of similar taxa to serve as biomonitor. Finally, the usefulness of several small mammal species as monitors of three contaminants -- benzo[a]pyrene, mercury, and strontium-90 -- present on or near the ORNL facilities was investigated. 133 refs., 5 figs., 20 tabs

Comparative evaluation of several small mammal species as monitors of heavy metals, radionuclides, and selected organic compounds in the environment

Energy Technology Data Exchange (ETDEWEB)

Talmage, S.S. (Tennessee Univ., Knoxville, TN (USA) Oak Ridge National Lab., TN (USA)); Walton, B.T. (Oak Ridge National Lab., TN (USA))

1990-08-01

The primary purpose of this study was to evaluate which small mammal species are the best monitors of specific environmental contaminants. The evaluation is based on the published literature and on an analysis of small mammals trapped at several sites on the Oak Ridge National Laboratory (ORNL) Reservation in Oak Ridge, Tennessee. Studies on the uptake of heavy metals, radionuclides, and organic chemicals are reviewed in Chapter II to evaluate several small mammal species for their capacity to serve as sentinels for the presence, accumulation, and effects of various contaminants. Where several species were present at a site, a comparative evaluation was made and species are ranked for their capacity to serve as monitors of specific contaminants. Food chain accumulation and food habits of the species are used to establish a relationship with suitability as a biomonitor. Tissue-specific concentration factors were noted in order to establish target tissues. Life histories, habitat, and food habits are reviewed in order to make generalizations concerning the ability of similar taxa to serve as biomonitor. Finally, the usefulness of several small mammal species as monitors of three contaminants -- benzo(a)pyrene, mercury, and strontium-90 -- present on or near the ORNL facilities was investigated. 133 refs., 5 figs., 20 tabs.

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions, Calendar Year 2010

International Nuclear Information System (INIS)

2011-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada National Security Site (NNSS, formerly the Nevada Test Site) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) (CFR, 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as those from the damaged Fukushima nuclear power plant in Japan. Because this report is intended to discuss radioactive air emissions during calendar year 2010, data on radionuclides in air from the 2011 Fukushima nuclear power plant releases are not presented but will be included in the report for calendar year 2011. The NNSS demonstrates compliance with the NESHAP

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions, Calendar Year 2011

International Nuclear Information System (INIS)

2012-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan. Radionuclides from the Fukushima nuclear power plant were detected at the NNSS in March 2011 and are discussed further in Section III. The NNSS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the EPA for use on the

Determination of correlation and scaling factors of radionuclides in the contaminated soils from experimental lysimetric field

International Nuclear Information System (INIS)

Dulanska, S.

2009-04-01

Correlation and regression analyses are often confused in evaluations of experimental results. However, the correlation analysis describes the influence of one variable level changes to changes of the other variable levels and holds for the variables measured quantitatively. It detects the existence and nature of dependencies, measures the goodness-of-fit of an actual model and tests the hypotheses of statistical significance of the model proposed. The y variable does not depend on the x variable but two random variables, x and y, vary jointly. The regression model, however, takes the independent variable x as a non-random variable and the dependent variable y as a random one, in contrast to the correlation model. There are a number of common difficulties associated with real datasets. The first involves the detection and elimination of outliers in the original data. We think of data as being divided into two classes (1) good observations (the majority of data) reflecting population scatter of data and (2) the outliers (if any) being a part of the so-called influential fatal points or noise. The goal of any outlier detection is to find this true partition and, thus, separate good from outlying observations. Regression diagnostics represent procedures for an examination of the regression triplet (data, model, method) for identification of (a) the data quality for a proposed model; (b) the model quality for a given set of data; (c) a fulfillment of all least-squares assumptions. Scheme and statistical evaluation of suitable scaling models for the monitoring of observed radionuclides 241 Am, 238 Pu and 239 , 240 Pu in real contaminated soils of experimental lysimetric field on the basis of experimental results were the objectives. Suitable scaling models for 241 Am, 238 Pu and 239 , 240 Pu radionuclide monitoring in contaminated soil samples placed in an experimental lysimeter have been proven by a regression triplet analysis. Estimates of and parameters for all

Radionuclide generators

International Nuclear Information System (INIS)

Lambrecht, R.M.; Wollongong Univ.; Tomiyoshi, K.; Sekine, T.

1997-01-01

The present status and future directions of research and development on radionuclide generator technology are reported. The recent interest to develop double-neutron capture reactions for production of in vivo generators; neutron rich nuclides for radio-immunotherapeutic pharmaceuticals: and advances with ultra-short lived generators is highlighted. Emphasis is focused on: production of the parent radionuclide; the selection and the evaluation of support materials and eluents with respect to the resultant radiochemical yield of the daughter, and the breakthrough of the radionuclide parent: and, the uses of radionuclide generators in radiopharmaceutical chemistry, biomedical and industrial applications. The 62 Zn → 62 Cu, 66 Ni → 66 Cu, 103m Rh → 103 Rh, 188 W → 188 Re and the 225 Ac → 221 Fr → 213 Bi generators are predicted to be emphasized for future development. Coverage of the 99 Mo → 99m Tc generator was excluded, as it the subject of another review. The literature search ended June, 1996. (orig.)

Osmotic blood-brain barrier modification: clinical documentation by enhanced CT scanning and/or radionuclide brain scanning

International Nuclear Information System (INIS)

Neuwelt, E.A.; Specht, H.D.; Howieson, J.; Haines, J.E.; Bennett, M.J.; Hill, S.A.; Frenkel, E.P.

1983-01-01

Results of initial clinical trials of brain tumor chemotherapy after osmotic blood-brain barrier disruption are promising. In general, the procedure is well tolerated. The major complication has been seizures. In this report, data are presented which indicate that the etiology of these seizures is related to the use of contrast agent (meglumine iothalamate) to monitor barrier modification. A series of 19 patients underwent a total of 85 barrier modification procedures. Documentation of barrier disruption was monitored by contrast-enhanced computed tomographic (CT) scanning, radionuclide brain scanning, or a combination of both techniques. In 56 procedures (19 patients) monitored by enhanced CT, seizures occurred a total of 10 times in eight patients. Twenty-three barrier modification procedures (in nine of these 19 patients) documented by nuclear brain scans alone, however, resulted in only one focal motor seizure in each of two patients. In eight of the 19 patients who had seizures after barrier disruption and enhanced CT scan, four subsequently had repeat procedures monitored by radionuclide scan alone. In only one of these patients was further seizure activity noted; a single focal motor seizure was observed. Clearly, the radionuclide brain scan does not have the sensitivity and spatial resolution of enhanced CT, but at present it appears safer to monitor barrier modification by this method and to follow tumor growth between barrier modifications by enhanced CT. Four illustrative cases showing methods, problems, and promising results are presented

Metals, Metalloids and Radionuclides in the Baltic Sea Ecosystem

International Nuclear Information System (INIS)

Szefer, P.

2002-01-01

The state of knowledge of the distribution, bioavailability, biomagnification, discrimination, fate and sources of chemical pollutants (metals, metalloids, radionuclides and nutrients) in all compartments (atmosphere, water, deposits, biota) of the Baltic environment is presented. Particular components of the Baltic ecosystem are considered as potential monitors of pollutants. Budgets of chemical elements and the ecological status of the Baltic Sea in the past, present and future are presented. Estimates of health risks to man in respect to some toxic metals and radionuclides in fish and seafood are briefly discussed. The content of the book makes possible the identification of gaps in our environmental knowledge of the Baltic Sea, with certain sections establishing possible priorities, key areas or strategies for future research

Application of the nuclide identification system SHAMAN in monitoring the Comprehensive Test Ban Treaty

International Nuclear Information System (INIS)

Aarnio, P.A.; Ala-Heikkilae, J.J.; Hakulinen, T.T.; Nikkinen, M.T.

1998-01-01

SHAMAN is an expert for qualitative and quantitative radionuclide identification in gamma spectrometry. SHAMAN requires as input the calibrations, peak search, and fitting results from reliable spectral analysis software, such as SAMPO. SHAMAN uses a comprehensive reference library with 2600 radionuclides and 80 000 gamma-lines, as well as a rule base consisting of sixty inference rules. Identification results are presented both via an interactive graphical interface and in the form of configurable text reports. An organization has been established for monitoring the recent Comprehensive Test Ban Treaty. For radionuclide monitoring, 80 stations will be set up around the world. Air-filter gamma-spectra will be collected from these stations on a daily basis and they will need to be reliably analyzed with minimum turnaround time. SHAMAN is currently being evaluated within the prototype monitoring system as an automated radionuclide identifier, in parallel with existing radionuclide identification software. In air-filter monitoring, very low concentrations of radionuclides are measured from bulky sources in close geometry and with long counting time. In this case true coincidence summing and self-absorption become important factors. SHAMAN is able to take into account these complicated phenomena, and the results it produces have been found to be very reliable and accurate. (author)

Recent developments in assessment of long-term radionuclide behavior in the geosphere-biosphere subsystem

International Nuclear Information System (INIS)

Smith, G.M.; Smith, K.L.; Kowe, R.; Pérez-Sánchez, D.; Thorne, M.; Thiry, Y.; Read, D.; Molinero, J.

2014-01-01

Decisions on permitting, controlling and monitoring releases of radioactivity into the environment rely on a great variety of factors. Important among these is the prospective assessment of radionuclide behavior in the environment, including migration and accumulation among and within specific environmental media, and the resulting environmental and human health impacts. Models and techniques to undertake such assessments have been developed over several decades based on knowledge of the ecosystems involved, as well as monitoring of previous radionuclide releases to the environment, laboratory experiments and other related research. This paper presents developments in the assessment of radiation doses and related research for some of the key radionuclides identified as of potential significance in the context of releases to the biosphere from disposal facilities for solid radioactive waste. Since releases to the biosphere from disposal facilities involve transfers from the geosphere to the biosphere, an important aspect is the combined effects of surface hydrology, near-surface hydrogeology and chemical gradients on speciation and radionuclide mobility in the zone in which the geosphere and biosphere overlap (herein described as the geosphere-biosphere subsystem). In turn, these aspects of the environment can be modified as a result of environmental change over the thousands of years that have to be considered in radioactive waste disposal safety assessments. Building on the experience from improved understanding of the behavior of the key radionuclides, this paper proceeds to describe development of a generic methodology for representing the processes and environmental changes that are characteristic of the interface between the geosphere and the biosphere. The information that is provided and the methodology that is described are based on international collaborative work implemented through the BIOPROTA forum, (www.bioprota.org). - Highlights: • Geological

Environmental and Source Monitoring for Purposes of Radiation Protection. Safety Guide (Spanish ed.)

International Nuclear Information System (INIS)

2010-01-01

The purpose of this Safety Guide is to provide international guidance, coherent with contemporary radiation protection principles and IAEA safety requirements, on the strategy of monitoring in relation to: (a) control of radionuclide discharges under practice conditions, and (b) intervention, such as in cases of nuclear or radiological emergencies or past contamination of areas with long lived radionuclides. Three categories of monitoring are discussed: monitoring at the source of the discharge (source monitoring), monitoring in the environment (environmental monitoring) and monitoring of individual exposure in emergencies (individual monitoring). The Safety Guide also provides general guidance on assessment of the doses to critical groups of the population due to the presence of radioactive materials or radiation fields in the environment both from routine operation of nuclear and other related facilities (practice) and from nuclear or radiological emergencies and past contamination of areas with long lived radionuclides (intervention). The dose assessments are based on the results of source monitoring, environmental monitoring, individual monitoring or their combinations. This Safety Guide is primarily intended for use by national regulatory bodies and other agencies involved in national systems of radiation monitoring, as well as by operators of nuclear installations and other facilities where natural or human made radionuclides are treated and monitored. Contents: 1. Introduction; 2. Meeting regulatory requirements for monitoring in practices and interventions; 3. Responsibilities for monitoring; 4. Generic aspects of monitoring programmes; 5. Programmes for monitoring in practices and interventions; 6. Technical conditions for monitoring procedures; 7. Considerations in dose assessment; 8. Interpretation of monitoring results; 9. Quality assurance; 10. Recording of results; 11. Education and training; Glossary.

The biokinetic of incorporates radionuclides; Die Biokinetik von inkorporierten Radionukliden

Energy Technology Data Exchange (ETDEWEB)

Breustedt, Bastian [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Inst. fuer Strahlenforschung; Giussani, Augusto [Bundesamt fuer Strahlenschutz, Oberschleissheim (Germany). Arbeitsgruppe ' ' Externe und interne Dosimetrie, Biokinetik' '

2017-08-01

Incorporated radionuclides from nuclear accidents, fission product releases or nuclear medical administration are distributed in the human body in organs and tissue, absorbed 9or excreted. The interpretation of incorporation monitoring results and the estimation of the internal doses that cannot be measured directly need mathematical methods and the formulation of biokinetic models.

MODELLING OF RADIONUCLIDE MIGRATION IN THE SYSTEM OF NUCLEAR POWER PLANT BIOLOGICAL PONDS

Directory of Open Access Journals (Sweden)

Ю. Кутлахмедов

2011-04-01

Full Text Available Migration of radionuclide coming from nuclear power plant into the system of biological pondsand then into the water reservoir-cooler is considered in the article. The theme of the work ismodeling of radionuclide migration process in the system of biological ponds on the example of thePivdennoukrainska nuclear power plant using chamber models method. Typical water ecosystemconsisting of three chambers (chamber-water, chamber-biota and chamber-bed silt was the basistaken by the authors. Application of chamber models method allowed authors to develop thedynamic chamber model of radionuclide migration in nuclear power plant biological ponds. Thismodel allows to forecast values and dynamics of radioactive water pollution based on limitedecosystem monitoring data. Thus, parameters of radioactive capacity of nuclear power plantbiological ponds system and water reservoir-cooler were modeled by authors, the estimation andprognosis of radionuclide distribution and accumulation in the system of nuclear power plantbiological ponds were done. Authors also explain the roles of basin water, biomass and bed silt inradionuclide deposition

Rulison Monitoring Plan

Energy Technology Data Exchange (ETDEWEB)

None

2010-07-01

The Project Rulison Monitoring Plan has been developed as part of the U.S. Department of Energy (DOE) Office of Legacy Management's mission to protect human health and the environment. The purpose of the plan is to monitor fluids from gas wells for radionuclides that would indicate contamination is migrating from the Rulison detonation zone to producing gas wells, allowing action to be taken before the contamination could pose a risk. The Monitoring Plan (1) lists the contaminants present and identifies those that have the greatest potential to migrate from the detonation zone (radionuclide source term), (2) identifies locations that monitor the most likely transport pathways, (3) identifies which fluids will be sampled (gas and liquid) and why, (4) establishes the frequency of sampling, and (5) specifies the most practical analyses and where the analysis results will be reported. The plan does not affect the long-term hydrologic sampling conducted by DOE since 1972, which will continue for the purpose of sampling shallow groundwater and surface water near the site. The Monitoring Plan was developed in anticipation of gas wells being drilled progressively nearer the Rulison site. DOE sampled 10 gas wells in 1997 and 2005 at distances ranging from 2.7 to 7.6 miles from the site to establish background concentrations for radionuclides. In a separate effort, gas industry operators and the Colorado Oil and Gas Conservation Commission (COGCC) developed an industry sampling and analysis plan that was implemented in 2007. The industry plan requires the sampling of gas wells within 3 miles of the site, with increased requirements for wells within 1 mile of the site. The DOE plan emphasizes the sampling of wells near the site (Figure 1), specifically those with a bottom-hole location of 1 mile or less from the detonation, depending on the direction relative to the natural fracture trend of the producing formation. Studies indicate that even the most mobile

Development of a new generation of waste form for entrapment and immobilization of highly volatile and soluble radionuclides.

Energy Technology Data Exchange (ETDEWEB)

Rodriguez, Mark Andrew; Bencoe, Denise Nora; Brinker, C. Jeffrey; Murphy, Andrew Wilson; Holt, Kathleen Caroline; Turnham, Rigney; Kruichak, Jessica Nicole; Tellez, Hernesto; Miller, Andy; Xiong, Yongliang; Pohl, Phillip Isabio; Ockwig, Nathan W.; Wang, Yifeng; Gao, Huizhen

2010-09-01

The United States is now re-assessing its nuclear waste disposal policy and re-evaluating the option of moving away from the current once-through open fuel cycle to a closed fuel cycle. In a closed fuel cycle, used fuels will be reprocessed and useful components such as uranium or transuranics will be recovered for reuse. During this process, a variety of waste streams will be generated. Immobilizing these waste streams into appropriate waste forms for either interim storage or long-term disposal is technically challenging. Highly volatile or soluble radionuclides such as iodine ({sup 129}I) and technetium ({sup 99}Tc) are particularly problematic, because both have long half-lives and can exist as gaseous or anionic species that are highly soluble and poorly sorbed by natural materials. Under the support of Sandia National Laboratories (SNL) Laboratory-Directed Research & Development (LDRD), we have developed a suite of inorganic nanocomposite materials (SNL-NCP) that can effectively entrap various radionuclides, especially for {sup 129}I and {sup 99}Tc. In particular, these materials have high sorption capabilities for iodine gas. After the sorption of radionuclides, these materials can be directly converted into nanostructured waste forms. This new generation of waste forms incorporates radionuclides as nano-scale inclusions in a host matrix and thus effectively relaxes the constraint of crystal structure on waste loadings. Therefore, the new waste forms have an unprecedented flexibility to accommodate a wide range of radionuclides with high waste loadings and low leaching rates. Specifically, we have developed a general route for synthesizing nanoporous metal oxides from inexpensive inorganic precursors. More than 300 materials have been synthesized and characterized with x-ray diffraction (XRD), BET surface area measurements, and transmission electron microscope (TEM). The sorption capabilities of the synthesized materials have been quantified by using stable

Development of a new generation of waste form for entrapment and immobilization of highly volatile and soluble radionuclides

International Nuclear Information System (INIS)

Rodriguez, Mark Andrew; Bencoe, Denise Nora; Brinker, C. Jeffrey; Murphy, Andrew Wilson; Holt, Kathleen Caroline; Turnham, Rigney; Kruichak, Jessica Nicole; Tellez, Hernesto; Miller, Andy; Xiong, Yongliang; Pohl, Phillip Isabio; Ockwig, Nathan W.; Wang, Yifeng; Gao, Huizhen

2010-01-01

The United States is now re-assessing its nuclear waste disposal policy and re-evaluating the option of moving away from the current once-through open fuel cycle to a closed fuel cycle. In a closed fuel cycle, used fuels will be reprocessed and useful components such as uranium or transuranics will be recovered for reuse. During this process, a variety of waste streams will be generated. Immobilizing these waste streams into appropriate waste forms for either interim storage or long-term disposal is technically challenging. Highly volatile or soluble radionuclides such as iodine ( 129 I) and technetium ( 99 Tc) are particularly problematic, because both have long half-lives and can exist as gaseous or anionic species that are highly soluble and poorly sorbed by natural materials. Under the support of Sandia National Laboratories (SNL) Laboratory-Directed Research and Development (LDRD), we have developed a suite of inorganic nanocomposite materials (SNL-NCP) that can effectively entrap various radionuclides, especially for 129 I and 99 Tc. In particular, these materials have high sorption capabilities for iodine gas. After the sorption of radionuclides, these materials can be directly converted into nanostructured waste forms. This new generation of waste forms incorporates radionuclides as nano-scale inclusions in a host matrix and thus effectively relaxes the constraint of crystal structure on waste loadings. Therefore, the new waste forms have an unprecedented flexibility to accommodate a wide range of radionuclides with high waste loadings and low leaching rates. Specifically, we have developed a general route for synthesizing nanoporous metal oxides from inexpensive inorganic precursors. More than 300 materials have been synthesized and characterized with x-ray diffraction (XRD), BET surface area measurements, and transmission electron microscope (TEM). The sorption capabilities of the synthesized materials have been quantified by using stable isotopes I and

Stable elements and radionuclides in shoreline alder stands at Olkiluoto in 2005

International Nuclear Information System (INIS)

Roivainen, P.

2006-08-01

In Finland, the final disposal of spent nuclear fuel from Finnish nuclear power plants is to take place in a repository, which will be built in Olkiluoto bedrock. According to the current plans, operation of the facility will start in 2020. Before this, a safety case has to be drawn up to substantiate the safety of the final disposal solution. The drawing up of the safety case also involves an assessment of impact on organisms other than human. Several radionuclides have a stable chemical analogue. Chemical analogues often display similar behaviour in the forest ecosystem. For this reason, information about radionuclides can also be obtained by studying stable elements. The purpose of this thesis was to study the migration of elements, radionuclides in particular, in the food webs of the Olkiluoto forest ecosystem. The objective was to produce concentration ratios between the various sub-components of the forest ecosystem. These ratios can be utilised in modelling. Three alder stands on the shores of Olkiluoto were used as monitoring plots. Littoral alder stands are an important biotope in terms of a recipient of the potential radionuclide contamination from the repository. Yet, research on littoral alder stands has so far been quite limited. From all the monitoring plots, a sample was taken of humus, mineral soil, understorey, plant roots and forest litter. Small mammals and earthworms were also to be caught from the monitoring plots, but no earthworms could be caught in any of the areas. All the collected samples were analysed for element concentrations using the ICP-AES method. Soil and plant samples were also analysed with a gamma spectrometer for activity concentrations of gamma active radionuclides. Activity concentrations of Cs-137 and K-40 could be determined in all soil and plant samples. The highest activity concentration of Cs-137 was found in humus, and the lowest in mineral soil. The activity concentration of K-40 was at its highest in mineral soil and

Sorption and desorption reactions of radionuclides with a crushed basalt-bentonite packing material

International Nuclear Information System (INIS)

Barney, G.S.; Lane, D.L.; Allen, C.C.; Jones, T.E.

1985-04-01

Current design of waste packages for disposal of high-level radioactive wastes in underground basalt formations includes a layer of packing material that surrounds the waste container. One of the functions of this material is to limit the release of radionuclides from a breached container into groundwater by providing a low hydraulic conductivity zone and by sorbing dissolved radionuclides. The objective of this study was to assess the radionuclide sorption capability of a proposed packing material composed of 25% sodium bentonite and 75% crushed basalt (by weight). Sorption and desorption reactions of several important waste radioelements (neptunium, uranium, plutonium, technetium, selenium, and radium) were investigated in the absence of air at 90 0 C. Uranium and neptunium were sorbed by slow reactions that follow first-order kinetics. The reaction rates are probably controlled by reduction of weakly sorbed uranium(VI) and neptunium(V) by ferrous iron in the crushed basalt component. Technetium(VII) was not reduced or sorbed under these conditions. Freundlich sorption and desorption isotherms for a given radionuclide were non-singular and show a strong tendency for sorption hysteresis. Applying the isotherm data to a one-dimensional transport model indicated that hysteretic sorption on the packing material provides an important safety factor in controlling releases of some radionuclides

Radionuclide Air Emission Report for 2009

Energy Technology Data Exchange (ETDEWEB)

Wahl, Linnea

2010-06-01

Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the EPA radioactive air emission regulations in 40CFR61, Subpart H (EPA 1989). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2009, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]). These minor sources included more than 100 stack sources and one source of diffuse emissions. There were no unplanned emissions from the Berkeley Lab site. Emissions from minor sources (stacks and diffuse emissions) either were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2009 is 7.0 x 10{sup -3} mrem/yr (7.0 x 10{sup -5} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 1.5 x 10{sup -1} person-rem (1.5 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2009.

Radionuclides in terrestrial ecosystems

International Nuclear Information System (INIS)

Allen, S.E.; Horrill, A.D.; Howard, B.J.; Lowe, V.P.W.; Parkinson, J.A.

1983-07-01

The subject is discussed under the headings: concentration and spatial distribution of radionuclides in grazed and ungrazed saltmarshes; incorporation of radionuclides by sheep grazing on an estuarine saltmarsh; inland transfer of radionuclides by birds feeding in the estuaries and saltmarshes at Ravenglass; radionuclides in contrasting types of coastal pastures and taken up by individual plant species found in west Cumbria; procedures developed and used for the measurement of alpha and gamma emitters in environmental materials. (U.K.)

The accumulation of radionuclides by Dreissena polymorpha molluscs - The Accumulation of Radionuclides from Water and Food in the Dreissena polymorpha Mollusks

Energy Technology Data Exchange (ETDEWEB)

Jefanova, O.; Marciulioniene, D. [Nature Research Centre, Akademijos str. 2, LT-08412 Vilnius, Lietuva (Lithuania)

2014-07-01

The specific activity of {sup 137}Cs, {sup 60}Co, {sup 54}Mn, {sup 90}Sr was measured in mollusks Dreissena polymorpha samples from lake Drukshiai that is the cooling pond of the Ignalina NPP. Item the accumulation of {sup 137}Cs, {sup 90}Sr, {sup 144}Ce, {sup 106}Ru in the mollusks from water and from phytoplankton which is a part of their diet was evaluated under laboratory conditions. The data of long-term (1991-2009) studies conducted at six monitoring stations of lake Drukshiai show that in 1991 {sup 137}Cs in mollusks Dreissena polymorpha was found only in that lake's area which was influenced by the effluent that got into lake from the industrial drainage channel of Ignalina NPP. In later periods of the investigation the {sup 137}Cs specific activity was detected in mollusks samples which had been collected at other monitoring stations (the aquatory of lake Drukshiai). Meanwhile {sup 60}Co and {sup 54}Mn in Dreissena polymorpha were detected only in that lake's area which was impacted by the industrial drainage channel. The data of long-term investigation show that the major amount of radionuclides has come into lake Drukshiai through the industrial drainage system of Ignalina NPP. Albeit {sup 137}Cs, {sup 90}Sr, {sup 144}Ce, {sup 106}Ru get into the mollusks through a large amount of the water rather than from the food (phytoplankton), therefore the food can also be the main source of radionuclides in the organism of these mollusks in aquatic environment when there are low levels of specific activities of these radionuclides. (authors)

MAFF monitoring of the terrestrial environment

International Nuclear Information System (INIS)

Sherlock, J.C.

1991-01-01

This paper addresses the MAFF food surveillance programme, in particular our Terrestrial Radioactivity Monitoring Programme (TRAMP), and the estimation of dietary intake of radionuclides. The MAFF programme exists primarily to demonstrate that authorized discharges of radioactivity to the environment do not result in individuals receiving doses of radiation in excess of accepted limits. The estimation radionuclide intake ensures over estimation rather than underestimation of dose. Improvements in detection limits and absorption level research could lower the calculated dose to man from radionuclides in food without losing their validity. (author)

Radionuclide data

International Nuclear Information System (INIS)

Anon.

1992-01-01

Chapter 8 presents tables on selected alpha, beta, gamma and x-ray emitters by increasing energy; information on specific activity for selected radionuclides; naturally occurring radionuclides; the natural decay series; and the artificially produced neptunium series. A table of alpha emitters is listed by increasing atomic number and by energy. The table of β emitters presented is useful in identifying β emitters whose energies and possibly half-lives have been determined by standard laboratory techniques. It is also a handy guide to β-emitting isotopes for applications requiring specific half-lives and/or energies. Gamma rays for radionuclides of importance to radiological assessments and radiation protection are listed by increasing energy. The energies and branching ratios are important for radionuclide determinations with gamma spectrometry detectors. This section also presents a table of x-ray energies which are useful for radiochemical analyses. A number of nuclides emit x-rays as part of their decay scheme. These x-rays may be counted with Ar proportional counters, Ge planar or n-type Ge co-axial detectors, or thin crystal NaI(T1) scintillation counters. In both cases, spectral measurements can be made and both qualitative and quantitative information obtained on the sample. Nuclear decay data (energy and probability by radiation type) for more than one hundred radionuclides that are important to health physicists are presented in a schematic manner

Airborne remote sensing of estuarine intertidal radionuclide concentrations

International Nuclear Information System (INIS)

Rainey, M.P.

1999-08-01

The ability to map industrial discharges through remote sensing provides a powerful tool in environmental monitoring. Radionuclide effluents have been discharged, under authorization, into the Irish Sea from BNFL (British Nuclear Fuels Pic.) sites at Sellafield and Springfields since 1952. The quantitative mapping of this anthropogenic radioactivity in estuarine intertidal zones is crucial for absolute interpretations of radionuclide transport. The spatial resolutions of traditional approaches e.g. point sampling and airborne gamma surveys are insufficient to support geomorphic interpretations of the fate of radionuclides in estuaries. The research presented in this thesis develops the use of airborne remote sensing to derive high-resolution synoptic data on the distribution of anthropogenic radionuclides in the intertidal areas of the Ribble Estuary, Lancashire, UK. From multidate surface sediment samples a significant relationship was identified between the Sellafield-derived 137 Cs and 241 Am and clay content (r 2 = 0.93 and 0.84 respectively). Detailed in situ, and laboratory, reflectance (0.4-2.5μm) experiments demonstrated that significant relationships exist between Airborne Thematic Mapper (ATM) simulated reflectance and intertidal sediment grain-size. The spectral influence of moisture on the reflectance characteristics of the intertidal area is also evident. This had substantial implications for the timing of airborne image acquisition. Low-tide Daedalus ATM imagery (Natural Environmental Research Council) was collected of the Ribble Estuary on May 30th 1997. Preprocessing and linear unmixing of the imagery allowed accurate sub-pixel determinations of sediment clay content distributions (r 2 = 0.81). Subsequently, the established relationships between 137 Cs and 241 Am and sediment grain-size enabled the radionuclide activity distributions across the entire intertidal area (92 km 2 ) to be mapped at a geomorphic scale (1.75 m). The accuracy of these maps

Biogeochemical Processes Controlling Microbial Reductive Precipitation of Radionuclides

International Nuclear Information System (INIS)

Fredrickson, James K.; Brooks, Scott C.

2004-01-01

This project is focused on elucidating the principal biogeochemical reactions that govern the concentrations, chemical speciation, and distribution of the redox sensitive contaminants uranium (U) and technetium (Tc) between the aqueous and solid phases. The research is designed to provide new insights into the under-explored areas of competing geochemical and microbiological oxidation-reduction reactions that govern the fate and transport of redox sensitive contaminants and to generate fundamental scientific understanding of the identity and stoichiometry of competing microbial reduction and geochemical oxidation reactions. These goals and objectives are met through a series of hypothesis-driven tasks that focus on (1) the use of well-characterized microorganisms and synthetic and natural mineral oxidants, (2) advanced spectroscopic and microscopic techniques to monitor redox transformations of U and Tc, and (3) the use of flow-through experiments to more closely approximate groundwater environments. The results are providing an improved understanding and predictive capability of the mechanisms that govern the redox dynamics of radionuclides in subsurface environments. For purposes of this poster, the results are divided into three sections: (1) influence of Ca on U(VI) bioreduction; (2) localization of biogenic UO 2 and TcO 2 ; and (3) reactivity of Mn(III/IV) oxides.

Radionuclides in domestic and imported foods in the United States, 1987-1992

International Nuclear Information System (INIS)

Cunningham, W.C.; Anderson, D.L.; Baratta, E.J.

1994-01-01

Findings from the U.S. Food and Drug Administration's Radionuclides in Foods program are summarized for foods collected between October 1, 1986, and September 30, 1992. Concentrations of radionuclide activity in the Total Diet Study and reactor-survey foods were in Range I or low in Range II of the surveillance and control recommendations of the Federal Radiation Council; no control actions were suggested. Dietary intake of 90 Sr continued the general decline observed since 1961. Approximately 2600 test portions of imported foods were analyzed for contamination associated with the Chernobyl nuclear accident. Concentrations of radionuclide activity were below limits of detection for the vast majority of the imported food test portions but were above the levels of concern for 23 portions. Since 1986, the fraction of imported food test portions having measurable amounts of contamination has steadily declined, as have the average concentrations of radionuclide activity; however, contamination is still occasionally found. Continued monitoring of both domestic and imported foods is planned. 17 refs., 2 figs., 2 tabs

Natural radionuclides in soils from Sao Paulo State cerrado forest

International Nuclear Information System (INIS)

Miranda, Marcia V.F.E.S.; Farias, Emerson E.G. de; Cantinha, Rebeca S.; Franca, Elvis J. de

2015-01-01

Considering the long life history, forests should be preferentially evaluated for the monitoring of radionuclides, mainly artificial radioisotopes. However, little is known about nuclides from Uranium and Thorium series, as well as, K-40, in soils from the Sao Paulo State forests. Soils are the main reservoir of natural radionuclides for vegetation, thereby deserving attention. Taking into account the advantages of High-Resolution Gamma-ray Spectrometry (HRGS), diverse radionuclides can be quantified simultaneously. In this work natural radionuclides in soils from the Estacao Ecologica de Assis were evaluated by HRGS. Samples of 0-10 cm depth were collected under crown projection of most abundant tree species of long-term plots installed within the Estacao Ecologica de Assis, Sao Paulo State, Brazil. After drying and milling until 0.5 mm particle size, test portions of 30 g were transferred to polypropylene vials, sealed with silicone and kept under controlled conditions until 30 days to achieve secular equilibrium. A group of gamma-ray spectrometers was used to analyze about 27 samples by 80,000 seconds. Activity concentrations of Pb-214, Ac-228 and K-40 and their respective expanded analytical uncertainties at the 95% confidence level were calculated by Genie software from Canberra. Abnormal values were not detected for radionuclides in soils samples, however K-40 activity concentrations changed considerably due to the mineral cycling, in which K and, consequently K-40, is mainly stocked in vegetation in spite of soils. (author)

Natural radionuclides in soils from Sao Paulo State cerrado forest

Energy Technology Data Exchange (ETDEWEB)

Miranda, Marcia V.F.E.S.; Farias, Emerson E.G. de; Cantinha, Rebeca S.; Franca, Elvis J. de, E-mail: mvaleria@cnen.gov.br, E-mail: emersonemiliano@yahoo.com.br, E-mail: rebecanuclear@gmail.com, E-mail: ejfranca@cnen.gov.br [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil)

2015-07-01

Considering the long life history, forests should be preferentially evaluated for the monitoring of radionuclides, mainly artificial radioisotopes. However, little is known about nuclides from Uranium and Thorium series, as well as, K-40, in soils from the Sao Paulo State forests. Soils are the main reservoir of natural radionuclides for vegetation, thereby deserving attention. Taking into account the advantages of High-Resolution Gamma-ray Spectrometry (HRGS), diverse radionuclides can be quantified simultaneously. In this work natural radionuclides in soils from the Estacao Ecologica de Assis were evaluated by HRGS. Samples of 0-10 cm depth were collected under crown projection of most abundant tree species of long-term plots installed within the Estacao Ecologica de Assis, Sao Paulo State, Brazil. After drying and milling until 0.5 mm particle size, test portions of 30 g were transferred to polypropylene vials, sealed with silicone and kept under controlled conditions until 30 days to achieve secular equilibrium. A group of gamma-ray spectrometers was used to analyze about 27 samples by 80,000 seconds. Activity concentrations of Pb-214, Ac-228 and K-40 and their respective expanded analytical uncertainties at the 95% confidence level were calculated by Genie software from Canberra. Abnormal values were not detected for radionuclides in soils samples, however K-40 activity concentrations changed considerably due to the mineral cycling, in which K and, consequently K-40, is mainly stocked in vegetation in spite of soils. (author)

Miscellaneous applications of radionuclide imaging

International Nuclear Information System (INIS)

Mishkin, F.S.; Freeman, L.M.

1984-01-01

The procedures discussed in this chapter are either developmental, in limited clinical use, or frankly moribund. A number of radionuclide imaging techniques have proved disappointing when approached from a purely anatomic point of view. This is particularly evident to our colleagues with the explosive growth of the noninvasive imaging procedures, magnetic resonance imaging (NMR), CT, and ultrasound, and the introduction of the less invasive digital radiographic approach to vascular opacification, all of which are capable of providing exquisite anatomic or tissue detail beyond the reach of current or reasonably priced nuclear medicine imaging systems. Yet, most nuclear medicine procedures possess the unique advantage of portraying a physiologic function without interfering with that function. Moreover, the procedures can be employed under conditions of stress, which are likely to bring out pathophysiologic abnormalities that remain masked when unchallenged. Information concerning form without functional data has less meaning than both together. The physiologic information inherent in nuclear medicine imaging may often provide not only key diagnostic information but also illuminate a therapeutic trail. Yet, it is often slighted in favor of the anatomic quest. While mastery of the nuances of imaging details remains critical, radionuclide image interpretation must rest upon a firm physiologic foundation. For this reason, this chapter emphasizes the physiologic approach

U.S. Department of Energy Report, 2005 LANL Radionuclide Air Emissions

Energy Technology Data Exchange (ETDEWEB)

Keith W. Jacobson, David P. Fuehne

2006-09-01

Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2006.

Deposition and interception of radionuclides. Current knowledge and future requirements

International Nuclear Information System (INIS)

1998-12-01

Following an accidental or routine release of radionuclides into the environment, a good knowledge of deposition processes is necessary in order to accurately predict the radiation dose to members of the public. In order to understand the environmental impact of released radionuclides and their transfer through the environment, including the food chain to man, there have been numerous studies on deposition of radionuclides to a range of surfaces such as bare soil, crops, forests, water bodies and urban surfaces. The RADREM committee provides a forum for liaison on UK research and monitoring in the areas of radioactive substances and radioactive waste management. RADREM has set up four sub-committees to cover issues related to radioactivity in the atmospheric, terrestrial and aquatic environments as well as those related radioactive waste management. One of the sub-committee tasks is to organise seminars and workshops on specific topics of interest. The first of these was the workshop on 'Deposition and Interception of Radionuclides: Current knowledge and future requirements' organised last year by the Ministry of Agriculture, Fisheries and Food (MAFF), acting as secretariat for the Terrestrial Environment Sub-Committee (TESC) of RADREM. The intent of this workshop was to provide an opportunity to exchange information on deposition-related aspects between representatives from various interested parties including government, regulatory bodies, industry and research organisations. Through presentations and discussions, this workshop addressed current developments in the areas of deposition and interception of radionuclides by various surfaces and served to identify areas which need further research. Papers were presented on various aspects of deposition and interception of radionuclides including deposition into grass, fruits and other crops as well as deposition into urban areas and forests

Radionuclides in small mammals of the Saskatchewan prairie, including implications for the boreal forest and Arctic tundra

International Nuclear Information System (INIS)

Thomas, P.A.

1995-01-01

The focus of the study reported was to collect and examine baseline data on radionuclides in small prairie mammal food chains and to assess the feasibility of using small mammals as radionuclide monitors in terrestrial ecosystems, in anticipation of possible future nuclear developments in northern Saskatchewan and the Northwest Territories. The study report begins with a literature review that summarizes existing data on radionuclides in small mammals, their food, the ambient environment in Canadian terrestrial ecosystems, principles of terrestrial radioecology, soil and vegetation studies, and food chain studies. It then describes a field study conducted to investigate small mammal food chains at three southwestern Saskatchewan prairie sites. Activities included collection and analysis of water, soil, grains, and foliage samples; trapping of small mammals such as mice and voles, and analysis of gastrointestinal tract samples; and determination of food chain transfer of selected radionuclides from soil to plants and to small mammals. Recommendations are made for future analyses and monitoring of small mammals. Appendices include information on radiochemical methods, soil/vegetation studies and small mammal studies conducted at northern Saskatchewan mine sites, and analyses of variance

Simulations of the x-ray imaging capabilities of the silicon drift detectors (SDD) for the LOFT wide-field monitor

DEFF Research Database (Denmark)

Evangelista, Y.; Campana, R.; Del Monte, E.

2012-01-01

Detector (LAD), carrying an unprecedented effective area of 10 m^2, is complemented by a coded-mask Wide Field Monitor, in charge of monitoring a large fraction of the sky potentially accessible to the LAD, to provide the history and context for the sources observed by LAD and to trigger its observations...... on their most interesting and extreme states. In this paper we present detailed simulations of the imaging capabilities of the Silicon Drift Detectors developed for the LOFT Wide Field Monitor detection plane. The simulations explore a large parameter space for both the detector design and the environmental...

Science center capabilities to monitor and investigate Michigan’s water resources, 2016

Science.gov (United States)

Giesen, Julia A.; Givens, Carrie E.

2016-09-06

Michigan faces many challenges related to water resources, including flooding, drought, water-quality degradation and impairment, varying water availability, watershed-management issues, stormwater management, aquatic-ecosystem impairment, and invasive species. Michigan’s water resources include approximately 36,000 miles of streams, over 11,000 inland lakes, 3,000 miles of shoreline along the Great Lakes (MDEQ, 2016), and groundwater aquifers throughout the State.The U.S. Geological Survey (USGS) works in cooperation with local, State, and other Federal agencies, as well as tribes and universities, to provide scientific information used to manage the water resources of Michigan. To effectively assess water resources, the USGS uses standardized methods to operate streamgages, water-quality stations, and groundwater stations. The USGS also monitors water quality in lakes and reservoirs, makes periodic measurements along rivers and streams, and maintains all monitoring data in a national, quality-assured, hydrologic database.The USGS in Michigan investigates the occurrence, distribution, quantity, movement, and chemical and biological quality of surface water and groundwater statewide. Water-resource monitoring and scientific investigations are conducted statewide by USGS hydrologists, hydrologic technicians, biologists, and microbiologists who have expertise in data collection as well as various scientific specialties. A support staff consisting of computer-operations and administrative personnel provides the USGS the functionality to move science forward. Funding for USGS activities in Michigan comes from local and State agencies, other Federal agencies, direct Federal appropriations, and through the USGS Cooperative Matching Funds, which allows the USGS to partially match funding provided by local and State partners.This fact sheet provides an overview of the USGS current (2016) capabilities to monitor and study Michigan’s vast water resources. More

High resolution simultaneous measurements of airborne radionuclides

International Nuclear Information System (INIS)

Abe, T.; Yamaguchi, Y.; Tanaka, K.; Komura, K.

2006-01-01

High resolution (2-3 hrs) simultaneous measurements of airborne radionuclides, 212 Pb, 210 Pb and 7 Be, have been performed by using extremely low background Ge detectors at Ogoya Underground Laboratory. We have measured above radionuclides at three monitoring points viz, 1) Low Level Radioactivity Laboratory (LLRL) Kanazawa University, 2) Shishiku Plateau (640 m MSL) located about 8 km from LLRL to investigate vertical difference of activity levels, and 3) Hegura Island (10 m MSL) located about 50 km from Noto Peninsula in the Sea of Japan to evaluate the influences of Asian continent or mainland of Japan on the variation to the activity levels. Variations of short-lived 212 Pb concentration showed noticeable time lags between at LLRL and at Shishiku Plateau. These time lags might be caused by change of height of a planetary boundary layer. On the contrary, variations of long-lived 210 Pb and 7 Be showed simultaneity at three locations because of homogeneity of these concentrations all over the area. (author)

Radionuclide generators

International Nuclear Information System (INIS)

Lambrecht, R.M.

1983-01-01

The status of radionuclide generators for chemical research and applications related to the life sciences and biomedical research are reviewed. Emphasis is placed upon convenient, efficient and rapid separation of short-lived daughter radionuclides in a chemical form suitable for use without further chemical manipulation. The focus is on the production of the parent, the radiochemistry associated with processing the parent and daughter, the selection and the characteristic separation methods, and yields. Quality control considerations are briefly noted. The scope of this review includes selected references to applications of radionuclide generators in radiopharmaceutical chemistry, and the life sciences, particularly in diagnostic and therapeutic medicine. The 99 Mo-sup(99m)Tc generator was excluded. 202 references are cited. (orig.)

Humic substances in natural waters and their complexation with trace metals and radionuclides: a review. [129 references

Energy Technology Data Exchange (ETDEWEB)

Boggs, S. Jr.; Livermore, D.; Seitz, M.G.

1985-07-01

Dissolved humic substances (humic and fulvic acids) occur in surface waters and groundwaters in concentrations ranging from less than 1 mg(C)/L to more than 100 mg(C)/L. Humic substances are strong complexing agents for many trace metals in the environment and are also capable of forming stable soluble complexes or chelates with radionuclides. Concentrations of humic materials as low as 1 mg(C)/L can produce a detectable increase in the mobility of some actinide elements by forming soluble complexes that inhibit sorption of the radionuclides onto rock materials. The stability of trace metal- or radionuclide-organic complexes is commonly measured by an empirically determined conditional stability constant (K'), which is based on the ratio of complexed metal (radionuclide) in solution to the product concentration of uncomplexed metal and humic complexant. Larger values of stability constants indicate greater complex stability. The stability of radionuclide-organic complexes is affected both by concentration variables and envionmental factors. In general, complexing is favored by increased of radionuclide, increased pH, and decreased ionic strength. Actinide elements are generally most soluble in their higher oxidation states. Radionuclides can also form stable, insoluble complexes with humic materials that tend to reduce radionuclide mobility. These insoluble complexes may be radionuclide-humate colloids that subsequently precipitate from solution, or complexes of radionuclides and humic substances that sorb to clay minerals or other soil particulates strongly enough to immobilize the radionuclides. Colloid formation appears to be favored by increased radionuclide concentration and lowered pH; however, the conditions that favor formation of insoluble complexes that sorb to particulates are still poorly understood. 129 refs., 25 figs., 19 tabs.

Use of aquatic mosses for monitoring artificial radionuclides downstream of the nuclear power plant of Bugey (River Rhone, France)

International Nuclear Information System (INIS)

Beaugelin-Seiller, K.; Brottet, D.

1994-01-01

The detection of radionuclides in water, downstream of nuclear installations located on river banks, is often very difficult notably because of their low concentrations. Thus the use of biological indicators is an interesting process to detect radioactive contamination of an aquatic ecosystem. From 1986 to 1990, artificial radionuclides were measured in freshwater mosses sampled downstream of the nuclear power station of Bugey. These field data on the whole, have shown a comparatively good qualitative and quantitative relationship between radioactive composition of liquid waste and radionuclides detected in mosses. In other respects, the results showed up a relatively clear hierarchical structure in the affinity of the different radionuclides for the mosses. To specify these relations, mesh bags containing allochtonous mosses were immersed at four stations downstream of the power plant and regularly sampled during a 10-h waste discharge period. (author)

Impacts of species introductions on the health of fish communities receiving chronic radionuclide exposures

International Nuclear Information System (INIS)

Yankovich, T.L.; Casselman, J.M.; Cornett, R.J.J.

2006-01-01

A study was conducted to evaluate the potential impacts of a northern pike introduction on the health of a fish community receiving chronic radionuclide exposure, primarily from 90 Sr. Overall, although significant changes occurred in the community composition and the health of fish populations following the pike introduction, these were not linked to radionuclide dose to fishes. This finding was further supported by assessing the health of forage fishes, which did not significantly change in the pre-versus post-pike fish communities and were comparable in condition to forage fishes inhabiting lakes with background radionuclide levels. Application of such resilient species as 'baseline organisms' can provide a useful tool in the routine monitoring of ecosystems affected by multiple stressors. (author)

Radionuclides in radiation-induced bystander effect; may it share in radionuclide therapy?

Science.gov (United States)

Widel, M

2017-01-01

For many years in radiobiology and radiotherapy predominated the conviction that cellular DNA is the main target for ionizing radiation, however, the view has changed in the past 20 years. Nowadays, it is assumed that not only directed (targeted) radiation effect, but also an indirect (non-targeted) effect may contribute to the result of radiation treatment. Non-targeted effect is relatively well recognized after external beam irradiation in vitro and in vivo, and comprises such phenomena like radiation-induced bystander effect (RIBE), genomic instability, adaptive response and abscopal (out of field) effect. These stress-induced and molecular signaling mediated phenomena appear in non-targeted cells as variety responses resembling that observed in directly hit cells. Bystander effects can be both detrimental and beneficial in dependence on dose, dose-rate, cell type, genetic status and experimental condition. Less is known about radionuclide-induced non-targeted effects in radionuclide therapy, although, based on characteristics of the radionuclide radiation, on experiments in vitro utilizing classical and 3-D cell cultures, and preclinical study on animals it seems obvious that exposure to radionuclide is accompanied by various bystander effects, mostly damaging, less often protective. This review summarizes existing data on radionuclide induced bystander effects comprising radionuclides emitting beta- and alpha-particles and Auger electrons used in tumor radiotherapy and diagnostics. So far, separation of the direct effect of radionuclide decay from crossfire and bystander effects in clinical targeted radionuclide therapy is impossible because of the lack of methods to assess whether, and to what extent bystander effect is involved in human organism. Considerations on this topic are also included.

Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

International Nuclear Information System (INIS)

Barfuss, Brad C.; Barnett, J. M.; Ballinger, Marcel Y.

2009-01-01

Battelle-Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy's Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided

Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

Energy Technology Data Exchange (ETDEWEB)

Barfuss, Brad C.; Barnett, J. Matthew; Ballinger, Marcel Y.

2009-04-08

Battelle—Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy’s Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided.

Development and evaluation of in vivo monitoring techniques of high energy radionuclides in the lungs in emergency situations; Desenvolvimento e avaliação de técnicas de monitoração in vivo de radionuclídeos de alta energia nos pulmões em situações de emergência

Energy Technology Data Exchange (ETDEWEB)

Mello, J.Q.; Lucena, E.A.; Dantas, A.L.A.; Dantas, B.M., E-mail: jquince@bolsista.ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Divisão de Dosimetria. Laboratório de Monitoração in vivo

2017-07-01

Emergency situations in nuclear power plants involving the release of radioactive materials require the use of monitoring techniques for individuals exposed to risks of radionuclide incorporation. Such techniques should provide rapid results and provide sufficient sensitivity for the detection of activities that result in internal doses consistent with exposure limits. A wide variety of radionuclides can be identified and quantified by means of in vivo monitoring techniques in the human body and their availability is of great importance in remediation actions. This work presents the development and validation of an in vivo monitoring method for the evaluation of inhaled radionuclide incorporation. The monitoring system, consisting of an 8 x 4 NaI (Tl) detector installed on the IRD Whole-Body Counter, was calibrated with a chest and lung simulator type LLNL containing {sup 152}Eu. The detection efficiencies corresponding to the most intense photon energies of {sup 152}Eu were calculated and a calibration curve in the range of 100 to 1400 keV was obtained. From this curve, the detection efficiencies, the minimum detectable activities and the detectable minimum effective doses corresponding to the most relevant radionuclides in the case of a radioactive pen-releasing accident were calculated. The technique presents adequate sensitivity for in vivo monitoring in such situations, being able to detect activities that result in effective doses committed below 1 mSv, considering the most probable scenarios of internal exposure.

Spot measurements of radionuclides in air, water and solids with a single instrument

International Nuclear Information System (INIS)

Philipsborn, H. von

1998-01-01

A unique instrument for measuring environmental radionuclides and novel methods for their concentrative sampling are described here which meet high requirements of sensitivity, easy and reliable handling, and low cost for most applications in field screening, monitoring and training. (author)

Radioactive effluent monitoring at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Simpson, O.D.

1975-01-01

The Effluent and Radiation Measurements Laboratory at the Idaho National Engineering Laboratory (INEL) has recently upgraded capabilities in the field of monitoring and analysis of radioactive airborne and liquid effluents using the techniques of gamma-ray spectrometry. The techniques and equipment used include remotely-operated, computer-based Ge(Li) spectrometers which obtain data on a real-time basis. Permanent record files are maintained of both the effluent release values and the gamma-ray data from which the release values are calculated. Should values for release levels ever be challenged, the gamma-ray spectral information for any measurement can be recalled and analyzed as needed. Daily effluent release reports are provided to operating personnel which contributes to prompt correction of any operational problems. Monthly, quarterly, and annual reports are compiled which provide inventories of the radionuclides released. A description of the effluent monitoring, reporting and records system developed at INEL for this application will be presented

Radionuclide cardiography in medical practice

International Nuclear Information System (INIS)

Strangfeld, D.; Mohnike, W.; Schmidt, J.; Heine, H.; Correns, H.J.

1986-01-01

This publication is a compendium on all aspects of radionuclide diagnostics concerning cardiovascular system diseases. Starting with introductory remarks on the control of cardiovascular diseases the contribution of radionuclide cardiology to functional cardiovascular diagnostics as well as pathophysiological and pathobiochemical aspects of radiocardiography are outlined. Radiopharmaceuticals used in radiocardiography, physical and technical problems in application of radionuclides and their measuring techniques are discussed. In individual chapters radionuclide ventriculography, myocardial scintiscanning, circulatory diagnostics, radionuclide diagnostics of arterial hypertension, of thrombosis and in vitro diagnostics of thrombophilia are treated in the framework of clinical medicine

Importance of monitoring the content of fission mixture radionuclides in foodstuffs

International Nuclear Information System (INIS)

Hrusovsky, J.; Mizik, P.; Tokosova, M.

1988-01-01

Briefly characterized are the risks of individual radionuclides for man due to food chain contamination as a result of normal operation of nuclear power facilities and their accidents. A task has arisen for the veterinary service to secure radiometric inspection of foods defined by ICRP in its concept of radiation protection of man. It is noted that the low level counting methods differ to a certain extent from those of determining activities higher by orders of magnitude and require specially equipped laboratories and trained specialists. (Z.M.)

The separation of radionuclide migration by solution and particle transport in LLRW repository buffer material

International Nuclear Information System (INIS)

Torok, J.; Buckley, L.P.; Woods, B.L.

1989-01-01

Laboratory-scale lysimeter experiments were performed with simulated waste forms placed in candidate buffer materials which have been chosen for a low-level radioactive waste repository. Radionuclide releases into the effluent water and radionuclide capture by the buffer material were determined. The results could not be explained by traditional solution transport mechanisms, and transport by particles released from the waste form and/or transport by buffer particles were suspected as the dominant mechanism for radionuclide release from the lysimeters. To elucidate the relative contribution of particle and solution transport, the waste forms were replaced by a wafer of neutron-activated buffer soaked with selected soluble isotopes. Particle transport was determined by the movement of gamma-emitting neutron-activation products through the lysimeter. Solution transport was quantified by comparing the migration of soluble radionuclides relative to the transport of neutron activation products. The new approach for monitoring radionuclide migration in soil is presented. It facilitates the determination of most of the fundamental coefficients required to model the transport process

Approaches to modelling radionuclide transfer in agricultural systems

International Nuclear Information System (INIS)

Mitchell, N. G.

1995-01-01

Radiological dose assessment requires information describing the concentration and distribution of radionuclides in the environment. This information can be obtained from monitoring but is also evaluated with the aid of mathematical models. In such models the pathways of radionuclides from the release point to man are described in terms of transfer between compartments. The main pathways to be considered include: deposition to vegetation and soils; transfer from soil-to-plant; uptake and turnover in domestic animals; and, intake by man. The development of mathematical models for simulating transfer via these pathways depends on: an understanding of the system under study, in particular for those processes that are most important in the overall transfer to man; the availability of data to determine the structure and parameters for the model; the computing systems available; the knowledge of the user of the model; and, the application of the model. (author)

Metabolism of radionuclides in domestic animals

International Nuclear Information System (INIS)

Wirth, E.; Leising, C.

1986-01-01

The reactor accident at Chernobyl has shown that shortly after the contamination of the environment radionuclides can be found in animal products. The main contamination pathways of domestic animas are: uptake of radionuclides by foodstuffs; uptake of radionuclides by contaminated drinking water; uptake of radionuclides by inhalation; uptake of radionuclides through skin; uptake of radionuclides by ingestion of soil particles. Generally the uptake of radionuclides by food is the dominant exposure pathway. In rare cases the inhalation of radionuclides or the uptake by drinking water may be of importance. The metabolism of incorporated radionuclides is comparable to the respective metabolism of essential mass or trace elements or heavy metals. Radioisotopes of essential elements are for instance iron 55, manganese 54, cobalt 58 and cobalt 60. Other elements are typical antagonists to essential elements, e.g. strontium 90 is an antagonist to calcium or cesium 137 to potassium. Lead 210 and plutonium 239 behave similarly as heavy metals. Generally the knowledge of the metabolism of trace and mass elements, of antagonistic and synergistic elements and heavy metals can be applied to these radionuclides

Phase 1 summaries of radionuclide concentration data for vegetation, river water, drinking water, and fish

International Nuclear Information System (INIS)

Denham, D.H.; Dirkes, R.L.; Hanf, R.W.; Poston, T.M.; Thiede, M.E.; Woodruff, R.K.

1993-06-01

The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at the Hanford Site since 1944. As part of the HEDR Project, the Environmental Monitoring Data Task (Task 05) staff assemble, evaluate, and summarize key historical measurements of radionuclide concentrations in the environment as a result of Hanford operations. The scope of work performed during Phase I included initiating the search, recovery, and inventory of environmental reports. Summaries of the environmental monitoring data that were recovered and evaluated are presented for specific periods of interest. These periods include vegetation monitoring data (primarily sagebrush) for the years 1945 through 1947, Columbia River water and drinking water monitoring data for the years 1963 through 1966, and fish monitoring data for the years 1964 through 1966. Concern was limited to those radionuclides identified as the most likely major contributors to the dose potentially received by the public during the times of interest: phosphorous-32, copper-64, zinc-65, arsenic-76, and neptunium-239 in Columbia River fish and drinking water taken from the river, and iodine-131 in vegetation. This report documents the achievement of the Phase I objectives of the Environmental Monitoring Data Task

Establishment and application of a large calibration device of artificial radionuclide plane source

International Nuclear Information System (INIS)

Hu Mingkao; Zhang Jiyun; Wang Xinxing; Zhang Sheng

2010-01-01

With the expansion of the application fields of nuclear techniques and the development of economy, more and more airborne/vehicle and other large γ spectrometers are applied in the environment radiation monitoring of artificial radioactive nuclides. In order to ensure the reliability of the monitoring results, a large calibration device of artificial radionuclide plane source is established. The paper introduces the device's built history and the results of application. (authors)

Progress in determination of long-lived radionuclides by inductively coupled plasma mass spectrometry

International Nuclear Information System (INIS)

Becker, J.S.; Dietze, H.J.

2000-01-01

Mass spectrometric methods (such as inductively coupled plasma mass spectrometry - ICP-MS and laser ablation (LA)-ICP-MS) with their ability to provide a very sensitive multielemental and precise isotopic analysis have become established for the determination of radionuclides in quite different sample materials. The determination of long-lived radionuclides is of increasing interest for the characterization of radioactive waste materials and for the detection of radionuclide contamination in environmental materials in which several radioactive nuclides are present from fallout due to nuclear weapons testing, nuclear power plants or nuclear accidents. Due to its multielement capability, excellent sensitivity, low detection limits (up to sub pg I 1 range), very good precision, easy sample preparation and measurement procedures ICP-MS of aqueous solutions has been increasingly applied for the ultrasensitive determination of long-lived radionuclides such as 99 Tc, 129 I, 230 Th, 232 Th, 234 U, 235 U, 236 U, 239 Pu, 240 Pu and 241 Am and precise isotope ratio measurements of U,Th and Pu. The application especially of microanalytical methods (analysis of some MU by flow injection and on-line coupling techniques as capillary electrophoresis (CE-ICP-MS) or HPLC-ICP-MS) for the precise determination nuclide abundances and concentration of long-lived radionuclides at ultra trace concentration levels in radioactive waste and also for controlling contamination from radioactive waste in the environment is a challenging task

Global deposition of fallout radionuclides and their dietary intake

International Nuclear Information System (INIS)

Morisawa, Shinsuke

1993-01-01

Japanese foods depend largely on foreign countries and domestic food supply now is no more than 30 percents if feedstuffs for live-stocks are included. Therefore not only ecological/natural but also social, e.g., human activities related, transportation of fallout radionuclides are to be taken into accounts for estimation of baseline internal irradiation dose and health risks of Japanese peoples through dietary intake of radionuclides. In this study, mathematical model is developed and examined for practical application on estimating Japanese dietary intake level of fallout strontium-90, which is accumulated in various kinds of foodstuffs and is transported to Japan associated with worldwide trades of foods, under appropriate limitations such that direct deposition on plants and seafood intake pathways are not evaluated. Deposition of strontium-90 onto the surface soil was simulated using the model, the compartment model described by a set ordinary differential equations, and the estimates were examined by comparing them with the observed data colleted and complied by the global scale environmental monitoring networks. Sensitivity analysis is also practised to find possible reduction of dietary intake of fallout radionuclides and the related potential health risks. (author)

ALMERA Proficiency Test: Determination of Natural and Artificial Radionuclides in Soil and Water. IAEA-TEL-2011-04

International Nuclear Information System (INIS)

2013-01-01

The Analytical Laboratories for the Measurement of Environmental Radioactivity (ALMERA) network is a cooperative effort of analytical laboratories worldwide. Members of the network are nominated by their respective Member States on the expectation of providing reliable and timely analysis of environmental samples in the event of an accidental or intentional release of radioactivity. The ALMERA network consists of 131 laboratories representing 81 Member States at December 2012. The IAEA's Environment Laboratories in Seibersdorf and Monaco are the central coordinators of the ALMERA network activities. The IAEA helps the ALMERA network to maintain their readiness by coordinating activities, including the organization of meetings, development of standardized methods of sample collection and analysis, and organization of interlaboratory comparison exercises and proficiency tests as tools for external quality control. IAEA proficiency tests and interlaboratory comparison exercises are organized on a regular basis specifically for the members of the ALMERA network. At least one exercise is organized per year by the IAEA for the ALMERA network. These exercises are designed to monitor and to demonstrate the performance and analytical capabilities of the network members, and to identify gaps and problem areas where further development is needed. The ALMERA proficiency tests enable ALMERA members to report their results on gamma emitting radionuclides in a very short time frame, i.e. three days, which is what would be required for emergency response. This publication presents the results of the ALMERA proficiency test IAEA-TEL-2011-04 on the determination of natural and artificial radionuclides in water and soil. The methodologies, data evaluation approach, summary evaluation of each radionuclide and individual evaluation reports for each laboratory are also described

Computer-based radionuclide analyzer system

International Nuclear Information System (INIS)

Ohba, Kengo; Ishizuka, Akira; Kobayashi, Akira; Ohhashi, Hideaki; Tsuruoka, Kimitoshi.

1978-01-01

The radionuclide analysis in nuclear power plants, practiced for the purpose of monitoring the quality of the primary loop water, the confirmation of the performance of reactor cleanup system and monitoring the radioactive waste effluent, is an important job. Important as it is, it requires considerable labor of experts, because the samples to be analyzed are multifarious and very large in number, and in addition, this job depends much on manual work. With a view of saving the labor, simplifying and standardizing the work, reducing radiation exposure, and automatizing the work of analysis, the computerized analyzer system has been worked out. The results of its performance test at the operating power plant have proved that the development has fairly accomplished the objects and that the system is well useful. The developmental work was carried out by the cooperation between The Tokyo Electric Power Co. and Toshiba in about 4 years from 1974 to this year. (auth.)

Radioactivity and the environment: technical approaches to understand the role of arbuscular mycorrhizal plants in radionuclide bioaccumulation

Science.gov (United States)

Davies, Helena S.; Cox, Filipa; Robinson, Clare H.; Pittman, Jon K.

2015-01-01

Phytoaccumulation of radionuclides is of significant interest with regards to monitoring radionuclide build-up in food chains, developing methods for environmental bioremediation and for ecological management. There are many gaps in our understanding of the characteristics and mechanisms of plant radionuclide accumulation, including the importance of symbiotically-associated arbuscular mycorrhizal (AM) fungi. We first briefly review the evidence that demonstrates the ability of AM fungi to enhance the translocation of 238U into plant root tissues, and how fungal association may prevent further mobilization into shoot tissues. We then focus on approaches that should further advance our knowledge of AM fungi–plant radionuclide accumulation. Current research has mostly used artificial cultivation methods and we consider how more ecologically-relevant analysis might be performed. The use of synchrotron-based X-ray fluorescence imaging and absorption spectroscopy techniques to understand the mechanisms of radionuclide transfer from soil to plant via AM fungi is evaluated. Without such further knowledge, the behavior and mobilization of radionuclides cannot be accurately modeled and the potential risks cannot be accurately predicted. PMID:26284096

HYSPLIT's Capability for Radiological Aerial Monitoring in Nuclear Emergencies: Model Validation and Assessment on the Chernobyl Accident

International Nuclear Information System (INIS)

Jung, Gunhyo; Kim, Juyoul; Shin, Hyeongki

2007-01-01

The Chernobyl accident took place on 25 April 1986 in Ukraine. Consequently large amount of radionuclides were released into the atmosphere. The release was a widespread distribution of radioactivity throughout the northern hemisphere, mainly across Europe. A total of 31 persons died as a consequence of the accident, and about 140 persons suffered various degrees of radiation sickness and health impairment in the acute health impact. The possible increase of cancer incidence has been a real and significant increase of carcinomas of the thyroid among the children living in the contaminated regions as the late health effects. Recently, a variety of atmospheric dispersion models have been developed and used around the world. Among them, HYSPLIT (HYbrid Single-Particle Lagrangian Integrated Trajectory) model developed by NOAA (National Oceanic and Atmospheric Administration)/ARL (Air Resources Laboratory) is being widely used. To verify the HYSPLIT model for radiological aerial monitoring in nuclear emergencies, a case study on the Chernobyl accident is performed

Monitoring of noble gas radioisotopes in nuclear power plant effluents

International Nuclear Information System (INIS)

Kabat, M.J.

1985-01-01

Monitoring of gaseous radionuclides in the effluents of nuclear facilities is an essential requirement in effluent management programs. Since there is no practical way of removing noble gas radioisotopes from air at release pathways, their accurate monitoring is essential for providing appropriate environmental protection. Emitted γ dose-rate is the limiting factor for concentration-time integral of noble gas in gaseous effluents of reactor facilities. The external exposure to the public from a semi-infinite cloud is directly proportional to both the noble gas isotope concentration and the integrated γ energy per disintegration. Both can be directly measured in gaseous effluent pathways with a suitable detector. The capability of NaI(T1), CaF 2 (Eu) and plastic scintillation detectors to measure the γ-Ci.MeV content of noble gas releases was experimentally evaluated. The combination of CaF 2 (Eu) detector in a pressurized through-flow chamber, with a charge integrating scaler well complied with both γ energy response and detection sensitivity requirements. Noble gas source terms and effluent monitoring criteria are discussed, theoretical and experimental results are presented and a practical, on-line noble gas monitoring system is described

Generic procedures for monitoring in a nuclear or radiological emergency

International Nuclear Information System (INIS)

1999-06-01

One of the most important aspects of managing a radiological emergency is the ability to promptly and adequately assess the need for protective actions. Protective action accident management must make use of the key relevant information available. Decision-making and accident assessment will be an iterative and dynamic process aimed at refining the initial evaluation as more detailed and complete information becomes available. Emergency monitoring is one of the main sources for obtaining needed information. This publication is in the scope of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Legal Series No. 14) under which the IAEA is authorized to assist a State Party or a Member State among other matters in developing appropriate radiation monitoring programmes, procedures and standards (Article 5). The scope of this manual is restricted to practical guidance for environmental and source monitoring during a nuclear or other radiological emergency. It does not address emergency response preparedness, nor does it cover the emergency management aspects of accident assessment. This manual is organised into sections relating to measurements in order of priority of a major reactor accident, namely: ambient gamma/beta dose rates from plume, ground deposition or source; radionuclide concentrations in air; deposition maps for 131 I and 137 Cs and other important radionuclides; radionuclide mix in deposition and radionuclide concentrations in food, drinking water and other samples. The introductory section provides an overview of the design of emergency monitoring and sampling programmes, monitoring teams and their qualifications and training, monitoring equipment and instrumentation, protective actions for emergency monitoring teams and quality assurance and quality control checks

Drift-Scale Radionuclide Transport

International Nuclear Information System (INIS)

Houseworth, J.

2004-01-01

The purpose of this model report is to document the drift scale radionuclide transport model, taking into account the effects of emplacement drifts on flow and transport in the vicinity of the drift, which are not captured in the mountain-scale unsaturated zone (UZ) flow and transport models ''UZ Flow Models and Submodels'' (BSC 2004 [DIRS 169861]), ''Radionuclide Transport Models Under Ambient Conditions'' (BSC 2004 [DIRS 164500]), and ''Particle Tracking Model and Abstraction of Transport Process'' (BSC 2004 [DIRS 170041]). The drift scale radionuclide transport model is intended to be used as an alternative model for comparison with the engineered barrier system (EBS) radionuclide transport model ''EBS Radionuclide Transport Abstraction'' (BSC 2004 [DIRS 169868]). For that purpose, two alternative models have been developed for drift-scale radionuclide transport. One of the alternative models is a dual continuum flow and transport model called the drift shadow model. The effects of variations in the flow field and fracture-matrix interaction in the vicinity of a waste emplacement drift are investigated through sensitivity studies using the drift shadow model (Houseworth et al. 2003 [DIRS 164394]). In this model, the flow is significantly perturbed (reduced) beneath the waste emplacement drifts. However, comparisons of transport in this perturbed flow field with transport in an unperturbed flow field show similar results if the transport is initiated in the rock matrix. This has led to a second alternative model, called the fracture-matrix partitioning model, that focuses on the partitioning of radionuclide transport between the fractures and matrix upon exiting the waste emplacement drift. The fracture-matrix partitioning model computes the partitioning, between fractures and matrix, of diffusive radionuclide transport from the invert (for drifts without seepage) into the rock water. The invert is the structure constructed in a drift to provide the floor of the

Chapter 2. Radionuclides in the biosphere

International Nuclear Information System (INIS)

Toelgyessy, J.; Harangozo, M.

2000-01-01

This is a chapter of textbook of radioecology for university students. In this chapter authors deal with role of radionuclides in the biosphere. Chapter consists of next parts: (1) Natural radionuclides in biosphere; (2) Man-made radionuclides in the biosphere; (3) Ecologically important radionuclides; (4) Natural background; (5) Radiotoxicity and (6) Paths of transfer of radionuclides from the source to human

On release of radionuclides from a near-surface radioactive waste repository to the environment

Directory of Open Access Journals (Sweden)

Gudelis Arūnas

2015-09-01

Full Text Available A closed near-surface radioactive waste repository is the source of various radionuclides causing the human exposure. Recent investigations confirm an effectiveness of the engineering barriers installed in 2006 to prevent the penetration of radionuclides to the environment. The tritium activity concentration in groundwater decreased from tens of kBq/l to below hundreds of Bq/l. The monitoring and groundwater level data suggest the leaching of tritium from previously contaminated layers of unsaturated zone by rising groundwater while 210Pb may disperse as a decay product of 226Ra daughters.

An overview of measurements of radionuclides in foods of the Comunidad Valenciana (Spain)

International Nuclear Information System (INIS)

Ballesteros, L.; Ortiz, J.; Gallardo, S.; Martorell, S.

2015-01-01

Environmental radioactivity monitoring includes the determination of radionuclides in foods since they are an important way of intake of radionuclides to the human organism. Moreover, knowledge of the levels of radionuclides in foodstuffs will inform about the environmental radioactivity background permitting to control possible contamination due to human activity, such as agriculture activity, nuclear power plants or other radioactive facilities. The Environmental Radioactivity Laboratory (LRA) at the Universitat Politècnica de València (UPV) performs measurements on representative foods from all over the Comunidad Valenciana (CV). Those measurements are part of several monitoring programs promoted by the Generalitat Valenciana. A total of 2200 samples of fruits, cereals, vegetables, milk, meat, eggs and fish coming from markets, agricultural cooperatives or small producers have been analyzed. A gamma-ray spectrometry analysis has been performed in all samples. It has been detected 40 K in all samples, 7 Be in some of them. Radiochemical separation of 90 Sr has been carried out in some of the samples collected, mainly orange and lettuce. Samples of lettuce and chard collected following Fukushima Nuclear Power Plant (NPP) accident present activity concentration of 131 I (0.10–1.51 Bq kg −1 ). In this paper, a review of the data obtained at the 1991–2013 period in the framework of the development of the Environmental monitoring program is presented. - Highlights: • Radioactivity levels have been monitored in foods of Comunidad Valenciana (Spain). • γ-Ray spectrometry analysis and radiochemical separation of Sr-90 have been performed. • K-40, Be-7, and Sr-90 has been detected in samples collected. • Samples collected after Fukushima accident show activity concentration of I-131.

New production cross sections for the theranostic radionuclide 67Cu

Science.gov (United States)

Pupillo, Gaia; Sounalet, Thomas; Michel, Nathalie; Mou, Liliana; Esposito, Juan; Haddad, Férid

2018-01-01

The cross sections of the 68Zn(p,2p)67Cu, 68Zn(p,2n)67Ga and 68Zn(p,3n)66Ga reactions were measured at the ARRONAX facility by using the 70 MeV cyclotron, with particular attention to the production of the theranostic radionuclide 67Cu. Enriched 68Zn material was electroplated on silver backing and exposed to a low-intensity proton beam by using the stacked-foils target method. Since 67Cu and 67Ga radionuclides have similar half-lives and same γ-lines (they both decay to 67Zn), a radiochemical process aimed at Cu/Ga separation was mandatory to avoid interferences in γ-spectrometry measurements. A simple chemical procedure having a high separation efficiency (>99%) was developed and monitored during each foil processing, thanks to the tracer isotopes 61Cu and 66Ga. Nuclear cross sections were measured in the energy range 35-70 MeV by using reference reactions recommended by the International Atomic Energy Agency (IAEA) to monitor beam flux. In comparison with literature data a general good agreement on the trend of the nuclear reactions was noted, especially with latest measurements, but slightly lower values were obtained in case of 67Cu. Experimental results of the 68Zn(p,2p)67Cu, 68Zn(p,2n)67Ga and 68Zn(p,3n)66Ga reactions were also compared with the theoretical values estimated by using the software TALYS. The production yield of the theranostic radionuclide 67Cu was estimated considering the results obtained in this work.

Application od scaling technique for estimation of radionuclide inventory in radioactive waste

International Nuclear Information System (INIS)

Hertelendi, E.; Szuecs, Z.; Gulyas, J.; Svingor, E.; Csongor, J.; Ormai, P.; Fritz, A.; Solymosi, J.; Gresits, I.; Vajda, N.; Molnar, Zs.

1996-01-01

Safety studies related to the disposal of low- and intermediate waste indicate that the long term risk is determined by the presence of long-lived nuclides such as 14 C, 59 Ni, 63 Ni, 99 Tc, 129 I and the transuranium elements. As most of these nuclides are difficult to measure, the correlation between these critical nuclides and some other easily measurable key nuclides such as 60 Co and 137 Cs has been investigated for typical waste streams of Paks Nuclear Power Plant (Hungary) and scaling factors have been proposed. An automated gamma-scanning monitor has been purchased and calibrated to determine the gamma-emitting radionuclides. Radiochemical methods have been developed to determine significant difficult-to-measure radionuclides. The radionuclides of interest have been 3 H, 14 C, 90 Sr, 55 Fe, 59 Ni, 99 Tc, 129 I and TRUs. The measurements taken so far have revealed brand new information and data on radiological composition of waste of WWER-type reactors. The reliability of the radioanalytical methods was checked by an international intercomparison test. For all radionuclides the Hungarian results were in the average range of the total data set. (author)

Transfer of conservative and non-conservative radionuclides from the Sellafield nuclear fuel reprocessing plant to the coastal waters of Ireland

International Nuclear Information System (INIS)

Mcmahon, C.A.; Fegan, M.; Wong, J.; Long, S.C.; Mckittrick, L.; Thomas, K.; Rafferty, B.

2004-01-01

The Radiological Protection Institute of Ireland has monitored levels of anthropogenic radionuclides in the Irish marine environment for over 20 years. While the primary objective of the monitoring programme is to assess the exposure of the Irish population resulting from the presence of these radionuclides in the marine environment, the programme also aims to assess the geographical distribution and temporal variations of the radionuclides. The programme involves the routine sampling of and testing for radioactivity in fish, shellfish, seaweed, sediments and seawater. The data generated in the course of this programme, as well as in a separate study of changing plutonium isotopic ratios in Fucus vesiculosus from the west coast of Ireland, are used in this paper to estimate transport times from the Sellafield nuclear fuel reprocessing plant to the western Irish Sea and from the Irish Sea to the west coast of Ireland. The results obtained are discussed in the paper and the transfer times estimated for particle-reactive radionuclides (plutonium isotopes) compared with those obtained for more conservative radionuclides ( 137 Cs and 99 Tc). Transfer factors (calculated as the ratio between observed concentrations in the environment and an average discharge rate τ years earlier, where τ is the transport time) are also presented. (author)

Radiation environmental real-time monitoring and dispersion modeling

International Nuclear Information System (INIS)

Kovacik, A.; Bartokova, I.; Omelka, J.; Melicherova, T.

2014-01-01

The system of real-time radiation monitoring provided by MicroStep-MIS is a turn-key solution for measurement, acquisition, processing, reporting, archiving and displaying of various radiation data. At the level of measurements, the monitoring stations can be equipped with various devices from radiation probes, measuring the actual ambient gamma dose rate, to fully automated aerosol monitors, returning analysis results of natural and manmade radionuclides concentrations in the air. Using data gathered by our radiation probes RPSG-05 integrated into monitoring network of Crisis Management of the Slovak Republic and into monitoring network of Slovak Hydrometeorological Institute, we demonstrate its reliability and long-term stability of measurements. Data from RPSG-05 probes and GammaTracer probes, both of these types are used in the SHI network, are compared. The sensitivity of RPSG-05 is documented on data where changes of dose rate are caused by precipitation. Qualities of RPSG-05 probe are illustrated also on example of its use in radiation monitoring network in the United Arab Emirates. A more detailed information about radioactivity of the atmosphere can be obtained by using spectrometric detectors (e.g. scintillation detectors) which, besides gamma dose rate values, offer also a possibility to identify different radionuclides. However, this possibility is limited by technical parameters of detector like energetic resolution and detection efficiency in given geometry of measurement. A clearer information with less doubts can be obtained from aerosol monitors with a built-in silicon detector of alpha and beta particles and with an electrically cooled HPGe detector dedicated for gamma-ray spectrometry, which is performed during the sampling. Data from a complex radiation monitoring network can be used, together with meteorological data, in radiation dispersion model by MicroStep-MIS. This model serves for simulation of atmospheric propagation of radionuclides

Geomorphological applications of environmental radionuclides

International Nuclear Information System (INIS)

Quine, T.A.; Walling, D.

1998-01-01

Geomorphologists have shown increasing interest in environmental radionuclides since pioneering studies by Ritchie and McHenry in the USA and Campbell, Longmore and Loughran in Australia. Environmental radionuclides have attracted this interest because they provide geomorphologists with the means to trace sediment movement within the landscape. They, therefore, facilitate investigation of subjects at the core of geomorphology, namely the rates and patterns of landscape change. Most attention has been focussed on the artificial radionuclide caesium-137 ( 137 Cs) but more recently potential applications of the natural radionuclides lead-210 ( 210 Pb) and beryllium-7( 7 Be) have been investigated (Walling et al., 1995; Wallbrink and Murray, 1996a, 1996b). The origin, characteristics and applications of these radionuclides are summarised. These radionuclides are of value as sediment tracers because of three important characteristics: a strong affinity for sediment; a global distribution and the possibility of measurement at low concentration. Geomorphological applications of environmental radionuclides provide unique access to detailed qualitative data concerning landscape change over a range of timescales

Recent developments in assessment of long-term radionuclide behavior in the geosphere-biosphere subsystem.

Science.gov (United States)

Smith, G M; Smith, K L; Kowe, R; Pérez-Sánchez, D; Thorne, M; Thiry, Y; Read, D; Molinero, J

2014-05-01

Decisions on permitting, controlling and monitoring releases of radioactivity into the environment rely on a great variety of factors. Important among these is the prospective assessment of radionuclide behavior in the environment, including migration and accumulation among and within specific environmental media, and the resulting environmental and human health impacts. Models and techniques to undertake such assessments have been developed over several decades based on knowledge of the ecosystems involved, as well as monitoring of previous radionuclide releases to the environment, laboratory experiments and other related research. This paper presents developments in the assessment of radiation doses and related research for some of the key radionuclides identified as of potential significance in the context of releases to the biosphere from disposal facilities for solid radioactive waste. Since releases to the biosphere from disposal facilities involve transfers from the geosphere to the biosphere, an important aspect is the combined effects of surface hydrology, near-surface hydrogeology and chemical gradients on speciation and radionuclide mobility in the zone in which the geosphere and biosphere overlap (herein described as the geosphere-biosphere subsystem). In turn, these aspects of the environment can be modified as a result of environmental change over the thousands of years that have to be considered in radioactive waste disposal safety assessments. Building on the experience from improved understanding of the behavior of the key radionuclides, this paper proceeds to describe development of a generic methodology for representing the processes and environmental changes that are characteristic of the interface between the geosphere and the biosphere. The information that is provided and the methodology that is described are based on international collaborative work implemented through the BIOPROTA forum, www.bioprota.org. Copyright © 2013 Elsevier Ltd. All

DOE capabilities for in-situ characterization and monitoring of formation properties in the vadose zone

International Nuclear Information System (INIS)

Hearst, J.R.; Brodeur, J.R.; Koizumi, C.J.; Conaway, J.G.; Mikesell, J.L.; Nelson, P.H.; Stromswold, D.C.; Wilson, R.D.

1993-09-01

The DOE Environmental Restoration (ER) Program faces the difficult task of characterizing the properties of the subsurface and identifying and mapping a large number of contaminants at landfills, surface disposal areas, spill sites, nuclear waste tanks, and subsurface contaminant plumes throughout the complex of DOE facilities. Geophysical borehole logs can measure formation properties such as bulk density, water content, and lithology, and can quantitatively analyze for radionuclides and such elements as chlorine and heavy metals. Since these measurements can be replaced as desired, they can be used for both initial characterization and monitoring of changes in contaminant concentration and water content (sometimes linked to contaminant migration), at a fraction of the cost of conventional sampling. The techniques develop at several DOE laboratories, and the experience that the authors have gained in making in-situ measurements in the vadose zone, are applicable to problems at many other DOE sites. Moreover, they can capitalize on existing inventories of boreholes. By building on this experience workers involved in ER projects at those sites should be able to obtain high-quality data at substantial reductions in cost and time

Generator for radionuclide

International Nuclear Information System (INIS)

Weisner, P.S.; Forrest, T.R.F.

1985-01-01

This invention provides a radionuclide generator of the kind in which a parent radionuclide, adsorbed on a column of particulate material, generates a daughter radionuclide which is periodically removed from the column. This invention is particularly concerned with technetium generators using single collection vials. The generator comprises a column, a first reservoir for the eluent, a second reservoir to contain the volume of eluent required for a single elution, and means connecting the first reservoir to the second reservoir and the second reservoir to the column. Such a generator is particularly suitable for operation by vacuum elution

The production of radionuclides for nuclear medicine from a compact, low-energy accelerator system.

Science.gov (United States)

Webster, William D; Parks, Geoffrey T; Titov, Dmitry; Beasley, Paul

2014-05-01

The field of nuclear medicine is reliant on radionuclides for medical imaging procedures and radioimmunotherapy (RIT). The recent shut-downs of key radionuclide producers have highlighted the fragility of the current radionuclide supply network, however. To ensure that nuclear medicine can continue to grow, adding new diagnostic and therapy options to healthcare, novel and reliable production methods are required. Siemens are developing a low-energy, high-current - up to 10 MeV and 1 mA respectively - accelerator. The capability of this low-cost, compact system for radionuclide production, for use in nuclear medicine procedures, has been considered. The production of three medically important radionuclides - (89)Zr, (64)Cu, and (103)Pd - has been considered, via the (89)Y(p,n), (64)Ni(p,n) and (103)Rh(p,n) reactions, respectively. Theoretical cross-sections were generated using TALYS and compared to experimental data available from EXFOR. Stopping power values generated by SRIM have been used, with the TALYS-generated excitation functions, to calculate potential yields and isotopic purity in different irradiation regimes. The TALYS excitation functions were found to have a good agreement with the experimental data available from the EXFOR database. It was found that both (89)Zr and (64)Cu could be produced with high isotopic purity (over 99%), with activity yields suitable for medical diagnostics and therapy, at a proton energy of 10MeV. At 10MeV, the irradiation of (103)Rh produced appreciable quantities of (102)Pd, reducing the isotopic purity. A reduction in beam energy to 9.5MeV increased the radioisotopic purity to 99% with only a small reduction in activity yield. This work demonstrates that the low-energy, compact accelerator system under development by Siemens would be capable of providing sufficient quantities of (89)Zr, (64)Cu, and (103)Pd for use in medical diagnostics and therapy. It is suggested that the system could be used to produce many other

Process for encapsulating radionuclides

International Nuclear Information System (INIS)

Brownell, L.E.; Isaacson, R.E.

1976-01-01

Radionuclides are immobilized in virtually an insoluble form by reacting at a temperature of at least 90 0 C as an aqueous alkaline mixture having a solution pH of at least 10, containing a source of silicon, the radionuclide waste, and a metal cation. The molar ratio of silicon to the metal cation is on the order of unity to produce a gel from which complex metalosilicates crystallize to entrap the radionuclides within the resultant condensed crystal lattice. The product is a silicious stone-like material which is virtually insoluble and nonleachable in alkaline or neutral environment. One embodiment provides for the formation of the complex metalo-silicates, such as synthetic pollucite, by gel formation with subsequent calcination to the solid product; another embodiment utilizes a hydrothermal process, either above ground or deep within basalt caverns, at greater than atmospheric pressures and a temperature between 90 and 500 0 C to form complex metalo-silicates, such as strontium aluminosilicate. Another embodiment provides for the formation of complex metalo-silicates, such as synthetic pollucite, by slurrying an alkaline mixture of bentonite or kaolinite with a source of silicon and the radionuclide waste in salt form. In each of the embodiments a mobile system is achieved whereby the metalo-silicate constituents reorient into a condensed crystal lattice forming a cage structure with the condensed metalo-silicate lattice which completely surrounds the radionuclide and traps the radionuclide therein; thus rendering the radionuclide virtually insoluble

Identification and analysis of main radionuclides that potentially contribute to the internal dose for workers at radiopharmacy facilities

International Nuclear Information System (INIS)

Sanches, Matias Puga

2004-01-01

The optimization principle in radiation protection means that there is a reasonable balance between resources used to monitor exposures and the benefits due to the monitoring program. Programs for the monitoring of workers handling radioactive materials are influenced by numerous factors. Estimation of internal doses due to inhalation or ingestion of radioactive materials is often based on measurements of the activity in the tissues of the body and in excreta, following a given intake. In order to enable dose estimations using the biokinetic models recommended by the ICRP and laboratory data, it is proposed to carry out comprehensive study to identify the main radionuclides that potentially contribute to the internal dose of workers at radiopharmacy facilities. The applied methodology for identification of these radionuclides takes into account criteria set out by the ICRP and IAEA. The practical purpose to set up this study was to establish a consistent approach to ensure that the dose assessments are as simple as possible and guarantee the necessary quality standards. The result of this study has indicated the requirement of routine measurements for seven radionuclides over all range of radioactive material compounds, handled at the radiopharmacy plant of IPEN, avoiding unjustifiable work concerning activity levels that are not relevant for the health of the occupationally exposed persons. The main intake pathways, the appropriate monitoring frequencies and derived reference level have also been identified. (author)

The Navruz Project: Transboundary Monitoring for Radionuclides and Metals in Central Asia Rivers. Data Report

Energy Technology Data Exchange (ETDEWEB)

Passell, Howard D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Barber, David S. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Betsill, J. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Littlefield, Adriane C. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mohagheghi, Amir H. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Shanks, Sonoya T. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Yuldashev, Bekhzad [Inst. of Nuclear Physics, Tashkent (Uzbekistan); Saalikhbaev, Umar [Inst. of Nuclear Physics, Tashkent (Uzbekistan); Radyuk, Raisa [Inst. of Nuclear Physics, Tashkent (Uzbekistan); Djuraev, Akram [Tajik Academy of Sciences, Dushanbe (Tajikistan); Djuraev, Anwar [Tajik Academy of Sciences, Dushanbe (Tajikistan); Vasilev, Ivan [Inst. of Physics, Bishkek (Kyrgyzstan); Tolongutov, Bajgabyl [Inst. of Physics, Bishkek (Kyrgyzstan); Valentina, Alekhina [Inst. of Physics, Bishkek (Kyrgyzstan); Solodukhin, Vladimir [Inst. of Nuclear Physics, Almaty (Kazakhstan); Pozniak, Victor [Inst. of Nuclear Physics, Almaty (Kazakhstan)

2003-04-01

The Navruz Project is a cooperative, transboundary, river monitoring project involving rivers and institutions in Kazakhstan, Kyrgyzstan, Tajikistan, and Uzbekistan, and facilitated by Sandia National Laboratories in the U.S. The Navruz Project focuses on waterborne radionuclides and metals because of their importance to public health and nuclear materials proliferation concerns in the region. The Project also collects data on basic water quality parameters. Data obtained in this project are shared among all participating countries and the public through a world-wide web site (http://www.cmc.sandia.org/Central/centralasia.html), and are available for use in further studies and in regional transboundary water resource management efforts. This report includes graphs showing selected data from the Fall 2000 and Spring 2001 sampling seasons. These data include all parameters grouped into six regions, including main rivers and some tributaries in the Amu Darya and Syr Darya river systems. This report also assembles all data (in tabular form) generated by the project from Fall 2000 through Fall 2001. This report comes as the second part of a planned three-part reporting process. The first report is the Sampling and Analysis Plan and Operational Manual, SAND 2002-0484. This is the second report.

Potential radionuclide emissions from stacks on the Hanford site, Part 1: Dose assessment

Energy Technology Data Exchange (ETDEWEB)

Davis, W.E.; Barnett, J.M. [Westinghouse Hanford Company, Richland, WA (United States)

1995-02-01

On February 3, 1993, the U.S. Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the U.S. Environmental Protection Agency, Region 10. The Compliance Order requires RL to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission monitoring requirements in 40 CFR 61, Subpart H, and to continuously monitor radionuclide emissions in accordance with requirements in 40 CFR 61.93. The Information Request required RL to provide a written Compliance Plan to meet the requirements of the Compliance Order. A Compliance Plan was submitted to EPA, Region 10, on April 30, 1993. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company stacks registered with the Washington State Department of Health on the Hanford Site. Stacks that have the potential emissions to cause an effective dose equivalent to a maximum exposed individual greater than 0.1 mrem/y must be monitored continuously for radionuclide emissions. Five methods were approved by EPA, Region 10 for performing the assessments: Release Fractions from Appendix D of 40 CFR 61, Back Calculations Using A HEPA Filtration Factor, Nondestructive Assay of HEPA Filters, A Spill Release Fraction, and Upstream of HEPA Filter Air Concentrations. The first two methods were extremely conservative for estimating releases. The third method, which used a state-of-the-art portable gamma spectrometer, yielded surprising results from the distribution of radionuclides on the HEPA filters. All five methods are described. Assessments using a HEPA Filtration Factor for back calculations identified 32 stacks that would have emissions that would cause an EDE to the MEI greater than 0.1 mrem y{sup {minus}1}. The number was reduced to 15 stacks when the other methods were applied. The paper discusses reasons for the overestimates.

Review of the ecological parameters of radionuclide turnover in vertebrate food chains

International Nuclear Information System (INIS)

Kitchings, T.; DiGregorio, D.; Van Voris, P.

1976-01-01

Ecological studies of radionuclides in the environment have a long tradition in developing the capability to identify and predict movement and concentration of nuclides in agricultural food chains leading to man. Food chain pathways and transfer coefficients for the nonagricultural portions of natural and managed ecosystems characteristic of affected habitats adjacent to nuclear facilities have not been adequately characterized to establish reliable models for radionuclide releases. This information is necessary in order to assess the impact that such installations will have on the biota of natural ecosystems. Since food chains are the major processes transferring elements from one trophic level to another in terrestrial ecosystems, information is needed on the (a) food-chain transfer pathways, (b) bioconcentration by each trophic component and (c) turnover rates by receptor organisms. These data are prerequisite inputs for food-chain transport models and can be correlated with species characteristics (e.g., body weight and feeding habits), to provide indices for predictive calculations. Application of these models for radionuclide transfer can aid in the assessment of radioactive releases from nuclear reactor facilities to terrestrial nonagricultural food chains

Radionuclide retardation project at GTS - An overview of lessons learned and ongoing experiments

International Nuclear Information System (INIS)

Moeri, A.

2001-01-01

The joint Nagra/JNC Radionuclide Migration Programme has now been ongoing for more than 15 years in Nagra's Grimsel Test Site (GTS). The main aim of the programme has been the direct testing of radionuclide transport models in as realistic a manner as possible. The understanding and modelling of both the processes and the structures influencing radionuclide transport/retardation in fractured granitic host rocks have matured as has the experimental technology, which has contributed to develop confidence in the applicability of the underlying research models in a repository performance assessment. In this paper, three in situ experiments which were carried out in a discrete granitic shear zone are briefly presented: The Migration Experiment (MI), the Excavation Experiment (EP) and the ongoing Colloid and Radionuclide Retardation Experiment (CRR). Each project expanded on the experimental experience and research results from the preceding experiment. MI provided a sound data base of in situ tracer breakthrough curves which was used to derive relevant transport parameters by inverse modelling in order to enhance the capability for predictive modelling of tracer transport in a granitic shear zone. The Excavation Project (EP) then focussed on the excavation of the dipole flow field in order to describe the flow paths within the shear zone dipole and the retardation behaviour of sorbing radionuclides that are relevant to post-closure safety. The ongoing CRR experiment actually investigates the influence of bentonite colloids on the radionuclide transport behaviour through a fractured granitic host rock. Again, the experience in planning and handling of complex tracer field experiments gained in the proceeding experiments will be availed. The methodology adopted for the geological and hydrological characterisation of water-conducting features and the simplification of this characterisation for modelling purposes proved to be indeed effective on the modelling of

Results on improved environmental monitoring at the Ignalina NPP site

International Nuclear Information System (INIS)

Gudelis, A.; Remeikis, V.; Gubachev, I.; Batalin, J.

2002-01-01

(Li)-detector was used. The typical gamma-ray spectrum obtained with HPGe well-type detector is shown in Fig. 1. Here, the activity of 60 Co is about 100 mBq, and this value corresponds to activity concentration in surface air layer of 0.8 μBq/m 3 . The air samplers used for radioecological monitoring near the INPP are located in different directions from the source, at the distances from a few km to 30 km. Application of new measuring techniques allows to detect various artificial radionuclides at every monitoring station. Correlation between activity concentration of 54 Mn and 60 Co and prevailing wind direction during air sampling is determined. This improved environmental monitoring system is capable to detect the radionuclides discharged not only from the stacks of the INPP but also transferred from distant unknown sources. Hence, it can be used for any source identification

The influence of soil type and climate on the uptake of radionuclides into wheat

International Nuclear Information System (INIS)

Mitchell, N.G.

1992-03-01

The study investigated the uptake by winter wheat of radionuclides deposited onto the soil surface following a hypothetical accidental release to atmosphere from a nuclear power station. A series of lysimeters were filled with four soil types characteristic of wheat growing areas of Europe. Four radionuclides ( 137 Cs, 144 Ce, 106 Ru, 125 Sb) were watered onto the soil surface and the subsequent contamination of winter wheat crops was monitored over two seasons. Subsidiary experiments considered: effects of ploughing and pot size on root uptake; movement of radionuclides in soil profiles; soil contamination of wheat plants and of grain leaving the field; the influence of climate on root uptake; and, the availability of radionuclides. Compared with the literature, this study found a smaller range of transfer factors appropriate to agricultural soils that predominate in the wheat growing areas of the EEC. The use of pots or tubes to investigate soil-to-plant transfer was justified. The study showed that resuspension of radionuclides bound to soil particles must be considered when assessing soil-to-plant transfer. It was demonstrated that the contribution of soil-bound activity to the radionuclide content of combine harvested grain is underestimated in existing dose assessment methodologies by at least an order of magnitude on average and by over two orders of magnitude in extreme cases. Climatic conditions simulated in a growth chamber had little impact on radionuclide transfer. The relative availability of radionuclides for extraction by ammonium acetate did not reflect percentage transfer to grain. Ploughing reduced uptake by winter wheat, resulted in different patterns of transfer between cultivation treatments and influenced the distribution of activity between grain and straw. Results of this work were used in the development of a multi-compartmental time-dependent model called WHEAT which predicts radionuclide transfer from soil to winter wheat. (author)

Monitoring of radionuclides in the vicinities of Finnish nuclear power plants in 1995 and 1996

International Nuclear Information System (INIS)

Ilus, E.; Ikaeheimonen, T.K.; Klemola, S.

2002-12-01

Monitoring radioactive substances around Finnish nuclear power plants continued in 1995 and 1996 in accordance with regular environmental monitoring programmes. Altogether, some 1000 samples are analysed annually from the terrestrial and aquatic environments of the two power plants. Trace amounts of activation products originating from airborne releases from the local power plants were detected in several air and deposition samples. At Loviisa, observations were made in twenty aerosol samples; at Olkiluoto they were made once during the reporting period. The concentrations were very low, from a few microbecquerels to a few tens of microbecquerels per cubic metre. A similar pattern was also tenable for the deposition samples. No traces of local discharge nuclides were detected in foodstuffs, drinking water, or garden products. In mushrooms and wild berries picked from the Loviisa area,only Chernobyl derived cesium isotopes and natural 40 K were found. Local discharge nuclides were more abundant in the aquatic environment, especially in samples of indicator organisms, sinking matter, and sediments. The dominant artificial radionuclides in the vicinity of the power plants were still the cesium isotopes, especially 137 Cs but also 134 Cs, originating from the Chernobyl accident. In seawater, elevated 3H concentrations were more frequent in Loviisa, but no traces of other discharge nuclides were detected. At Olkiluoto, small amounts of activation products were detected in seawater samples taken during the maintenance outages at the power plant. The concentrations of local discharge nuclides in indicator organisms and sinking matter were somewhat higher and their distribution range was wider in the sea area of Olkiluoto. However, the concentrations were so low that they did not increase the radiation burden in the environment. Small amounts of 60 Co originating from the local power plant were detected in sediments at adistance of about 15 km from Olkiluoto. (orig.)

Alizarin Complexone Functionalized Mesoporous Silica Nanoparticles: A Smart System Integrating Glucose-Responsive Double-Drugs Release and Real-Time Monitoring Capabilities.

Science.gov (United States)

Zou, Zhen; He, Dinggeng; Cai, Linli; He, Xiaoxiao; Wang, Kemin; Yang, Xue; Li, Liling; Li, Siqi; Su, Xiaoya

2016-04-06

The outstanding progress of nanoparticles-based delivery systems capable of releasing hypoglycemic drugs in response to glucose has dramatically changed the outlook of diabetes management. However, the developed glucose-responsive systems have not offered real-time monitoring capabilities for accurate quantifying hypoglycemic drugs released. In this study, we present a multifunctional delivery system that integrates both delivery and monitoring issues using glucose-triggered competitive binding scheme on alizarin complexone (ALC) functionalized mesoporous silica nanoparticles (MSN). In this system, ALC is modified on the surface of MSN as the signal reporter. Gluconated insulin (G-Ins) is then introduced onto MSN-ALC via benzene-1,4-diboronic acid (BA) mediated esterification reaction, where G-Ins not only blocks drugs inside the mesopores but also works as a hypoglycemic drug. In the absence of glucose, the sandwich-type boronate ester structure formed by BA binding to the diols of ALC and G-Ins remains intact, resulting in an fluorescence emission peak at 570 nm and blockage of pores. Following a competitive binding, the presence of glucose cause the dissociation of boronate ester between ALC and BA, which lead to the pores opening and disappearance of fluorescence. As proof of concept, rosiglitazone maleate (RSM), an insulin-sensitizing agent, was doped into the MSN to form a multifunctional MSN (RSM@MSN-ALC-BA-Ins), integrating with double-drugs loading, glucose-responsive performance, and real-time monitoring capability. It has been demonstrated that the glucose-responsive release behaviors of insulin and RSM in buffer or in human serum can be quantified in real-time through evaluating the changes of fluorescence signal. We believe that this developed multifunctional system can shed light on the invention of a new generation of smart nanoformulations for optical diagnosis, individualized treatment, and noninvasive monitoring of diabetes management.

Canadian database for radionuclide transfer in the environment

Energy Technology Data Exchange (ETDEWEB)

Sheppard, S C; Corbett, B J [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1995-04-01

The transfer of radionuclides throughout the biosphere is described in models that rely on a series of transfer parameters. These parameters are typically based on experimental or monitoring observations, and describe processes such as soil-to-plant transfer, soil-to-atmosphere transfer, and water-to-fish transfer. The parameters values used in many applications to date have come from around the world. However, data from Canadian settings are generally preferable for Canadian safety assessment applications. This is particularly true for geographically unique parameters relating to specific soils and environments. This database was constructed to record future radionuclide transfer parameter data systematically and completely, and to record particularly valuable existing data. The database supports element-specific parameters. Because the emphasis is on Canadian data, the data are indexed by geographic and physiographic region. In addition to the specific transfer parameter values, there is provision for a substantial amount of ancillary data. The database now operates with dBase software. (author). 1 tab.

Canadian database for radionuclide transfer in the environment

International Nuclear Information System (INIS)

Sheppard, S.C.; Corbett, B.J.

1995-04-01

The transfer of radionuclides throughout the biosphere is described in models that rely on a series of transfer parameters. These parameters are typically based on experimental or monitoring observations, and describe processes such as soil-to-plant transfer, soil-to-atmosphere transfer, and water-to-fish transfer. The parameters values used in many applications to date have come from around the world. However, data from Canadian settings are generally preferable for Canadian safety assessment applications. This is particularly true for geographically unique parameters relating to specific soils and environments. This database was constructed to record future radionuclide transfer parameter data systematically and completely, and to record particularly valuable existing data. The database supports element-specific parameters. Because the emphasis is on Canadian data, the data are indexed by geographic and physiographic region. In addition to the specific transfer parameter values, there is provision for a substantial amount of ancillary data. The database now operates with dBase software. (author). 1 tab

Radionuclide ventriculography in children with Duchenne muscular dystrophy

International Nuclear Information System (INIS)

Tian Jiahe

1992-01-01

The ventricular functions of 22 children with Duchenne disease(DD) were studied by radionuclide multi-gated ventriculography using in-vivo labeled 99m Tc-RBC and compared with those of 30 age-matched normal children, 20 congenital heart disease and 7 congestive cardiomyopathy. 21 parameters were evaluated, including RV and LV EF, systolic and diastolic functions and phase distribution, etc. It was found that the DD patients showed several specific cardiac functional alterations, i.e, slight but significant abnormality in both systolic and diastolic function, special phase delay at post-lateral segment of LV in 81.8% of the patients. It is concluded that (1) all DD patients have definite evidence of heart injury; (2) the injury is mainly on the left side of the heart, influencing entire cardiac cycle; (3) there is specific phase abnormality in DD patients; (4) the radionuclide ventriculography is of great value in monitoring of these cardiac functional changes

Natural analogue studies of the role of colloids, natural organics and microorganisms on radionuclide transport

International Nuclear Information System (INIS)

McCarthy, J.F.

1994-01-01

Colloids may be important as a geochemical transport mechanism for radionuclides at geological repositories if they are (1) present in the groundwater, (2) stable with respect to both colloidal and chemical stabilities, (3) capable of adsorbing radionuclides, especially if the sorption is irreversible, and (4) mobile in the subsurface. The available evidence from natural analogue and other field studies relevant to these issues is reviewed, as is the potential role of mobile microorganisms (open-quotes biocolloidsclose quotes) on radionuclide migration. Studies have demonstrated that colloids are ubiquitous in groundwater, although colloid concentrations in deep, geochemically stable systems may be too low to affect radionuclide transport. However, even low colloid populations cannot be dismissed as a potential concern because colloids appear to be stable, and many radionuclides that adsorb to colloids are not readily desorbed over long periods. Field studies offer somewhat equivocal evidence concerning colloid mobility and cannot prove or disprove the significance of colloid transport in the far-field environment. Additional research is needed at new sites to properly represent a repository far-field. Performance assessment would benefit from natural analogue studies to examine colloid behavior at sites encompassing a suite of probable groundwater chemistries and that mimic the types of formations selected for radioactive waste repositories

Radio-sensitivity and 40K, 3H, 14C levels in dark-striped field mice, apodemus agrarius coreae, as a potential biological monitor for enviro-radiation and radionuclides

International Nuclear Information System (INIS)

Kim, Hee Sun; Song, Seung Yeon; Kim, Eun Joo; Choi, Hoon; Shin, Suk Chul; Kim, Chong Soon; Nishimura, Y.

2006-01-01

To understand how environmental effects of radiation and radionuclides from radiation facilities relate to human beings, the development of an unmanned monitoring system is required. For the reasons of that, the International Atomic Energy Agency (IAEA) suggests a method to evaluate the effects of radiation emitted from radiation facilities on marine water, freshwater, and habitats for land animals and plants on its Technical Report Series 190, 288, and 332. Recently, International Commission on Radiological Protection (ICRP) Publication No. 91 (2003) was consecutively published to protect non-human animals and plants from environmental radiation and radioactive materials. This study examined the potential usefulness of dark-striped field mice as a biological indicator of enviro-radiation and radionuclides around nuclear power plants and radioactive waste storage facilities. For the purpose, dark-striped mice were collected in regions of Korea where there are no radiation facilities. Their external morphological characters and isoenzyme patterns were observed. As a result, the most dark-striped mice scattered in Korea are Apodemus agrarius coreae

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2009

International Nuclear Information System (INIS)

2010-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada Test Site (NTS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NTS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NTS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NTS. After nuclear testing ended in 1992, NTS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium were also emitted to air at the NLVF, an NTS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) limits the release of radioactivity from a U.S. Department of Energy facility to 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation not related to NTS activities. Unrelated doses could come from naturally occurring radioactive elements or from sources such as medically or commercially used radionuclides. The NTS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the U.S. Environmental Protection Agency for use on the NTS in 2001 and has been the sole method used since 2005. Six locations on the NTS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo-critical receptor stations, because no

Radionuclide transfer from mother to embryo

International Nuclear Information System (INIS)

Toader, M.; Vasilache, R.A.; Scridon, R.; Toader, M.L.

1998-01-01

The transfer of radionuclides from mother to embryo is still a matter of high interest. Therefore, the relation was investigated between the amount of radionuclides in the embryo and the dietary intake of the mother, this for two scenarios: a recurrent intake of variable amounts of radionuclides, and a long-term intake of a relatively constant amount of radionuclides, the radionuclide being 137 Cs. In the first case, the amount of radionuclides present in the embryo increases with the age of the embryo and with the intake of the mother. In the second case, no correlation could be found between the age of the embryo and its radioactive content; only the correlation between the intake of the mother and the radionuclide content of the embryo remained. (A.K.)

Environmental monitoring around the Swedish Nuclear Facilities

International Nuclear Information System (INIS)

Bondesson, A.; Luening, M.; Wallberg, L.; Wijk, H.

1999-01-01

The environmental monitoring programme for the nuclear facilities has shown that the radioactive discharges increase the concentrations of some radionuclides in the local marine environment around the Swedish nuclear facilities. Samples from the terrestrial environment rarely show increased radionuclide concentrations. From a radiological point of view the most important nuclide in the environmental samples usually is CS-137. However, the largest part of the present concentrations of Cs-137 in the Swedish environment originate from the Chernobyl accident. The concentrations of radionuclides that can be found in biota around the nuclear facilities are much lower than the concentration levels that are known to give acute damage to organisms. The total radiation doses from the discharges of radionuclides are small. (au)

LOW CONTENT OF RADIONUCLIDES IN NATURAL ENVIRONMENT AND PRODUCTION AS A RATIONALE FOR DEVELOPMENT OF RECREATIONAL POTENTIAL OF NORTHERN BUKOVINA

Directory of Open Access Journals (Sweden)

Natalia OMEL’CHENKO

2017-06-01

Full Text Available Investigation on food products contamination by Cesium-137 and Strontium-90, detection of content of natural radionuclides (Radium-226, Thorium-232, Potassium-40 in raw materials and finished products of building industry, monitoring of some radionuclides content in soils of mountainous area of Northern Bukovina was carried out. All the results were analyzed and discussed in view of the life safety position. Data on radionuclides content in surrounding natural environment as well as in building and food industry production confirm Northern Bukovina territory’s attractiveness and safety for recreation areas development.

Radionuclide diagnosis of emergency states

International Nuclear Information System (INIS)

Ishmukhametov, A.I.

1985-01-01

Solution of emergency state radionuclide diagnostics from the technical point of view is provided by the application of the mobile quick-operating equipment in combination with computers, by the use of radionuclides with acceptable for emergency medicine characteristics and by development of radionuclide investigation data propcessing express-method. Medical developments include the study of acute disease and injury radioisotope semiotics, different indication diagnostic value determining, comparison of the results, obtained during radionuclide investigation, with clinicolaboratory and instrumental data, separation of methodical complex series

Special monitoring in nuclear medicine

International Nuclear Information System (INIS)

Beltran, C.C.; Puerta, J.A.; Morales, J.

2006-01-01

Colombia counts with around 56 centers of Nuclear Medicine, 70 Nuclear Doctors and more of 100 Technologists in this area. The radioisotopes more used are the 131 I and the 99m Tc. The radiological surveillance singular in the country is carried out for external dosimetry, being the surveillance by incorporation of radioactive materials very sporadic in our media. Given the necessity to implement monitoring programs in the incorporation of radionuclides of the occupationally exposed personnel, in the routine practice them routine of Nuclear Medicine, it was implemented a pilot program of Special Monitoring with two centers of importance in the city of Medellin. This program it was carried out with the purpose of educating, to stimulate and to establish a program of reference monitoring with base in the National Program of Monitoring in the radionuclides Incorporation that serves like base for its application at level of all the services of Nuclear Medicine in the country. This monitoring type was carried out with the purpose of obtaining information on the work routine in these centers, form of manipulation and dosage of the radionuclides, as well as the administration to the patient. The application of the program was carried out to define the frequency of Monitoring and analysis technique for the implementation of a program of routine monitoring, following the recommendations of the International Commission of Radiological Protection. For their application methods of activity evaluation were used in urine and in 7 workers thyroid, of those which only two deserve an analysis because they presented important activities. The measures were carried out during one month, every day by means in urine samples and to the most critic case is practiced two thyroid measures, one in the middle of the period and another when concluding the monitoring. To the other guy is practiced an activity count in thyroid when concluding the monitoring period. The obtained result of the

Analysis of the Monitoring Network at the Salmon, Mississippi, Site

Energy Technology Data Exchange (ETDEWEB)

None

2013-08-01

The Salmon site in southern Mississippi was the location of two underground nuclear tests and two methane-oxygen gas explosion tests conducted in the Tatum Salt Dome at a depth of 2,715 feet below ground surface. The U.S. Atomic Energy Commission (a predecessor agency of the U.S. Department of Energy [DOE]) and the U.S. Department of Defense jointly conducted the tests between 1964 and 1970. The testing operations resulted in surface contamination at multiple locations on the site and contamination of shallow aquifers. No radionuclides from the nuclear tests were released to the surface or to groundwater, although radionuclide-contaminated drill cuttings were brought to the surface during re-entry drilling. Drilling operations generated the largest single volume of waste materials, including radionuclide-contaminated drill cuttings and drilling fluids. Nonradioactive wastes were also generated as part of the testing operations. Site cleanup and decommissioning began in 1971 and officially ended in 1972. DOE conducted additional site characterization between 1992 and 1999. The historical investigations have provided a reasonable understanding of current surface and shallow subsurface conditions at the site, although some additional investigation is desirable. For example, additional hydrologic data would improve confidence in assigning groundwater gradients and flow directions in the aquifers. The U.S. Environmental Protection Agency monitored groundwater at the site as part of its Long-Term Hydrologic Monitoring Program from 1972 through 2007, when DOE's Office of Legacy Management (LM) assumed responsibility for site monitoring. The current monitoring network consists of 28 monitoring wells and 11 surface water locations. Multiple aquifers which underlie the site are monitored. The current analyte list includes metals, radionuclides, and volatile organic compounds (VOCs).

MARFA version 3.2.2 user's manual: migration analysis of radionuclides in the far field

International Nuclear Information System (INIS)

Painter, Scott; Mancillas, James

2009-12-01

The computer code Migration Analysis of Radionuclides in the Far Field (MARFA) uses a particle-based Monte Carlo method to simulate the transport of radionuclides in a sparsely fractured geological medium. Transport in sparsely fractured rock is of interest because this medium may serve as a barrier to migration of radionuclides to the accessible environment. The physical processes represented in MARFA include advection, longitudinal dispersion, Fickian diffusion into an infinite or finite rock matrix, equilibrium sorption, decay, and in-growth. Multiple non-branching decay chains of arbitrary length are supported. This document describes the technical basis and input requirements for MARFA Version 3.2.2. MARFA Version 3.2 included new capabilities to accommodate transient flow velocities and sorption parameters, which are assumed to be piecewise constant in time. Version 3.2.1 was a minor change from Version 3.2 to allow a more convenient input format for sorption information. New capabilities in Version 3.2.2 include an option to specify a non-zero start time for the simulation, an optional input parameter that decreases the amount of retention within a single fracture because of flow channeling, and an alternative method for sampling the radionuclide source. MARFA uses the particle on random streamline segment algorithm /Painter et al. 2006/, a Monte Carlo algorithm combining time-domain random walk methods with pathway stochastic simulation. The algorithm uses non-interacting particles to represent packets of radionuclide mass. These particles are moved through the system according to rules that mimic the underlying physical transport and retention processes. The set of times required for particles to pass through the geological barrier are then used to reconstruct discharge rates (mass or activity basis). Because the algorithm uses non-interacting particles, the transport and retention processes are limited to those that depend linearly on radionuclide

A review of measurement and characterisation of airborne long-lived alpha-emitting radionuclides

International Nuclear Information System (INIS)

Bigu, J.

1993-01-01

Sampling principles, monitoring instrumentation and characterisation of Long-Lived Radioactive Dust (LLRD) generated in U-Th mine and mill operations are discussed. Methods and techniques for the quantification, radionuclide identification and the study of other important characteristics of LLRD (e.g., electrical charge) are reviewed. Furthermore, field and laboratory measurements and methods of radiation dose assessment are revised. Some emphasis is placed in this work on occupational worker exposure assessment and the principles, methods and techniques of 'external' radiation exposure, internal dosimetry, and dosimetric models. It is clear that in spite of constant advances in the several areas which are the subject of this paper, there is still considerable room for improvement. For example, there is no universally accepted sampling protocol and sampler for routine LLRD monitoring for occupational hygiene exposure calculation purposes. Other areas for improvement could include calibration of instrumentation and improved sensitivity in radionuclide quantification and identification. 105 refs., 6 tabs., 3 figs

Anthropogenic radionuclides in the environment

Energy Technology Data Exchange (ETDEWEB)

Hu, Q; Weng, J; Wang, J

2007-11-15

Studies of radionuclides in the environment have entered a new era with the renaissance of nuclear energy and associated fuel reprocessing, geological disposal of high-level nuclear wastes, and concerns about national security with respect to nuclear non-proliferation. This work presents an overview of anthropogenic radionuclide contamination in the environment, as well as the salient geochemical behavior of important radionuclides. We first discuss the following major anthropogenic sources and current development that contribute to the radionuclide contamination of the environment: (1) nuclear weapons program; (2) nuclear weapons testing; (3) nuclear power plants; (4) commercial fuel reprocessing; (5) geological repository of high-level nuclear wastes, and (6) nuclear accidents. Then, we summarize the geochemical behavior for radionuclides {sup 99}Tc, {sup 129}I, and {sup 237}Np, because of their complex geochemical behavior, long half-lives, and presumably high mobility in the environment. Biogeochemical cycling and environment risk assessment must take into account speciation of these redox-sensitive radionuclides.

Radionuclide daughter inventory generator code: DIG

International Nuclear Information System (INIS)

Fields, D.E.; Sharp, R.D.

1985-09-01

The Daughter Inventory Generator (DIG) code accepts a tabulation of radionuclide initially present in a waste stream, specified as amounts present either by mass or by activity, and produces a tabulation of radionuclides present after a user-specified elapsed time. This resultant radionuclide inventory characterizes wastes that have undergone daughter ingrowth during subsequent processes, such as leaching and transport, and includes daughter radionuclides that should be considered in these subsequent processes or for inclusion in a pollutant source term. Output of the DIG code also summarizes radionuclide decay constants. The DIG code was developed specifically to assist the user of the PRESTO-II methodology and code in preparing data sets and accounting for possible daughter ingrowth in wastes buried in shallow-land disposal areas. The DIG code is also useful in preparing data sets for the PRESTO-EPA code. Daughter ingrowth in buried radionuclides and in radionuclides that have been leached from the wastes and are undergoing hydrologic transport are considered, and the quantities of daughter radionuclide are calculated. Radionuclide decay constants generated by DIG and included in the DIG output are required in the PRESTO-II code input data set. The DIG accesses some subroutines written for use with the CRRIS system and accesses files containing radionuclide data compiled by D.C. Kocher. 11 refs

Atmospheric radionuclide deposits biomonitoring in the neighbourhood of NPP Temelin in the year 2000

International Nuclear Information System (INIS)

Cechak, T.; Kluson, J.; Smejkalova, M.; Thinova, L.; Trojek, T.

2001-01-01

In this paper the results of bio-monitoring of atmospheric radionuclide deposits in the neighbourhood of NPP Temelin in the year 2000 are presented.Monitored area contained 27 sampled locations along eight radial profiles interesting the area of interest up to distance of 20 km from NPP Temelin (the measuring points are located 2-5-10-20 km form NPP). The samples were taken from forest humus, surface pine bark, Shreber moss, edible mushrooms and forest berries.The pine bark and moss were sampled at the selected sites twice yearly , at spring and fall of 2000, forest humus once in spring month of 2000, mushrooms and berries once in a growing season of 2000. In total 203 samples were collected. For the determination of radionuclide presence and their activity in samples was selected a method of Iaboratory gamma spectroscopy. The measured values corresponded to nominal values on natural background, depending mainly of geological substrata (soil contents), concentration of radon in soil or air etc. The methodology selected enables identification of individual contaminants and their contribution or occurrence. With the exception of the identified 137 Cs it is not possible to identify among the measured spectra any significant contribution of any other radionuclides

Radionuclide Concentrations in Terrestrial Vegetation and Soil Samples On and Around the Hanford Site, 1971 Through 2008

Energy Technology Data Exchange (ETDEWEB)

Simmons, Mary Ann; Poston, Ted M.; Fritz, Brad G.; Bisping, Lynn E.

2011-07-29

Environmental monitoring is conducted on the U.S. Department of Energy (DOE) Hanford Site to comply with DOE Orders and federal and state regulations. Major objectives of the monitoring are to characterize contaminant levels in the environment and to determine site contributions to the contaminant inventory. This report focuses on surface soil and perennial vegetation samples collected between 1971 and 2008 as part of the Pacific Northwest National Laboratory Surface Environmental Surveillance Project performed under contract to DOE. Areas sampled under this program are located on the Hanford Site but outside facility boundaries and on public lands surrounding the Hanford Site. Additional samples were collected during the past 8 years under DOE projects that evaluated parcels of land for radiological release. These data were included because the same sampling methodology and analytical laboratory were used for the projects. The spatial and temporal trends of six radionuclides collected over a 38-year period were evaluated. The radionuclides----cobalt-60, cesium-137, strontium-90, plutonium-238, plutonium-239/240, and uranium (reported either as uranium-238 or total uranium)----were selected because they persist in the environment and are still being monitored routinely and reported in Hanford Site environmental reports. All these radionuclides were associated with plutonium production and waste management of activities occurring on the site. Other sources include fallout from atmospheric testing of nuclear weapons, which ended in 1980, and the Chernobyl explosion in 1986. Uranium is also a natural component of the soil. This assessment of soil and vegetation data provides important information on the distribution of radionuclides in areas adjacent to industrial areas, established perimeter locations and buffer areas, and more offsite nearby and distant locations. The concentrations reflect a tendency for detection of some radionuclides close to where they were

Environmental radiation monitoring around the nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Woo; Choi, Geun Sik and others

2001-02-01

Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry.

Environmental radiation monitoring around the nuclear facilities

International Nuclear Information System (INIS)

Lee, Chang Woo; Choi, Young Ho

2000-02-01

Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry. (author)

Environmental radiation monitoring around the nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Woo; Choi, Young Ho

2000-02-01

Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author)

Environmental radiation monitoring around the nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Woo; Choi, Young Ho; Lee, M.H. [and others

1999-02-01

Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author). 3 refs., 50 tabs., 12 figs.

Environmental radiation monitoring around the nuclear facilities

International Nuclear Information System (INIS)

Lee, Chang Woo; Choi, Geun Sik and others

2001-02-01

Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry

Environmental radiation monitoring around the research reactors

International Nuclear Information System (INIS)

Lee, Chang Woo; Lee, Hyun Duk; Kim, Sam Rang; Choi, Yong Ho; Kim, Jeong Moo; Lee, Myeon Joo; Lee, Myeong Ho; Hong, Kwang Hee; Lim, Moon Ho; Lee, Won Yoon; Park, Do Won; Choi, Sang Do

1993-04-01

Environmental radiation monitoring was carried out measurement of environmental radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross α, β radioactivity in environmental sample was not found abnormal data. γ-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry. (Author)

Radionuclides in the environment in the south of Spain, anthropogenic enhancements due to industry

Energy Technology Data Exchange (ETDEWEB)

Manjon, G. [Depto. de Fisica Aplicada 2, E.T.S. Arquitectura, Universidad de Sevilla, Av. Reina Mercedes 2, 41012 - Sevilla (Spain)

2007-07-01

Levels of natural radionuclides in the environment are affected by human activities in the South of Spain. Industry wastes, such as phospho-gypsum, have been released to an estuary since sixties until 1997. Nowadays the wastes management is careful with environment protection, which can be clearly observed today in the radionuclides pattern. Different sources of radionuclides (industry wastes, tidal action and mining) can be distinguished in the estuary. Uranium isotopes, {sup 226}Ra, {sup 210}Pb and {sup 210}Po were determined in water and sediment samples for this study. An iron recycling factory is working close to Seville (South of Spain). A {sup 137}Cs source was accidentally burnt in a furnace of this factory in 2001. The environmental impact of this accident was immediately denatured. Monitoring procedure and results are sho vn in this contribution. Radionuclides measurement involves difficult techniques. In this communication a procedure to determine the activity concentration of {sup 210}Pb by liquid scintillation counting is presented. Two quality tests, using gamma- and alpha-spectrometry were applied to the {sup 210} Pb results. (Author)

Radionuclides in the environment in the south of Spain, anthropogenic enhancements due to industry

International Nuclear Information System (INIS)

Manjon, G.

2007-01-01

Levels of natural radionuclides in the environment are affected by human activities in the South of Spain. Industry wastes, such as phospho-gypsum, have been released to an estuary since sixties until 1997. Nowadays the wastes management is careful with environment protection, which can be clearly observed today in the radionuclides pattern. Different sources of radionuclides (industry wastes, tidal action and mining) can be distinguished in the estuary. Uranium isotopes, 226 Ra, 210 Pb and 210 Po were determined in water and sediment samples for this study. An iron recycling factory is working close to Seville (South of Spain). A 137 Cs source was accidentally burnt in a furnace of this factory in 2001. The environmental impact of this accident was immediately denatured. Monitoring procedure and results are sho vn in this contribution. Radionuclides measurement involves difficult techniques. In this communication a procedure to determine the activity concentration of 210 Pb by liquid scintillation counting is presented. Two quality tests, using gamma- and alpha-spectrometry were applied to the 210 Pb results. (Author)

Tracing Fukushima Radionuclides in the Northern Hemisphere -An Overview

Science.gov (United States)

Thakur, Punam; Ballard, Sally; Nelson, Roger

2013-04-01

A massive 9.0 earthquake and ensuing tsunami struck the northern coast of the Honshu-island, Japan on March 11, 2011 and severely damaged the electric system of the Fukushima- Daiichi Nuclear Power Plant (NPP). The structural damage to the plant disabled the reactor's cooling systems. Subsequent fires, a hydrogen explosion and possible partial core meltdowns released radioactive fission products into the atmosphere. The atmospheric release from the crippled Fukushima NPP started on March 12, 2011 with a maximum release phase from March 14 to 17. The radioactivity released was dominated by volatile fission products including isotopes of the noble gases xenon (Xe-133) and krypton (Kr-85); iodine (I-131,I-132); cesium (Cs-134,Cs-136,Cs-137); and tellurium (Te-132). The non-volatile radionuclides such as isotopes of strontium and plutonium are believed to have remained largely inside the reactor, although there is evidence of plutonium release into the environment. Global air monitoring across the northern hemisphere was increased following the first reports of atmospheric releases. According to the source term, declared by the Nuclear and Industrial Safety Agency (NISA) of Japan), approximately 160 PBq (1 PBq (Peta Becquerel = 10^15 Bq)) of I-131 and 15 PBq of Cs-137 (or 770 PBq "iodine-131 equivalent"), were released into the atmosphere. The 770 PBq figure is about 15% of the Chernobyl release of 5200 PBq of "iodine-131 equivalent". For the assessment of contamination after the accident and to track the transport time of the contaminated air mass released from the Fukushima NPP across the globe, several model calculations were performed by various research groups. All model calculations suggested long-range transport of radionuclides from the damaged Fukushima NPP towards the North American Continent to Europe and to Central Asia. As a result, an elevated level of Fukushima radionuclides were detected in air, rain, milk, and vegetation samples across the northern

Critical review: Radionuclide transport, sediment transport, and water quality mathematical modeling; and radionuclide adsorption/desorption mechanisms

Energy Technology Data Exchange (ETDEWEB)

Onishi, Y.; Serne, R.J.; Arnold, E.M.; Cowan, C.E.; Thompson, F.L. [Pacific Northwest Lab., Richland, WA (United States)

1981-01-01

This report describes the results of a detailed literature review of radionuclide transport models applicable to rivers, estuaries, coastal waters, the Great Lakes, and impoundments. Some representatives sediment transport and water quality models were also reviewed to evaluate if they can be readily adapted to radionuclide transport modeling. The review showed that most available transport models were developed for dissolved radionuclide in rivers. These models include the mechanisms of advection, dispersion, and radionuclide decay. Since the models do not include sediment and radionuclide interactions, they are best suited for simulating short-term radionuclide migration where: (1) radionuclides have small distribution coefficients; (2) sediment concentrations in receiving water bodies are very low. Only 5 of the reviewed models include full sediment and radionuclide interactions: CHMSED developed by Fields; FETRA SERATRA, and TODAM developed by Onishi et al, and a model developed by Shull and Gloyna. The 5 models are applicable to cases where: (1) the distribution coefficient is large; (2) sediment concentrations are high; or (3) long-term migration and accumulation are under consideration. The report also discusses radionuclide absorption/desorption distribution ratios and addresses adsorption/desorption mechanisms and their controlling processes for 25 elements under surface water conditions. These elements are: Am, Sb, C, Ce, Cm, Co, Cr, Cs, Eu, I, Fe, Mn, Np, P, Pu, Pm, Ra, Ru, Sr, Tc, Th, {sup 3}H, U, Zn and Zr.

Static and mobile networks design for atmospheric accidental releases monitoring

International Nuclear Information System (INIS)

Abida, R.

2010-01-01

The global context of my PhD thesis work is the optimization of air pollution monitoring networks, but more specifically it concerns the monitoring of accidental releases of radionuclides in air. The optimization problem of air quality measuring networks has been addresses in the literature. However, it has not been addresses in the context of surveillance of accidental atmospheric releases. The first part of my thesis addresses the optimization of a permanent network of monitoring of radioactive aerosols in the air, covering France. The second part concerns the problem of targeting of observations in case of an accidental release of radionuclides from a nuclear plant. (author)

RADBASE: A PC-based radionuclide data base for environmental site assessment

International Nuclear Information System (INIS)

Dundon, S.T.; Heger, A.S.

1992-01-01

A personal computer-based code, RADBASE, is being developed as a tool for reviewing environmental risk data. RADBASE has been designed to display the properties of radionuclides encountered in environmental restoration programs. The code contains five major features that display (a) physical properties, (b) pathways and toxicity data, (c) means of production and common uses, (d) federal radiation protection standards and action levels, and (e) bibliographic information. The benefits of the radionuclide data base contained in this code include time efficiency and update capability. This code separates itself from similar codes on the basis of its interactive data files, windows environment, and content. The user must only be equipped with basic information on a site and possess a minimum amount of user knowledge to operate and access additional data applicable to the constituents at the site

Radionuclide air emissions at Department of Energy facilities

Energy Technology Data Exchange (ETDEWEB)

Duvall, K. [Department of Energy, Washington, DC (United States)

1995-02-01

Facilities operated by the U.S. Department of Energy (DOE) handle and process radioactive materials in conjunction with their research, nuclear materials production, remediation and waste disposal activities. Radionuclide emissions to the atmosphere from DOE facilities are regulated by the Environmental Protection Agency (EPA) under 40 CFR Part 61, Subpart H for emissions other than radon. Subpart H requires DOE to monitor emissions from stacks and calculate a potential offsite dose to an individual using EPA approved methods and procedures. DOE has applied to EPA for approval to use alternative methods for some of the EPA requirements for continuous monitoring. The use of alternative methods such as single-point sampling with a shrouded probe will have an impact at several major DOE facilities. These facilities are identified.

Development of an environmental radiation analysis research capability in the UAE

International Nuclear Information System (INIS)

Kim, Sung-yeop; Kim, Chankyu; Lee, Kun Jai; Chang, Soon Heung; Elmasri, Hasna; Beeley, Philip A.

2013-01-01

The UAE has started a nuclear energy program with the aim of having its first four units on-line between 2017 and 2020 and it is important that the country has an environmental radiation analysis capability to support this program. Khalifa University is therefore implementing a research laboratory to support both experimental analysis and radionuclide transport modeling in the aquatic and terrestrial environment. This paper outlines the development of this capability as well as the work in progress and planned for the future. - Highlights: • New university environmental radiation laboratory established in UAE. • Facilities included for alpha, beta and gamma radiometrics. • Transport modeling capability is being established. • Laboratory also used for education and training. • Robotic methods for sampling and analysis are under development

Intercomparisons in the radiation monitoring network of the Czech Republic

Energy Technology Data Exchange (ETDEWEB)

Tuckova, S; Malatova, I [National Radiation Protection Inst., Prague (Czech Republic); Drabova, D [State Office for Nuclear Safety, Prague (Czech Republic)

1996-12-31

In Czech Republic, altogether 11 laboratories, equipped by semiconductor gamma spectrometry supply regularly to the Centre of Radiation Monitoring Network the measured data about the radionuclide activity concentration in different environmental samples, participating thus in monitoring of radiation situation in the country. The Center of Radiation Monitoring Network of Czech Republic periodically organizes through its reference laboratories interlaboratory comparison tests ensuring thus quality of the measurements within the radiation monitoring network. A ring intercomparison test was organized in 1994. The piece of steel rather highly contaminated by {sup 60}Co was used. In the intercomparison test 1994-1995 of pulverized concrete breeze-block containing fly ash with natural radionuclides were used. Results of this measurement is given as an example (authors).

Accumulation of radionuclides in selected marine biota from Manjung coastal area

Energy Technology Data Exchange (ETDEWEB)

Abdullah, Anisa, E-mail: coppering@ymail.com; Hamzah, Zaini; Wood, Ab. Khalik [Faculty of Applied Sciences, Universiti Teknologi MARA, 40450, Shah Alam, Selangor (Malaysia); Saat, Ahmad [Faculty of Applied Sciences, Universiti Teknologi MARA, 40450, Shah Alam, Selangor (Malaysia); Institute of Science, Universiti Teknologi MARA, 40450 Shah Alam, Selangor (Malaysia); Alias, Masitah [TNB Reasearch Sdn. Bhd., Kawasan Institusi Penyelidikan, 43000 Kajang, Selangor (Malaysia)

2015-04-29

Distribution of radionuclides from anthropogenic activities has been intensively studied due to the accumulation of radionuclides in marine ecosystem. Manjung area is affected by rapid population growth and socio-economic development such as heavy industrial activities including coal fired power plant, iron foundries, port development and factories, agricultural runoff, waste and toxic discharge from factories.It has radiological risk and toxic effect when effluent from the industries in the area containing radioactive materials either being transported to the atmosphere and deposited back over the land or by run off to the river and flow into coastal area and being absorbed by marine biota. Radionuclides presence in the marine ecosystem can be adversely affect human health when it enters the food chain. This study is focusing on the radionuclides [thorium (Th), uranium (U), radium-226 ({sup 226}Ra), radium-228 ({sup 228}Ra) and potassium-40 ({sup 40}K)] content in marine biota and sea water from Manjung coastal area. Five species of marine biota including Johnius dussumieri (Ikan Gelama), Pseudorhombus malayanus (Ikan Sebelah), Arius maculatus (Ikan Duri), Portunus pelagicus (Ketam Renjong) and Charybdis natator (Ketam Salib) were collected during rainy and dry seasons. Measurements were carried out using Inductively Coupled Plasma Mass Spectrometer (ICPMS). The results show that the concentration of radionuclides varies depends on ecological environment of respective marine biota species. The concentrations and activity concentrations are used for the assessment of potential internal hazard index (H{sub in}), transfer factor (TF), ingestion dose rate (D) and health risk index (HRI) to monitor radiological risk for human consumption.

Accumulation of radionuclides in selected marine biota from Manjung coastal area

International Nuclear Information System (INIS)

Abdullah, Anisa; Hamzah, Zaini; Wood, Ab. Khalik; Saat, Ahmad; Alias, Masitah

2015-01-01

Distribution of radionuclides from anthropogenic activities has been intensively studied due to the accumulation of radionuclides in marine ecosystem. Manjung area is affected by rapid population growth and socio-economic development such as heavy industrial activities including coal fired power plant, iron foundries, port development and factories, agricultural runoff, waste and toxic discharge from factories.It has radiological risk and toxic effect when effluent from the industries in the area containing radioactive materials either being transported to the atmosphere and deposited back over the land or by run off to the river and flow into coastal area and being absorbed by marine biota. Radionuclides presence in the marine ecosystem can be adversely affect human health when it enters the food chain. This study is focusing on the radionuclides [thorium (Th), uranium (U), radium-226 ( 226 Ra), radium-228 ( 228 Ra) and potassium-40 ( 40 K)] content in marine biota and sea water from Manjung coastal area. Five species of marine biota including Johnius dussumieri (Ikan Gelama), Pseudorhombus malayanus (Ikan Sebelah), Arius maculatus (Ikan Duri), Portunus pelagicus (Ketam Renjong) and Charybdis natator (Ketam Salib) were collected during rainy and dry seasons. Measurements were carried out using Inductively Coupled Plasma Mass Spectrometer (ICPMS). The results show that the concentration of radionuclides varies depends on ecological environment of respective marine biota species. The concentrations and activity concentrations are used for the assessment of potential internal hazard index (H in ), transfer factor (TF), ingestion dose rate (D) and health risk index (HRI) to monitor radiological risk for human consumption

Accumulation of radionuclides in selected marine biota from Manjung coastal area

Science.gov (United States)

Abdullah, Anisa; Hamzah, Zaini; Saat, Ahmad; Wood, Ab. Khalik; Alias, Masitah

2015-04-01

Distribution of radionuclides from anthropogenic activities has been intensively studied due to the accumulation of radionuclides in marine ecosystem. Manjung area is affected by rapid population growth and socio-economic development such as heavy industrial activities including coal fired power plant, iron foundries, port development and factories, agricultural runoff, waste and toxic discharge from factories.It has radiological risk and toxic effect when effluent from the industries in the area containing radioactive materials either being transported to the atmosphere and deposited back over the land or by run off to the river and flow into coastal area and being absorbed by marine biota. Radionuclides presence in the marine ecosystem can be adversely affect human health when it enters the food chain. This study is focusing on the radionuclides [thorium (Th), uranium (U), radium-226 (226Ra), radium-228 (228Ra) and potassium-40 (40K)] content in marine biota and sea water from Manjung coastal area. Five species of marine biota including Johnius dussumieri (Ikan Gelama), Pseudorhombus malayanus (Ikan Sebelah), Arius maculatus (Ikan Duri), Portunus pelagicus (Ketam Renjong) and Charybdis natator (Ketam Salib) were collected during rainy and dry seasons. Measurements were carried out using Inductively Coupled Plasma Mass Spectrometer (ICPMS). The results show that the concentration of radionuclides varies depends on ecological environment of respective marine biota species. The concentrations and activity concentrations are used for the assessment of potential internal hazard index (Hin), transfer factor (TF), ingestion dose rate (D) and health risk index (HRI) to monitor radiological risk for human consumption.

Radiation-related monitoring and environmental research at the Nevada Test Site

International Nuclear Information System (INIS)

Anspaugh, L.R.; Patton, S.E.; Shinn, J.H.; Black, S.C.; Costa, C.F.; Elle, D.R.; Essington, E.H.; Gilbert, R.O.; Gonzalez, D.A.; Hunter, R.B.; Medica, P.A.; McArthur, R.D.; Thompson, C.B.; O'Farrell, T.P.; Romney, E.M.

1990-01-01

Beginning with the first nuclear-weapons-related tests at the Nevada Test Site (NTS) in 1951, a radiation-related monitoring program was established to determine the levels and distribution of radionuclides released. Primary methods involved survey-meter-equipped field-monitoring teams and placement of film badges and air-sampling devices at fixed locations. Beginning in the mid-1950s, more stringent standards, the results of this monitoring program, and the results of related research programs led to increased engineering efforts to reduce local fallout. With passage of the National Environmental Policy Act and increased concern about possible effects of radiation exposure, environmental activities related to the NTS increased. There is now an extensive monitoring program at the NTS to assess radiological conditions resulting from past tests and from continued testing of nuclear-weapons devices. In populated areas near NTS, there is also a monitoring effort that relies on assistance from local communities. Other efforts include reconstruction of radiation doses received by offsite residents during the 1950s and 1960s, determination of the current inventory and distribution of radionuclides in surface soil, and studies of the movement of radionuclides in the desert ecosystem

Investigate the Capabilities of Remotely Sensed Crop Indicators for Agricultural Drought Monitoring in Kansas

Science.gov (United States)

Zhang, J.; Becker-Reshef, I.; Justice, C. O.

2013-12-01

Although agricultural production has been rising in the past years, drought remains the primary cause of crop failure, leading to food price instability and threatening food security. The recent 'Global Food Crisis' in 2008, 2011 and 2012 has put drought and its impact on crop production at the forefront, highlighting the need for effective agricultural drought monitoring. Satellite observations have proven a practical, cost-effective and dynamic tool for drought monitoring. However, most satellite based methods are not specially developed for agriculture and their performances for agricultural drought monitoring still need further development. Wheat is the most widely grown crop in the world, and the recent droughts highlight the importance of drought monitoring in major wheat producing areas. As the largest wheat producing state in the US, Kansas plays an important role in both global and domestic wheat markets. Thus, the objective of this study is to investigate the capabilities of remotely sensed crop indicators for effective agricultural drought monitoring in Kansas wheat-grown regions using MODIS data and crop yield statistics. First, crop indicators such as NDVI, anomaly and cumulative metrics were calculated. Second, the varying impacts of agricultural drought at different stages were explored by examining the relationship between the derived indicators and yields. Also, the starting date of effective agricultural drought early detection and the key agricultural drought alert period were identified. Finally, the thresholds of these indicators for agricultural drought early warning were derived and the implications of these indicators for agricultural drought monitoring were discussed. The preliminary results indicate that drought shows significant impacts from the mid-growing-season (after Mid-April); NDVI anomaly shows effective drought early detection from Late-April, and Late-April to Early-June can be used as the key alert period for agricultural

Low-cost bioremediation of heavy metals and radionuclides of contaminated soils

International Nuclear Information System (INIS)

Sathiyamoorthy, P.; Golan-Goldhrish, A.

2005-01-01

The environmental pollution by toxic metals, especially lead (Pb), mercury (Hg), cadmium (Cd), nickel (Ni), copper (Cu), selenium (Se), chromium (Cr) and radionuclides ( 137 Cs, 90 Sr, 238 Pu, 226 Ra) is a potential hazard to health and welfare of mankind. Rapid industrial revolution has left an international legacy of soil and water contaminated with a combination of toxic and potentially carcinogenic compounds and heavy metals. Many of the contaminated sites were abandoned due to high cost of traditional clean-up approaches. Various approaches are being practiced to decontaminate heavy metals and radionuclides from polluted-soil. Remediation of heavy metal and radionuclides contaminated soils poses a significant expense to many industries and government organizations. Remediation cost in the United States and European Union alone is expected to exceed US$20 billion annually. Bioremediation strategy depends on the limitations of technology, cost and nature of the contaminant in the soil. Certain higher plants are capable of accumulation of heavy metals (2-5 %) in roots and shoots to the level far exceeding those present in the soils, these are called hyper-accumulators. Using heavy metal hyper-accumulating higher plants for environmental clean-up of contaminated soil is a recently emerged technology known as 'phytoremediation'. Genetically engineered (Transgenic) plants have a remarkable potential to absorb heavy metals and show a new avenue for biotechnology technique in Phytoremediation. The cost-effective approach of using heavy metal and radionuclide hyper-accumulators in phytoremediation is discussed. (author)

Integrated report on radionuclide migration at the Savannah River shallow land burial site

International Nuclear Information System (INIS)

Towler, O.A. Jr.

1989-03-01

The impact of the SRP Solid Radioactive Waste Burial Ground on the environment has been studied since the early 1970s in four subtasks: subsurface monitoring of groundwater, lysimeter tests of waste, soil-water chemistry effects, and radionuclide transport modeling. This document summarizes and integrates the results of the four subtasks. More information has been gathered on the behavior of radionuclides in a solid waste disposal facility located in a humid region than from any other waste disposal site in the world. The design of closure for the SRP Burial Ground has been given a firm technical basis. The limiting pathways for radionuclide migration have been determined to be infiltrating rainwater and root penetration. Closure designs must therefore address both these factors. The designs for new storage/disposal facilities have also been given a firm technical basis. The major conclusions are that tritium will be stored for decay and not allowed to contact the groundwater, waste containing long-lived radionuclides such as iodine-129 must be stored for later geologic disposal, and above and below ground concrete vaults should be used for disposal of other low-level radioactive waste. 61 refs., 18 figs. 8 tabs

History of medical radionuclide production.

Science.gov (United States)

Ice, R D

1995-11-01

Radionuclide production for medical use originally was incidental to isotope discoveries by physicists and chemists. Once the available radionuclides were identified they were evaluated for potential medical use. Hevesy first used 32P in 1935 to study phosphorous metabolism in rats. Since that time, the development of cyclotrons, linear accelerators, and nuclear reactors have produced hundreds of radionuclides for potential medical use. The history of medical radionuclide production represents an evolutionary, interdisciplinary development of applied nuclear technology. Today the technology is represented by a mature industry and provides medical benefits to millions of patients annually.

Development of long-lived radionuclide transmutation technology -Development of long-lived radionuclide handling technology-

Energy Technology Data Exchange (ETDEWEB)

Park, Jin Hoh; Jung, Won Myung; Lee, Kyoo Il; Woo, Moon Sik; Cho, Kyung Tae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

The final goals of this research are completion of design for construction of wet hot cell and auxiliary facilities, and development of main equipments and technologies for remote operation and near real time monitoring system of radioactivity of solution. This wet hot cell and technology will be used for active test of the radionuclide partitioning process and for fission Mo separation and purification process. And high level radioactive and toxic materials will be treated as the form of solution in this wet hot cell. In this R. and D., the important objectives are (1)to provide safe operation, and (2)to keep radiation exposure to staff as low as practicable, (3)to protect the environment. 34 figs, 22 tabs, 44 refs. (Author).

Determination of radionuclide concentrations in ground level air using the ASS-500 high volume sampler

International Nuclear Information System (INIS)

Frenzel, E.; Arnold, D.; Wershofen, H.

1996-01-01

A method for determination of radionuclide concentrations in air aerosol samples collected by the high volume aerosol sampler ASS-500 was elaborated. The aerosol sampling station ASS-500 is a Stand alone, all-weather proofed instrument. It is designed for representative sampling of airborne radionuclides from ground level air at a height of about 1.5 m above ground level. The ASS-500 station enables continuous air monitoring both normal and emergency Situations. The collection of aerosols on the Petrianov FPP-15-1.5 type filter out of an air volume of about 100,000 m 3 (sampling period 1 wk) or of about 250,000 m 3 (sampling period 3 wk) admits accurate spectrometric low level measurements of natural and artificial radionuclides. The achieved detection limit is 0.5 μBq m -3 and 0.2 μBq m -3 for 137 Cs, respectively. A new developed air flow Meter system allows to enhance the collected air volume to about 150,000 m 3 per week and lowers the detection limit to -3 for 137 Cs for weekly collected aerosol samples. In Poland the CLOR uses 9 Stations ASS-500 at different sites as atmospheric radioactivity control system. On the basis of spectrometric measurements of natural and artificial radionuclides in the collected aerosol samples at the different sites, CLOR establishes a weekly report about the radiological situation at Poland for responsible authorities. The very low achievable detection limit of the Station ASS-500 due 10 the high air flow fate and the long possible sampling period were the key argument for other government radiation protection authorities in Europe to introduce the Station ASS-500 into their low level radionuclide atmospheric monitoring programs (Austria, Belarus, France, Germany, Iceland, Spain, Switzerland, Ukraine)

Assessment of necessary regularity of internal irradiation monitoring on the basis of direct and indirect methods of dosimetry

International Nuclear Information System (INIS)

Malykhin, V.M.; Ivanova, N.I.

1981-01-01

It is shown that when assessing the necessary periodicity of internal irradiation monitoring, it is required to take account of the nature (rhythm) of radionuclide intake to the organism during the monitoring period, the effective period of radionuclide biological half-life, its activity in the organism, sensitivity of the technique applied and the labour-consumig character of the monitoring method [ru

Initial site characterization and evaluation of radionuclide contaminated soil waste burial grounds

International Nuclear Information System (INIS)

Phillips, S.J.; Reisenauer, A.E.; Rickard, W.H.; Sandness, G.A.

1977-02-01

A survey of historical records and literature containing information on the contents of 300 Area and North Burial Grounds was completed. Existing records of radioactive waste location, type, and quantity within each burial ground facility were obtained and distributed to cooperating investigators. A study was then initiated to evaluate geophysical exploration techniques for mapping buried waste materials, waste containers, and trench boundaries. Results indicate that a combination of ground penetrating radar, magnetometer, metal detector, and acoustic measurements will be effective but will require further study, hardware development, and field testing. Drilling techniques for recovering radionuclide-contaminated materials and sediment cores were developed and tested. Laboratory sediment characterization and fluid transport and monitoring analyses were begun by installation of in situ transducers at the 300 North Burial Ground site. Biological transport mechanisms that control radionuclide movement at contaminated sites were also studied. Flora and fauna presently inhabiting specific burial ground areas were identified and analyzed. Future monitoring of specific mammal populations will permit determination of dose rate and pathways of contaminated materials contained in and adjacent to burial ground sites

Proposal of a calibration protocol of gamma chambers for estimation of the radionuclides incorporation in emergency situations

International Nuclear Information System (INIS)

Dantas, B.M.; Lucena, E.; Dantas, A.L.A.; Araujo, F.; Melo, D.; Teran, M.; Paolino, A.; Hermida, J.C.; Rojo, A.; Puerta, J.A.; Morales, J.; Lopez B, G.M.; Alfaro, M.; Ruiz, M.A.; Videla, R.; Pinones, O.; Gonzalez, S.; Navarro, T.; Cruz S, R.

2006-01-01

In the last years in several countries has come increasing the concern with the possibility of accidents related to the transport and manipulation of open sources used in nuclear medicine. This carried out to the search of alternative methods for the monitoring of workers and individuals of the public exposed to the radionuclides incorporation like 131 I, 201 Tl, 153 Sm among others. One of the options to assist the demand for monitoring of the radionuclides incorporation is the use of gamma chambers that are medical diagnostic equipment available in the own centers of nuclear medicine. The gamma chambers are used to obtain images of patient to which are administered a radionuclide of well-known activity with diagnostic purposes. These equipment have among its components elements that spectrometric systems like those used in the evaluation of the internal incorporation for direct measurements, reason why besides its use for diagnosis by image they can be gauged with anthropomorphic simulators and also with punctual sources for the quantification of the radionuclides activity, distributed homogeneously in the human body or located in specific organs. This work presents the development of a calibration protocol of gamma chambers for the in vivo determination of radionuclides and it proposes the implementation of the protocol in centers of nuclear medicine of the 9 countries participants of the project OAS-ARCAL-RLA/9/049-LXXVIII - Harmonization of procedures of internal dosimetry (Argentina, Brazil, Colombia, Cuba, Chile, Mexico, Peru, Uruguay and Spain). The protocol is the base to establish an integrated net to attend in the response to emergencies using nuclear medicine centers of public hospitals of the region. The proposal is an additional alternative for the monitoring of people in emergency situations where it is possible and feasible the use of the gamma chambers. This would avoid the person's transport with incorporation suspicion for a conventional whole

Area 11 case study of radionuclide movement by storm channel erosion: A baseline method and initial evaluation

International Nuclear Information System (INIS)

Shinn, J.H.; Gouveia, F.J.; Patton, S.E.; Fry, C.O.

1993-04-01

At the Nevada Test Site (NTS), where radionuclide contamination is found in surface soils, there is potential for water erosion to move radionuclides beyond the boundaries of controlled areas and into channels cut by infrequent storms. This loss of control and the increased risk of further movement are issues which require the development of a method for the quantitative monitoring of contamination and calculation of the radionuclide-movement rate. In this report the authors develop a method which is used to measure the amount and rate of movement of americium-241 ( 241 Am) in a storm channel, and which offers special features for establishment of baseline concentrations. This method was applied to the standing problem of the erosion of the plutonium contaminated open-quotes ground zeroclose quotes area of site open-quotes 11Dclose quotes in Area 11 of NTS. By establishing 241 Am concentrations in the storm channel, the concentrations of 239+240 Pu can also be calculated using a previously determined 239+240 Pu/ 241 Am ratio from soil samples collected in Area 11. The method utilizes systematic field surveys with a field instrument for detection of low-energy radiation (FIDLER), and provides a computational method which, when validated, could become a standard procedure for monitoring radionuclide movement in the washes and storm channels throughout the NTS

Hanford Site radionuclide national emission standards for hazardous air pollutants unregistered stack (power exhaust) source assessment

International Nuclear Information System (INIS)

Davis, W.E.

1994-01-01

On February 3, 1993, the US Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency, Region 10. The Compliance Order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission measurement requirements in 40 Code of Federal Regulations (CFR) 61, Subpart H, and to continuously measure radionuclide emissions in accordance with 40 CFR 61.93. This evaluation provides an assessment of the 39 unregistered stacks, under Westinghouse Hanford Company's management, and their potential radionuclide emissions, i.e., emissions with no control devices in place. The evaluation also determined if the effective dose equivalent from any of these stack emissions exceeded 0.1 mrem/yr, which will require the stack to have continuous monitoring. The result of this assessment identified three stacks, 107-N, 296-P-26 and 296-P-28, as having potential emissions that would cause an effective dose equivalent greater than 0.1 mrem/yr. These stacks, as noted by 40 CFR 61.93, would require continuous monitoring

Hanford Site radionuclide national emission standards for hazardous air pollutants unregistered stack (power exhaust) source assessment

Energy Technology Data Exchange (ETDEWEB)

Davis, W.E.

1994-08-04

On February 3, 1993, the US Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency, Region 10. The Compliance Order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission measurement requirements in 40 Code of Federal Regulations (CFR) 61, Subpart H, and to continuously measure radionuclide emissions in accordance with 40 CFR 61.93. This evaluation provides an assessment of the 39 unregistered stacks, under Westinghouse Hanford Company`s management, and their potential radionuclide emissions, i.e., emissions with no control devices in place. The evaluation also determined if the effective dose equivalent from any of these stack emissions exceeded 0.1 mrem/yr, which will require the stack to have continuous monitoring. The result of this assessment identified three stacks, 107-N, 296-P-26 and 296-P-28, as having potential emissions that would cause an effective dose equivalent greater than 0.1 mrem/yr. These stacks, as noted by 40 CFR 61.93, would require continuous monitoring.

Trends in radionuclide concentrations for wildlife and food products near Hanford for the period 1971 through 1988

International Nuclear Information System (INIS)

Eberhardt, L.E.; Cadwell, L.L.; Price, K.R.; Carlile, D.W.

1989-10-01

The objective of this summary investigation was to identify trends in radionuclide concentrations for wildlife and food products sampled from 1971 through 1988 as part of the Hanford Site Environmental Monitoring Program. No upward trends in radionuclide concentrations were detected for any wildlife or food products. Several sample types demonstrated significantly declining radionuclide concentrations. Three factors appeared to be responsible for the trends. First, the cessation of atmospheric testing by the United States and Soviet Union in 1971 contributed to the decline of radionuclides in some samples. Second, contaminants discharged to the Columbia River were reduced subsequent to the 1971 shutdown of the last Hanford nuclear reactor that used a once-through cooling water design. The reactor closing resulted in declines in activation products in oysters from Willapa Bay and in whitefish from the Hanford Reach of the Columbia River. Third, reductions in radionuclide concentrations in Hanford wildlife suggested a decreasing availability of environmental contaminants to wildlife. Remediation of areas having environmental surface contaminants on the Hanford Site was identified as a probable cause. 5 refs., 4 figs., 2 tabs

Technogenic and natural radionuclides in Black Sea sediments and algae

International Nuclear Information System (INIS)

Strezov, A.; Stoilova, T.; Petkov, N.; Hristoskova, M.

1999-01-01

Technogenic and natural emitters have been monitored since 1991 in marine samples from the Bulgarian Black Sea coast by low level gamma and alpha spectroscopy. The radionuclide content was determined in bottom sediment samples from 35 reference locations in the spring, summer and autumn during six consecutive years. Samples were collected and data obtained for the main Black Sea resorts and the main dwelling places along the Bulgarian Black Sea shore

Proposed radioactive liquid effluent monitoring requirements at the Savannah River Site

International Nuclear Information System (INIS)

Jannik, G.T.; Carlton, W.H.; Blunt, B.C.

1994-01-01

Clear regulatory guidance exists for structuring a radiological air monitoring program, however, there is no parallel guidance for radiological liquid monitoring. For Department of Energy (DOE) facilities, there are no existing applicable federal regulations, DOE orders, or DOE guidance documents that specify at what levels continuous monitoring, continuous sampling, or periodic confirmatory measurements of radioactive liquid effluents must be made. In order to bridge this gap and to technically justify and document liquid effluent monitoring decisions at DOE's Savannah River Site, Westinghouse Savannah River Company has proposed that a graded, dose-based approach be established, in conjunction with limits on facility radionuclide inventories, to determine the monitoring and sampling criteria to be applied at each potential liquid radioactive effluent point. The graded approach would be similar to--and a conservative extension of--the existing, agreed-upon SRS/EPA-IV airborne effluent monitoring approach documented in WSRC's NESHAP Quality Assurance Project Plan. The limits on facility radionuclide inventories are based on--and are a conservative extension of--the 10 CFR 834, 10 CFR 20, and SCR 61-63 annual limits on discharges to sanitary sewers. Used in conjunction with each other, the recommended source category criteria levels and facility radionuclide inventories would allow for the best utilization of resources and provide consistent, technically justifiable determinations of radioactive liquid effluent monitoring requirements

Naturally occurring radionuclides transfer factor on aquatic flora and fauna in Nagarjuna Sagar Dam near proposed uranium mining site

International Nuclear Information System (INIS)

Arunachalam, Kantha Deivi

2015-04-01

Naturally occurring radioactive element can be found in low levels within all rock, soil, and water. The present work aims to understand the transfer of naturally occurring radionuclides in different compartments of environment reflecting its behaviour in different tropic levels. The understanding and evaluation of the possible interactions of various naturally occurring radionuclides were done in the world's third largest man-made dam, Nagarjuna Sagar, built on river Krishna located in Andhra Pradesh, India. The naturally occurring radionuclides such as Uranium ( 238 U), Polonium ( 210 Po), Radium ( 226 Ra), and Lead ( 210 Pb) were analyzed in different matrices (i.e) sediment, water, and fish. The measurement of the naturally occurring radionuclides in the environment can be used as a reference baseline for long-term monitoring in the entire aquatic ecosystem

Biomedical research with cyclotron produced radionuclides: Progress report, February 1, 1988-September 30, 1988

International Nuclear Information System (INIS)

Laughlin, J.S.; Bading, J.R.; Balis, M.E.; Benua, R.S.; Brennan, M.F.; Gelbard, A.S.

1988-09-01

This report covers the completion of research carried out in the second year of a 3 year grant. During this period the new gamma camera system, which was designed in the Biophysics Laboratory and whose fabrication was funded by the Institute, was completed and bought into operation. It has capability to monitor simultaneously 3 different radionuclide labels, and to do so rapidly. These features are essential to the metabolic studies being carried out collaboratively by Dr. James Bading and Dr. Brennan's surgical research team. Design and fabrication of this instrument was essential regardless of whether there was access to a PET unit or not. Another instrumental development is the replacement of the cyclotron magnet coils, the addition of harmonic tuning coils and other improvements. The metabolic study program with labeled amino acids in man and animals has progressed significantly as is summarized. The list of compounds prepared and labeled with positron-emitting nuclides in our laboratory, some originally prepared here, illustrates another vital and active contribution to metabolic research from this laboratory

A meshless approach to radionuclide transport calculations

International Nuclear Information System (INIS)

Perko, J.; Sarler, B.

2005-01-01

Over the past thirty years numerical modelling has emerged as an interdisciplinary scientific discipline which has a significant impact in engineering and design. In the field of numerical modelling of transport phenomena in porous media, many commercial codes exist, based on different numerical methods. Some of them are widely used for performance assessment and safety analysis of radioactive waste repositories and groundwater modelling. Although they proved to be an accurate and reliable tool, they have certain limitations and drawbacks. Realistic problems often involve complex geometry which is difficult and time consuming to discretize. In recent years, meshless methods have attracted much attention due to their flexibility in solving engineering and scientific problems. In meshless methods the cumbersome polygonization of calculation domain is not necessary. By this the discretization time is reduced. In addition, the simulation is not as discretization density dependent as in traditional methods because of the lack of polygon interfaces. In this work fully meshless Diffuse Approximate Method (DAM) is used for calculation of radionuclide transport. Two cases are considered; First 1D comparison of 226 Ra transport and decay solved by the commercial Finite Volume Method (FVM) and Finite Element Method (FEM) based packages and DAM. This case shows the level of discretization density dependence. And second realistic 2D case of near-field modelling of radionuclide transport from the radioactive waste repository. Comparison is made again between FVM based code and DAM simulation for two radionuclides: Long-lived 14 C and short-lived 3 H. Comparisons indicate great capability of meshless methods to simulate complex transport problems and show that they should be seriously considered in future commercial simulation tools. (author)

Conditions and processes affecting radionuclide transport

Science.gov (United States)

Simmons, Ardyth M.; Neymark, Leonid A.

2012-01-01

Characteristics of host rocks, secondary minerals, and fluids would affect the transport of radionuclides from a previously proposed repository at Yucca Mountain, Nevada. Minerals in the Yucca Mountain tuffs that are important for retarding radionuclides include clinoptilolite and mordenite (zeolites), clay minerals, and iron and manganese oxides and hydroxides. Water compositions along flow paths beneath Yucca Mountain are controlled by dissolution reactions, silica and calcite precipitation, and ion-exchange reactions. Radionuclide concentrations along flow paths from a repository could be limited by (1) low waste-form dissolution rates, (2) low radionuclide solubility, and (3) radionuclide sorption onto geological media.

VKTA Rossendorf: Laboratory for Environmental and Radionuclide Analysis

International Nuclear Information System (INIS)

Koehler, M.; Knappik, R.; Fiola, K.

2015-01-01

The VKTA (Nuclear Engineering and Analytics Inc.) is charged by the Free State of Saxony with the decommissioning and waste management of the nuclear installations at the research site Dresden-Rossendorf. This task includes the safe management and disposal of fissile material and radioactive wastes. The acquired expertise and our solution-oriented way of working are the basis for a varied range of services especially the environmental and radionuclide analyzes. The Laboratory for Environmental and Radionuclide Analysis is accredited according to DIN EN ISO/IEC 17025 and provides a sound range of analytical and metrological services including their coordination and management. The personnel and the rooms, measuring and technical equipment are particularly designed for our special field, the measuring of radioactivity. We are focussed on measuring artificial and natural radionuclides in a wide range of activity and in different sample matrices (e.g., urine, faeces, metals, soil, concrete, food, liquids). With the flexible accreditation of the radionuclide analytics the Laboratory is able to react shortly to changing requirements in decommissioning, environmental monitoring and radiation protection. Essential chemical and radiochemical methods are e.g.: · Alpha particle spectrometry, · Liquid scintillation counting, · gamma ray spectrometry, including Ultra-Low-Level, · High-resolution ICP-MS, · Chromatographic methods such as ion chromatography, gas chromatography, HPLC, · Electrochemical measuring methods such as potentiometry, voltammetry. The Laboratory offers analytical services to the research site Dresden-Rossendorf and national and international customers adapting its analytical procedures to the special needs of customers. The presentation demonstrates on the basis of examples the work of Laboratory within the scope of decommissioning of nuclear facilities, especially at a research site, from radiological preliminary investigation to declaration of

Center of Excellence for Applied Mathematical and Statistical Research in support of development of multicrop production monitoring capability

Science.gov (United States)

Woodward, W. A.; Gray, H. L.

1983-01-01

Efforts in support of the development of multicrop production monitoring capability are reported. In particular, segment level proportion estimation techniques based upon a mixture model were investigated. Efforts have dealt primarily with evaluation of current techniques and development of alternative ones. A comparison of techniques is provided on both simulated and LANDSAT data along with an analysis of the quality of profile variables obtained from LANDSAT data.

Tonopah Test Range Air Monitoring: CY2015 Meteorological, Radiological, and Airborne Particulate Observations

International Nuclear Information System (INIS)

Nikolich, George; Shadel, Craig; Chapman, Jenny; McCurdy, Greg; Etyemezian, Vicken; Miller, Julianne J.; Mizell, Steve

2016-01-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). The operation resulted in radionuclide-contaminated soils at the Clean Slate I, II, and III sites. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III, and at the TTR Sandia National Laboratories (SNL) Range Operations Control (ROC) center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soil beyond the physical and administrative boundaries of the sites. Radionuclide assessment of airborne particulates in 2015 found the gross alpha and gross beta values of dust collected from the filters at the monitoring stations are consistent with background conditions. The meteorological and particle monitoring indicate that conditions for wind-borne contaminant movement exist at the Clean Slate sites and that, although the transport of radionuclide-contaminated soil by suspension has not been detected, movement by saltation is occurring.

Tonopah Test Range Air Monitoring: CY2015 Meteorological, Radiological, and Airborne Particulate Observations

Energy Technology Data Exchange (ETDEWEB)

Nikolich, George [Nevada University, Reno, NV (United States). Desert Research Inst.; Shadel, Craig [Nevada University, Reno, NV (United States). Desert Research Inst.; Chapman, Jenny [Nevada University, Reno, NV (United States). Desert Research Inst.; McCurdy, Greg [Nevada University, Reno, NV (United States). Desert Research Inst.; Etyemezian, Vicken [Nevada University, Reno, NV (United States). Desert Research Inst.; Miller, Julianne J. [Nevada University, Reno, NV (United States). Desert Research Inst.; Mizell, Steve [Nevada University, Reno, NV (United States). Desert Research Inst.

2016-09-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). The operation resulted in radionuclide-contaminated soils at the Clean Slate I, II, and III sites. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III, and at the TTR Sandia National Laboratories (SNL) Range Operations Control (ROC) center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soil beyond the physical and administrative boundaries of the sites. Radionuclide assessment of airborne particulates in 2015 found the gross alpha and gross beta values of dust collected from the filters at the monitoring stations are consistent with background conditions. The meteorological and particle monitoring indicate that conditions for wind-borne contaminant movement exist at the Clean Slate sites and that, although the transport of radionuclide-contaminated soil by suspension has not been detected, movement by saltation is occurring.

Laboratories new to the ICRM.

Science.gov (United States)

Karam, Lisa; Anagnostakis, Marios J; Gudelis, Arunas; Marsoem, Pujadi; Mauring, Alexander; Wurdiyanto, Gatot; Yücel, Ülkü

2012-09-01

The Scientific Committee of the ICRM decided, for the 2011 Conference, to present laboratories that are at a key developmental stage in establishing, expanding or applying radionuclide metrology capabilities. The expansion of radionuclide metrology capabilities is crucial to meet evolving and emerging needs in health care, environmental monitoring, and nuclear energy. Five laboratories (from Greece, Lithuania, Indonesia, Norway and Turkey) agreed to participate. Each laboratory is briefly introduced, and examples of their capabilities and standardization activities are discussed. Published by Elsevier Ltd.

Study on radionuclides transport from natural evaporating ponds to the atmosphere

International Nuclear Information System (INIS)

Liu Keqiang; Zou Changgui

1997-08-01

The results of simulated experiments, field monitoring and radiation health risk evaluation of radionuclides transport to the atmosphere from the natural evaporating ponds of a certain nuclear factory, and the estimating method of releasing source strength are presented. The estimated results of radiation health risk show that the maximum individual annual risk is 6.5 x 10 -9 and the total collective annual risk within a radius of 20 km is 3.2 x 10 -5 person, which are caused by operation of the evaporating ponds. It should be pointed out that the above estimated results only refer to one operating year (1990). If the cumulative effect of radionuclides deposition in ground is considered, the risk will increase a little with time until the dynamic balance is achieved. (5 ref., 8 tabs.)

Review of the ecological parameters of radionuclide turnover in vertebrate food chains

International Nuclear Information System (INIS)

Kitchings, T.; DiGregorio, D.; Van Voris, P.

1975-01-01

Ecological studies of radionuclides in the environment have a long tradition in developing the capability to identify and predict movement and concentration of nuclides in agronomic food chains leading to man. Food chain pathways and transfer coefficients for the non-agronomic portions of natural and managed ecosystems characteristic of affected habitats adjacent to nuclear facilities have not been adequately characterized to establish reliable dispersion models for radionuclide releases. This information is necessary in order to assess the impact that such installations will have on the biota of natural ecosystems. Since food chains are the major processes transferring elements from one trophic level to another in terrestrial ecosystems, information is needed on the food-chain transfer pathways, bioconcentration by each trophic component, and turnover rates by receptor organisms. These data are prerequisite inputs for food-chain transport models and can be correlated with species characteristics (e.g., body weight and feeding habitats), to provide indices for predictive dispersion calculations. Application of these models for radionuclide transfer can aid in the assessment of radioactive releases from nuclear reactor facilities to terrestrial non-agronomic food chains. (U.S.)

Production of vegetation samples containing radionuclides gamma emitters to attend the interlaboratory programs

International Nuclear Information System (INIS)

Souza, Poliana Santos de

2016-01-01

The production of environmental samples such as soil, sediment, water and vegetation with radionuclides for intercomparison tests is a very important contribution to environmental monitoring. Laboratories that carry out such monitoring need to demonstrate that their results are reliable. The IRD National Intercomparison Program (PNI) produces and distributes environmental samples containing radionuclides used to check the laboratories performance. This work demonstrates the feasibility of producing vegetation (grass) samples containing 60 Co, 65 Zn, 134 Cs, and 137 Cs by the spike sample method for the PNI. The preparation and the statistical tests followed the ISO guides 34 and 35 recommendations. The grass samples were dried, ground and passed through a sieve of 250 μm. 500 g of vegetation was treated in each procedure. Samples were treated by two different procedures:1) homogenizing of the radioactive solution containing vegetation by hand and drying in an oven and 2) homogenizing of the radioactive solution containing the vegetation in a rotatory evaporator and drying in an oven. The theoretical activity concentration of the radionuclides in the grass had a range of 593 Bq/kg to 683 Bq/kg. After gamma spectrometry analysis the results of both procedures were compared as accuracy, precision, homogeneity and stability. The accuracy, precision and short time stability from both methods were similar but the homogeneity test of the evaporation method was not approved for the radionuclides 60 Co and 134 Cs. Based on comparisons between procedures was chosen the manual agitation procedure for the grass sample for the PNI. The accuracy of the procedure, represented by the uncertainty and based on theoretical value had a range between -1.1 and 5.1% and the precision between 0.6 a 6.5 %. This result show is the procedure chosen for the production of grass samples for PNI. (author)