Environmental monitoring radiological programs for the nuclear centre and the low level radioactive waste facility in Mexico

International Nuclear Information System (INIS)

Quintero, E.; Cervantes, L.; Rojas, V.

2006-01-01

The National Institute of Nuclear Research of Mexico (ININ) has its Laboratory of Environmental Radiological Monitoring, (LVRA), to assure the critical population and the environment they are not exposed to radiation doses greater than the limits established by the national and international legislation, this laboratory carries out environmental monitoring radiological programs the Nuclear Centre and its surroundings and the Low Level Radioactive Waste Facility (CADER) and its around. In order to carry out these programs the LVRA has rooms for evaporation, drying, grinding, ashing of environmental and food samples, and a laboratory for gamma ray spectrometry, liquid scintillation, alpha-beta gross counting and computer room. Since the year 2000 the (ININ) has tried to implant the quality system ISO 9001:2000 including a its (LVRA). This quality system includes: a Plan of Quality, Quality Manual, programs of technical and administrative document elaboration, technical and administrative procedures, technical and administrative qualification programmes for the laboratory staff, maintenance and calibration programs for measurement systems and finally participation in national and international exercises of intercomparison. The ININ counts with the management of quality assurance to verify these programs, in addition, our Nuclear Regulatory Commission (CNSNS) carries out periodic audits to authorize the of use and handling of radioactive and nuclear material licenses of these facilities. In this work we presented the advances and difficulties found in the implantation of the quality system, also we present the benefits obtained with uses of this system, the samples analyses results, and the calculation of the annual dose to the critical population for the last five years. In addition, we presented the calculation the radionuclides concentration tendencies in different sample types, according to our (CNSNS) requirements. In the same way the results of the calibrations

A soil sampling intercomparison exercise for the ALMERA network

Energy Technology Data Exchange (ETDEWEB)

Belli, Maria [Istituto Superiore per la Protezione e la Ricerca Ambientale (ISPRA), Via di Castel Romano 100, I-00128 Roma (Italy)], E-mail: maria.belli@apat.it; Zorzi, Paolo de [Istituto Superiore per la Protezione e la Ricerca Ambientale (ISPRA), Via di Castel Romano 100, I-00128 Roma (Italy)], E-mail: paolo.dezorzi@isprambiente.it; Sansone, Umberto [International Atomic Energy Agency (IAEA), Agency' s Laboratories Seibersdorf, A-2444 Seibersdorf (Austria)], E-mail: u.sansone@iaea.org; Shakhashiro, Abduhlghani [International Atomic Energy Agency (IAEA), Agency' s Laboratories Seibersdorf, A-2444 Seibersdorf (Austria)], E-mail: a.shakhashiro@iaea.org; Gondin da Fonseca, Adelaide [International Atomic Energy Agency (IAEA), Agency' s Laboratories Seibersdorf, A-2444 Seibersdorf (Austria)], E-mail: a.gondin-da-fonseca-azeredo@iaea.org; Trinkl, Alexander [International Atomic Energy Agency (IAEA), Agency' s Laboratories Seibersdorf, A-2444 Seibersdorf (Austria)], E-mail: a.trinkl@iaea.org; Benesch, Thomas [International Atomic Energy Agency (IAEA), Agency' s Laboratories Seibersdorf, A-2444 Seibersdorf (Austria)], E-mail: t.benesch@iaea.org

2009-11-15

Soil sampling and analysis for radionuclides after an accidental or routine release is a key factor for the dose calculation to members of the public, and for the establishment of possible countermeasures. The IAEA organized for selected laboratories of the ALMERA (Analytical Laboratories for the Measurement of Environmental Radioactivity) network a Soil Sampling Intercomparison Exercise (IAEA/SIE/01) with the objective of comparing soil sampling procedures used by different laboratories. The ALMERA network is a world-wide network of analytical laboratories located in IAEA member states capable of providing reliable and timely analysis of environmental samples in the event of an accidental or intentional release of radioactivity. Ten ALMERA laboratories were selected to participate in the sampling exercise. The soil sampling intercomparison exercise took place in November 2005 in an agricultural area qualified as a 'reference site', aimed at assessing the uncertainties associated with soil sampling in agricultural, semi-natural, urban and contaminated environments and suitable for performing sampling intercomparison. In this paper, the laboratories sampling performance were evaluated.

A soil sampling intercomparison exercise for the ALMERA network

International Nuclear Information System (INIS)

Belli, Maria; Zorzi, Paolo de; Sansone, Umberto; Shakhashiro, Abduhlghani; Gondin da Fonseca, Adelaide; Trinkl, Alexander; Benesch, Thomas

2009-01-01

Soil sampling and analysis for radionuclides after an accidental or routine release is a key factor for the dose calculation to members of the public, and for the establishment of possible countermeasures. The IAEA organized for selected laboratories of the ALMERA (Analytical Laboratories for the Measurement of Environmental Radioactivity) network a Soil Sampling Intercomparison Exercise (IAEA/SIE/01) with the objective of comparing soil sampling procedures used by different laboratories. The ALMERA network is a world-wide network of analytical laboratories located in IAEA member states capable of providing reliable and timely analysis of environmental samples in the event of an accidental or intentional release of radioactivity. Ten ALMERA laboratories were selected to participate in the sampling exercise. The soil sampling intercomparison exercise took place in November 2005 in an agricultural area qualified as a 'reference site', aimed at assessing the uncertainties associated with soil sampling in agricultural, semi-natural, urban and contaminated environments and suitable for performing sampling intercomparison. In this paper, the laboratories sampling performance were evaluated.

DOE radiological calibrations intercomparison program: Results of fiscal year 1986

International Nuclear Information System (INIS)

Cummings, F.M.; Roberson, P.L.; McDonald, J.C.

1987-05-01

The Department of Energy Radiological Calibration Intercomparison Program was initiated in January 1986, under the research portion of the DOE Laboratory Accreditation Program. The program operates via the exchange of transfer standards, consisting of instrument sets and standard secondary beta sources. There are two instrument sets and the scheduled use has been staggered such that one set is available for use during each month. One set of secondary standard beta sources is available for use bimonthly. During the 1986 fiscal year, five laboratories used the instrument sets and three laboratories used the beta source set. Results were reported for all the measurements. The average and one standard deviation of the ratios of participant results to Pacific Northwest Laboratory calibration values were 1.12 +- 0.17 for gamma measurements. Those ratios for the gamma measurements varied from 0.98 to 3.06. The larger differences of results from measurements performed at two facilities were directly attributable to unfamiliarity with the intercomparison instruments. The average and one standard deviation of the ratios of participant results to PNL calibration values obtained using the secondary 90 Sr beta source was 1.02 +- 0.05, which is well within measurement uncertainties. The one participant who performed measurements using 147 Pm and 204 Tl sources obtained ratios of 0.68 and 1.11, respectively. No measurements were performed using neutron or x-ray sources

Quality Assurance In Radioactivity Measurements

International Nuclear Information System (INIS)

Riekstina, D.; Veveris, O.; Smilskalne, G.

2007-01-01

The credibility of obtained results is ensured by the quality assurance and control. The main requisitions involved in the quality assurance of the laboratory according to the requirements of LVS EN ISO/IEC 17025:2005 are: 1) the use of calibrated equipment only; 2) the regular and long-time use of reference materials in the control of equipment; 3) the estimation of uncertainty sources and determination of uncertainties within the given interval of credibility; 4) the validation and verification. The very important requirement is regular participation in the interlaboratory intercomparison exercises that makes it possible to estimate and find possible error sources and carry out the corrective actions. The measurements of the radioactivity of Cs-137, Co-60, H-3, the natural radioactive nuclides as well as other radionuclides in different environmental (soil, precipitation, different types of water, needles, et al.) samples, and in various radioactive polluted objects are carried out in the Laboratory of Radiation physics. The quality assurance system was implemented in our laboratory in 2000. Since 1999 laboratory is regular participant in the interlaboratory intercomparison exercises, organized by the RISO National Laboratory (Denmark) and IAEA (Vienna). The paper shows the laboratory's system of quality assurance and its implementation. We have the internal quality audit program that takes into account the requirements of LVS EN ISO/IEC 17025: 2005, but the main attention is paid to the intercomparison of the results of analyses of laboratories, their evaluation and interpretation. Only credible and justified results can be the basis for further use in any field, thus making it possible to make legitimate decisions. (Authors)

EPA's Radioactive Source Program

International Nuclear Information System (INIS)

Kopsick, D.

2004-01-01

The US EPA is the lead Federal agency for emergency responses to unknown radiological materials, not licensed, owned or operated by a Federal agency or an Agreement state (Federal Radiological Emergency Response Plan, 1996). The purpose of EPA's clean materials programme is to keep unwanted and unregulated radioactive material out of the public domain. This is achieved by finding and securing lost sources, maintaining control of existing sources and preventing future losses. The focus is on both, domestic and international fronts. The domestic program concentrates on securing lost sources, preventing future losses, alternative technologies like tagging of radioactive sources in commerce, pilot radioactive source roundup, training programs, scrap metal and metal processing facilities, the demolition industry, product stewardship and alternatives to radioactive devices (fewer radioactive source devices means fewer orphan sources). The international program consists of securing lost sources, preventing future losses, radiation monitoring of scrap metal at ports and the international scrap metal monitoring protocol

Intercomparison program of personal dosemeters in the Argentine Republic

International Nuclear Information System (INIS)

Gregori, B.N.; Papadopulos, S.B.; Kunst, J.J.

1998-01-01

During 1997, under the auspices of the Nuclear Regulatory Authority (ARN), its was held the third exercise of intercomparison of laboratories of personal dosimetry. The dosemeters were irradiated in X-ray beams ISO quality W60, W110, W200 and gamma sources cesium 137 and cobalt 60. The irradiation were performed kerma free in air and in phantom in order to study the capacity to evaluate both conditions. An extent range of doses (low-high) have been given 0.3 mSv- 20mSv in order to determine the operative performance o each laboratory. Over 19 laboratories of Argentina, participated 13 (65%) and finished the intercomparison 12 (60%) of them. The systems of dosimetry detection were based on film and TLD. During this intercomparison as inquiry about several items related with the laboratories have been made. In this work are shown the individual laboratory results of the intercomparison related with the acceptance curve criteria ICRP 60 and 55. (author)

Evaluation of Brazilian intercomparison program data from 1991 to 1995 of radionuclide assays in environmental samples

International Nuclear Information System (INIS)

Vianna, Maria Elizabeth Couto M.; Tauhata, Luiz; Oliveira, Antonio Eduardo de; Oliveira, Josue Peter de; Clain, Almir Faria; Ferreira, Ana Cristina M.

1998-01-01

Historical radioanalytical data from the Institute of Radiation Protection and Dosimetry (IRD) national intercomparison program from 1991 to 1995 were analyzed to evaluate the performance of sixteen Brazilian laboratories in radionuclide analyses in environmental samples. Data are comprised of measurements of radionuclides in 435 spiked environmental samples distributed in fifteen intercomparison runs comprised of 955 analyses. The general and specific radionuclide performances of the participating laboratories were evaluated relative to the reference value. Data analysis encourages improvements in beta emitter measurements

Second radiocarbon intercomparison program for the Chauvet-Pont d'Arc cave, Ardeche, France

International Nuclear Information System (INIS)

Quiles, A.; Valladas, H.; Kaltnecker, E.; Geneste, J.M.; Clottes, J.; Berthier, B.; Delque-Kolic, E.; Dumoulin, J.P.

2014-01-01

The Chauvet-Pont d'Arc Cave is one of the most important sites for the study of the earliest manifestations and development of prehistoric art at the beginning of the Upper Paleolithic. Different dating techniques have been performed thus far (AMS 14 C, U/Th TIMS, 36 Cl dating) to model the chronological framework of this decorated cave. The cave yielded several large charcoal fragments, which enabled the opportunity for obtaining multiple dates; thus, a First Radiocarbon Intercomparison Program (FIP) was initiated in 2004 using three charcoal pieces. The FIP demonstrated that those cross-dated samples belonged to a time period associated with the first human occupation. One of the statistical interests of an intercomparison program is to reduce the uncertainty on the sample age; thus, to further assess the accuracy of the chronological framework, the Second Intercomparison Program (SIP) involving 10 international 14 C laboratories was carried out on two pieces of charcoal found inside two hearth structures of the Galerie des Megaceros. Each laboratory used its own pretreatment and AMS facilities. In total, 21 and 22 measurements were performed, respectively, which yielded consistent results averaging ∼32 ka BP. Two strategies have currently been developed to identify statistical outliers and to deal with them; both lead to quasi-identical calibrated combined densities. Finally, the new results were compared with those of the FIP, leading to the important conclusion that five different samples from at least three different hearth structures give really tightened temporal densities, associated with one short human occupation in the Galerie des Megaceros. (authors)

Thorium in the workplace measurement intercomparison

International Nuclear Information System (INIS)

Modna, D.K.; Jerome, S.M.; White, M.A.; Woods, M.J.

2000-01-01

The monitoring of radionuclides in the nuclear industry has been recognized as the most straightforward way of assessing health and safety issues associated with the exposure of the workforce to potentially harmful radiation doses. Much of this is achieved by measurements in the workplace itself and by the bioassay and monitoring of workers in the industry. However, there also exists a significant 'non-nuclear' industry where workers are exposed to radioactive materials, for example where this involves thorium, which is made wide use of in the aerospace and other high technology industries. As such work involves the processing of thorium bearing materials, the workforce is potentially exposed to 232 Th and its daughter nuclides. Thus, to monitor the workforce effectively, it is important to be able to measure both 232 Th and the decay products of 232 Th where they are in an unknown state of radioactive equilibrium and this is where monitoring laboratories may experience some difficulty. Accordingly, the Health and Safety Laboratory in the UK has organized a EC wide project on the monitoring of thorium in the 'non-nuclear' workplace; this project is currently ongoing. We report the results of the first intercomparison of this project involving two solutions of 232 Th, one in radioactive equilibrium and one not in equilibrium with its daughters. The results are presented with some comments on how this intercomparison has progressed and how these first results will inform the rest of the project

Results of the IAEA/RCA personal dosemeter intercomparison

Energy Technology Data Exchange (ETDEWEB)

Tsujimura, Norio; Momose, Takumaro; Hayashi, Naomi [Environment and Safety Division, Tokai Works, Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

2000-06-01

The intercomparison of personal dosemeters for photon was carried out between 1990 and 1996 as part of the IAEA/RCA 'strengthening of radiation protection infrastructure' project. Japan Nuclear Cycle Development Institute participated in the intercomparison as one of the in-house personal dosimetry service organizations in Japan and also served the host irradiating laboratory. This report summarizes the dose evaluation results obtained from the JNC-TLD badges in the past four intercomparison programs. In the latest intercomparison the evaluated doses agreed to the reference doses with an accuracy of 10%. (author)

Psacoin level S intercomparison: An International code intercomparison exercise on a hypothetical safety assessment case study for radioactive waste disposal systems

International Nuclear Information System (INIS)

1993-06-01

This report documents the Level S exercise of the Probabilistic System Assessment Group (PSAG). Level S is the fifth in a series of Probabilistic Code Intercomparison (PSACOIN) exercises designed to contribute to the verification of probabilistic codes and methodologies that may be used in assessing the safety of radioactive waste disposal systems and concepts. The focus of the Level S exercise lies on sensitivity analysis. Given a common data set of model output and input values the participants were asked to identify both the underlying model's most important parameters (deterministic sensitivity analysis) and the link between the distributions of the input and output values (distribution sensitivity analysis). Agreement was generally found where it was expected and the exercise has achieved its objectives in acting as a focus for testing and discussing sensitivity analysis issues. Among the outstanding issues that have been identified are: (i) that techniques for distribution sensitivity analysis are needed that avoid the problem of statistical noise; (ii) that further investigations are warranted on the most appropriate way of handling large numbers of effectively zero results generated by Monte Carlo sampling; and (iii) that methods need to be developed for demonstrating that the results of sensitivity analysis are indeed correct

Report on the intercomparison run IAEA-384. Radionuclides in Fangataufa lagoon sediment

International Nuclear Information System (INIS)

Povinec, P.P.; Pham, M.K.

2000-01-01

The accurate and precise determinations of radionuclide concentrations in marine samples are important aspects of marine radioactivity assessments and the use of radionuclides in studies of oceanographic processes. To address the problem of data quality, and to assist Member States in verifying the performance of their laboratories, the IAEA Marine Environment Laboratory (MEL) in Monaco has conducted intercomparison exercises on radionuclides in marine samples for many years as part of its contribution to the IAEA's programme of Analytical Quality Control Services (AQCS). For this intercomparison exercise, in 1996 IAEA-MEL collected sediment in Fangataufa lagoon, French Polynesia. The sample aliquots were distributed during 1997-1998 for intercomparison of anthropogenic and natural radionuclides. 110 laboratories worldwide agreed to participate. Of these, only 94 sent results which could be used in the evaluation of this intercomparison exercise. This report describes the results obtained from 94 laboratories on anthropogenic and natural radionuclide determinations in Fangataufa lagoon sediment

Report on the intercomparison run IAEA-384. Radionuclides in Fangataufa lagoon sediment

Energy Technology Data Exchange (ETDEWEB)

Povinec, P P; Pham, M K

2000-07-01

The accurate and precise determinations of radionuclide concentrations in marine samples are important aspects of marine radioactivity assessments and the use of radionuclides in studies of oceanographic processes. To address the problem of data quality, and to assist Member States in verifying the performance of their laboratories, the IAEA Marine Environment Laboratory (MEL) in Monaco has conducted intercomparison exercises on radionuclides in marine samples for many years as part of its contribution to the IAEA's programme of Analytical Quality Control Services (AQCS). For this intercomparison exercise, in 1996 IAEA-MEL collected sediment in Fangataufa lagoon, French Polynesia. The sample aliquots were distributed during 1997-1998 for intercomparison of anthropogenic and natural radionuclides. 110 laboratories worldwide agreed to participate. Of these, only 94 sent results which could be used in the evaluation of this intercomparison exercise. This report describes the results obtained from 94 laboratories on anthropogenic and natural radionuclide determinations in Fangataufa lagoon sediment.

International whole body counter intercomparison based on BOMAB phantom simulating 4 years old child

International Nuclear Information System (INIS)

Battisti, P.; Tarroni, G.

1995-11-01

In April 1993 a whole body counter intercomparison campaign, The 1993 Intercomparison/Intercalibration, started. The campaign has been organized by The Canadian National Reference Centre for In-Vivo Monitoring of Radiation Protection Bureau, Health Canada and The United States Department of Energy and it was based on measurements on a BOMAB type phantom simulating a 4 years old child. The phantom was filled with radioactive tissue substitute resin and an unknown quantity of radioactivity. Each facility was asked to determine the identity and amount of the radionuclide(s), knowing that the specific activity in the 10 BOMAB's sections was the same. Each facility was also asked to calculate the minimum detectable activity of all the radionuclides detected in the phantom. 35 Facilities from 20 different Countries took part in the initiative. The Institute for Radiation Protection of the Environment Department of ENEA (ENEA AMB IRP) represented Italy. Intercomparison results supplied by ENEA AMB IRP as radionuclides identification, activity data and associated precision, minimum detectable activity levels, can be considered satisfactory and comparable with results supplied by similar-facilities

The program of international intercomparison of accident dosimetry; Le programme d'intercomparaison internationale de dosimetrie d'accident 10-12 juin 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-06-01

The French institute of radioprotection and nuclear safety (IRSN) has carried out in June 2002 an international intercomparison program for the testing of the physical and biological accident dosimetry techniques. The intercomparison is jointly organized by the IRSN and the OECD-NEA with the sustain of the European commission and the collaboration of the CEA centre of Valduc (France). About 30 countries have participated to this program. Each country has supplied its own dosimeters and biological samples which have been irradiated using the Silene reactor of CEA-Valduc or a {sup 60}Co source. These experiments allow to test the new dosimetric techniques that have been developed since the previous intercomparison program (1993) and to confirm or improve the performances of older techniques. Aside from the intercomparison exercise, this report makes a status of the known radiological accidents and of the effects of high doses of ionizing radiations on human health (symptoms, therapeutics). It explains the phenomenology of criticality accidents, the prevention means, and the history of such accidents up to the Tokai-Mura one in 1999. Finally, the dosimetry of criticality is presented with its physical and biological techniques. (J.S.)

Radioactive Waste Management Program Activities in Croatia

International Nuclear Information System (INIS)

Matanic, R.

2000-01-01

The concept of radioactive waste management in Croatia comprises three major areas: management of low and intermediate level radioactive waste (LILRW), spent fuel management and decommissioning. All the work regarding radioactive waste management program is coordinated by Hazardous Waste Management Agency (APO) and Croatian Power Utility (HEP) in cooperation with other relevant institutions. Since the majority of work has been done in developing low and intermediate level radioactive waste management program, the paper will focus on this part of radioactive waste management, mainly on issues of site selection and characterization, repository design, safety assessment and public acceptance. A short description of national radioactive waste management infrastructure will also be presented. (author)

Participation of the Laboratorio de Radiotoxicologia of IPEN, SP, Brazil, in laboratory inter-comparison programs

International Nuclear Information System (INIS)

Mesquita, Sueli Alexandra de; Carneiro, Janete Cristina G.

2005-01-01

The Radiotoxicology Laboratory (LRT) of IPEN/CNEN-SP has as mission to assess internal internal contamination from individuals through qualitative and quantitative analysis of radionuclides present in biological samples. The LRT is able to meet the demand for in vitro monitoring and radiological and nuclear emergencies, both in the case of occupational exposures, as individuals. With the purpose of increasing the reliability of the test results, and keeping it up to date on new analytical techniques, the LRT participates annually in two laboratory inter-comparison programs: a national, the PNI (Programa Nacional de Intercomparacao), promoted by IRD/CNEN and an international from PROCORAD (Association for the Promotion of Quality Controls in Radiotoxicological Bioassay). The present work shows the performance of the LRT by means of the results obtained in the exercises for the quantification of natural uranium and uranium isotopes, promoted by both the inter-comparison programs in the year of 2004. The analysis of the obtained results demonstrates the good performance achieved by LRT, and confirms the sustainability of its quality system, required in calibration and testing laboratories

ARM/GCSS/SPARC TWP-ICE CRM Intercomparison Study

Science.gov (United States)

Fridlind, Ann; Ackerman, Andrew; Petch, Jon; Field, Paul; Hill, Adrian; McFarquhar, Greg; Xie, Shaocheng; Zhang, Minghua

2010-01-01

Specifications are provided for running a cloud-resolving model (CRM) and submitting results in a standardized format for inclusion in a n intercomparison study and archiving for public access. The simulated case study is based on measurements obtained during the 2006 Tropical Warm Pool - International Cloud Experiment (TWP-ICE) led by the U. S. department of Energy Atmospheric Radiation Measurement (ARM) program. The modeling intercomparison study is based on objectives developed in concert with the Stratospheric Processes And their Role in Climate (SPARC) program and the GEWEX cloud system study (GCSS) program. The Global Energy and Water Cycle Experiment (GEWEX) is a core project of the World Climate Research PRogramme (WCRP).

Innovative methodology for intercomparison of radionuclide calibrators using short half-life in situ prepared radioactive sources

International Nuclear Information System (INIS)

Oliveira, P. A.; Santos, J. A. M.

2014-01-01

Purpose: An original radionuclide calibrator method for activity determination is presented. The method could be used for intercomparison surveys for short half-life radioactive sources used in Nuclear Medicine, such as 99m Tc or most positron emission tomography radiopharmaceuticals. Methods: By evaluation of the resulting net optical density (netOD) using a standardized scanning method of irradiated Gafchromic XRQA2 film, a comparison of the netOD measurement with a previously determined calibration curve can be made and the difference between the tested radionuclide calibrator and a radionuclide calibrator used as reference device can be calculated. To estimate the total expected measurement uncertainties, a careful analysis of the methodology, for the case of 99m Tc, was performed: reproducibility determination, scanning conditions, and possible fadeout effects. Since every factor of the activity measurement procedure can influence the final result, the method also evaluates correct syringe positioning inside the radionuclide calibrator. Results: As an alternative to using a calibrated source sent to the surveyed site, which requires a relatively long half-life of the nuclide, or sending a portable calibrated radionuclide calibrator, the proposed method uses a source preparedin situ. An indirect activity determination is achieved by the irradiation of a radiochromic film using 99m Tc under strictly controlled conditions, and cumulated activity calculation from the initial activity and total irradiation time. The irradiated Gafchromic film and the irradiator, without the source, can then be sent to a National Metrology Institute for evaluation of the results. Conclusions: The methodology described in this paper showed to have a good potential for accurate (3%) radionuclide calibrators intercomparison studies for 99m Tc between Nuclear Medicine centers without source transfer and can easily be adapted to other short half-life radionuclides

IAEA AQCS catalogue for reference materials and intercomparison exercises 1998/1999

International Nuclear Information System (INIS)

1999-01-01

Fore more than thirty years the International Atomic Energy Agency (IAEA), through its Analytical Quality Control Services (AQCS) programme, has been assisting Member States' laboratories to maintain and improve the reliability of their analyses by organizing intercomparison exercises and by preparing and distributing biological, environmental and marine reference materials. The catalogue consists principally of two parts: The list of all available IAEA reference materials grouped into five categories: reference materials for radionuclides; reference materials for trace, minor and major elements, including oxides; reference materials for stable isotopes; reference materials for organic contaminants and methyl mercury containing materials. Lists of all available IAEA reference materials sorted by analytes. In addition information on recommended half-life data and suppliers of radioactive sources is provided. Planned intercomparisons are advertised and request forms for participation in intercomparisons are included. Forms for ordering reference materials, quality control spectra for gamma-spectrometry on diskettes and AQCS related publications are also provided

The Brazilian National Intercomparison Program (PNI/IRD/CNEN): evaluation of 15 years of data

International Nuclear Information System (INIS)

Tauhata, Luiz; Vianna, Maria Elizabeth Couto M.; Oliveira, Antonio Eduardo de; Ferreira, Ana Cristina; Braganca, Maura Julia C.; Clain, Almir Faria; Quelvia de Faria, Rute

2006-01-01

The Instituto de Radioprotecao e Dosimetria has been coordinating the National Intercomparison Program (PNI) for 15 years, from 1991 to 2005. The objective is to evaluate the analytical performance of the laboratories in low-level activity concentration radionuclide assays in environmental samples. This work presents an evaluation of PNI data from 42 intercomparison runs, which distributed to 22 Brazilian laboratories 2511 samples evaluating 5768 radionuclide assays involving 32 radionuclides in the period from 1991 to 2004. The laboratory performance was evaluated using the Normalized Standard Deviation used by the U.S. EPA. For comparison aims, the Normalized Deviation, used by BIPM was also applied. Laboratory performance were grouped and evaluated in three periods of 5 years each. The first period shows, an average value of good performance of 71.2%, the second shows an average of 78.6% and the last an average of 82.3%. Performance for each kind of radionuclide is also presented

Croatian radioactive waste management program: Current status

International Nuclear Information System (INIS)

Matanic, R.; Lebegner, J.

2001-01-01

Croatia has a responsibility to develop a radioactive waste management program partly due to co-ownership of Krsko nuclear power plant (Slovenia) and partly because of its own medical and industrial radioactive waste. The total amount of generated radioactive waste in Croatia is stored in temporary storages located at two national research institutes, while radioactive waste from Krsko remains in temporary storage on site. National power utility Hrvatska Elektroprivreda (HEP) and Hazardous Waste Management Agency (APO) coordinate the work regarding decommissioning, spent fuel management and low and intermediate level radioactive waste (LILRW) management in Croatia. Since the majority of work has been done in developing the LILRW management program, the paper focuses on this part of radioactive waste management. Issues of site selection, repository design, safety assessment and public acceptance are being discussed. A short description of the national radioactive waste management infrastructure has also been presented. (author)

Further AMBER and Ecolego Intercomparisons

International Nuclear Information System (INIS)

Maul, Philip; Robinson, Peter; Broed, Robert

2004-01-01

The AMBER compartmental modelling software is used by Quintessa in undertaking Performance Assessment (PA) calculations for SKI. SSI and NRPA are supporting the development of Ecolego which is based on the Matlab/Simulink general purpose modelling software for undertaking PA calculations. Intercomparison calculations using AMBER and Ecolego have been undertaken based on calculation cases considered in SKB's SR97 assessment. The reasons for undertaking such intercomparisons included: 1. to give confidence in the use of AMBER and Ecolego for whole system PA calculations for a deep repository; and 2. to provide SKI and SSI with an understanding of some of the technical issues raised by seeking to repeat the SR97 calculations with different models and software. Conclusions drawn from these intercomparisons included: 1. Both modelling packages successfully reproduced SKB's SR97 calculations for the near field, geosphere and biosphere. 2. AMBER and Ecolego calculations were typically in agreement to within one significant figure, but in several instances the SR97 documentation was not sufficiently clear to enable the implementation of the models in AMBER and Ecolego to be unambiguous. In order to gain more information on the comparisons between the two codes, additional intercomparisons have been undertaken using input data from the Vault Safety Case originally undertaken as part of an IAEA research project (ISAM). The comparisons between the AMBER and Ecolego calculations for the ISAM vault safety case have shown excellent agreement. Calculations at specified times generally agree to around three significant figures, and calculations of peak radionuclide fluxes and concentrations agree to two significant figures. This agreement is particularly good given the large number of model compartments and the inclusion of decay changes of up to six members. The most important situation where agreement may not be as good as that generally found is where radionuclides have been

Evaluating natural radiation level by existing airborne radioactive data

International Nuclear Information System (INIS)

Mingkao, Hu; Changqing, Han; Jiangqi, Fang; Zhengxin, Shen

2002-01-01

Airborne Survey and Remote Sensing Center of Nuclear Industry, founded in the middle of 1950s, is a unique unit specialized in uranium exploration by airborne radioactive survey in China. Large numbers of airborne data of radioactivity and abundant experience have been accumulated for more than 40 years. All-round detailed investigation of environmental radiation levels in our country will not be completed in the near future. Thus, at present it is considered to evaluate natural radiation levels using the existing radioactive data. This paper introduces the results of analysis and study comparing airborne radioactive data for radiation environmental evaluation obtained from survey area in Gansu, China, in the 2001 with the measurement results by ground gamma ray radiation dose-rate instrument for environment. The air-earth inter-comparison error does not exceed 30% at radiation fields with a definite area, and the air-earth inter-comparison error does not exceed 60% at outcrop of granite. In 6km long profile that has various circumstances, such as desert, Gobi, farmland and residential area, minimum of air absorbed dose rate is 47nGy/h at an altitude of 1 meter above the soil plane, maximum is 68nGy/h. The inter-comparison errors are usually less than 20%, and maximum is 25.38%. This shows that it is feasible to obtain natural radiation levels rapidly if we could use the existing radioactive data adequately and make some correction, such as geology factor

Report of the Intercomparison program by thermoluminescent dosimetry for Secondary Standard Dosimetry Laboratories

International Nuclear Information System (INIS)

Papadopulos, Susana

2000-01-01

In this report the results of an intercomparison program within a research coordinated program are presented. This is a third phase of the study that consisted in to evaluate the implementation of the new ICRU quantities for individual monitoring by the SSDLs, their capabilities to perform irradiations in different angles and the interpretation of the standard ISO 4370-3. This phase as well the first one was coordinated by Argentina through the Autoridad Regulatoria Nuclear that verified the performance of the participant laboratories. The SSDL of Argentina calibrated the dosimetric system to be used, and sent a set of tld dosimeters for irradiation at the SSDL or dosimetry laboratories of nine countries of latin america

Importance of Intercomparison Exercises in Assessment of Internal Exposure by Whole-Body Counter

International Nuclear Information System (INIS)

Andrasi, A.

2001-01-01

Full text: Basic requirement for any kind of measurement is to check and prove the reliability and correctness of the measured results. Quality assurance programmes require several activities among which the participation in intercomparison exercises plays an important role. Since the determination of radioactive materials in the human body by whole-body counting technique implies many sources of uncertainties the reliability of calibration data and consequently the measured results have to be checked by participation in intercomparison quality control programmes. In these programmes mostly different kinds of phantoms simulating the human body are circulated among the participating laboratories, however sometimes contaminated persons are also subjects of intercomparison measurements. There are guidelines in several countries laid down concerning the requirements of whole-body counter measurements where the performance criteria for the relative bias, precision and minimum detectable amounts are formulated. These quantities are mostly the subject of intercomparison programmes. The whole body counter laboratory of the KFKI Atomic Energy Research Institute participated in intercomparison exercises several times in the last few years. The lessons learned during these activities helped in checking the capabilities of applied methods and measuring geometry as well as contributed in improving the accuracy of the measured results. A short overview on the previous international intercomparison exercises their main characteristics the results obtained and conclusions drawn are discussed in the paper with special attention to those in which also our laboratory participated. (author)

Educational support programs: Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

Williamson, R.C.

1989-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) currently sponsors two educationally related programs: the Radioactive Waste Management Fellowship Program and the Radioactive Waste Management Research Program for Historically Black Colleges and Universities (HBCU). The graduate fellowship program was implemented in 1985 to meet the US Department of Energy's (DOE's) expected manpower needs for trained scientists and engineers to assist in carrying out the activities of the Nuclear Waste Policy Act. It is recognized that a shortage of master's and doctoral level scientists and engineers in disciplines supportive of the nation's high-level radioactive waste management (RWM) program may impede the DOE's ability to properly carry out its mission under the act. The fellowship program encourages talented undergraduate students to enter graduate programs designed to educate and train them in fields directly related to RWM. The program supports graduate students in various disciplines, including nuclear science and engineering, health physics, and certain area of geology and chemical engineering. It also encourages universities to support and improve research activities and academic programs related to the management of spent nuclear fuel and high-level radioactive waste

Intercomparison of alpha particle spectrometry software packages

International Nuclear Information System (INIS)

1999-08-01

Software has reached an important level as the 'logical controller' at different levels, from a single instrument to an entire computer-controlled experiment. This is also the case for software packages in nuclear instruments and experiments. In particular, because of the range of applications of alpha-particle spectrometry, software packages in this field are often used. It is the aim of this intercomparison to test and describe the abilities of four such software packages. The main objectives of the intercomparison were the ability of the programs to determine the peak areas and the peak area uncertainties, and the statistical control and stability of reported results. In this report, the task, methods and results of the intercomparison are presented in order to asist the potential users of such software and to stimulate the development of even better alpha-particle spectrum analysis software

Intercomparison and calibration of dose calibrators used in nuclear medicine facilities

CERN Document Server

Costa, A M D

2003-01-01

The aim of this work was to establish a working standard for intercomparison and calibration of dose calibrators used in most of nuclear medicine facilities for the determination of the activity of radionuclides administered to patients in specific examinations or therapeutic procedures. A commercial dose calibrator, a set of standard radioactive sources, and syringes, vials and ampoules with radionuclide solutions used in nuclear medicine were utilized in this work. The commercial dose calibrator was calibrated for radionuclide solutions used in nuclear medicine. Simple instrument tests, such as linearity response and variation response with the source volume at a constant source activity concentration were performed. This instrument may be used as a reference system for intercomparison and calibration of other activity meters, as a method of quality control of dose calibrators utilized in nuclear medicine facilities.

Report on the intercomparison run: radionuclides in seawater and plankton collected outside Mururoa Atoll

International Nuclear Information System (INIS)

Ballestra, S.; Noshkin, V.

1991-07-01

This report contains a brief outline of the sampling program and a summary of all available radiological data provided by the three participants. The Direction des Centres d'Experimentations Nucleaires Laboratory (DIRCEN-CEA), Montlhery, France; The Lawrence Livermore National Laboratory (LLNL), Livermore, CA, USA; and the IAEA International Laboratory of Marine Radioactivity, (IAEA-ILMR), Principality of Monaco. The IAEA-ILMR results are complied in a separate report by Ballestra et al. (1991) that has details of the program and copies of the protocol and the ''Proces-verbal de constat'' produced by the legal representative at the end of the sampling program. A sampling program was designed to collect 3 large volume seawater and 2 plankton samples from locations near the territorial limit outside Mururoa Atoll. The different samples were to be used for a radiological intercomparison exercise. A legal representative from Papeete, Tahiti (French Polynesia) was given the task to verify the authenticity of the samples and to ensure that the protocol was followed by the participants. 4 refs, 1 fig., 3 tabs

Radioactivity standards distribution program, 1978--1979. Interim report, 1978--1979

International Nuclear Information System (INIS)

Ziegler, L.H.

1978-06-01

A program for the distribution of calibrated radioactive samples, as one function of EPA's quality assurance program for environmental radiation measurements, is described. Included is a discussion of the objectives of the distribution program and a description of the preparation, availability, and distribution of calibrated radioactive samples. Instructions and application forms are included for laboratories desiring to participate in the program. This document is not a research report. It is designed for use by personnel of laboratories participating or desiring to participate in the Radioactivity Standards Distribution Program, which is a part of the U.S. Environmental Protection Agency's quality assurance program

Intercomparison of high energy neutron personnel dosimeters

International Nuclear Information System (INIS)

McDonald, J.C.; Akabani, G.; Loesch, R.M.

1993-03-01

An intercomparison of high-energy neutron personnel dosimeters was performed to evaluate the uniformity of the response characteristics of typical neutron dosimeters presently in use at US Department of Energy (DOE) accelerator facilities. It was necessary to perform an intercomparison because there are no national or international standards for high-energy neutron dosimetry. The testing that is presently under way for the Department of Energy Laboratory Accreditation Program (DOELAP) is limited to the use of neutron sources that range in energy from about 1 keV to 2 MeV. Therefore, the high-energy neutron dosimeters presently in use at DOE accelerator facilities are not being tested effectively. This intercomparison employed neutrons produced by the 9 Be(p,n) 9 B interaction at the University of Washington cyclotron, using 50-MeV protons. The resulting neutron energy spectrum extended to a maximum of approximately 50-MeV, with a mean energy of about 20-MeV. Intercomparison results for currently used dosimeters, including Nuclear Type A (NTA) film, thermoluminescent dosimeter (TLD)-albedo, and track-etch dosimeters (TEDs), indicated a wide variation in response to identical doses of high-energy neutrons. Results of this study will be discussed along with a description of plans for future work

International intercomparison of dose measurements using EPR spectrometry of tooth enamel

International Nuclear Information System (INIS)

Wieser, A.; Chumak, V.; Pasalskaya, L.; Pavlenko, J.; Sholom, S.; Bailiff, I.; Baran, N.; Bougai, A.; Kolesnik, S.; Maksimenko, V.; Brik, A.; Matyash, M.; Scherbina, O.; Dubovsky, S.; Kirillov, V.; Minenko, V.; Finin, V.; Haskell, E.; Hayes, R.; Kenner, G.; Ivannikov, A.; Skvortsov, V.; Stepanenko, V.; Liidja, G.; Lippmaa, E.; Past, J.; Puskar, J.; Meijer, A.; Radchuk, V.; Vaher, Ue.

1996-01-01

Electron paramagnetic resonance (EPR) dosimetry with teeth is the only solid state dosimetry method that allows for direct measurement of the individual dose. It is considered to be a very promising tool for retrospective individual dosimetry after accidental radioactive releases. It will help to make a reliable assessment of the radiation risk. A number of laboratories are engaged in retrospective EPR dosimetry with teeth. There is consequently a need to develop a programme of intercalibration and intercomparison to check whether the results produced by different laboratories are either consistent or accurate. The Commission of the European Communities has initiated the project ECP10 entitled, Retrospective Dosimetry and Dose reconstruction. Within the joint Eu/CIS project the 1st International Intercomparison of EPR Dosimetry with Teeth' was started in 1994. Nine research laboratories were involved from Germany, Russia, Belarus, Ukraine, Estonia and USA

Practice and experience in traceability of radioactivity measurements of environmental samples

International Nuclear Information System (INIS)

Huang Zhijian

1990-01-01

This paper discusses some aspects on radioactivity measurement traceability and summarizes the work on quality assurance of radioactivity measurements of environmental samples in the laboratory, including transfer of standards, preparation of reference materials, and calibration of efficiency for volumse surces with Ge(Li) spectrometer. Some practical activitis regarding intercomparison of radioactivity measurements and other traceabillity-related activities are also described. Some sugestions relating to performing quality assurance are made

Performance of the participant laboratories in the National Intercomparison Program (PNI) in the period from 1991 to 2013

International Nuclear Information System (INIS)

Tauhata, Luiz; Vianna, Maria Elizabeth Couto Machado; Oliveira, Antonio Eduardo de; Braganca, Maura Julia Camara da Silva; Ferreira, Ana Cristina de Melo

2015-01-01

The statistical evaluation of the data of 23 years of the Brazilian Intercomparison Program shows the performance of the 24 Participant Laboratories of the country in the determination of 29 radionuclides in 10600 spiked samples of low level activity values. The results were shown a good performance and an evolution of the quality control for analyses of this kind of samples in this time period. (author)

Report of the results of the second phase of Research Coordinated Program of IAEA ''Regional Intercomparison of Personnel Dosimetry''

International Nuclear Information System (INIS)

Morales, J.; Diaz, E.; Hernandez, E.; Capote, E.

1998-01-01

In this report the results of an intercomparison program within a research coordinated program are presented. This is a second phase of the study that consisted in to evaluate the implementation of the new ICRU quantities for individual monitoring by the dosimetry laboratories. In this report the organization aspects, quality control of the irradiations performed by the reference laboratory (SSDL of the Centro de Proteccion e Higiene de las radiaciones) as well the results of the participant laboratories are included

Civilian radioactive waste management program plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy`s site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program`s ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program`s mission and vision, and summarizes the Program`s broad strategic objectives. Chapter 2 describes the Program`s approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program`s organization chart; the Commission`s regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms.

Summary report of the Department of Energy, Division of Operational and Environmental Safety: Quality Assurance Programs 1 through 4

International Nuclear Information System (INIS)

Welford, G.A.; Fisenne, I.M.; Sanderson, C.

1978-01-01

Analytical Laboratories which provide environmental monitoring data for assessment of radioactive contamination, under the Department of Energy (DOE) Contract, were requested to participate in a Quality Assurance Program. The Environmental Measurements Laboratory (EML) was asked to prepare intercomparison samples for radionuclide analysis of soil, water, air filters, tissue ash, and vegetation ash for distribution to the Analytical Laboratories. Samples were collected in the environment of DOE facilities, since only water and air samples could be conveniently spiked. A set of 6 to 8 samples is distributed quarterly to about 28 laboratories. EML performed multiple analyses on the samples, however, the results are considered intercomparisons not standards. This report summarizes the program and evaluates the data for Quality Assurance Programs (QAP) from 1 through 4

Radiation quality assurance intercomparison studies 1974--1975

International Nuclear Information System (INIS)

1975-10-01

The Quality Assurance Branch of the Monitoring Systems Research and Development Division at the U.S. Environmental Protection Agency's Environmental Monitoring and Support Laboratory-Las Vegas prepares and distributes calibrated low-level radioactive solutions to Federal, State, and private laboratories involved in environmental radiation monitoring and surveillance. These solutions are used for both the calibration of counting instruments and chemical yield determinations. Since the laboratories using these samples must have confidence in their accuracy, the Quality Assurance Branch has instituted intercomparison studies with the National Bureau of Standards and with the Energy Research and Development Administration Health and Service Laboratory. The results of the studies conducted during 1974 and 1975 are described

An Intercomparison of Model Predictions for an Urban Contamination Resulting from the Explosion of a Radiological Dispersal Device

Energy Technology Data Exchange (ETDEWEB)

Hwang, Won Tae; Jeong, Hyo Jun; Kim, Eun Han; Han, Moon Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-03-15

The METRO-K is a model for a radiological dose assessment due to a radioactive contamination in the Korean urban environment. The model has been taken part in the Urban Remediation Working Group within the IAEA's (International Atomic Energy Agency) EMRAS (Environmental Modeling for Radiation Safety) program. The Working Croup designed for the intercomparison of radioactive contamination to be resulted from the explosion of a radiological dispersal device in a hypothetical city. This paper dealt intensively with a part among a lot of predictive results which had been performed in the EMRAS program. The predictive results of three different models (METRO-K, RESRAD-RDD, CPHR) were submitted to the Working Group. The gap of predictive results was due to the difference of mathematical modeling approaches, parameter values, understanding of assessors. Even if final results (for example, dose rates from contaminated surfaces which might affect to a receptor) are similar, the understanding on the contribution of contaminated surfaces showed a great difference. Judging from the authors, it is due to the lack of understanding and information on radioactive terrors as well as the social and cultural gaps which assessors have been experienced. Therefore, it can be known that the experience of assessors and their subjective judgements might be important factors to get reliable results. If the acquisition of a little additional information is possible, it was identified that the METRO-K might be a useful tool for decision support against contamination resulting from radioactive terrors by improving the existing model.

An Intercomparison of Model Predictions for an Urban Contamination Resulting from the Explosion of a Radiological Dispersal Device

International Nuclear Information System (INIS)

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

2009-01-01

The METRO-K is a model for a radiological dose assessment due to a radioactive contamination in the Korean urban environment. The model has been taken part in the Urban Remediation Working Group within the IAEA's (International Atomic Energy Agency) EMRAS (Environmental Modeling for Radiation Safety) program. The Working Croup designed for the intercomparison of radioactive contamination to be resulted from the explosion of a radiological dispersal device in a hypothetical city. This paper dealt intensively with a part among a lot of predictive results which had been performed in the EMRAS program. The predictive results of three different models (METRO-K, RESRAD-RDD, CPHR) were submitted to the Working Group. The gap of predictive results was due to the difference of mathematical modeling approaches, parameter values, understanding of assessors. Even if final results (for example, dose rates from contaminated surfaces which might affect to a receptor) are similar, the understanding on the contribution of contaminated surfaces showed a great difference. Judging from the authors, it is due to the lack of understanding and information on radioactive terrors as well as the social and cultural gaps which assessors have been experienced. Therefore, it can be known that the experience of assessors and their subjective judgements might be important factors to get reliable results. If the acquisition of a little additional information is possible, it was identified that the METRO-K might be a useful tool for decision support against contamination resulting from radioactive terrors by improving the existing model.

Civilian radioactive waste management program plan. Revision 2

International Nuclear Information System (INIS)

1998-07-01

This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy's site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program's ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program's mission and vision, and summarizes the Program's broad strategic objectives. Chapter 2 describes the Program's approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program's organization chart; the Commission's regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms

Management of radioactive fuel wastes: the Canadian disposal program

International Nuclear Information System (INIS)

Boulton, J.

1978-10-01

This report describes the research and development program to verify and demonstrate the concepts for the safe, permanent disposal of radioactive fuel wastes from Canadian nuclear reactors. The program is concentrating on deep underground disposal in hard-rock formations. The nature of the radioactive wastes is described, and the options for storing, processing, packaging and disposing of them are outlined. The program to verify the proposed concept, select a suitable site and to build and operate a demonstration facility is described. (author)

Latinamerican Biological Dosimetry Network (LBDNET). International Biological Dosimetry intercomparison Program (exercise 2007-2008)

International Nuclear Information System (INIS)

Di Giorgio, Marina; Vallerga, Maria B.; Radl, A.; Taja, Maria R.

2009-01-01

This paper describes the International Biological Dosimetry Intercomparison Program (exercise 2007-2008) - developed within the framework of the IAEA regional project - RLA/9/054 (Establishment of national capabilities for response to radiological and nuclear emergency) whose general objectives are: assess reproducibility inter-laboratory; identify problems and provide the necessary modifications for collaborative work in accidental situations requiring activation of mutual assistance mechanisms which will form the basis of the Organization of LBDNET. This exercise involves the laboratories of the region: Argentina (laboratory support), Brazil, Chile, Cuba, Mexico, Peru and Uruguay and the laboratory of the Autonomous University of Barcelona-Espana (Joan Francesc Barquinero and staff). Finally, these countries will meet the next time for the drafting of a final report and later publication. (author)

Plasma vitrification program for radioactive waste treatment

International Nuclear Information System (INIS)

Hung, Tsungmin; Tzeng, Chinchin; Kuo, Pingchun

1998-01-01

In order to treat radioactive wastes effectively and solve storage problems, INER has developed the plasma arc technology and plasma process for various waste forms for several years. The plasma vitrification program is commenced via different developing stages through nine years. It includes (a) development of non-transferred DC plasma torch, (b) establishment of a lab-scale plasma system with home-made 100kW non-transferred DC plasma torch, (c) testing of plasma vitrification of simulated radioactive wastes, (d) establishment of a transferred DC plasma torch delivering output power more than 800 kW, (e) study of NOx reduction process for the plasma furnace, (f) development of a pilot-scale plasma melting furnace to verify the vitrification process, and (g) constructing a plasma furnace facility in INER. The final goal of the program is to establish a plasma processing plant with capacity of 250 kg/hr to treat the low-level radioactive wastes generated from INER itself and domestic institutes due to isotope applications. (author)

Intercomparison of 131I activity measurements in nuclear medicine

International Nuclear Information System (INIS)

Kim, G. Y.; Yang, H. K.; Lim, C. I.; Lee, H. K.; Jeong, H. K.

2004-01-01

Activity measurements in nuclear medicine using a dose calibrator have been performed for several decades and their reliability has varied. To minimise the radiation dose to patients with radionuclides, it is necessary to ensure that the sample administered is accurately assayed. Recognizing the importance of intercomparison in nuclear medicine and the need to make access to activity standards traceable to the international measurement system, the KFDA, as a national secondary standard dosimetry laboratory (SSDL), started an intercomparison program in 2002. This program was initiated by survey to all nuclear medicine centres regarding general information about their dose calibrators, radioisotopes etc. 71 nuclear medicine centres (79 dose calibrators) participated in the intercomparison program with 131 I isotope. To assess the accuracy of clinical measurements of the activity of 131 I solutions and to determine the reason for the disagreement, an intercomparison was conducted using 4 ml aliquots in 10 ml P6 vial with a total activity in the region of 10 -20 MBq. The reference time of decay for all solutions was 0:00 on 25 September 2002. The half-life used was 8.04 days. For the evaluation of solution in KFDA, a sealed, high pressure and re-entrant ionisation chamber, NPL-CRC radionuclide calibrators were used. The verification of our calibration quality was by means of a comparison with the Korea Primary Standard Laboratory (KRISS). The activity ratio of KFDA to KRISS for the 131 I solutions is 1.011. The difference between the value quoted by the clinic, A hospital and the value obtained by the KFDA, A KFDA , is expressed as a percent deviation, i.e. DEV(%) 100x(A hospital -A KFDA )/A KFDA . From the data obtained it was found that 61% of the calibrators showed a deviation within +/-5%; 23% had a deviation in the range 5% 131 I solution activity measurements, using dose calibrators in Koreas, and also to provide the participants with a traceable standard to

A report on intercomparison studies of computer programs which respectively model: i) radionuclide migration ii) equilibrium chemistry of groundwater

International Nuclear Information System (INIS)

Broyd, T.W.; McD Grant, M.; Cross, J.E.

1985-01-01

This report describes two intercomparison studies of computer programs which respectively model: i) radionuclide migration ii) equilibrium chemistry of groundwaters. These studies have been performed by running a series of test cases with each program and comparing the various results obtained. The work forms a part of the CEC MIRAGE project (MIgration of RAdionuclides in the GEosphere) and has been jointly funded by the CEC and the United Kingdom Department of the Environment. Presentations of the material contained herein were given at plenary meetings of the MIRAGE project in Brussels in March, 1984 (migration) and March, 1985 (equilibrium chemistry) respectively

Radioactive Waste Management Research Program Plan for high-level waste: 1987

International Nuclear Information System (INIS)

1987-05-01

This plan will identify and resolve technical and scientific issues involved in the NRC's licensing and regulation of disposal systems intended to isolate high level hazardous radioactive wastes (HLW) from the human environment. The plan describes the program goals, discusses the research approach to be used, lays out peer review procedures, discusses the history and development of the high level radioactive waste problem and the research effort to date and describes study objectives and research programs in the areas of materials and engineering, hydrology and geochemistry, and compliance assessment and modeling. The plan also details the cooperative interactions with international waste management research programs. Proposed Earth Science Seismotectonic Research Program plan for radioactive waste facilities is appended

Spanish program on disposal of radioactive wastes

International Nuclear Information System (INIS)

Lopez Perez, B.; Ramos Salvador, L.; Martines Martinez, A.

1977-01-01

The Spanish Energetic Program assumes an installed nuclear electrical power of 23.000 MWe by the year 1985. Therefore, Spain is making an effort in the managment of radioactive wastes, that can be synthesized in the following points: 1.- Make-up and review of the regulation on the management of radioactive wastes. 2.- Development of the processes and equipment for the treatment of solid, liquid and gaseous wastes from the CNEN ''Juan Vigon'', as well as those from the Nuclear Center of Soria. Solidification studies of RAA wastes arisen from the reprocessing. 3.- Evaluation of radioactive waste treatment systems of the new installed nuclear power plants. Assistance to the nuclear and radioactive facilities operators. 4.- Increase the storage capacity of the pilot repository for solid radioactive wastes of categories 1 and 2 IAEA, located in Sierra Albarrana. Studies of adequate geological formation for storage of solid wastes of IAEA categories 3 and 4. 5.- Studies about long term surface storage systems for solidified RAA wastes arisen from the reprocessing [es

Treatment and disposal of radioactive wastes from nuclear power plants. Research programs

International Nuclear Information System (INIS)

1992-09-01

The report presents programs for research, development and demonstration concerning radioactive waste disposal in underground facilities. The main topics are: Radioactive waste management, radioactive waste storage, capsules, environmental impacts, risk assessment, radionuclide migration, radioactive waste disposal, decommissioning, cost, and international cooperation. (129 refs.)

Environmental sampling program for a solar evaporation pond for liquid radioactive wastes

International Nuclear Information System (INIS)

Romero, R.; Gunderson, T.C.; Talley, A.D.

1980-04-01

Los Alamos Scientific Laboratory (LASL) is evaluating solar evaporation as a method for disposal of liquid radioactive wastes. This report describes a sampling program designed to monitor possible escape of radioactivity to the environment from a solar evaporation pond prototype constructed at LASL. Background radioactivity levels at the pond site were determined from soil and vegetation analyses before construction. When the pond is operative, the sampling program will qualitatively and quantitatively detect the transport of radioactivity to the soil, air, and vegetation in the vicinity. Possible correlation of meteorological data with sampling results is being investigated and measures to control export of radioactivity by biological vectors are being assessed

Research program on radioactive wastes - Overview report 2012

International Nuclear Information System (INIS)

Brander, S.

2013-01-01

This short report issued by the Swiss Federal Office of Energy (SFOE) takes a look at the work done within the framework of the Swiss Research Program on Radioactive Wastes. The program was developed in 2006/2007 by the various federal institutes and commissions involved together with an university of applied sciences. Points investigated included long-term aspects, the planning of deep repositories, opinion building and acceptance as well as depository concepts. Highlights in the research and development areas are discussed, including knowledge conservation, marking concepts, storage of radioactive wastes, repository conception, monitoring and sociological aspects. National and international co-operation in these areas are reported on

IAEA-MEL's AQCS programme for marine radioactivity measurements

International Nuclear Information System (INIS)

Povinec, P.P.; Gastaud, J.; Pham, M.K.

1999-01-01

The main objectives of the IAEA-MEL's Analytical Quality Control Services (AQCS) for marine radioactivity measurements are discussed and future plans for the organization of intercomparison exercises and the production of certified reference materials are presented. The new developments should also include implementation of quality assurance programmes in Member States' laboratories, training in quality management and accreditation programmes. (author)

R and D program of the Spanish National Company for Radioactive Wastes management

International Nuclear Information System (INIS)

Astudillo, J.

1993-01-01

The second R+D program of the Spanish National Company for Radioactive Wastes Management (ENRESA) has a whole budget of 56 million $ for the period 1991-1995. This program is included within the Spanish Energy Plan (PEN-91) and encompasses four main areas: 1) Low and medium level radioactive wastes 2) High level radioactive wastes 3) Decommissioning and dismantling of nuclear installations 4) Radiological protection The Spanish program is coordinated with policies of international organizations: CEC,OECD and IAEA

Intercomparison of Environmental Nuclear Radiation Measuring

Institute of Scientific and Technical Information of China (English)

GAO; Fei; NI; Ning; HOU; Jin-bing; SONG; Ming-zhe

2015-01-01

In 2015,Radiation Metrology Division of China Institute of Atomic Energy organized an environmental monitoring of nuclear radiation measuring intercomparison,and 9laboratories attended.The intercomparison included environmental level dosemeters and protection level

The second EURADOS intercomparison of national network systems used to provide early warning of a nuclear accident

International Nuclear Information System (INIS)

Saez-Vergara, J. C.; Thompson, I. M. G.; Gurriaran, R.; Dombrowski, H.; Funck, E.; Neumaier, S.

2007-01-01

In 1999 and 2002, the EURADOS Working Group on Environmental Monitoring organised two European intercomparison exercises of national network systems used to provide early warning in case of a nuclear accident. In total, 12 European countries, represented by more than 40 scientists, participated in these two intercomparisons with more than 35 different dose rate detectors. In addition, an in situ gamma spectrometry intercomparison was performed by a group of European scientists during the 2002 exercise. Results of these spectrometry measurements will be reported elsewhere. This report summarises the results of the second intercomparison, performed in 2002, at the environmental dosimetry facilities of the Physikalisch-Technische Bundesanstalt (PTB) in Germany. The unique combination of the ultra-low background Underground Laboratory (UDO) and two free-field sites (a floating platform on a lake showing an almost pure cosmic radiation field and a free-field gamma ray irradiation facility) provide the particular opportunity to precisely quantify the inherent background of the detectors and to calibrate them almost free of any background and traceable to PTB's primary standards. In addition, the intercomparison comprised investigations on the energy and dose rate dependence of the detectors' response to gamma radiation as well as on the response to cosmic radiation. Finally, the sensitivity of the detector systems to small dose rate variations, similar to that caused by a passing overhead radioactive plume, was studied under realistic free-field conditions. Following the Council Directive 96/29/EURATOM, the participants of the 2002 intercomparison were asked to report their results in terms of the operational quantity ambient dose equivalent, H*(10). Although the verification of the individual calibrations showed smaller discrepancies than those in the 1999 intercomparison, in a few cases, these discrepancies would be still unacceptably high in the case of a real

PNNL Results from 2010 CALIBAN Criticality Accident Dosimeter Intercomparison Exercise

International Nuclear Information System (INIS)

Hill, Robin L.; Conrady, Matthew M.

2011-01-01

This document reports the results of the Hanford personnel nuclear accident dosimeter (PNAD) and fixed nuclear accident dosimeter (FNAD) during a criticality accident dosimeter intercomparison exercise at the CEA Valduc Center on September 20-23, 2010. Pacific Northwest National Laboratory (PNNL) participated in a criticality accident dosimeter intercomparison exercise at the Commissariat a Energie Atomique (CEA) Valduc Center near Dijon, France on September 20-23, 2010. The intercomparison exercise was funded by the U.S. Department of Energy, Nuclear Criticality Safety Program, with Lawrence Livermore National Laboratory as the lead Laboratory. PNNL was one of six invited DOE Laboratory participants. The other participating Laboratories were: Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Savannah River Site (SRS), the Y-12 National Security Complex at Oak Ridge, and Sandia National Laboratory (SNL). The goals of PNNL's participation in the intercomparison exercise were to test and validate the procedures and algorithm currently used for the Hanford personnel nuclear accident dosimeters (PNADs) on the metallic reactor, CALIBAN, to test exposures to PNADs from the side and from behind a phantom, and to test PNADs that were taken from a historical batch of Hanford PNADs that had varying degrees of degradation of the bare indium foil. Similar testing of the PNADs was done on the Valduc SILENE test reactor in 2009 (Hill and Conrady, 2010). The CALIBAN results are reported here.

Environmental Assessment Radioactive Source Recovery Program

International Nuclear Information System (INIS)

1995-01-01

In a response to potential risks to public health and safety, the U.S. Department of Energy (DOE) is evaluating the recovery of sealed neutron sources under the Radioactive Source Recovery Program (RSRP). This proposed program would enhance the DOE's and the U.S. Nuclear Regulatory Commission's (NRC's) joint capabilities in the safe management of commercially held radioactive source materials. Currently there are no federal or commercial options for the recovery, storage, or disposal of sealed neutron sources. This Environmental Assessment (EA) analyzes the potential environmental impacts that would be expected to occur if the DOE were to implement a program for the receipt and recovery at the Los Alamos National Laboratory (LANL), Los Alamos, New Mexico, of unwanted and excess plutonium-beryllium ( 238 Pu-Be) and americium-beryllium ( 241 Am-Be) sealed neutron sources. About 1 kg (2.2 lb) plutonium and 3 kg (6.6 lb) americium would be recovered over a 15-year project. Personnel at LANL would receive neutron sources from companies, universities, source brokers, and government agencies across the country. These neutron sources would be temporarily stored in floor holes at the CMR Hot Cell Facility. Recovery reduces the neutron emissions from the source material and refers to a process by which: (1) the stainless steel cladding is removed from the neutron source material, (2) the mixture of the radioactive material (Pu-238 or Am-241) and beryllium that constitutes the neutron source material is chemically separated (recovered), and (3) the recovered Pu-238 or Am-241 is converted to an oxide form ( 238 PuO 2 or 241 AmO 2 ). The proposed action would include placing the 238 PuO 2 or 241 AmO 2 in interim storage in a special nuclear material vault at the LANL Plutonium Facility

GEOSAF Part II. Demonstration of the operational and long-term safety of geological disposal facilities for radioactive waste. IAEA international intercomparison and harmonization project

Energy Technology Data Exchange (ETDEWEB)

Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)

2015-07-01

International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory

Programs of recovery of radioactive wastes from the trenches and land decontamination of the radioactive waste storage center

International Nuclear Information System (INIS)

Jimenez D, J.; Reyes L, J.

1999-06-01

In this report there are the decontamination program of the land of the Radioactive Waste Storage Center, the Program of Recovery of the radioactive waste of the trenches, the recovery of polluted bar with cobalt 60, the recovery of minerals and tailings of uranium and of earth with minerals and tailings of uranium, the recovery of worn out sealed sources and the waste recovery with the accustomed corresponding actions are presented. (Author)

Intercomparison exercises

International Nuclear Information System (INIS)

Arunachalam, J.

2007-01-01

Intercomparison exercises are vital to many a national programmes. These are only tools available with the laboratories to prove their competence to an international audience and also for the accrediting agencies to assess a laboratory

Third IAEA nuclear accident intercomparison experiment

Energy Technology Data Exchange (ETDEWEB)

Miric, I; Ubovic, Z

1974-05-15

The purpose of this report is to present the results of the International Atomic Energy Agency intercomparison experiments held at the 'Boris Kidric' Institute, Vinca, in May 1973. The experiments are parts of a multilaboratory intercomparison programme sponsored by the IAEA for the evaluation of nuclear accident dosimetry systems and eventually recommendation of dosimetry systems that will provide adequate informations in the event of a criticality accident. The previous two studies were held at the Valduc Centre near Dijon (France) in June 1970 and at the ORNL in Oak Ridge (USA), in May 1971. Parts of the intercomparison studies were coordination meetings. The topics and conclusions of the Third coordination meeting are given in the Chairman's Report of F.F. Haywood. This paper will deal, therefore, only with data concerning the Third intercomparison experiments in which the RB reactor at Vinca was used as a source of mixed radiation. (author)

Third IAEA nuclear accident intercomparison experiment

International Nuclear Information System (INIS)

Miric, I.; Ubovic, Z.

1974-05-01

The purpose of this report is to present the results of the International Atomic Energy Agency intercomparison experiments held at the 'Boris Kidric' Institute, Vinca, in May 1973. The experiments are parts of a multilaboratory intercomparison programme sponsored by the IAEA for the evaluation of nuclear accident dosimetry systems and eventually recommendation of dosimetry systems that will provide adequate informations in the event of a criticality accident. The previous two studies were held at the Valduc Centre near Dijon (France) in June 1970 and at the ORNL in Oak Ridge (USA), in May 1971. Parts of the intercomparison studies were coordination meetings. The topics and conclusions of the Third coordination meeting are given in the Chairman's Report of F.F. Haywood. This paper will deal, therefore, only with data concerning the Third intercomparison experiments in which the RB reactor at Vinca was used as a source of mixed radiation. (author)

Intercomparison On Depth Dose Measurement

International Nuclear Information System (INIS)

Rohmah, N; Akhadi, M

1996-01-01

Intercomparation on personal dose evaluation system has been carried out between CSRSR-NAEA of Indonesia toward Standard Laboratory of JAERI (Japan) and ARL (Australia). The intercomparison was in 10 amm depth dose measurement , Hp (10), from the intercomparison result could be stated that personal depth dose measurement conducted by CSRSR was sufficiently good. Deviation of dose measurement result using personal dosemeter of TLD BG-1 type which were used by CSRSR in the intercomparison and routine photon personal dose monitoring was still in internationally agreed limit. Maximum deviation of reported doses by CSRSR compared to delivered doses for dosemeter irradiation by JAERI was -10.0 percent and by ARL was +29 percent. Maximum deviation permitted in personal dose monitoring is ± 50 percent

Results Assessment of Intercomparison Exercise CSN/CIEMAT-2010 among Spanish National Laboratories of Environmental Radioactivity (Diet Ashes)

International Nuclear Information System (INIS)

Gasco, C.; Trinidad, J. A.; Llaurado, M.; Suarez, J. A.

2012-01-01

This report describes the results assessment of the intercomparison exercise among environmental radioactivity laboratories, organised by Spanish Regulatory Institution (CSN) and prepared and evaluated by UAB and CIEMAT respectively. The exercise has been carried out following the international standards ISO-43 and ISO/IUPAC that provide a useful guide to perform proficiency tests and inter-laboratories comparisons. The selected matrix for this year (2010) was a diet ash obtained from the ashing of a whole fresh diet (breakfast, lunch and dinner), that was enriched with artificial radionuclides (Cs-137, Co-60,Fe-55,Ni-63,Sr-90,Am-241,Pu-238,Pu-239,240 y C-14) and contained natural radionuclides (U-234, U-238, U-natural Th-230, Th-234, Ra-226, Ra-228, Pb-210, Pb-212, Pb-214, Bi-214, Ac-228, Tl-208, K-40) at environmental level of activity concentration. The z-score test was applied to determine how much the laboratories differ from the reference value. The reference value for this exercise was the median of the results from the different laboratories and their standard deviations to achieve a more complete and objective study of the laboratories performance. The participant laboratories have demonstrated a satisfactory quality level for measuring the natural and artificial radionuclides content in this matrix. The reference values obtained through the medians show a negative bias for Pb-210 and Th-234 when comparing to the given values of external qualified laboratories from ENEA and IRSN and positive one for K-40. (Author)

Report on the intercomparison run IAEA-152 radionuclides in milk powder

International Nuclear Information System (INIS)

Cooper, E.L.; LaBrecque, J.J.; Dekner, R.; Reichel, F.; Schelenz, R.

1988-09-01

The results of the intercomparison on milk powder (IAEA-152) for the determination of elevated levels of radioactivity are reported. The data from thirty-nine laboratories from eighteen different countries have been considered and include the determination of the following radionuclides: 134 Cs, 137 Cs, 40 K, 90 Sr. According to a statistical evaluation sufficient data for recommended mean values and confidence intervals have been received for: 134 Cs: 764 Bq/kg (722-802); 137 Cs: 2129 Bq/kg (2053-2209); 40 K: 539 Bq/kg (510-574); 90 Sr: 7.7 Bq/kg (7.0-8.3). Reference date: 31 August 1987. 3 refs, figs and tabs

Report on the intercomparison run IAEA-154 radionuclides in whey powder

International Nuclear Information System (INIS)

Cooper, E.L.; LaBrecque, J.J.; Dekner, R.; Reichel, F.; Schelenz, R.

1988-09-01

The results of the intercomparison on whey powder (IAEA-154) for the determination of elevated levels of radioactivity are reported. The data for thirty-one laboratories from sixteen different countries have been considered and include the determination of the following radionuclides: 134 Cs, 137 Cs, 40 K, 90 Sr. According to a statistical evaluation sufficient data for recommended mean values and confidence intervals have been received for: 134 Cs: 1355 Bq/kg (1295-1417); 137 Cs: 3749 Bq/kg (3613-3887); 40 K: 1575 Bq/kg (1511-1644); 90 Sr: 6.9 Bq/kg (6.0-8.0). Reference date: 31 August 1987. 3 refs, figs and tabs

Radioactive Waste Management Fellowship Program: Summary of program activities for calendar year 1986

International Nuclear Information System (INIS)

1987-01-01

This document describes a graduate fellowship program designed to guide future scientists and engineers toward a career in high level radioactive waste management. Oak Ridge Associated Universities administers this program on behalf of 17 participating universities. The report summarizes the background and qualifications of the last year's applicants and awardees and provides examples of the distributed literature describing the program. 8 figs

Results from 2010 Caliban Criticality Dosimetry Intercomparison

Energy Technology Data Exchange (ETDEWEB)

Veinot, K. G.

2011-10-12

The external dosimetry program participated in a criticality dosimetry intercomparison conducted at the Caliban facility in Valduc, France in 2010. Representatives from the dosimetry and instrumentation groups were present during testing which included irradiations of whole-body beta/gamma (HBGT) and neutron thermoluminescent dosimeters (TLDs), a fixed nuclear accident dosimeter (FNAD), electronic alarming dosimeters, and a humanoid phantom filled with reference man concentrations of sodium. This report reviews the testing procedures, preparations, irradiations, and presents results of the tests.

Development of a package program for estimating ground level concentrations of radioactive gases

International Nuclear Information System (INIS)

Nilkamhang, W.

1986-01-01

A package program for estimating ground level concentration of radioactive gas from elevate release was develop for use on IBM P C microcomputer. The main program, GAMMA PLUME NT10, is based on the well known VALLEY MODEL which is a Fortran computer code intended for mainframe computers. Other two options were added, namely, calculation of radioactive gas ground level concentration in Ci/m 3 and dose equivalent rate in mren/hr. In addition, a menu program and editor program were developed to render the program easier to use since the option could be readily selected and the input data could be easily modified as required through the keyboard. The accuracy and reliability of the program is almost identical to the mainframe. Ground level concentration of radioactive radon gas due to ore program processing in the nuclear chemistry laboratory of the Department of Nuclear Technology was estimated. In processing radioactive ore at a rate of 2 kg/day, about 35 p Ci/s of radioactive gas was released from a 14 m stack. When meteorological data of Don Muang (average for 5 years 1978-1982) were used maximum ground level concentration and the dose equivalent rate were found to be 0.00094 p Ci/m 3 and 5.0 x 10 -10 mrem/hr respectively. The processing time required for the above problem was about 7 minutes for any case of source on IBM P C which was acceptable for a computer of this class

Intercomparison of IAEA airborne particulate matter reference material. Appendix 19

International Nuclear Information System (INIS)

Landsberger, Sheldon; Wu, De; Vermette, Stephen; Cizek, William

1995-01-01

Fifty air filters with fine and coarse fractions were prepared from NIST 2710 contaminated soil. Eighteen pairs were made and sent to seventeen laboratories of the CRP program on Applied Research on Air Pollution Using Nuclear-Related Analytical Techniques for elemental determination. The results of this intercomparison are discussed in this paper. (author)

The April 1994 and October 1994 radon intercomparisons at EML

International Nuclear Information System (INIS)

Fisenne, I.M.; George, A.C.; Perry, P.M.; Keller, H.W.

1995-10-01

Quality assurance/quality control (QA/QC) are the backbone of many commercial and research processes and programs. QA/QC research tests the state of a functioning system, be it the production of manufactured goods or the ability to make accurate and precise measurements. The quality of the radon measurements in the US have been tested under controlled conditions in semi-annual radon gas intercomparison exercises sponsored by the Environmental Measurements Laboratory (EML) since 1981. The two Calendar Year 1994 radon gas intercomparison exercises were conducted in the EML exposure chamber. Thirty-two groups including US Federal facilities, USDOE contractors, national and state laboratories, universities and foreign institutions participated in these exercises. The majority of the participant's results were within ±10% of the EML value at radon concentrations of 570 and 945 Bq m -3

Recommended regulatory program plan for low-level radioactive waste management in Maryland

International Nuclear Information System (INIS)

1986-01-01

The National Program for Low-Level Radioactive Waste Management was instituted by the US Department of Energy to assist the states in carrying out this new federal policy. Based on the premise that the safe disposal of low-level waste is technologically feasible and that states have the necessary degree of authority to set management policy, the National Program is helping them to develop a responsive, comprehensive regulatory program. The State of Maryland is actively engaged with the National Program in its efforts to form a comprehensive management program. The purpose of this plan is to review existing statutory and regulatory program responsibilities and provide a recommended management scheme for low-level radioactive waste

The ARM-GCSS Intercomparison Study of Single-Column Models and Cloud System Models

International Nuclear Information System (INIS)

Cederwall, R.T.; Rodriques, D.J.; Krueger, S.K.; Randall, D.A.

1999-01-01

The Single-Column Model (SCM) Working Group (WC) and the Cloud Working Group (CWG) in the Atmospheric Radiation Measurement (ARM) Program have begun a collaboration with the GEWEX Cloud System Study (GCSS) WGs. The forcing data sets derived from the special ARM radiosonde measurements made during the SCM Intensive Observation Periods (IOPs), the wealth of cloud and related data sets collected by the ARM Program, and the ARM infrastructure support of the SCM WG are of great value to GCSS. In return, GCSS brings the efforts of an international group of cloud system modelers to bear on ARM data sets and ARM-related scientific questions. The first major activity of the ARM-GCSS collaboration is a model intercomparison study involving SCMs and cloud system models (CSMs), also known as cloud-resolving or cloud-ensemble models. The SCM methodologies developed in the ARM Program have matured to the point where an intercomparison will help identify the strengths and weaknesses of various approaches. CSM simulations will bring much additional information about clouds to evaluate cloud parameterizations used in the SCMs. CSMs and SCMs have been compared successfully in previous GCSS intercomparison studies for tropical conditions. The ARM Southern Great Plains (SGP) site offers an opportunity for GCSS to test their models in continental, mid-latitude conditions. The Summer 1997 SCM IOP has been chosen since it provides a wide range of summertime weather events that will be a challenging test of these models

Historic low-level radioactive waste federal policies, programs and oversight

International Nuclear Information System (INIS)

Blanchette, M.; Kenney, J.; Zelmer, B.

2011-01-01

'Full text:' The management of radioactive waste is one of the most serious environmental problems facing Canadians. From the early industrial uses of radioactive material in the 1930s to the development of nuclear power reactors and the medical and experimental use of radio-isotopes today, there has been a steady accumulation of waste products. Historic waste is low-level radioactive waste for which the federal government has accepted responsibility for long-term management. This paper will outline the policy framework used to govern institutional and financial arrangements for the disposal of radioactive waste by waste producers and owners and the major radioactive projects in which the Government of Canada is currently involved. It will provide an overview of the organizations established for the management of historic radioactive waste and NRCan's oversight role. Finally, an overview of the historic waste program activities managed on behalf of the federal government through these organizations in the Port Hope area, the Greater Toronto Area, in Fort McMurray, Alberta and along the Northern Transportation Route is provided. Canada's Policy Framework for Radioactive Waste, sets out principles that govern the institutional and financial arrangements for disposal of radioactive waste by waste producers and owners. According to the Policy Framework: The federal government will ensure that radioactive waste disposal is carried out in a safe, environmentally sound, comprehensive, cost-effective and integrated manner; The federal government has the responsibility to develop policy, to regulate, and to oversee producers and owners; and, The waste producers and owners are responsible, in accordance with the principle of 'polluter pays', for the funding, organization, management and operation of disposal and other facilities required for their wastes. Arrangements may be different for nuclear fuel waste, low-level radioactive waste and

Photon dosimetry intercomparisons at Tygerberg and Groote Schuur hospitals

International Nuclear Information System (INIS)

Jones, D.T.L.; Symons, J.E.; Schreuder, A.N.; Van der Merwe, E.J.; Rossouw, A.; Hough, J.K.; Lazarus, G.L.

1994-08-01

A national photon dosimetry intercomparison was undertaken at 8 hospitals at the beginning of 1989 prior to the commencement of randomised clinical trials involving neutron therapy at the National Accelerator Centre. The results obtained were in agreement at all but two hospitals. Following these studies it was agreed that a uniform photon dosimetry protocol, the AAPM TG2 protocol, be adopted countrywide. The clinical program at the National Accelerator Centre is now far advanced and it was deemed appropriate to undertake a new photon dosimetry intercomparison at two local hospitals, through which all patients are referred. The procedure involved was to compare the doses measured at each hospital under specified conditions by National Accelerator staff with the doses measured by the hospital physicists using their own equipment and protocols. The results obtained were in good agreement, confirming the validity of the dosimetry techniques used. 8 refs., 8 tabs

Quality assurance requirements and description for the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

1992-01-01

The Quality Assurance Requirements and Description (QARD) is the principal quality assurance document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the Quality Assurance Program. The QARD contains regulatory requirements and program commitments necessary for the development of an effective quality assurance program. Quality assurance implementing documents must be based on, and consistent with, QARD requirements. The QARD applies to the following: (1) acceptance of spent nuclear fuel and high-level radioactive waste; (2) transport of spent nuclear fuel and high-level radioactive waste; (3) the Monitored Retrievable Storage (MRS) facility through application for an operating license; (4) Mined Geologic Disposal System (MGDS), including the site characterization activities (exploratory studies facility (ESF) and surface based testing), through application for an operating license; (5) the high-level-waste form from production through acceptance. Section 2.0 defines in greater detail criteria for determining work subject to QARD requirements. The QARD is organized into sections, supplements, appendices, and a glossary. The sections contain requirements that are common to all Program elements. The supplements contain requirements for specialized activities. The appendices contain requirements that are specific to an individual Program element. The glossary establishes a common vocabulary for the Quality Assurance Program

EURADOS intercomparison 2012 for neutron dosemeters

International Nuclear Information System (INIS)

Fantuzzi, E.; Chevallier, M.A.; Cruz-Suarez, R.; Luszik-Bhadra, M.; Mayer, S.; Thomas, D.J.; Tanner, R.; Vanhavere, F.

2014-11-01

EURADOS, within the work performed by Working Group 2 - Harmonization of Individual Monitoring in Europe, has started a self-sustained programme of regular intercomparisons and has successfully executed three intercomparisons for whole body photon dosemeters (IC2008, IC2010, IC2012) and one intercomparison for extremity dosemeters for photon and beta fields (IC2009). In 2012, the EURADOS intercomparison IC2012n was launched for personal neutron dosemeters routinely used to measure personal dose equivalent, Hp(10), in individual monitoring. No systems under development were allowed to participate. IC2012n was carried out by a EURADOS nominated Organization Group (OG) consisting of: Marie- Anne Chevallier (IRSN, F), Rodolfo Cruz-Suarez (IAEA, UN-Vienna), Marlies Luszik-Bhadra (PTB, D), Sabine Mayer (PSI, CH), David J. Thomas (NPL, UK), Rick Tanner (PHE, UK), Filip Vanhavere (SCK-CEN, B) led by a Coordinator, Elena Fantuzzi (ENEA, I). 31 participants registered for the comparison, with 34 dosimetry systems. In total 816 dosemeters were irradiated in selected neutron fields on an ISO slab phantom. The irradiations were performed at 2 European accredited laboratories which are both National Primary Metrology Laboratories for ionizing radiation: NPL (National Physical Laboratory, UK) and PTB (Physikalisch-Technische Bundesanstalt, D). All irradiations were carried out according to the irradiation plan developed by the OG. The overall results show that most, although not all, dosimetric systems perform acceptably well (within a factor of 2) for irradiations with a bare radionuclide source ( 252 Cf at 0 ), whilst more than half of the systems underestimate the reference value for irradiations from non-normal angles of incidence irradiations ( 252 Cf at 45 ) or for simulated workplace fields ( 252 Cf(D 2 O) or 252 Cf source behind a shadow cone). The performance for 250 keV mono-energetic neutron irradiations varies mainly reflecting the detection principle on which the

Result of the intercomparison exercise on radon measuring instruments and radon detectors 'bev- radon ring 2005'

International Nuclear Information System (INIS)

Baumgartner, A.; Maringer, F.J.; Michai, P.; Kreuziger, M.

2006-01-01

In spring 2005 the Federal Office of Metrology and Surveying (B.E.V.) invited all in Austria working radon measuring institutes to an intercomparison exercise at the radon calibration laboratory in the Arsenal. The aim of this intercomparison was on the one hand an objective inquiry and documentation of the current metrological potential on the section of radon measurement in Austria - both quantitative and qualitative- and on the other hand an initiative for the participating laboratories to optimize and improve their applied calibration-, measurement and analyse technique. Ten contacted Austrian radon laboratories were prepared to participate on the radon intercomparison exercise. The intercomparison exercise was carried out from 14. till 29. June at the radon calibration laboratory in the Arsenal of the B.E.V.. As radon emanation source a five stepped arranged, at the Arsenal built radon source was used. The source ( A.D.O.T.T.O. 1 is filled with a certified Ra- 226-standard solution of the Czech Metrological Institute (C.M.I.), Prag. A simple statistic based model was used for the evaluation and assessment of the results from the participants, which consider the statistic nature of the radioactive decay combined uncertainty. Altogether 183 measuring instruments participated the intercomparison exercise. Two reference measuring instruments, 22 active and 159 passive measuring instruments. The active measuring instruments formed 6 types of instruments and as passive radon detectors were 7 different types used from the participants. The positioning of the radon measuring instruments and detectors in the radon calibration laboratory was executed in regard to statistic points of view. From the active measuring instruments 17 could qualify and from the passive methods six from eight participants were in compliance to the given criteria. Radon measurements, which could have financial and economics relating implications (e.g. architectural redevelopment or

Intercomparison exercises - a 'must' or a 'need'

International Nuclear Information System (INIS)

Paraschiva, Mircea-Valentin; Cherestes, Margareta; Cherestes, Codrut

2011-01-01

The national legislation and the IAEA's Basic Safety Standards Series require the implementation of a QA programme for approval of dosimetry services. The implementation of a quality system according to EN ISO/IEC17025:2005 standard is a way to demonstrate that the dosimetry service is technically competent and capable of generating technically valid results. There are around fifty different standards relevant to individual monitoring, which indicates the complexity and difficulty of understanding and using the appropriate standard in routine work. The new recommendations published by European Commission - RP-160 - bring together requirements and guidance given in 96/29/EURATOM Directive, ICRP Publications, ICRU Reports and IAEA technical documents. The aim of these recommendations is to address the growing need for improvement and harmonization of practices and procedures used in individual dosimetry, for a mutual recognition of dose assessments performed by Approved Dosimetry Services across Europe. An intercomparison exercise among dosimetry services is like a performance test. The results of intercomparisons are published but anonimized. In many Member States participation in international intercomparisons is strongly recommended as results can be used to support an application for approval or accreditation. In this paper we present the results of our participation in two intercomparison exercises: EURADOS Intercomparison 2008 and EURADOS Intercomparison 2010. The results are displayed using the 'trumpet curves' (ISO 14146). The corrective actions are presented and also the lessons learned. At first exercise, in 2008, we have participated with one dosimetric system - photographic dosemeter - and at the second one, we have participated with two dosimetric systems: photographic and thermoluminescent. (authors)

Implementation of a management applied program for solid radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Lee, Y. H.; Kim, T. K.; Kang, I. S.; Cho, H. S.; Son, J. S. [KAERI, Taejon (Korea, Republic of)

2004-07-01

Solid radioactive wastes are generated from the Post-irradiated Fuel Examination Facility, the Irradiated Material Examination Facility, the Research Reactor, and the laboratories at KAERI. A data collection of a solid radioactive waste treatment process of a research organization became necessary while developing the RAWMIS(Radioactive Waste Management Integration System) which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by treatment process. Data on the actual treatment process that is not limited experiment improve by a document, human traces, saving of material resources and improve with efficiency of tracking about a radioactive waste and a process and give help to radioactive waste material balance and inventory study.

NCRP Program Area Committee 5: Environmental Radiation and Radioactive Waste Issues.

Science.gov (United States)

Chen, S Y; Napier, Bruce

2016-02-01

Program Area Committee 5 of the National Council on Radiation Protection and Measurements (NCRP) focuses its activities on environmental radiation and radioactive waste issues. The Committee completed a number of reports in these subject areas, most recently NCRP Report No. 175, Decision Making for Late-Phase Recovery from Major Nuclear or Radiological Incidents. Historically this Committee addressed emerging issues of the nation pertaining to radioactivity or radiation in the environment or radioactive waste issues due either to natural origins or to manmade activities.

Report on the intercomparison run and certified reference material IAEA-381. Radionuclides in Irish sea water

International Nuclear Information System (INIS)

Povinec, P.P.; Pham, M.K.; Ballestra, S.

1999-01-01

The accurate and precise determinations of radionuclide concentrations in marine samples are important aspects of marine radioactivity assessments and the use of radionuclides in studies of oceanographic processes. To address the problem of data quality, the IAEA Marine Environment Laboratory (MEL) in Monaco has conducted intercomparison exercises on radionuclides in marine samples for many years as part of its contribution to the IAEA's programme of Analytical Quality Control Services (AQCS). For this intercomparison exercise, the Federal Maritime and Hydrographic Agency, Hamburg, Germany (BSH) collected sea water from the Irish Sea in 1993. IAEA-MEL distributed sample aliquots during 1995-1996 for intercomparison of anthropogenic and natural radionuclides. About 80 laboratories world-wide were approached with a questionnaire for participation. Of these, only 43 accepted the invitation because of financial constraints (the participating laboratories were asked to pay transportation expenses). As the sample was collected in the Irish Sea, elevated levels of anthropogenic radionuclides were expected due to discharges from the Sellafield reprocessing plant. Participants were informed that the expected activities for anthropogenic radionuclides would be in the ranges: 90 Sr: 50-500 Bq/kg, 137 Cs: 100-1000 Bq/kg, 239+240 Pu: 1-50Bq/kg, 241 Am: 1-50Bq/kg. This report describes the results obtained from 28 laboratories on anthropogenic and natural radionuclide determinations in sea water

Dosimetric intercomparison in Cobalt 60 unities using TLD-100 crystals and CaSO4: Dy + Ptfe

International Nuclear Information System (INIS)

Gaona, E.; Azorin N, J.; Perez P, M.A.; Castillo H, M.; Flores F, F.; Guzman R, L.V.

1999-01-01

The purpose of this work is to design and construct a phantom in basis of thermoplastic polymer of methyl methacrylate that is reutilizable and which allows to do an analysis of the absorbed doses in thermoluminescent crystals (Tl) exposed to cobalt 60 to establish the dosimetric intercomparison in cobalt units which allows to do the follow-up of the Quality assurance programs, standardization of calibration procedures, dosimetry and TLD post intercomparison in radiotherapy. This work allows also prove new thermoluminescent materials of national manufacture developed by Juan Azorin and collaborators as the CaSO 4 : Dy + Ptfe. This is a first study which is realized in Mexico with the system crystal-phantom for aims to intercomparison in cobalt 60 units. In this work participate eight unities of cobalt 60 of different trades belonging at four radiotherapy centers. The results of the dose intercomparison of the eight unities of cobalt 60 were in the range 0.95-1.13, taking in account that the values between 0.95 and 1.05 were considered acceptable in terms of the requirements by the standing legislation. (Author)

TLD Intercomparison in accelerators for radiotherapy in three Latin american countries

International Nuclear Information System (INIS)

Gaona, E.; Azorin N, J.; Perez, M.A.; Picon, C.; Castellanos, E.; Plazas, M.C.; Murcia, G.; Archundia, L.

1998-01-01

In Radiotherapy one of the objectives is to establish and to give follow up to quality assurance programs which make sure that the doses administered to the patients with cancer are a high probability of a success in external radiation. Likewise, one of the present preoccupations of the United Nations Agencies as well as the International Atomic Energy Agency and the Pan-American Health Organization is the optimal employment of the radiations in the treatment of cancer patients since the administered dose in Radiotherapy suffers considerable variations by the lack of quality assurance programs. The use of Electron linear accelerators requires a program of quality assurance that includes expert personnel, equipment and adequate facilities. The more used methodology for the dosimetry calibration and characterization of X-ray beams and high energy electrons for radiotherapy use is using a ionization chamber dosemeter calibrated in a regional secondary standardization laboratory. However, to establish and give follow up to the quality assurance programs it is necessary the dosimetric intercomparison through TLD. In this study it was designed plastic phantoms with TLD crystals and it was made its characterization to realize an absorbed dose analysis in the crystals exposed at X-ray beams 6 MV and high energy electrons 10 and 12 MeV to standardize the dosimetric procedures and proceeding to realize an International Pilot intercomparison of absorbed doses in TLD crystals in three Latin American countries: Mexico, Peru and Colombia with the participation of accelerators of five different institutions. The found results show that the majority of the measured doses with TLD in the different accelerators were in the 0.95-1.05 range though it had two cases outside of this range. The use of the phantoms with TLD crystals shows that they are of excellent aid to make analysis of the doses administered to the patients and an intercomparison of results to standardize procedures at

EURADOS intercomparison 2012 for neutron dosemeters

Energy Technology Data Exchange (ETDEWEB)

Fantuzzi, E. [ENEA-Radiation Protection Institute, Bologna (Italy); Chevallier, M.A. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France); Cruz-Suarez, R. [International Atomic Energy Agency, Vienna (Austria); Luszik-Bhadra, M. [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany); Mayer, S. [Paul Scherrer Institute (PSI), Villigen (Switzerland); Thomas, D.J. [National Physical Laboratory (NPL), Teddington (United Kingdom); Tanner, R. [Public Health England, Oxon (United Kingdom); Vanhavere, F. [SCK-CEN, Belgian Nuclear Research Centre, Mol (Belgium)

2014-11-15

EURADOS, within the work performed by Working Group 2 - Harmonization of Individual Monitoring in Europe, has started a self-sustained programme of regular intercomparisons and has successfully executed three intercomparisons for whole body photon dosemeters (IC2008, IC2010, IC2012) and one intercomparison for extremity dosemeters for photon and beta fields (IC2009). In 2012, the EURADOS intercomparison IC2012n was launched for personal neutron dosemeters routinely used to measure personal dose equivalent, Hp(10), in individual monitoring. No systems under development were allowed to participate. IC2012n was carried out by a EURADOS nominated Organization Group (OG) consisting of: Marie- Anne Chevallier (IRSN, F), Rodolfo Cruz-Suarez (IAEA, UN-Vienna), Marlies Luszik-Bhadra (PTB, D), Sabine Mayer (PSI, CH), David J. Thomas (NPL, UK), Rick Tanner (PHE, UK), Filip Vanhavere (SCK-CEN, B) led by a Coordinator, Elena Fantuzzi (ENEA, I). 31 participants registered for the comparison, with 34 dosimetry systems. In total 816 dosemeters were irradiated in selected neutron fields on an ISO slab phantom. The irradiations were performed at 2 European accredited laboratories which are both National Primary Metrology Laboratories for ionizing radiation: NPL (National Physical Laboratory, UK) and PTB (Physikalisch-Technische Bundesanstalt, D). All irradiations were carried out according to the irradiation plan developed by the OG. The overall results show that most, although not all, dosimetric systems perform acceptably well (within a factor of 2) for irradiations with a bare radionuclide source ({sup 252}Cf at 0 ), whilst more than half of the systems underestimate the reference value for irradiations from non-normal angles of incidence irradiations ({sup 252}Cf at 45 ) or for simulated workplace fields ({sup 252}Cf(D{sub 2}O) or {sup 252}Cf source behind a shadow cone). The performance for 250 keV mono-energetic neutron irradiations varies mainly reflecting the detection

Intercomparison on the measurements of radionuclides in the ceramic brick of China

International Nuclear Information System (INIS)

Zhang Jing; Xu Cuihua; Zhang Qing

2007-01-01

Objective: To inspect the veracity and reiteration of γ-spectrometry in radioactive measurements. Methods: To be performed by multilateral intercomparison on measurements of radionuclides in two kinds of Chinese ceramic brick samples with γ-spectrometry between laboratories of Japan and of China. Results: The maximum difference of which the values measured by our laboratory related to the total average is 4.21%, and with an equipotent probability of positive and negative difference occurred. These showed that the veracity and reiteration of our measurement system are fine without obviously system errors. Conclusion: It has proved that the quality guarantee system and quality control technology of our γ-spectrum system is perfected and effective up to now. (authors)

RCA/IAEA third external dosimetry intercomparisons in East Asia region

International Nuclear Information System (INIS)

Yamamoto, H.; Yoshizawa, M.; Murakami, H.; Momose, T.; Tsujimura, N.; Kanai, K.; Cruz-Suarez, R.

2007-01-01

Several intercomparison exercises were organised by the International Atomic Energy Agency (IAEA) on the determination of operational quantities at the regional or inter-regional basis. In East Asia region, a third phase of the intercomparison finished in mid 2004. It was organised within the frame of the Regional Cooperation Agreement (RCA) as a follow-up to previous exercises carried out during 1990-1992 and 1995-1996. The results of this intercomparison for the determination of operational quantities were satisfactory for all Member States. The laboratories demonstrated a good performance in quantities tested. The purpose of this paper is to present the results of the RCA/IAEA intercomparison and the future of RCA activities in support of assessment of occupational exposure by organising intercomparison runs. (authors)

Radioactivity studies in the Romanian national repository for radioactive waste - Baita, Bihor region, during 14 years of resource development

International Nuclear Information System (INIS)

Dragolici, F.; Rotarescu, G.; Luca, A.; Peic, T.; Postelnicu, C.; Dragolici, A.C.

2000-01-01

The main objective of the study is focused on active surveillance, by periodic measurements of the radioactivity and the possible migration, during the last 14 years, of the radioactive elements stored at the Romanian National Repository for Radioactive Waste-Baita, Bihor region. Hence, water, soil and vegetation samples were collected every three months, from 57 points, chosen in agreement with the National Commission for Nuclear Activities Control and with the local Public Health Institutions. After the sample collection, radiometric measurements were made. The main steps of the study were: the collection of the samples, radiometric measurements, radiochemical analysis of the uranium and progeny, processing and the interpretation of the obtained data; detection of any gamma radionuclides using gamma spectrometry; and the processing, interpretation and intercomparison of the results. Throughout the 14 years of surveillance, it was demonstrated that the National Repository for Radioactive Waste activity has had no negative impact on the operator staff, environment and population. Also, no migration of the deposited radionuclides was detected throughout the whole area. (author)

Solid, low-level radioactive waste certification program

International Nuclear Information System (INIS)

Grams, W.H.

1991-11-01

The Hanford Site solid waste treatment, storage, and disposal facilities accept solid, low-level radioactive waste from onsite and offsite generators. This manual defines the certification program that is used to provide assurance that the waste meets the Hanford Site waste acceptance criteria. Specifically, this program defines the participation and responsibilities of Westinghouse Hanford Company Solid Waste Engineering Support, Westinghouse Hanford Company Quality Assurance, and both onsite and offsite waste generators. It is intended that waste generators use this document to develop certification plans and quality assurance program plans. This document is also intended for use by Westinghouse Hanford Company solid waste technical staff involved in providing assurance that generators have implemented a waste certification program. This assurance involves review and approval of generator certification plans, and review of generator's quality assurance program plans to ensure that they address all applicable requirements. The document also details the Westinghouse Hanford Company Waste Management Audit and Surveillance Program. 5 refs

Intercomparison Measurements Zavazna Poruba '98

International Nuclear Information System (INIS)

Kostial, J.; Nemcovic, V.; Cabanekova, H.; Durcik, M.; Svatosova, O.; Fueloep, M.; Buban, P.; Galbavy, V.; Dzubara, M.; Svatos, J.

1998-01-01

The periodical intercomparison exercises of mobile radiological laboratories was organized in order to improve the measuring methods and to gain a good basis for quality assurance. 20 teams from 10 countries were registered for the workshop from which 20 arrived and participated only as observers. There altogether 73 participants. The list of participants is enclosed in and of this report. The aims of 1998 intercomparison measurements were: (1) to compare the results of the measurements by in-situ spectrometry assuming the different distribution; (2) to improve cooperation among different institutions in Europe; (3) to test the ability of the teams to produce results at the spot; (4) to test the teams capability to produce results for Cs-137 with real distribution without having soil density and alpha/ro prior measurement. The program of the workshop consisted from two parts: field exercises and presentations. Field exercises were: (1) In-situ gamma spectrometry of natural and artificial radionuclides and their contribution to ambient dose rate over an area with heterogeneous distribution of the contamination of cesium-137 at Zavazna Poruba. (2) Dose rate measurement from cobalt-60 source; (3) Identification and determination of activity and depth of a buried source by in-situ spectrometry; (4) Search for lost sources by mobile radiological laboratory; (6) In-situ measurements and dose rate measurement above the water-level of Liptovska Mara; (6) In-situ gamma spectrometry on the bank of the dam an area Liptovsky Trnovec

Intercomparison of gamma ray analysis software packages

International Nuclear Information System (INIS)

1998-04-01

The IAEA undertook an intercomparison exercise to review available software for gamma ray spectra analysis. This document describes the methods used in the intercomparison exercise, characterizes the software packages reviewed and presents the results obtained. Only direct results are given without any recommendation for a particular software or method for gamma ray spectra analysis

Atmospheric Correction Inter-Comparison Exercise

Directory of Open Access Journals (Sweden)

Georgia Doxani

2018-02-01

Full Text Available The Atmospheric Correction Inter-comparison eXercise (ACIX is an international initiative with the aim to analyse the Surface Reflectance (SR products of various state-of-the-art atmospheric correction (AC processors. The Aerosol Optical Thickness (AOT and Water Vapour (WV are also examined in ACIX as additional outputs of AC processing. In this paper, the general ACIX framework is discussed; special mention is made of the motivation to initiate the experiment, the inter-comparison protocol, and the principal results. ACIX is free and open and every developer was welcome to participate. Eventually, 12 participants applied their approaches to various Landsat-8 and Sentinel-2 image datasets acquired over sites around the world. The current results diverge depending on the sensors, products, and sites, indicating their strengths and weaknesses. Indeed, this first implementation of processor inter-comparison was proven to be a good lesson for the developers to learn the advantages and limitations of their approaches. Various algorithm improvements are expected, if not already implemented, and the enhanced performances are yet to be assessed in future ACIX experiments.

On the methodology of the intercomparison of TND evaluations

International Nuclear Information System (INIS)

Yiftah, S.; Caner, M.; Gur, Y.

1979-03-01

The paper presents the problems which arise when two independent complete nuclear data evaluations of the same nuclide are available. A detailed intercomparison of the evaluations can be a multi-levelled exercise of considerable detail, the stages of which cannot always be performed. However, a detailed intercomparison can be a rich source for improving considerably the nuclear data used for the different applications. Preliminary examples of intercomparison are given for illustrative purpose. (B.G.)

Electron spin resonance intercomparison studies on irradiated foodstuffs

Energy Technology Data Exchange (ETDEWEB)

Raffi, J [CEA Centre d` Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (FR)

1992-07-01

The results of intercomparison studies organized by the Community Bureau of Reference on the use of electron spin resonance spectroscopy for the identification of irradiated food are presented. A qualitative intercomparison was carried out using beef and trout bones, sardine scales, pistachio nut shells, dried grapes and papaya. A quantitative intercomparison involving the use of poultry bones was also organized. There was no difficulty in identifying meat bones, dried grapes and papaya. In the case of fish bones there is a need for further kinetic studies using different fish species. The identification of pistachio nut shells is more complicated and further research is needed prior to the organization of a further intercomparison. Laboratories were able to distinguish between chicken bones irradiated in the range 1 to 3 KGy or 7 to 10 KGy although there was a partial overlap between the results from different laboratories.

Electron spin resonance intercomparison studies on irradiated foodstuffs

International Nuclear Information System (INIS)

Raffi, J.

1992-01-01

The results of intercomparison studies organized by the Community Bureau of Reference on the use of electron spin resonance spectroscopy for the identification of irradiated food are presented. A qualitative intercomparison was carried out using beef and trout bones, sardine scales, pistachio nut shells, dried grapes and papaya. A quantitative intercomparison involving the use of poultry bones was also organized. There was no difficulty in identifying meat bones, dried grapes and papaya. In the case of fish bones there is a need for further kinetic studies using different fish species. The identification of pistachio nut shells is more complicated and further research is needed prior to the organization of a further intercomparison. Laboratories were able to distinguish between chicken bones irradiated in the range 1 to 3 KGy or 7 to 10 KGy although there was a partial overlap between the results from different laboratories

Development of a Comprehensive Radioactive Waste Management Program in the Kingdom of Morocco

International Nuclear Information System (INIS)

Abderrahim, Bouhi; Bouchta, Moussaif; El Maati, Mouldoura; Touria, Lambarki; Touria, El Ghailassai; Fischer, R.

2009-01-01

The Kingdom of Morocco has been a signatory of the International Atomic Energy Agency (IAEA) Joint Convention on the Management of Spent Fuel and Radioactive Waste since 1999. In fact Morocco was the first African country to ratify the joint convention. The Centre National de Energie des Sciences et des Techniques Nucleaires (CNESTEN) has been designated as the lead entity within the country for radioactive waste management. Morocco is in the process of receiving authorization to begin operating a new 2 MW MARK-II TRIGA research reactor at its Nuclear Energy Research Center (CENM) in Maamora. With the commissioning of the research reactor imminent, the waste management program has been preparing to disposition waste streams from the reactor, associated research operations, production of radioisotopes and anticipated future needs. The center is also the designated collection and storage facility for radioactive waste generated in the country, primarily spent sealed sources. This paper focuses on developing a radioactive waste management program that meets international standards in a class C country as described in Selection of Efficient Options for Processing and Storage of Radioactive Waste in Countries with Small Amounts of Waste Generation (class C countries are countries with research reactors but without nuclear power plants). In building their radioactive waste management program Morocco has made good use of experts from the IAEA and under a Sister Laboratory Agreement has worked with waste management personnel from the United States. This cooperative approach has provided assistance to Morocco in developing a safe and compliant program. Developing waste stream disposition pathways for all possible waste types can be especially challenging given the lack of commercial waste management infrastructure within the country. This paper will detail how waste management decisions are made, the waste management technology that was selected and how waste conditioning

Implementation of a management applied program for liquid radioactive waste treatment

International Nuclear Information System (INIS)

Lee, Y. H.; Ann, S. J.; Jo, H. S.; Son, J. S.

2003-01-01

A data collection of a liquid radioactive waste treatment process of a research organization became necessary while developing the RAWMIS(Radioactive Waste Management Integration System) which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by treatment process. Data on the actual treatment process that is not limited experiment improve by a document, human traces, saving of material resources and improve with efficiency of tracking about a radioactive waste and a process and give help to radioactive waste material valance and inventory study

Evaluation of NAA laboratory results in inter-comparison on determination of trace elements in food and environmental samples

International Nuclear Information System (INIS)

Diah Dwiana Lestiani; Syukria Kurniawati; Natalia Adventini

2012-01-01

Inter-comparison program is a good tool for improving quality and to enhance the accuracy and precision of the analytical techniques. By participating in this program, laboratories could demonstrate their capability and ensuring the quality of analysis results generated by analytical laboratories. The Neutron Activation Analysis (NAA) laboratory at National Nuclear Energy Agency of Indonesia (BATAN), Nuclear Technology Center for Materials and Radiometry-PTNBR laboratory participated in inter-comparison tests organized by NAA working group. Inter-comparison BATAN 2009 was the third inter-laboratory analysis test within that project. The participating laboratories were asked to analyze for trace elements using neutron activation analysis as the primary technique. Three materials were distributed to the participants representing foodstuff, and environmental material samples. Samples were irradiated in rabbit facility of G.A. Siwabessy reactor with neutron flux ~ 10 13 n.cm -2 .s -1 , and counted with HPGe detector of gamma spectrometry. Several trace elements in these samples were detected. The accuracy and precision evaluation based on International Atomic Energy Agency (IAEA) criteria was applied. In this paper the PTNBR NAA laboratory results is evaluated. (author)

Result of the intercomparison exercise on radon measuring instruments and radon detectors 'bev- radon ring 2005'

Energy Technology Data Exchange (ETDEWEB)

Baumgartner, A. [Vienna Univ. of Technology, Atominstitut, Wien (Austria); Maringer, F.J.; Michai, P.; Kreuziger, M. [BEV-Federal Office of Metrology and Surveying, Wien (Austria)

2006-07-01

In spring 2005 the Federal Office of Metrology and Surveying (B.E.V.) invited all in Austria working radon measuring institutes to an intercomparison exercise at the radon calibration laboratory in the Arsenal. The aim of this intercomparison was on the one hand an objective inquiry and documentation of the current metrological potential on the section of radon measurement in Austria - both quantitative and qualitative- and on the other hand an initiative for the participating laboratories to optimize and improve their applied calibration-, measurement and analyse technique. Ten contacted Austrian radon laboratories were prepared to participate on the radon intercomparison exercise. The intercomparison exercise was carried out from 14. till 29. June at the radon calibration laboratory in the Arsenal of the B.E.V.. As radon emanation source a five stepped arranged, at the Arsenal built radon source was used. The source ( A.D.O.T.T.O. 1 is filled with a certified Ra- 226-standard solution of the Czech Metrological Institute (C.M.I.), Prag. A simple statistic based model was used for the evaluation and assessment of the results from the participants, which consider the statistic nature of the radioactive decay combined uncertainty. Altogether 183 measuring instruments participated the intercomparison exercise. Two reference measuring instruments, 22 active and 159 passive measuring instruments. The active measuring instruments formed 6 types of instruments and as passive radon detectors were 7 different types used from the participants. The positioning of the radon measuring instruments and detectors in the radon calibration laboratory was executed in regard to statistic points of view. From the active measuring instruments 17 could qualify and from the passive methods six from eight participants were in compliance to the given criteria. Radon measurements, which could have financial and economics relating implications (e.g. architectural redevelopment or

1982 radon intercomparison exercises at EML

International Nuclear Information System (INIS)

Fisenne, I.M.; George, A.C.; Keller, H.W.

1983-03-01

This report summarizes the results of two radon measurement intercomparison exercises held in 1982. Sixteen organizations, including five United States federal departments, two state governments, two national laboratories, three universities, three private sector laboratories and Swedish National Institute participated in these exercises. The results indicate good agreement among the participants at the 30 pCi 222 Rn/L level. With the continued interest and cooperation of groups involved in radon measurements, twp intercomparison exercises are planned during 1983

Long-term leach testing of solidified radioactive waste forms (International Standard Publication ISO 6961:1982)

International Nuclear Information System (INIS)

Stefanik, J.

2001-01-01

Processes are developed for the immobilization of radionuclides by solidification of radioactive wastes. The resulting solidification products are characterized by strong resistance to leaching aimed at low release rates of the radionuclides to the environment. To measure this resistance to leaching of the solidified materials: glass, glass-ceramics, bitumen, cement, concrete, plastics, a long-term leach test is presented. The long-term leach test is aimed at: a) the comparison of different kinds or compositions of solidified waste forms; b) the intercomparison between leach test results from different laboratories on one product; c) the intercomparison between leach test results on products from different processes

Program integration on the Civilian Radioactive Waste Management System

International Nuclear Information System (INIS)

Trebules, V.B.

1995-01-01

The recent development and implementation of a revised Program Approach for the Civilian Radioactive Waste Management System (CRWMS) was accomplished in response to significant changes in the environment in which the program was being executed. The lack of an interim storage site, growing costs and schedule delays to accomplish the full Yucca Mountain site characterization plan, and the development and incorporation of a multi-purpose (storage, transport, and disposal) canister (MPC) into the CRWMS required a reexamination of Program plans and priorities. Dr. Daniel A. Dreyfus, the Director of the Office of Civilian Radioactive Waste Management (OCRWM), established top-level schedule, targets and cost goals and commissioned a Program-wide task force of DOE and contractor personnel to identify and evaluate alternatives to meet them. The evaluation of the suitability of Yucca Mountain site by 1998 and the repository license application data of 2001 were maintained and a target date of January 1998 for MPC availability was established. An increased multi-year funding profile was baselined and agreed to by Congress. A $1.3 billion reduction in Yucca Mountain site characterization costs was mandated to hold the cost to $5 billion. The replanning process superseded all previous budget allocations and focused on program requirements and their relative priorities within the cost profiles. This paper discusses the process for defining alternative scenarios to achieve the top-level program goals in an integrated fashion

Comprehensive Australasian multicentre dosimetric intercomparison: issues, logistics and recommendations.

Science.gov (United States)

Ebert, M A; Harrison, K M; Cornes, D; Howlett, S J; Joseph, D J; Kron, T; Hamilton, C S; Denham, J W

2009-02-01

The present paper describes the logistics of the 2004-2008 Australasian Level III Dosimetry Intercomparison. Dosimetric intercomparisons (or 'audits') can be used in radiotherapy to evaluate the accuracy and quality of radiation delivery. An intercomparison was undertaken in New Zealand and Australia to evaluate the feasibility and logistics of ongoing dosimetric intercomparisons that evaluate all steps in the radiotherapy treatment process, known as a 'Level III' intercomparison. The study commenced in 2002 with the establishment of a study team, definition of the study protocol, acquisition of appropriate equipment and recruitment of participating radiotherapy centres. Measurements were undertaken between October 2004 and March 2008, and included collation of data on time, costs and logistics of the study. Forty independent Australian and New Zealand radiotherapy centres agreed to participate. Measurement visits were made to 37 of these centres. Data is presented on the costs of the study and the level of support required. The study involved the participation of 16 staff at the study centre who invested over 4000 hours in the study, and of over 200 professionals at participating centres. Recommendations are provided for future phantom-based intercomparisons. It is hoped that the present paper will be of benefit to any centres or groups contemplating similar activities by identifying the processes involved in establishing the study, the potential hazards and pitfalls, and expected resource requirements.

Intercomparison of low-level tritium in water

International Nuclear Information System (INIS)

Sipka, V.; Zupancic, M.; Hadzisehovic, M.; Bacic, S.; Vukovic, Z.

1989-01-01

In 1985 the Section of Isotope Hydrology of the IAEA organized the fourth intercomparison for low-level tritium counting in waters. Four water samples with different 3 H concentration were sent to 85 laboratories willing to participate. The results from the different laboratories were presented in the unified questionnaires and coded. The participation in the intercomparisons for every laboratory doing low-level 3 H measurements in the waters is very important and useful. This is a best way to check the entire procedure and methods of the measurements and the reliability of the standards used. Since our laboratories are doing the natural 3 H concentration measurement in the waters for the environmental control and hydrology reasons it was necessary to take part in this intercomparison. Our standard procedure was applied. The 3 H activity in the samples was measured by liquid scintillation counting after an electrolytic enrichment. The results of our measurements of the four water samples, received from the organizers, are presented on the figures and tables presenting summary of the intercomparison. It is clear that our measurement (procedure and standards) have given satisfactory results (author)

Eurados self-sustained programme of intercomparisons for individual monitoring services

International Nuclear Information System (INIS)

Grimbergen, T. W. M.; Figel, M.; Romero, A. M.; Stadtmann, H.; McWhan, A. F.

2011-01-01

Within EURADOS working group 2, a system for self-sustained intercomparisons for individual monitoring services for external radiation was developed. With the intercomparison results, the participants can show compliance within their quality management system, compare their results with those from other participants and develop plans for improvement of their system. The costs of the exercises are covered by the participants fees. In this programme, the first intercomparison exercise for whole-body dosemeters has been executed in 2008 with 62 participating dosimetry systems from participants across Europe. In general, film systems show the largest deviations, although the results of some participants indicate that it is possible to achieve results with a film system with similar quality as for thermoluminescence dosimetry (TLD) systems. A second intercomparison has been organised for extremity dosemeters in 2009. For 2010 it is planned to organise a second intercomparison for whole-body dosemeters. (authors)

The new orphaned radioactive sources program in the United States

International Nuclear Information System (INIS)

Naraine, N.; Karhnak, J.M.

1998-01-01

Exposure of the public to uncontrolled radioactive sources has become an significant concern to the United States (US) Government because of the continuous increase in the number of sources that are being found, sometimes without proper radiation markings. This problem is primarily due to inadequate control, insufficient accountability, and improper disposal of radioactive materials. The US Environmental Protection Agency (EPA) has funded a cooperative 'orphaned' source initiative with the Conference of Radiation Control Program Directors (CRCPD) to bring under control unwanted sources and thus reduce the potential for unnecessary exposure to the public, workers and the environment. The program is being developed through the cooperative efforts of government agencies and industry, and will provide a quick and efficient method to bring orphaned sources under control and out of potentially dangerous situations. (author)

Intercomparison of PIXE spectrometry software packages

International Nuclear Information System (INIS)

2003-02-01

During the year 2000, an exercise was organized to make a intercomparison of widely available software packages for analysis of particle induced X ray emission (PIXE) spectra. This TECDOC describes the method used in this intercomparison exercise and presents the results obtained. It also gives a general overview of the participating software packages. This includes basic information on their user interface, graphical presentation capabilities, physical phenomena taken in account, way of presenting results, etc. No recommendation for a particular software package or method for spectrum analysis is given. It is intended that the readers reach their own conclusions and make their own choices, according to their specific needs. This TECDOC will be useful to anyone involved in PIXE spectrum analysis. This TECDOC includes a companion CD with the complete set of test spectra used for intercomparison. The test spectra on this CD can be used to test any PIXE spectral analysis software package

PROGER - Management program for radioactive wastes in research institutions

International Nuclear Information System (INIS)

Ferreira, Rubemar S.; Costa, Maria Regina Ferro; Ramos Junior, Anthenor C.; Esposito, Irapoan; Vaz, Solange dos Reis e; Pontedeiro, Elizabeth May; Gomes, Carlos de Almeida

1997-01-01

This article demonstrates the feasibility of a program, denominated PROGER, and aimed at the improvement of radioactive waste management activities in research institutions in Brazil. This program involves implementation, correction and updating of waste management techniques in those institutions that already possess a waste management system or its full set-up for the institutions where it is non-existent. Partial results are presented, concerning characteristics and quantities of wastes, and the methodology utilized by PROGER discussed

Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages

International Nuclear Information System (INIS)

1993-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Uranium determination in natural U O2 samples for the laboratory intercomparison program of Agencia Brasileiro-Argentina de Contabilidade e Controle de Materiais Nucleares (ABACC)

International Nuclear Information System (INIS)

Avelar, Marta M.; Palmieri, Helena E.L.; Reis Fagundes, Oliene dos

1997-01-01

The modified Davies and Gray method for uranium titration to analyse nuclear materials is the procedure used by the CDTN's chemical laboratory. Its analytical performance was evaluated through the participation in the intercomparison program with the Brazilian - Argentine Agency for Accountability and Control of Nuclear Materials (ABACC). One sample of natural uranium dioxide was analysed. The precision and accuracy of the measurements are reported and discussed in this paper. (author). 7 refs., 1 fig., 2 tabs

Intercomparison of radon gas detectors 1999 and 2000 at PSI

International Nuclear Information System (INIS)

Schuler, Christoph; Butterweck, Gernot

2000-10-01

This report describes the results of two radon intercomparison exercises performed by the Reference Laboratory for Radon Gas Activity Concentration Measurements at Paul Scherrer Institut from Sep 9th to Oct 6th, 1999, and from March 21st to 28th, 2000. Radon gas detectors and instruments were exposed in the PSI Radon Chamber in reference atmospheres to 1060 kBqhm -3 radon gas exposure at an average radon gas concentration of 6400 Bqm -3 and to 2050 kBqhm -3 radon gas exposure at an average radon gas concentration of 12500 Bqm -3 , respectively. These intercomparison exercises determined the performance of electret ionisation chambers, track etch detectors and measuring instruments at high humidity (1999 Intercomparison Exercise) and at a high radon gas exposure (2000 Intercomparison Exercise). In the 1999 Intercomparison Exercise, electret ionisation chambers revealed an influence on high humidity. This effect may be due to impurities on a microscopic scale on the electrets of these detectors. With few exceptions, in both the 1999 and the 2000 Radon Intercomparison Exercise the deviations of the measurement results to the reference radon gas concentration values were less than 15% (traceability criterion) and the standard deviation of the results of five detectors less than 15% (reproducibility criterion). (author) [de

Historically Black Colleges and Universities Radioactive Waste Management Research Program: Summary of activities, 1985-1986

International Nuclear Information System (INIS)

1986-01-01

This report summarizes the 1985 to 1986 activities of the Historically Black Colleges and Universities (HBCUs) Radioactive Waste Management Research Program sponsored by the Office of Civilian Radioactive Waste Management of the US Department of Energy (DOE). The first set of three awards was made in September,1984. In September, 1985, two of these projects were renewed and a new proposal was funded. The program has been enthusiastically received by the community of HBCUs and the program sponsor

Report on the intercomparison run IAEA-373: Determination of radionuclides in grass sample IAEA-373

Energy Technology Data Exchange (ETDEWEB)

Strachnov, V; Larosa, J; Dekner, R; Fajgelj, A; Zeisler, R

1996-02-01

Activities in environmental monitoring of radioactive substances require natural matrix reference materials for laboratory quality assessment and support of international compatibility. A grass sample collected in the Ukraine by the International Atomic Energy Agency's (IAEA's) programme on Analytical Quality Assurance Services (AQCS) has been prepared and distributed for a world-wide intercomparison on the determination of natural and man-made radionuclides and selected trace elements. The data from 110 laboratories representing 42 countries have been evaluated and allowed the establishment of recommended activity values for K-40, Sr-90, Cs-134 and Cs-137. Information values are given for the concentrations of Mn, Rb, Th and Zn. (author)

Intercomparison of techniques for inspection and diagnostics of heavy water reactor pressure tubes. Additional information

International Nuclear Information System (INIS)

2009-03-01

The reports from Argentina, Canada, India, Korea and Romania are presented concerning the projects carried out under the Coordinated Research Program (CRP) I3.30.10 of the International Agency for Atomic Energy - Vienna related to 'Intercomparison of Techniques for Pressure Tube Inspection and Diagnostics'

INEEL Radioactive Liquid Waste Reduction Program

International Nuclear Information System (INIS)

Millet, C.B.; Tripp, J.L.; Archibald, K.E.; Lauerhauss, L.; Argyle, M.D.; Demmer, R.L.

1999-01-01

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most

Intercomparison Measurements Exercises of Mobile Radiological Laboratories (invited paper)

International Nuclear Information System (INIS)

Martincic, R.

2000-01-01

After the reactor accident in Chernobyl, the importance of mobile radiological laboratories became evident and in situ gamma spectrometry became a common method for the rapid detection of gamma emitters in the environment. Since then different institutions in European countries have organised periodic intercomparison exercises of mobile radiological laboratories to improve the measurement methods and the preparedness of emergency monitoring teams. The general objectives of these workshops are to promote the knowledge and to exchange the experiences of emergency monitoring teams that use mobile radiological laboratories, as well as to foster the international harmonisation of emergency monitoring procedures and cooperation among teams. Finally, the results of intercomparison measurements have shown that such exercises are mandatory for rapid, efficient and correct environmental monitoring in nuclear or radiological emergencies. An overview of these intercomparison measurements is given, results from the 1999 intercomparison workshop are presented and lessons learned are discussed. (author)

Identification of irradiated foodstuffs: results of a European test intercomparison

International Nuclear Information System (INIS)

Raffi, J.; Belliardo, J.-J.; Agnel, J.-P.; Vincent, P.

1993-01-01

The results of an intercomparison, organized by the Community Bureau of Reference (Commission of the European Communities), on the use of Electron Spin Resonance spectroscopy for the identification of irradiated food are presented. A qualitative intercomparison was carried out using beef and trout bones, sardine scales, pistachio nut shells, dried grapes and papaya. Protocols are proposed for meat bones, fish bones (with some restrictions) and fruits such as dried grapes and papaya. The protocol for pistachio nuts and fruits such as strawberries is more complicated and further research is needed prior the organization of future intercomparisons. A quantitative intercomparison on poultry bones was also organized. Laboratories were able to distinguish between chicken bones irradiated at 1 to 3 kGy or 7 to 10 kGy. (author)

An international intercomparison of absorbed dose measurements for radiation therapy

International Nuclear Information System (INIS)

Taiman Kadni; Noriah Mod Ali

2002-01-01

Dose intercomparison on an international basis has become an important component of quality assurance measurement i.e. to check the performance of absorbed dose measurements in radiation therapy. The absorbed dose to water measurements for radiation therapy at the SSDL, MINT have been regularly compared through international intercomparison programmes organised by the IAEA Dosimetry Laboratory, Seibersdorf, Austria such as IAEA/WHO TLD postal dose quality audits and the Intercomparison of therapy level ionisation chamber calibration factors in terms of air kerma and absorbed dose to water calibration factors. The results of these intercomparison in terms of percentage deviations for Cobalt 60 gamma radiation and megavoltage x-ray from medical linear accelerators participated by the SSDL-MINT during the year 1985-2001 are within the acceptance limit. (Author)

Neutron dosimetry intercomparison run for verification of the neutron fluence

International Nuclear Information System (INIS)

Penev, I.; Kinova, L.

2001-01-01

For the neutron fluence verification the intercomparison runs Balakovo and KORPUS have been carried out. The participation in the international intercomparison runs shows that in order to more precisely verify the calculated values of the neutron fluence more intercomparison exercises are necessary. Due to such exercises the results improved after calibration of Nb performed and are in a very good agreement with RIIAR results in spite of the different approaches in the determination of its activity

Factor of radioactive waste on nuclear power program

International Nuclear Information System (INIS)

Syed Abdul Malik Syed Zain

2009-01-01

Global warming phenomena and rising oil prices have brought the excitement of open space use of nuclear power. Arguments in favor of this technology range in terms of more environmentally friendly, energy diversification and cost efficiency has prompted the government to widen the choice of nuclear power be considered as a serious alternative. Despite the attractive factors to the use of these powers, there are also factors that stem from the continued development of nuclear power. These include the factor of safety, security, security of fuel supply, and public attention is often associated with radioactive waste management. This article attempts to debate specific to radioactive waste management factors that impact on public acceptance of a country's nuclear power program, especially in Malaysia. Starting from the absence of radioactive waste management policy to model uncertainty of the landfill and complications in selecting a repository site shows the basic infrastructure is still lacking. In addition, previous experience handling thorium waste has not reached a final settlement after several years of implementation. It reinforced the perception about the level of public confidence in the competence and attitude of local workers who are not very encouraging to pursue this advanced.

The participation of ATOMKI in the G-2 international intercomparison of high precision gamma-ray spectrometry measurements

International Nuclear Information System (INIS)

Gaspar, A.; Lakatos, T.; Sulik, B.; Toeroek, I.

1981-01-01

International intercomparison had been organized by the IAEA in high precision gamma spectrometry. Five mixed-spectrum sources were prepared and sent to the participants by the IAEA for relative gamma emission rate measurements. This source type enables the whole measuring method and procedure to be tested. Measurements were carried out using two independent methods: a.) simple normalization to an additional radioactive source; b.) using a time variant pulse processor and random pulse generator for correction of dead-time and pile-up losses. The results agreed in most cases within +-1% with the IAEA results. (R.J.)

National environmental radiation monitoring program: towards formulating policy on radioactive waste management

International Nuclear Information System (INIS)

Sukiman Sarmani

2002-01-01

Though Malaysia has no nuclear power station, but the management of its low level radioactive waste generated from industrial activities involves most of the same issues that must be considered in countries with nuclear power. These include public consultation at all stages, an open approach, high level scientific and engineering input and political decision by the Government. A carefully planned approach, which involves the public and gives time to build trust and confidence, is necessary for success. It is also pertinent to establish accurate and reliable data on environmental radiation to accurately assess possible risk. This is where a national monitoring program on environmental radiation is very important. While accurate data will help formulate sound policy on radioactive waste management, it should also be readily available to the public to gain support and acceptance. This paper presents arguments on the importance of a national monitoring program for environmental radiation as an input for formulating a policy on radioactive waste management in Malaysia. (Author)

Research program on radioactive wastes 2013-2016

International Nuclear Information System (INIS)

Berner, U.; Bossart, P.; Brander, S.; Schaub, P.; Frank, E.; Hugi, M.; Holocher, J.; Schlüchter, Ch.

2013-06-01

This report issued by the Swiss Federal Office of Energy (SFOE) takes a look at the work done within the framework of the 2012 Swiss Research Program on radioactive wastes. The implementation program for the period 2013 - 2016 is discussed. Long-term aspects such as knowledge conservation and marking concepts are investigated and regional participation in the planning of repositories is discussed. Environmental protection, the planning of repositories and the definition of their content are discussed. Monitoring concepts and emergency closure in crisis situations are also looked at. The associated material technologies and repository design are discussed. Finally, ethical considerations and environmental policies are discussed. Two appendices include information on the timelines involved as well as information on the players involved and their areas of competence

Intercomparison of in vivo monitoring systems in Europe. Results from Risoe National Laboratory

International Nuclear Information System (INIS)

Lauridsen, B.; Soegaard-Hansen, J.

1996-12-01

This report contains the contribution from Risoe National Laboratory to the European project: 'Intercomparison of in Vivo Monitoring Systems in Europe'. The whole-body counter at Risoe and the measurement on a phantom used as an intercalibration object in the project is described. In four case studies, prepared by the project coordinator, intakes of radionuclides and resulting doses are calculated. These calculations are based on informations on the radioactive materials taken into the body, routes of intake and on body contents of radionuclides from simulated single or multiple whole-body measurement. The answer from Risoe National Laboratory to two questionnaires - one on the whole-body counting facility and calibration methods and one on the legal requirements is the country - is listed. (au)

Quality assurance of external exposure measurement for national survey of environmental natural radioactive level

International Nuclear Information System (INIS)

Yue Qingyu

1995-01-01

This paper summarizes the quality assurance work of external exposure measurement for national survey of environmental natural radioactive level. It mainly introduces instrumentation used in external exposure measurement and its properties, the measurement results of three times of national in-site intercomparison, and in-site sample check results of measurement results from 29 provinces, cities and autonomous regions and Wuhan, Baotou cities

Psacoin level 1A intercomparison probabilistic system assessment code (PSAC) user group

International Nuclear Information System (INIS)

Nies, A.; Laurens, J.M.; Galson, D.A.; Webster, S.

1990-01-01

This report describes an international code intercomparison exercise conducted by the NEA Probabilistic System Assessment Code (PSAC) User Group. The PSACOIN Level 1A exercise is the third of a series designed to contribute to the verification of probabilistic codes that may be used in assessing the safety of radioactive waste disposal systems or concepts. Level 1A is based on a more realistic system model than that used in the two previous exercises, and involves deep geological disposal concepts with a relatively complex structure of the repository vault. The report compares results and draws conclusions with regard to the use of different modelling approaches and the possible importance to safety of various processes within and around a deep geological repository. In particular, the relative significance of model uncertainty and data variability is discussed

Intercomparison of Rn-222 determination from groundwater

DEFF Research Database (Denmark)

Vesterbacka, P.; Pettersson, H.; Hanste, U.-M.

2010-01-01

An intercomparison exercise on Rn-222 determination in groundwater was organized between eight Nordic laboratories. The individual laboratory results were in most cases within 20% of the median value and within reported uncertainties. Considering the particular difficulties in preparing, transpor......An intercomparison exercise on Rn-222 determination in groundwater was organized between eight Nordic laboratories. The individual laboratory results were in most cases within 20% of the median value and within reported uncertainties. Considering the particular difficulties in preparing...

Dosimetry intercomparisons in European medical device sterilization plants

DEFF Research Database (Denmark)

Miller, A.; Sharpe, P.H.G.

2000-01-01

Dosimetry intercomparisons have been carried out involving two-thirds of all European radiation sterilization facilities. Dosimeters for the intercomparisons were supplied by two accredited calibration laboratories. The results show good agreement, and indicate overall dosimetry accuracy of the o...... of the order of +/-5% (1 sigma) for both Co-60 and electron beam plants. (C) 2000 Elsevier Science Ltd. All rights reserved....

3. Research Coordination Meeting (RCM) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'. Working material

International Nuclear Information System (INIS)

2007-01-01

To meet expressed Member States' needs, the IAEA has initiated a Coordinated Research Project (CRP) on 'Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste'. The final goal of the CRP is to deepen the understanding of the dynamics of transmutation systems, e.g. the accelerator driven system, especially systems with deteriorated safety parameters, qualify the available methods, specify the range of validity of methods, and formulate requirements for future theoretical developments. Should transient experiments be available, the CRP will pursue experimental benchmarking work. In any case, based on the results, the CRP will conclude on the potential need of transient experiments and make appropriate proposals for experimental programs. The Technical Meeting in Chennai was the 3rd Research Coordination Meeting (RCM) of the CRP The man objectives of the RCM were to: - Discuss and perform inter-comparisons of the various benchmark results; - Prepare the first draft of the final CRP Report Status of the analyses and inter-comparisons of the results. The main objective of the CRP was to study innovative technology options for incinerating/utilizing radioactive wastes. The CRP's benchmarking exercises focused on eight innovative transmutation 'Domains', which correspond to different critical and sub-critical concepts or groups of concepts: I. Critical fast reactor, solid fuel, with fertile; II. Critical fast reactor, solid fuel, fertile-free; III. ADS, solid fuel, with fertile; IV. ADS, solid fuel, fertile-free; V. Critical reactor and ADS, molten salt fuel, with fertile; VI. Critical reactor and ADS, molten salt fuel, fertile-free; VII. Critical fast reactor and ADS, gas cooled; VIII. Fusion/fission hybrid system. For each of these Domains, the discussions and inter-comparisons considered the following issues: - Reactor-models; - Scenarios/phenomena; - Static analyses; - Dynamic analyses; - Methods; - Codes; - Neutronic data base

Dosimetry intercomparisons between fast neutron radiotherapy facilities

International Nuclear Information System (INIS)

Almond, P.R.; Smith, A.R.; Smathers, J.B.; Otte, V.A.

1975-01-01

Neutron dosimetry intercomparisons have been made between M.D. Anderson Hospital and Tumor Institute, Naval Research Laboratory, University of Washington Hospital, and Hammersmith Hospital. The parameters that are measured during these visits are: tissue kerma in air, tissue dose at depth of dose maximum, depth dose, beam profiles, neutron/gamma ratios and photon calibrations of ionization chambers. A preliminary report of these intercomparisons will be given including a comparison of the calculation and statement of tumor doses for each institution

Intercomparison of analysis methods for seismically isolated nuclear structures. Papers and working materials presented at the 3. research coordination meeting

International Nuclear Information System (INIS)

1998-01-01

The Coordinated research program on Intercomparison of analysis methods for seismically isolated nuclear structures involved participants from Italy, Japan, Republic of Korea, Russia, United Kingdom, USA, EC. The purpose of the meeting was to review the progress on the finite element prediction of the force-deformation behaviour of seismic isolators and to discuss the first set of analytical results for the prediction of the response of base-oscillated structures to earthquake inputs. The intercomparison of predictions of bearing behaviour has identified important unexpected issues requiring deeper investigation

IAEA intercomparisons in the frame of the occupational radiation protection programme

International Nuclear Information System (INIS)

Mrabit, K.; Cruz Suarez, R.

2005-01-01

The IAEA safety activities to support the assessment of occupational exposure through a comprehensive set of safety guides, safety reports and other related documents will soon be completed. Several intercomparison exercises were organized by the IAEA on the determination of radionuclides in human urine samples, whole body counting and external dosimetry. These previous intercomparison exercises revealed significant differences in the approaches, methods and assumptions, and consequently in the results. This underlined the importance of this kind of intercomparison programme as a key element of the international harmonization of quantities and units. The purpose of this paper is to present the current and future IAEA activities in support of assessment of occupational exposure by organizing intercomparison runs

Argentine Republic intercomparison programme for personal dosimeters

International Nuclear Information System (INIS)

Gregori, Beatriz N.; Papadopulos, Susana B.; Kunst, Juan J.; Cruzate, Juan A.; Saravi, Margarita C.

2004-01-01

In 1997 an Intercomparison Program for individual monitoring started in order to test (on a voluntary basis) the performance in absorbed dose and personal dose equivalent determinations. The aim of the program was also to gain some insight into the general aspects related to the type of the personnel dosimeter used, the calibration procedures, the phantom spectral dependence and the management of radiological quantities. The Regional Reference Center for Dosimetry (CCR), of the Argentine National Atomic Energy Commission and the Physical Dosimetry Laboratory of the Argentine National Regulatory Authority, performed the irradiations. Those were done free air and on ICRU phantom, using X-ray, quality ISO: W60, W80, W110 and W200; and 137 Cs and 60 Co gamma rays, normal and angular (0, 30, 60 degrees) incidence. In the framework of the Program, an upgraded workshop took place and the national standard, IRAM 17146, was elaborated as well. In this work, the laboratories performance and its temporal evolution is shown from 1997 up to 2002. The suggestions to improve their performance are also included. (author)

Michigan high-level radioactive waste program. Technical progress report for 1985

International Nuclear Information System (INIS)

1986-01-01

In 1985, five crystalline rock formations located in Michigan's Upper Peninsula were under consideration in the regional phase of the Department of Energy's (DOE) search for the site of the nation's second high-level radioactive waste repository. The Michigan Department of Public Health has been designated by the Governor as lead state agency in matters related to high-level radioactive waste (HLRW). Mr. Lee E. Jager, Chief of the Department's Bureau of Environmental and Occupational Health, has been designated as the state contact person in this matter, and the Bureau's Division of Radiological Health, Office of Radioactive Waste Management (ORWM), has been designated to provide staff support. Recognizing that adequate state involvement in the various aspects of the Federal high-level radioactive waste (HLRW) programs would require a range of expertise beyond the scope of any single state agency, Governor Blanchard established the High-Level Radioactive Waste Task Force in 1983. In support of the Task Force efforts concerning the implementation of its change, the Department negotiated and concluded an agreement with the DOE, under which federal funds are provided to support state HLRW activities. This report outlines state activities for the calendar year 1985, funded under that agreement

Survey of radioactive contamination for foodstuffs

International Nuclear Information System (INIS)

Lee, Wan No; Lee, Chang Wu; Choi, Geun Sik; Cho, Yeong Hyeon; Kang, Mun Ja; Cheong, Geun Ho; Kim, Hui Ryeong; Park, Du Won; Park, Hyo Guk; Kwak, Ji Yeon

2006-11-01

After the Chernobyl nuclear accident in 1986, a lot of countries including EU, Japan, USA are to strengthen survey of radioactive contamination for foodstuffs. Our country has also surveyed radioactive contamination of the imported foodstuffs and started to check continuously the radioactivity contamination of the open market foodstuffs since 2003. In this year, imported foodstuffs(130 samples) and domestic foodstuffs(10 samples) are analyzed to investigate the radioactive contamination. Sampled foodstuffs items are collected from the open markets; one group is the imported foodstuffs and the other group is the domestic foodstuffs producted around nuclear facilities and northeast of Sokcho city concerning recent situations. Samples are usually bought from traditional markets, mart, department store or the Internet. After pretreatments such as drying, ashing, and homogenization, all samples were analyzed by gamma spectrometer system for survey and assessment of radioactive contamination. The 131 I radionuclide isn't detected among all foodstuffs(imported and domestic). The 137 Cs radionuclide among the regulation radionuclides( 137 Cs, 13 4 C s, 131 I) of food code is only detected at the imported foodstuffs but its level is far below the maximum permitted level. For the improvement of measurement confidence, the developed analysis method is tested by the participation of the national and international intercomparison. The developed method based on test results and international standard would be used at radioactive analysis as well as an education of relative workers. It could be applied as the basis data for amending the analysis method of food code. It is technically supported for radioactive analysis of commercial company and the government including KFDA. Finally these results would be used to solve an ambiguous anxiety of a people for radiation exposure by foodstuffs intake and help the KFDA to manage systematically the radioactive contamination and to give

The international comparison of radioactivity measurements on a solution of cesium-139

International Nuclear Information System (INIS)

Steyn, J.; Botha, S.M.; Van Staden, J.C.

1976-03-01

The participation by the NPRL in an intercomparison of radioactivity measurements as organised by the BIPM is fully described. The radioisotope involved, cesium 139, was made available to the BIPM by the NPRL in carrier-free form. The NPRL used the 4π gamma coincidence counting method with an internal liquid scintillation counter as 4π detector. The preliminary results released by the BIPM show the presence of relatively large systematic errors [af

Intercomparisons for integrating the radon-thoron detector of NIRP, China with NIRS, Japan

International Nuclear Information System (INIS)

Wu, Yunyun; Cui, Hongxing; Zhang, Qingzhao; Shang, Bing

2015-01-01

Intercomparisons play an important role in maintaining a reasonable and accurate standard of measurement and quality. Integrating the radon-thoron detector of the National Institute for Radiological Protection (NIRP), China has continuously been a subject of four rounds of international intercomparisons organised by the National Institute of Radiological Sciences (NIRS), Japan during 2007-12. The intercomparisons were held at NIRS. The exercises included different exposures for both radon and thoron. The results of the intercomparison for the detectors of NIRP for both radon and thoron exposures were in the range of ±20 % from the reference value and were categorised as 'Category I' in the intercomparison carried out in 2011. The radon and thoron results of the LD-P detector in four rounds of intercomparison exercises were summarised, and uncertainties of all the radon and thoron results of NIRP were within the acceptable range of 30 % in environment. Radon and thoron measurement results between NIRP and NIRS were basically in agreement. (authors)

Summary report of the state surveillance program on the transportation of radioactive materials

International Nuclear Information System (INIS)

1977-11-01

From 1973 to 1976, a surveillance program was conducted in New Jersey, Oregon, Missouri, New York, Illinois, Texas, Louisiana, South Carolina, Minnesota, and New York City to provide training support for State radiation personnel and to determine actual radiation exposure conditions and radioactive material package handling practices through the terminals of air carriers and freight forwarders. NRC and DOT along with the participating States, developed the surveillance program. In general, the results did not indicate a public health or safety problem due to the transportation of radioactive materials. Some employees of several freight forwarders, are, however, receiving annual exposures in excess of 500 mrem. Recommendations are given

Participation of the IPEN/CNEN/SP Environmental Diagnostic Division on programs of laboratory intercomparisons in environmental samples

International Nuclear Information System (INIS)

Cotrim, Marycel Barboza; Sato, Ivone Mulako; Salvador, Vera Lucia R.; Dantas, Elizabeth Sonoda Keiko; Cantagallo, Maria Ines; Lemes, Marcos Jose L.; Scapin, Marcos Antonio; Sisti, Cristina; Silveira, Elias Santana; Furusawa, Helio Akira; Pires, Maria Aparecida Faustino

2003-01-01

The present work presents the participation of the Environmental Diagnostic Division Laboratories (MQA) at the intercomparison national and international laboratories, (PI/SABESP - Interlaboratory Sao Paulo, Brazil, Program; Program for Interlaboratorial Analytic Quality Control of Metals in Water (CBM/COMETRO); Programa para La Calidad de las Mediciones Quimicas (PCQM/INTI) - Argentine, and the Commission d'Etablissement des Methodes d'Analyse, France (CETAMA/CEA). Those essay providers have using statistical tests such as the t-Student, Zscore and Cochran and Grubbs for the data evaluations. The obtained results are presented involving the analytical such as atomic absorption spectrometry: flame, graphite oven and hydride generation (AAS), emission spectrometry with induced plasma (ICP-OES), X-ray fluorescence WD-XRFS), ion chromatography and voltametry (VRA). The elements such as B, Al, K, Mg, Ca, Cr, Fe, Co, Cu, Zn and Pb, and the anions such as Cl-, NO 3 - , SO 4 2- and F - , were determined at trace level (mgL -1 ), and the elements such as Cr, As, Cd, Pb e Hg, at the trace level (μgL -1 ) in water matrices. The evaluation of analytical results, in the period 1997 to 2002, demonstrate a continuous improvement evidencing the importance of Laboratories participation at those type of exercises

Reproducibility in cyclostratigraphy: initiating an intercomparison project

Science.gov (United States)

Sinnesael, Matthias; De Vleeschouwer, David; Zeeden, Christian; Claeys, Philippe

2017-04-01

The study of astronomical climate forcing and the application of cyclostratigraphy have experienced a spectacular growth over the last decades. In the field of cyclostratigraphy a broad range in methodological approaches exist. However, comparative study between the different approaches is lacking. Different cases demand different approaches, but with the growing importance of the field, questions arise about reproducibility, uncertainties and standardization of results. The radioisotopic dating community, in particular, has done far-reaching efforts to improve reproducibility and intercomparison of radioisotopic dates and their errors. To satisfy this need in cyclostratigraphy, we initiate a comparable framework for the community. The aims are to investigate and quantify reproducibility of, and uncertainties related to cyclostratigraphic studies and to provide a platform to discuss the merits and pitfalls of different methodologies, and their applicabilities. With this poster, we ask the feedback from the community on how to design this comparative framework in a useful, meaningful and productive manner. In parallel, we would like to discuss how reproducibility should be tested and what uncertainties should stand for in cyclostratigraphy. On the other hand, we intend to trigger interest for a cyclostratigraphic intercomparison project. This intercomparison project would imply the analysis of artificial and genuine geological records by individual researchers. All participants would be free to determine their method of choice. However, a handful of criterions will be required for an outcome to be comparable. The different results would be compared (e.g. during a workshop or a special session), and the lessons learned from the comparison could potentially be reported in a review paper. The aim of an intercomparison project is not to rank the different methods according to their merits, but to get insight into which specific methods are most suitable for which

Luminescence dating of architectural ceramics from an early medieval abbey: The St Philbert Intercomparison (Loire Atlantique, France)

Energy Technology Data Exchange (ETDEWEB)

Guibert, P. [CNRS-Universite Bordeaux, UMR 5060, IRAMAT-CRP2A, Maison de l' Archeologie, F-33607 Pessac (France)], E-mail: guibert@u-bordeaux3.fr; Bailiff, I.K. [University of Durham, Department of Archaeology, Luminescence Laboratory, South Road, Durham, DH1 3LE (United Kingdom); Blain, S. [CNRS-Universite Bordeaux, UMR 5060, IRAMAT-CRP2A, Maison de l' Archeologie, F-33607 Pessac (France); University of Durham, Department of Archaeology, Luminescence Laboratory, South Road, Durham, DH1 3LE (United Kingdom); Gueli, A.M. [LDL and BBCC, Department of Physics and Astronomy, Centro Siciliano di Fisica Nucleare e di Struttura della Materia, Universita di Catania and INFN Sezione di Catania, via Santa Sofia 64, I-95123 Catania (Italy); Martini, M.; Sibilia, E. [INFN, CNR-INFN and CUDAM, Univ. Milano Bicocca, U5, via R. Cozzi 53, I-20125 Milano (Italy); Stella, G.; Troja, S.O. [LDL and BBCC, Department of Physics and Astronomy, Centro Siciliano di Fisica Nucleare e di Struttura della Materia, Universita di Catania and INFN Sezione di Catania, via Santa Sofia 64, I-95123 Catania (Italy)

2009-05-15

An experimental intercomparison was performed with brick samples from an early medieval building in the west of France, the St-Philbert-de-Grandlieu abbey. A potentially complex set of microdosimetric problems emerged from characterisation measurements, providing a robust test of the routine procedures used by each laboratory. The dating results obtained using quartz coarse grains and fine grain samples span over a large period of time, exhibiting overdispersion, and where systematic deviations appear between quartz and fine grain chronologies. Factors causing such scatter are analysed in detail, including internal radioactivity of quartz grains, millimetre-scale heterogeneity in the fabric, and the observation and modelling of fading behaviour of fine grain minerals.

Luminescence dating of architectural ceramics from an early medieval abbey: The St Philbert Intercomparison (Loire Atlantique, France)

International Nuclear Information System (INIS)

Guibert, P.; Bailiff, I.K.; Blain, S.; Gueli, A.M.; Martini, M.; Sibilia, E.; Stella, G.; Troja, S.O.

2009-01-01

An experimental intercomparison was performed with brick samples from an early medieval building in the west of France, the St-Philbert-de-Grandlieu abbey. A potentially complex set of microdosimetric problems emerged from characterisation measurements, providing a robust test of the routine procedures used by each laboratory. The dating results obtained using quartz coarse grains and fine grain samples span over a large period of time, exhibiting overdispersion, and where systematic deviations appear between quartz and fine grain chronologies. Factors causing such scatter are analysed in detail, including internal radioactivity of quartz grains, millimetre-scale heterogeneity in the fabric, and the observation and modelling of fading behaviour of fine grain minerals.

Improvement program of state supervision system for radioactive and nuclear installations

International Nuclear Information System (INIS)

Cardenas, J.

1993-01-01

The current program begins as part of a policy to take care of the development of the cuban nuclear program and with the objective of improving the state supervision system of nuclear and radioactive facilities on the basis of the national experience, good skills internationally accepted and taking into account IAEA recommendations. The program develops the following topics: reorientation and restructure of state supervision, review of the current nuclear legislature, update of regulations of facility safety and qualification and training of state supervision personnel

Environmental monitoring and radiation protection programs of Novi Han radioactive waste repository

International Nuclear Information System (INIS)

Christoskova, M.; Kostova, M.; Sheherov, L.; Bekiarov, P.; Iovtchev, M.

2000-01-01

The system for monitoring and control as an important part of the safety management of the Novi Han Radioactive Waste Repository contains two independent programs: environmental monitoring of the site (controlled area), the restricted access area and the surveillance area (supervised area) of the repository and radiation protection program including personal dosimetric control and indoor dosimetric control of workplaces in the buildings of the repository. The main activities related to the programs implementation are presented

Mobile Radiological Laboratories Intercomparison Measurements - Chernobyl

International Nuclear Information System (INIS)

Martincic, R.; Glavic-Cindro, D.; Korun, M.; Pucelj, B.; Vodenik, B.

2001-01-01

Full text: In last decade different institutions in European countries have organised periodic intercomparison exercises of mobile radiological laboratories to improve the preparedness of emergency monitoring teams. The 12th Regular Workshop on Mobile Radiological Laboratories was held in Exclusion Zone of the Chernobyl NPP, Ukraine from September 13 to September 18, 1999 under the acronym MORAL-12. The European Centre of Technological Safety (TESEC), Kiev, Ukraine and J. Stefan Institute, Ljubljana, Slovenia organised Intercomparison Measurements 99 jointly under the auspices of the International Atomic Energy Agency (IAEA). Nineteen teams from 9 countries and IAEA participated in the Workshop. Six field and personal and equipment contamination control exercises were prepared and conducted at two measuring sites with very different ambient dose rate levels. The Workshop pointed out that such exercises are very valuable for rapid, efficient and harmonised emergency response in case of nuclear or radiological emergency. The teams had an opportunity to test their ability to perform field measurements in the contaminated environment, and to report results on the spot, as well as to test their emergency preparedness and persistence. They gained new experiences for fieldwork under stress conditions. An overview and results of these intercomparison measurements are presented and lessons learned are discussed. (author)

A users guide to the radioactive waste inventory program 'DATABASE'

International Nuclear Information System (INIS)

Prince, G.A.; Tymons, B.J.

1984-09-01

The program computes an inventory of radioactive waste accumulation in a form such that a variety of interrogation, collation and summary functions can be used to access the stored information. Database is designed to be used online, that is the user will communicate with it at a computer terminal, and the program will display the result of each enquiry. It has the potential to automate much of the searching and adding up which was involved in compiling and using waste inventories in the past. (author)

Methods for estimating costs of transporting spent fuel and defense high-level radioactive waste for the civilian radioactive waste management program

International Nuclear Information System (INIS)

Darrough, M.E.; Lilly, M.J.

1989-01-01

The US Department of Energy (DOE), through the Office of Civilian Radioactive Waste Management, is planning and developing a transportation program for the shipment of spent fuel and defense high-level waste from current storage locations to the site of the mined geologic repository. In addition to its responsibility for providing a safe transportation system, the DOE will assure that the transportation program will function with the other system components to create an integrated waste management system. In meeting these objectives, the DOE will use private industry to the maximum extent practicable and in a manner that is cost effective. This paper discusses various methodologies used for estimating costs for the national radioactive waste transportation system. Estimating these transportation costs is a complex effort, as the high-level radioactive waste transportation system, itself, will be complex. Spent fuel and high-level waste will be transported from more than 100 nuclear power plants and defense sites across the continental US, using multiple transport modes (truck, rail, and barge/rail) and varying sizes and types of casks. Advance notification to corridor states will be given and scheduling will need to be coordinated with utilities, carriers, state and local officials, and the DOE waste acceptance facilities. Additionally, the waste forms will vary in terms of reactor type, size, weight, age, radioactivity, and temperature

United States Program on Spent Nuclear Fuel and High-Level Radioactive Waste Management

International Nuclear Information System (INIS)

Stewart, L.

2004-01-01

The President signed the Congressional Joint Resolution on July 23, 2002, that designated the Yucca Mountain site for a proposed geologic repository to dispose of the nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The United States (U.S.) Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is currently focusing its efforts on submitting a license application to the U.S. Nuclear Regulatory Commission (NRC) in December 2004 for construction of the proposed repository. The legislative framework underpinning the U.S. repository program is the basis for its continuity and success. The repository development program has significantly benefited from international collaborations with other nations in the Americas

Pilot internship program on radioactive waste at Vanderbilt University

International Nuclear Information System (INIS)

1988-01-01

The fourth year of the program began with the selection of the new interns. Mailings were sent to prospective graduate students and rising juniors at Vanderbilt University with grade point averages of 3.0 or better (out of 4.0) advertising the availability of internships in radioactive waste disposal. New interns were selected. All of the interns selected in the fourth year chose to return to Vanderbilt after their field assignment

A program for evolution from storage to disposal of radioactive wastes at CRNL

International Nuclear Information System (INIS)

Dixon, D.F.

1985-10-01

This report reviews past and current radioactive waste management practices at the Chalk River Nuclear Laboratories (CRNL) and outlines the proposed future program. For nearly 40 years, radioactive wastes have been generated at CRNL and have also been received there on a continuing basis from hospitals, industries, universities and miscellaneous other sources across Canada. The solid wastes now at CRNL have been either stored or buried and their total consolidated volume is approaching 50 000 m 3 . Much of that waste will require disposal as will the future wastes of similar character. The waste management program plan describes the proposed development of safe disposal facilities which could be built on site to accommodate most, if not all, of the radioactive wastes for which CRNL has responsibility. Three reference disposal concepts, each potentially capable of accepting a portion of the wastes, are described. One of these, the intrusion-resistant shallow land burial (SLB) concept, could be suitable for disposal of most of the CRNL wastes. It is proposed that a prototype SLB facility be designed, constructed and operated on the CRNL property and filled by 1992 to provide a focus for disposal research and development programs and to accumulate experience in all aspects of waste management. 53 refs

Beneficial role of conflict in radioactive waste management programs

International Nuclear Information System (INIS)

Payne, B.A.; Williams, R.G.

1985-01-01

Of the technical, political, and social problems associated with radioactive waste management, least is known about the latter two. Lay persons tend to generalize negative attitudes about other nuclear activity to radioactive waste management. Thus, conflict appears inevitable between the general public, citizen action groups, and decision-makers on radioactive waste management. The basis of conflict, we believe, can be found in the value orientation of certain groups and in differing perceptions of risk. Research on similar controversial issues reveals that conflict may be beneficial in the long run by contributing to the public's participation level and understanding of the issues, and to the decision-makers' appreciation of the lay perspective. The paper is in three parts. First, we review the sources of conflict over radioactive waste management issues. The negative attitudes and fears of the public toward different types of projects involving radioactivity, value conflicts, and differential perceptions of risk are cited as sources. Next we discuss the consequences of conflict in terms of sociological theory. Finally, we discuss how conflict can be directed and managed to produce an informed decision-making process. When the public is sensitized to an issue, when prevailing attitudes on the issue are negative, and when perceived risks are high - all of which are characteristic of waste management issues - specific steps should be taken to establish a legitimate process of communication and interaction between the public and the sponsor agency. When conflict is recognized as inevitable, the goal of a communications program is no longer to avoid it. It is to use the increased awareness to increase knowledge about waste management issues and public participation in decisions so that the final solution is acceptable at some level to all parties

Reference values and evaluation of the results of intercomparisons

International Nuclear Information System (INIS)

Aigner, H.; Deron, S.; Kuhn, E.

1981-01-01

The need of a reference value for the composition of materials distributed in intercomparisons is generally recognized. A single reference laboratory or a group of reference laboratories may be used to establish this reference value. The respective advantages and limitations of the two approaches are discussed. The reference measurements must be evaluated to provide the confidence limits of the reference value but also an estimate of the possible heterogeneity of the materials and its samples. The results of the intercomparison measurements should themselves be evaluated to test and discuss the significance of the biases of individual and selected groups of laboratories or techniques. The approach taken by the Analytical Quality Control Services of the International Atomic Energy Agency is illustrated by the SR-1 intercomparison on uranium assay in UO 2 powder

BASIC Program for the calculation of radioactive activities

International Nuclear Information System (INIS)

Cortes P, A.; Tejera R, A.; Becerril V, A.

1990-04-01

When one makes a measure of radioactive activity with a detection system that operates with a gamma radiation detector (Ge or of NaI (Tl) detector), it is necessary to take in account parameters and correction factors that making sufficiently difficult and tedious those calculations to using a considerable time by part of the person that carries out these measures. Also, this frequently, can to take to erroneous results. In this work a computer program in BASIC language that solves this problem is presented. (Author)

Results of the dosimetry intercomparison

International Nuclear Information System (INIS)

Dure, Elsa S.

2000-07-01

The appropriate way to verify the accuracy of the results of dose reported by the laboratories that offer lend personal dosimetry service is in the periodic participation of round of intercomparison dosimetry, undertaken by laboratories whose standards are trace (Secondary Laboratory). The Laboratory of External Personal Dosimetry of the CNEA-PY has participated in three rounds of intercomparison. The first two were organized in the framework of the Model Project RLA/9/030 RADIOLOGICAL WASTE SECURITY, and the irradiations were carried out in the Laboratory of Regional Calibration of the Center of Nuclear Technology Development, Belo Horizonte-Brazil (1998) and in the National Laboratory of Metrology of the ionizing radiations of the Institute of Radioprotection and Dosimetry, Rio de Janeiro-Brazil (1999). The third was organized by the IAEA and the irradiations were made in the Physikalisch-Technische Bundesanstalt PTB, Braunschweig - Federal Republic of Germany (1999-2000) [es

Radiological Threat Reduction (RTR) program: implementing physical security to protect large radioactive sources worldwide

International Nuclear Information System (INIS)

Lowe, Daniel L.

2004-01-01

The U.S. Department of Energy's Radiological Threat Reduction (RTR) Program strives to reduce the threat of a Radiological Dispersion Device (RDD) incident that could affect U.S. interests worldwide. Sandia National Laboratories supports the RTR program on many different levels. Sandia works directly with DOE to develop strategies, including the selection of countries to receive support and the identification of radioactive materials to be protected. Sandia also works with DOE in the development of guidelines and in training DOE project managers in physical protection principles. Other support to DOE includes performing rapid assessments and providing guidance for establishing foreign regulatory and knowledge infrastructure. Sandia works directly with foreign governments to establish cooperative agreements necessary to implement the RTR Program efforts to protect radioactive sources. Once necessary agreements are in place, Sandia works with in-country organizations to implement various security related initiatives, such as installing security systems and searching for (and securing) orphaned radioactive sources. The radioactive materials of interest to the RTR program include Cobalt 60, Cesium 137, Strontium 90, Iridium 192, Radium 226, Plutonium 238, Americium 241, Californium 252, and Others. Security systems are implemented using a standardized approach that provides consistency through out the RTR program efforts at Sandia. The approach incorporates a series of major tasks that overlap in order to provide continuity. The major task sequence is to: Establish in-country contacts - integrators, Obtain material characterizations, Perform site assessments and vulnerability assessments, Develop upgrade plans, Procure and install equipment, Conduct acceptance testing and performance testing, Develop procedures, and Conduct training. Other tasks are incorporated as appropriate and commonly include such as support of reconfiguring infrastructure, and developing security

DCHAIN: A user-friendly computer program for radioactive decay and reaction chain calculations

International Nuclear Information System (INIS)

East, L.V.

1994-05-01

A computer program for calculating the time-dependent daughter populations in radioactive decay and nuclear reaction chains is described. Chain members can have non-zero initial populations and be produced from the preceding chain member as the result of radioactive decay, a nuclear reaction, or both. As presently implemented, chains can contain up to 15 members. Program input can be supplied interactively or read from ASCII data files. Time units for half-lives, etc. can be specified during data entry. Input values are verified and can be modified if necessary, before used in calculations. Output results can be saved in ASCII files in a format suitable for including in reports or other documents. The calculational method, described in some detail, utilizes a generalized form of the Bateman equations. The program is written in the C language in conformance with current ANSI standards and can be used on multiple hardware platforms

International intercomparison and harmonization projects for demonstrating the safety of radioactive waste management, decommissioning and radioactive waste disposal

International Nuclear Information System (INIS)

Metcalf, Phil; O'Donnell, Patricio; Jova Sed, Luis; Batandjieva, Borislava; Rowat, John; Kinker, Monica

2008-01-01

Full text: The Joint Convention on the safety of spent fuel management and the safety of radioactive waste management and the international safety standards on radioactive waste management, decommissioning and radioactive waste disposal call for assessment and demonstration of the safety of facilities and activities; during siting, design and construction prior to operation, periodically during operation and at the end of lifetime or upon closure of a waste disposal facility. In addition, more recent revisions of the international safety standards require the development of a safety case for such facilities and activities, documentation presenting all the arguments supporting the safety of the facilities and activities covering site and engineering features, quantitative safety assessment and management systems. Guidance on meeting these safety requirements also indicates the need for a graded approach to safety assessment, with the extent and complexity of the assessment being proportional to the complexity of the activity or facility, and its propensity for radiation hazard. Safety assessment approaches and methodologies have evolved over several decades and international interest in these developments has been considerable as they can be complex and often subjective, which has led to international projects being established aimed at harmonization. The IAEA has sponsored a number of such initiatives, particularly in the area of disposal facility safety, but more recently in the areas of pre disposal waste management and decommissioning, including projects known as ISAM, ASAM, SADRWMS and DeSa. The projects have a number of common aspects including development of standardized methodological approaches, application on test cases and assessment review; they also have activity and facility specific elements. The paper presents an overview of the projects, the outcomes from the projects to date and their future direction aimed very much at practical application of

Intercomparison of active personal dosemeters in interventional radiology

International Nuclear Information System (INIS)

Clairand, I.; Struelens, L.; Bordy, J. M.; Daures, J.; Debroas, J.; Denozieres, M.; Donadille, L.; Gouriou, J.; Itie, C.; Vaz, P.; D'Errico, F.

2008-01-01

The use of active personal dosemeters (APD) in interventional radiology was evaluated by Working Group 9 (Radiation protection dosimetry of medical staff) of the CONRAD project, which is a Coordination Action supported by the European Commission within its sixth Framework Programme. Interventional radiology procedures can be very complex and they can lead to relatively high doses to personnel who stand close to the primary radiation field and are mostly exposed to radiation scattered by the patient. For the adequate dosimetry of the scattered photons, APDs must be able to respond to low-energy [10-100 keV] and pulsed radiation with relatively high instantaneous dose rates. An intercomparison of five APD models deemed suitable for application in interventional radiology was organised in March 2007. The intercomparison used pulsed and continuous radiation beams, at CEA-LIST (Saclay (France)) and IRSN (Fontenay-aux-Roses (France)), respectively. A specific configuration, close to the clinical practice, was considered. The reference dose, in terms of Hp(10), was derived from air kerma measurements and from the measured and calculated energy distributions of the scattered radiation field. Additional Monte Carlo calculations were performed to investigate the energy spectra for different experimental conditions of the intercomparison. The results of this intercomparison are presented in this work and indicate which APDs are able to provide a correct response when used in the specific low-energy spectra and dose rates of pulsed X-rays encountered in interventional radiology. (authors)

EURADOS intercomparison 2006 to harmonise European early warning dosimetry systems

International Nuclear Information System (INIS)

Dombrowski, H.; Neumaier, S.; Thompson, I. M. G.; Wissmann, F.

2009-01-01

In 2006, the European Radiation Dosimetry (EURADOS) Working Group on Environmental Radiation Monitoring (WG3) organised a third European intercomparison of dosimetry systems operated in national early warning networks. Similar to the intercomparisons in 1999 and 2002, the main aim of this exercise was to support the process of harmonisation of area monitoring in Europe by providing the network operators with basic information on the calibration and performance of their dosimetry systems. In order to characterise these systems, their following basic parameters were investigated: the response to terrestrial and cosmic radiation, the detectors' inherent background, the response at low dose rates, the energy dependence of the response as well as the sensitivity of the detector systems to small changes of the dose rate in a natural environmental radiation field. In the 2006 EURADOS intercomparison, scientists from seven countries participated to study the characteristics of 11 detector systems. All results are presented in terms of the operational quantity ambient dose equivalent, H * (10). The advent of this quantity has caused the development of new detector systems for area monitoring. Some of these new systems participated in a EURADOS intercomparison for the first time. The results are consistently presented together with uncertainties so that statistical effects can be distinguished from real detector features, which improves the interpretation of the results. By using the results of this intercomparison, some detectors were re-calibrated. The achievable improvements concerning harmonisation in dose-rate measurements in the natural environment are discussed. (authors)

Optimal interpolation method for intercomparison of atmospheric measurements.

Science.gov (United States)

Ridolfi, Marco; Ceccherini, Simone; Carli, Bruno

2006-04-01

Intercomparison of atmospheric measurements is often a difficult task because of the different spatial response functions of the experiments considered. We propose a new method for comparison of two atmospheric profiles characterized by averaging kernels with different vertical resolutions. The method minimizes the smoothing error induced by the differences in the averaging kernels by exploiting an optimal interpolation rule to map one profile into the retrieval grid of the other. Compared with the techniques published so far, this method permits one to retain the vertical resolution of the less-resolved profile involved in the intercomparison.

Directory of certificates of compliance for radioactive materials packages. Volume 3, Revision 14: Report of NRC approved quality assurance programs for radioactive materials packages

International Nuclear Information System (INIS)

1994-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

The Program for Climate Model Diagnosis and Intercomparison (PCMDI) Software Development: Applications, Infrastructure, and Middleware/Networks

Energy Technology Data Exchange (ETDEWEB)

Williams, Dean N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2011-06-30

The status of and future plans for the Program for Climate Model Diagnosis and Intercomparison (PCMDI) hinge on software that PCMDI is either currently distributing or plans to distribute to the climate community in the near future. These software products include standard conventions, national and international federated infrastructures, and community analysis and visualization tools. This report also mentions other secondary software not necessarily led by or developed at PCMDI to provide a complete picture of the overarching applications, infrastructures, and middleware/networks. Much of the software described anticipates the use of future technologies envisioned over the span of next year to 10 years. These technologies, together with the software, will be the catalyst required to address extreme-scale data warehousing, scalability issues, and service-level requirements for a diverse set of well-known projects essential for predicting climate change. These tools, unlike the previous static analysis tools of the past, will support the co-existence of many users in a productive, shared virtual environment. This advanced technological world driven by extreme-scale computing and the data it generates will increase scientists’ productivity, exploit national and international relationships, and push research to new levels of understanding.

Intercomparison of transuranics in sediments

International Nuclear Information System (INIS)

Nilsson, K.

1981-01-01

This paper summarizes the results of a recent intercomparison of transuranic analyses in Nordic sediments undertaken by five laboratories. Five different samplers were tested to determine their consistency and utility. Plutonium and americium were determined in all the samples and the analysis of variance is discussed. (author)

IAEA reference materials for quality assurance of marine radioactivity measurements

International Nuclear Information System (INIS)

Povinec, P.P.; Pham, M.K.

2001-01-01

The IAEA's Marine Environment Laboratory has been assisting laboratories in Analytical Quality Control Services (AQCS) for the analysis of radionuclides in the marine environment since the early seventies. AQCS through world-wide and regional intercomparison exercises and the provision of reference methods and reference materials (RM) have been recognized as an important component of quality assurance/quality control. A total of 43 intercomparison exercises were organized and 37 RM were produced for marine radioactivity studies. All important marine matrices were covered, e.g., seawater, marine sediments of different chemical compositions, fish, shellfish and seaplants. RM were prepared from samples collected at contaminated sites (e.g., the Irish Sea, the Baltic Sea, the Arabian Sea, Mururoa and Bikini Atolls, etc.) as well as from sites affected only by global fallout (e.g., the Pacific Ocean). Available RM are listed in the IAEA biennial catalogue and can be purchased at a minimal price. An overview of prepared RM for radionuclides in marine matrices is presented and discussed in more detail. (author)

Developing a public involvement policy for the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Smith, S.; Summerson, J.; Gleason, M.E.; Reyes, P.C.

1994-01-01

The Civilian Radioactive Waste Management Program is entering its second decade. Given the Department of Energy's current efforts toward openness and culture change, the role of stakeholders is likely to evolve throughout the 1990s to enable greater participation by these external parties in making program decisions. Although the program has a tradition of inviting its stakeholders to review and comment on its activities, it also is known for employing on occasion what has been derisively called a open-quotes decide-announce-defendclose quotes strategy. Program efforts to involve the public have come under considerable criticism for being inadequate, inconsistent, lacking in follow-through, and offered on a sporadic and selective basis. The program is vulnerable to these criticisms because ground rules for public involvement have never been firmly established as part of the program's routine operations. This deficiency has contributed, in part, to stakeholder doubts about the program's sincerity in engaging in a meaningful dialogue with them. The program and its stakeholders both could benefit from an official public involvement policy that would serve as a guidepost for interactions between program officials and stakeholders. Such a policy, developed in concert with stakeholders, would ensure that all parties understand how stakeholder participation is to occur. This paper reviews (1) events establishing the need for a formal public involvement policy; (2) public involvement initiatives that will inform the process of developing a new policy; (3) current efforts to develop a Department of Energy public involvement policy; and (4) key elements for inclusion in a public involvement policy developed specifically for the Civilian Radioactive Waste Management Program

National Syrian Program for Radioactive Waste Management

International Nuclear Information System (INIS)

Othman, I.; Takriti, S.

2009-06-01

A national plan for radioactive waste management has been presented. It includes identifying, transport, recording, classifying, processing and disposal. It is an important reference for radioactive waste management for those dealing with radioactive waste, and presents a complete protection to environemnt and people. (author)

Low-level waste (LLW) reclamation program for the Point Lepreau Solid Radioactive Waste Management Facility (SRWMF)

International Nuclear Information System (INIS)

Mersereau, M.; McIntyre, K.

2006-01-01

Low level radioactive waste retrieved from intermediate storage vaults at Point Lepreau Generating Station has been sorted to remove the non-radioactive portion. The program began with trials to validate procedures and equipment, followed by a production run that is on-going. Waste boxes are opened and sorted at a ventilated sorting table. The sorted waste is directed to the station's free-release ('Likely Clean') waste stream or to the radioactive waste stream, depending on activity measurements. The radioactive waste content of the sorted materials has been reduced by 96% (by mass) using this process. (author)

Low-level waste (LLW) reclamation program for the Point Lepreau Solid Radioactive Waste Management Facility (SRWMF)

Energy Technology Data Exchange (ETDEWEB)

Mersereau, M.; McIntyre, K. [Point Lepreau Generating Station, Lepreau, New Brunswick (Canada)]. E-mail: MMersereau@nbpower.com; KMcIntyre@nbpower.com

2006-07-01

Low level radioactive waste retrieved from intermediate storage vaults at Point Lepreau Generating Station has been sorted to remove the non-radioactive portion. The program began with trials to validate procedures and equipment, followed by a production run that is on-going. Waste boxes are opened and sorted at a ventilated sorting table. The sorted waste is directed to the station's free-release ('Likely Clean') waste stream or to the radioactive waste stream, depending on activity measurements. The radioactive waste content of the sorted materials has been reduced by 96% (by mass) using this process. (author)

Management of radioactive materials and wastes: status, stakes and perspectives

International Nuclear Information System (INIS)

Champion, Didier; Devin, Patrick; Tanguy, Loic; Bernard, Herve; Minon, Jean-Paul; Leclaire, Arnaud; Gilli, Ludivine; Lheureux, Yves; Pescatore, Claudio; Barbey, Pierre; Schneider, Thierry; Gay, Didier; Forest, Isabelle; Hemidy, Pierre-Yves; Baglan, Nicolas; Desnoyers, Bruno; Pieraccini, Michel; Poncet, Philippe; Seguin, Bertille; Calvez, Marianne; Leclerc, Elisabeth; Bancelin, Estelle; Fillion, Eric; Segura, Yannick; Vernaz, Etienne; Granier, Guy; De Preter, Peter; Petitfrere, Michael; Laye, Frederic; Nakamura, Takashi; Gin, Stephane; Lebaron-Jacobs, Laurence; Dinant, Sophie; Vacquier, Blandine; Crochon, Philippe; Griffault, Lise; Smith, Graham

2013-10-01

studies - Safety and continuous improvements (Estelle BANCELIN - EDF, Eric FILLION - CEA); - Comparative analysis between a very-low level waste storage facility and a conventional waste storage facility (Yannick SEGURA - ANDRA); - Research on nuclear wastes (Etienne VERNAZ - CEA); - Wastes characterization and intercomparison exercise (Guy GRANIER - CETAMA); - Belgium situation with respect to the long-term management of radioactive wastes (Peter DE PRETER - ONDRAF); - Wastes management in post-accident situation - the CODIRPA works (Frederic LAYE - ASN); - Wastes management in contaminated areas: Japanese situation and experience feedback 2 years after the Fukushima accident (Takashi NAKAMURA - JANUS); Radioactive waste management in the USA (Stephane GIN - CEA) - Monitoring and environmental impact of radioactive waste storage sites (Sophie DINANT - ANDRA); - Lessons learnt from a mortality and cancer impact study in the vicinity of the Aube storage facility (Blandine VACQUIER - InVS); - Evaluation of dosimetric impacts of uranium mine tailings using modeling and comparison with environmental monitoring results (Philippe CROCHON - AREVA); - Cigeo's long-term impact - methodology and presentation of the biosphere approach (Lise GRIFFAULT - ANDRA); - Evaluation of long-term impacts of radioactive waste storage facilities - Lessons learnt and perspectives of the BIOPROTA program (Graham SMITH - GMS Abingdon Ltd)

Optimization of radioactive waste management system by application of multiobjective linear programming

International Nuclear Information System (INIS)

Shimizu, Yoshiaki

1981-01-01

A mathematical procedure is proposed to make a radioactive waste management plan comprehensively. Since such planning is relevant to some different goals in management, decision making has to be formulated as a multiobjective optimization problem. A mathematical programming method was introduced to make a decision through an interactive manner which enables us to assess the preference of decision maker step by step among the conflicting objectives. The reference system taken as an example is the radioactive waste management system at the Research Reactor Institute of Kyoto University (KUR). Its linear model was built based on the experience in the actual management at KUR. The best-compromise model was then formulated as a multiobjective linear programming by the aid of the computational analysis through a conventional optimization. It was shown from the numerical results that the proposed approach could provide some useful informations to make an actual management plan. (author)

Quality assurance program description for shipping packages of radioactive material

International Nuclear Information System (INIS)

1978-01-01

This quality assurance plan describes the quality assurance program at the Pacific Northwest Laboratory (PNL), for shipping packages of radioactive material. The purpose of this report is to describe how PNL will comply with the Code of Federal Regulations, Title 10, Part 71, Appendix E. In compliance with the instructions from the Nuclear Regulatory Commission (NRC), the 18 criteria from Appendix E are covered

Second Latin American intercomparison on internal dose assessment

International Nuclear Information System (INIS)

Rojo, A.; Puerta, N.; Gossio, S.; Gomez Parada, I.; Cruz Suarez, R.; Lopez, E.; Medina, C.; Lastra Boylan, J.; Pinheiro Ramos, M.; Mora Ramirez, E.; Alves dos Reis, A.; Yanez, H.; Rubio, J.; Vironneau Janicek, L.; Somarriba Vanegas, F.; Puerta Ortiz, J.; Salas Ramirez, M.; Lopez Bejerano, G.; Da Silva, T.; Miri Oliveira, C.; Teran, M.; Alfaro, M.; Garcia, T.; Angeles, A.; Dure Romero, E.; Farias de Lima, F.

2016-01-01

Internal dosimetry intercomparisons are essential for the verification of applied models and the consistency of results. To that aim, the First Regional Intercomparison was organised in 2005, and that results led to the Second Regional Intercomparison Exercise in 2013, which was organised in the frame of the RLA 9/066 and coordinated by Autoridad Regulatoria Nuclear of Argentina. Four simulated cases covering intakes of 131 I, 137 Cs and Tritium were proposed. Nineteen centres from thirteen different countries participated in this exercise. This paper analyses the participants' results in this second exercise in order to test their skills and acquired knowledge, particularly in the application of the IDEAS Guidelines. It is important to highlight the increased number of countries that participated in this exercise compared with the first one and, furthermore, the improvement in the overall performance. The impact of the International Atomic Energy Agency (IAEA) Projects since 2003 has led to a significant enhancement of internal dosimetry capabilities that strengthen the radiation protection of workers. (authors)

The health physics programs in low-level radioactive waste management at the Institute of Nuclear Energy Research, Republic of China

International Nuclear Information System (INIS)

Chen, W-L.

1986-01-01

The primary mission of the health physics programs in low-level radioactive management is to ensure radiation safety for personnel and environment of the Institute of Nuclear Energy Research (INER), and also for the general public surrounding INER. In view of the above, the Health Physics programs in low-level radioactive waste management are divided into three sub-programs: the radiation control program, the environmental survey and bioassay program, and the radiation dosimetry supporting program. The general guidelines, responsibilities, and performance of these programs will be discussed in this paper in the following order. The responsibility of radiation control group is to conduct area monitoring and radiation surveillance for the radioactive waste treatment workers. It includes the control of radiation field level of the working area, servicing personnel dosimeters, instruction on radiation safety, and handling of radiation accidents. The responsibility of the environmental survey and bioassay group is to perform environmental surveys and bioassays. Environmental gamma monitoring stations were installed both on-site and off-site at INER. For bioassays, urine samples are taken from radioactive waste treatment workers, and for internal contamination checks of workers, total body counting systems are being used. The main responsibility of the radiation dosimetry group is to provide radiation dosimetrical support to the radiation control group and the environmental survey and bioassay group. Some typical work of the radiation dosimetry group is the qualitative assay and quantitative determination of radioactive samples, and calibration of dosimeters and survey meters

RCA/IAEA third external dosimetry intercomparison in East Asia

International Nuclear Information System (INIS)

Momose, T.; Yamamoto, H.; Cruz Suarez, R.

2005-01-01

Full text: Several intercomparison exercises were organized by the International Atomic Energy Agency (IAEA) on the determination of operational quantities at the regional or interregional basis. These exercises revealed significant differences in the approach, methods and assumptions, and consequently in the measurement results obtained by participating laboratories. In the East Asia region, the third phase of the Hp(10) intercomparison, organized within the frame of the Regional Cooperation Agreement (RCA) as a follow-up to previous exercises during 1990-92 and 1995-96, was completed mid-2004. The first phase grouped 25 laboratories from 16 member states, and 4 Secondary Standards Dosimetry Laboratories irradiated dosimeters in 6 different qualities for photon and beta radiations. In the second phase, 23 laboratories from 16 member states participated, and 3 Secondary Standards Dosimetry Laboratories provided irradiation in 5 different radiation qualities simulating workplace fields. The results of the second phase for the determination of operational quantities Hp(d) were satisfactory for all participating Member States, with marked improvement from the first phase; the laboratories demonstrated good performance in both quantities tested. These results underline the importance of such an intercomparison programme as a key element towards the harmonization of quantities and units on an international level. This paper presents the results of this RCA/IAEA intercomparison, and also the forthcoming RCA activities supporting intercomparison runs for the assessment of occupational exposure. Member states strongly recommend that the IAEA continue acting as a focal point for, inter alia, training in all forms, particularly in measurements and dosimetry techniques. This exercise also stressed the importance for the IAEA to take an active role in establishing a network of monitoring laboratories for radiation protection purposes, as it would provide for better information

Low-level radioactive waste research program plan

International Nuclear Information System (INIS)

O'Donnell, E.; Lambert, J.

1989-11-01

The Waste Management Branch, Division of Engineering, Office of Nuclear Regulatory Research, has developed a strategy for conducting research on issues of concern to the US Nuclear Regulatory Commission (NRC) in its efforts to ensure safe disposal of low-level radioactive waste (LLW). The resulting LLW research program plan provides an integrated framework for planning the LLW research program to ensure that the program and its products are responsive and timely for use in NRC's LLW regulatory program. The plan discusses technical and scientific issues and uncertainties associated with the disposal of LLW, presents programmatic goals and objectives for resolving them, establishes a long-term strategy for conducting the confirmatory and investigative research needed to meet these goals and objectives, and includes schedules and milestones for completing the research. Areas identified for investigation include waste form and other material concerns, failure mechanisms and radionuclide releases, engineered barrier performance, site characterization and monitoring, and performance assessment. The plan proposes projects that (1) analyze and test actual LLW and solidified LLW under laboratory and field conditions to determine leach rates and radionuclide releases, (2) examine the short- and long-term performance of concrete-enhanced LLW burial structures and high-integrity containers, and (3) attempt to predict water movement and contaminant transport through low permeability saturated media and unsaturated porous media. 4 figs., 3 tabs

Soil sampling intercomparison exercise by selected laboratories of the ALMERA Network

International Nuclear Information System (INIS)

2009-01-01

The IAEA's Seibersdorf Laboratories in Austria have the programmatic responsibility to provide assistance to Member State laboratories in maintaining and improving the reliability of analytical measurement results, both in radionuclide and trace element determinations. This is accomplished through the provision of reference materials of terrestrial origin, validated analytical procedures, training in the implementation of internal quality control, and through the evaluation of measurement performance by the organization of worldwide and regional interlaboratory comparison exercises. The IAEA is mandated to support global radionuclide measurement systems related to accidental or intentional releases of radioactivity in the environment. To fulfil this obligation and ensure a reliable, worldwide, rapid and consistent response, the IAEA coordinates an international network of analytical laboratories for the measurement of environmental radioactivity (ALMERA). The network was established by the IAEA in 1995 and makes available to Member States a world-wide network of analytical laboratories capable of providing reliable and timely analysis of environmental samples in the event of an accidental or intentional release of radioactivity. A primary requirement for the ALMERA members is participation in the IAEA interlaboratory comparison exercises, which are specifically organized for ALMERA on a regular basis. These exercises are designed to monitor and demonstrate the performance and analytical capabilities of the network members, and to identify gaps and problem areas where further development is needed. In this framework, the IAEA organized a soil sampling intercomparison exercise (IAEA/SIE/01) for selected laboratories of the ALMERA network. The main objective of this exercise was to compare soil sampling procedures used by different participating laboratories. The performance evaluation results of the interlaboratory comparison exercises performed in the framework of

Annual radioactive waste tank inspection program -- 1993

International Nuclear Information System (INIS)

McNatt, F.G. Sr.

1994-05-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1993 to evaluate these vessels, and evaluations based on data accrued by inspections made since the tanks were constructed, are the subject of this report. The 1993 inspection program revealed that the condition of the Savannah River Site waste tanks had not changed significantly from that reported in the previous annual report. No new leaksites were observed. No evidence of corrosion or materials degradation was observed in the waste tanks. However, degradation was observed on covers of the concrete encasements for the out-of-service transfer lines to Tanks 1 through 8

A Methodological Inter-Comparison of Gridded Meteorological Products

Science.gov (United States)

Newman, A. J.; Clark, M. P.; Longman, R. J.; Giambelluca, T. W.; Arnold, J.

2017-12-01

Here we present a gridded meteorology inter-comparison using the state of Hawaíi as a testbed. This inter-comparison is motivated by two general goals: 1) the broad user community of gridded observation based meteorological fields should be aware of inter-product differences and the reasons they exist, which allows users to make informed choices on product selection to best meet their specific application(s); 2) we want to demonstrate the utility of inter-comparisons to meet the first goal, yet highlight that they are limited to mostly generic statements regarding attribution of differences that limits our understanding of these complex algorithms and obscures future research directions. Hawaíi is a useful testbed because it is a meteorologically complex region with well-known spatial features that are tied to specific physical processes (e.g. the trade wind inversion). From a practical standpoint, there are now several monthly climatological and daily precipitation and temperature datasets available that are being used for impact modeling. General conclusions that have emerged are: 1) differences in input station data significantly influence product differences; 2) prediction of precipitation occurrence is crucial across multiple metrics; 3) derived temperature statistics (e.g. diurnal temperature range) may have large spatial differences across products; and 4) attribution of differences to methodological choices is difficult and may limit the outcomes of these inter-comparisons, particularly from a development viewpoint. Thus, we want to continue to move the community towards frameworks that allow for multiple options throughout the product generation chain and allow for more systematic testing.

IAEA coordinated research program on the evaluation of solidified high-level radioactive waste products

International Nuclear Information System (INIS)

Grover, J.R.; Schneider, K.J.

1979-01-01

A coordinated research program on the evaluation of solidified high-level radioactive waste products has been active with the IAEA since 1976. The program's objectives are to integrate research and to provide a data bank on an international basis in this subject area. Results and considerations to date are presented

Physical countermeasures to sustain acceptable living and working conditions in radioactively contaminated residential areas

DEFF Research Database (Denmark)

Andersson, Kasper Grann; Roed, Jørn; Eged, K.

2003-01-01

The Chernobyl accident highlighted the need in nuclear preparedness for robust, effective and sustainable countermeasure strategies for restoration of radioactively contaminated residential areas. Under the EC-supported STRATEGY project a series ofinvestigations were made of countermeasures...... that were deemed potentially applicable for implementation in such events in European Member States. The findings are presented in this report, in a standardised datasheet format to clarify the features of theindividual methods and facilitate intercomparison. The aspects of averted doses and management...

Calibration and intercomparison methods of dose calibrators used in nuclear medicine facilities

International Nuclear Information System (INIS)

Costa, Alessandro Martins da

1999-01-01

Dose calibrators are used in most of the nuclear medicine facilities to determine the amount of radioactivity administered to a patient in a particular investigation or therapeutic procedure. It is therefore of vital importance that the equipment used presents good performance and is regular;y calibrated at a authorized laboratory. This occurs of adequate quality assurance procedures are carried out. Such quality control tests should be performed daily, other biannually or yearly, testing, for example, its accuracy and precision, the reproducibility and response linearity. In this work a commercial dose calibrator was calibrated with solution of radionuclides used in nuclear medicine. Simple instrument tests, such as response linearity and the response variation of the source volume increase at a constant source activity concentration, were performed. This instrument can now be used as a working standard for calibration of other dose calibrators/ An intercomparison procedure was proposed as a method of quality control of dose calibrators used in nuclear medicine facilities. (author)

Report on the Intercomparison Exercises 1993

DEFF Research Database (Denmark)

Aminot, A.; Boer, J. de; Cofino, W.

This report covers the intercomparison exercises - 1993 of the project Quasimeme - Quality Assurance of Information for Marine Environmental Monitoring in Europe. The report is prepared under contract for the measurement and testing programme (BCR) of the European Community....

Radioactive contamination of environment

International Nuclear Information System (INIS)

Chytil, I.

1981-01-01

A computer model is discussed describing radioactivity transport between the source and the organism. The model is to be applied in assessing the effect of a nuclear installation on the organism. Fortran and Pascal appear to be the most appropriate computer languages. With respect to internal memory requirements, the program file is estimated to consist of a control program and a number of subprograms. Upon setting the radioactivity transport and the output requirements the control program should recall the necessary subprograms. The program file should allow the complete data file and the solutions of all possible radioactivity transport variants to be inputted. It is envisaged that several subprograms will be available for one type of radioactivity transport, this depending on different accuracy of the transport description. Thus, the requirements for input data will also differ. (Z.M.)

Results of the 1999. Intercomparison of Individual Monitoring Systems under the IAEA Model Project RLA/9/030

International Nuclear Information System (INIS)

Da Silva, Teogenes

2000-01-01

In this report the results of the second phase of the intercomparison program within the framework of the IAEA model project RLA/9/030 are presented. In this second phase the objective was to evaluate the performance in terms of the quantity personal dose equivalent, Hp (10) for x and gamma radiation in the energy range form 20 KeV to 1.25 MeV. The main purpose of phase II should be the verification of the quality and reliability of the personnel monitoring system of each participating country. The Centro de Desenvolvimento da Tecnologia Nuclear was the reference laboratory that verified the performance of the participant laboratories. The following countries were invited to participate in the 1999 intercomparison: Bolivia, Colombia, Costa Rica, Dominican Republic, el Salvador, Guatemala, Jamaica, Nicaragua, Panama and Paraguay

The role of intercomparisons and intercalibrations in the improvement of internal dose assessment

International Nuclear Information System (INIS)

Griffith, R.V.

2000-01-01

In vivo monitoring and dose assessment is a highly technical field. Moreover, it is carried out by a relatively small number of specialists. A number of technical steps can be taken to improve internal dosimetry programmes. However, one of the most valuable activities for overall improvement of measurement programmes is active participation in national and international intercomparisons and intercalibrations. These bring a number of benefits to the internal dosimetry programme, including validation of measurement practices, harmonisation of techniques, information exchange, and training. The number of intercalibration and intercomparison activities conducted on the national and international level has grown in recent years. These activities may involve actual measurement programmes or calculation exercises to compare approaches used for assessment of internal dose from measurement results. When conducted effectively such programmes are a highly cost effective use of limited resources. They also contribute to the credibility of the overall dosimetry process. Intercomparisons should be an important component of the in vivo measurement programme. Cooperation between the organisers of various intercomparison activities is essential to avoid unnecessary duplication and ensure the most effective use of the participants' time and energy. Future activities should address the use of simplified phantoms and source arrays to expedite shipping, reduce cost, and contribute to more timely conduct of intercomparisons. It is also important that managers and regulatory authorities be prepared to support intercomparison and intercalibration programmes. (author)

Performance of dichromate dosimetry systems in calibration and dose intercomparison

International Nuclear Information System (INIS)

Bof, E.S.; Smolko, E.

1999-01-01

This report presents the results of the High Dose Dosimetry Laboratory of Argentina during ten years of international intercomparisons for high dose with the International Dose Assurance Service (IDAS) of the IAEA, using the standard high dose dichromate dosimetry system, and the results of a high dose intercomparison regional exercise in which our Laboratory acted as a reference laboratory, using the standard high dose and low dose dichromate dosimetry system. (author)

Traceability system for radioactivity standards in Japan

International Nuclear Information System (INIS)

Hino, Yoshio

2000-01-01

The electrotechnical laboratory (ETL) is the one of the largest national research institute, affiliated with the Ministry of International Trade and Industry (MITI). The ETL has a role to maintain the national standards of electricity, acoustics, visible light, ionizing radiation and radioactivity. The primary radioactivity standards have been established in ETL mainly with the 4πβ-γ coincidence method. The liquid scintillation counters and multi-wire proportional counters are also used for pure-beta and surface emission rate standards, respectively. As for the traceability, the primary standard sources are transferred to the Japan Radio Isotope Association (JRIA), and the JRIA measure these sources to calibrate their secondary standard equipments such as high pressurized 4π ionization chambers, high pore Ge and Nal (Tl) gamma spectrometers. The primary sources are also sent to the BIPM and neighboring countries for the intercomparisons to keep the consistency of the national standards. In this paper, these measurement techniques for the primary standardization and transfer system will be introduced, and some results of comparisons for certificate the traceability system will be described. (author)

An integrated approach to strategic planning in the civilian high-level radioactive waste management program

International Nuclear Information System (INIS)

Sprecher, W.M.; Katz, J.; Redmond, R.J.

1992-01-01

This paper describes the approach that the Office of Civilian Radioactive Waste Management (OCRWM) of the Department of Energy (DOE) is taking to the task of strategic planning for the civilian high-level radioactive waste management program. It highlights selected planning products and activities that have emerged over the past year. It demonstrates that this approach is an integrated one, both in the sense of being systematic on the program level but also as a component of DOE strategic planning efforts. Lastly, it indicates that OCRWM strategic planning takes place in a dynamic environment and consequently is a process that is still evolving in response to the demands placed upon it

The fourth radioactive waste management program of the Commission of the European Communities (1990-1994)

International Nuclear Information System (INIS)

Orlowski, S.; Schaller, K.H.; Simon, R.

1992-01-01

The fourth radioactive waste management program 1990-1994 is aimed at perfecting and demonstrating a system of management of radioactive waste, including unprocessed irradiated fuels where these are considered as waste, which will ensure, at the various stages, the best possible protection of man and the environment. In particular, research continues on the characterization and qualification of the various barriers, both engineered and natural (geological) considered in the multiple barrier disposal concept, and the findings are used to evaluate the long-term safety of this waste disposal concept. The program is implemented mainly through shared-cost research contracts with appropriate organizations, undertakings and companies - public or private - established in the European Community Member States. It is composed of two parts; Part A deals with waste management studies and associated research and development actions, whereas in Part B, the construction and operation of underground pilot and/or site validation facilities for deep geological disposal of radioactive waste open to Community joint activities are covered. (author)

Intercomparison measurements of activity of 99mTc and 131I in nuclear medicine services at Recife city, Pernambuco state, Brazil

International Nuclear Information System (INIS)

Barreto, F.C.P.; Santos, M.A.P dos; Oliveira, M.L.; Lima, F.F. de

2007-01-01

The aim of this work is to present the results of the first round of intercomparison measurements of activity of 99m Tc and 131 I. This round was carried out in Recife/PE. Six nuclear medicine services (NMS), public and private, participated in this intercomparison. Additionally to the activity measurement, some information about equipment (calibration and quality control program) and human resources was obtained. All NMS participants complied with the limit established by CNEN for the accuracy of measurement (+- 10%) for 99m Tc and 131 I. Measurements will be repeated for 99m Tc and 131 I, and additional rounds will be performed including different radionuclides. (author)

Users manual. Pursuit program of use licenses of radioactive material or generator equipment of ionizing radiations

International Nuclear Information System (INIS)

Becerril M, V.M.; Villarreal, J.E.

1992-05-01

The objective of the program 'Databases for the pursuit of licenses of use of radioactive material', it consists on the application of a computer system carried out in dbase IV that it allows the control of the all the information related with those licenses for use, possession and storage of radioactive material or generator equipment of ionizing radiations. (Author)

Atmospheric Correction Inter-comparison Exercise (ACIX)

Science.gov (United States)

Vermote, E.; Doxani, G.; Gascon, F.; Roger, J. C.; Skakun, S.

2017-12-01

The free and open data access policy to Landsat-8 (L-8) and Sentinel-2 (S-2) satellite imagery has encouraged the development of atmospheric correction (AC) approaches for generating Bottom-of-Atmosphere (BOA) products. Several entities have started to generate (or plan to generate in the short term) BOA reflectance products at global scale for L-8 and S-2 missions. To this end, the European Space Agency (ESA) and National Aeronautics and Space Administration (NASA) have initiated an exercise on the inter-comparison of the available AC processors. The results of the exercise are expected to point out the strengths and weaknesses, as well as communalities and discrepancies of various AC processors, in order to suggest and define ways for their further improvement. In particular, 11 atmospheric processors from five different countries participate in ACIX with the aim to inter-compare their performance when applied to L-8 and S-2 data. All the processors should be operational without requiring parametrization when applied on different areas. A protocol describing in details the inter-comparison metrics and the test dataset based on the AERONET sites has been agreed unanimously during the 1st ACIX workshop in June 2016. In particular, a basic and an advanced run of each of the processor were requested in the frame of ACIX, with the aim to draw robust and reliable conclusions on the processors' performance. The protocol also describes the comparison metrics of the aerosol optical thickness and water vapour products of the processors with the corresponding AERONET measurements. Moreover, concerning the surface reflectances, the inter-comparison among the processors is defined, as well as the comparison with the MODIS surface reflectance and with a reference surface reflectance product. Such a reference product will be obtained using the AERONET characterization of the aerosol (size distribution and refractive indices) and an accurate radiative transfer code. The inter-comparison

Preliminary Calculation of the Indicators of Sustainable Development for National Radioactive Waste Management Programs

International Nuclear Information System (INIS)

Cheong, Jae Hak; Park, Won Jae

2003-01-01

As a follow up to the Agenda 21's policy statement for safe management of radioactive waste adopted at Rio Conference held in 1992, the UN invited the IAEA to develop and implement indicators of sustainable development for the management of radioactive waste. The IAEA finalized the indicators in 2002, and is planning to calculate the member states' values of indicators in connection with operation of its Net-Enabled Waste Management Database system. In this paper, the basis for introducing the indicators into the radioactive waste management was analyzed, and calculation methodology and standard assessment procedure were simply depicted. In addition, a series of innate limitations in calculation and comparison of the indicators was analyzed. According to the proposed standard procedure, the indicators for a few major countries including Korea were calculated and compared, by use of each country's radioactive waste management framework and its practices. In addition, a series of measures increasing the values of the indicators was derived so as to enhance the sustainability of domestic radioactive waste management program.

Nuclear accident dosimetry, Report on the Third IAEA intercomparison experiment at Vinca, Yugoslavia

Energy Technology Data Exchange (ETDEWEB)

NONE

1977-03-15

The objective of this report is to present the results of the third IAEA intercomparison experiment held at the Boris Kidric Institute, Vinca, in May 1973. These experiments were a part of multi laboratory intercomparison programme sponsored by the IAEA for evaluation of nuclear accident dosimetry systems that ought to provide adequate information in the event of criticality accidents. This report deals with the data concerning the Third intercomparison experiments in which the RB reactor at Vinca was used as a source of mixed radiation.

Site Study Plan for background environmental radioactivity, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

The Background Environmental Radioactivity Site Study Plan describes a field program consisting of an initial radiological survey and a radiological sampling program. The field program includes measurement of direct radiation and collection and analysis of background radioactivity samples of air, precipitation, soil, water, milk, pasture grass, food crops, meat, poultry, game, and eggs. The plan describes for each study: the need for the study, the study design, data management and use, schedule of proposed activities, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project (SRP) Requirements Document. 50 refs., 11 figs., 7 tabs

SECOND LATIN AMERICAN INTERCOMPARISON ON INTERNAL DOSE ASSESSMENT.

Science.gov (United States)

Rojo, A; Puerta, N; Gossio, S; Gómez Parada, I; Cruz Suarez, R; López, E; Medina, C; Lastra Boylan, J; Pinheiro Ramos, M; Mora Ramírez, E; Alves Dos Reis, A; Yánez, H; Rubio, J; Vironneau Janicek, L; Somarriba Vanegas, F; Puerta Ortiz, J; Salas Ramírez, M; López Bejerano, G; da Silva, T; Miri Oliveira, C; Terán, M; Alfaro, M; García, T; Angeles, A; Duré Romero, E; Farias de Lima, F

2016-09-01

Internal dosimetry intercomparisons are essential for the verification of applied models and the consistency of results'. To that aim, the First Regional Intercomparison was organised in 2005, and that results led to the Second Regional Intercomparison Exercise in 2013, which was organised in the frame of the RLA 9/066 and coordinated by Autoridad Regulatoria Nuclear of Argentina. Four simulated cases covering intakes of (131)I, (137)Cs and Tritium were proposed. Ninteen centres from thirteen different countries participated in this exercise. This paper analyses the participants' results in this second exercise in order to test their skills and acquired knowledge, particularly in the application of the IDEAS Guidelines. It is important to highlight the increased number of countries that participated in this exercise compared with the first one and, furthermore, the improvement in the overall performance. The impact of the International Atomic Energy Agency (IAEA) Projects since 2003 has led to a significant enhancement of internal dosimetry capabilities that strengthen the radiation protection of workers. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Radioactive waste management - an educational challenge

International Nuclear Information System (INIS)

Tulenko, J.S.

1991-01-01

University Radioactive Waste Management educational programs are being actively advanced by the educational support activities of the Offices of Civilian Radioactive Waste Management (OCRWM) and Environmental Restoration and Waste Management (ERWM) of the DOE. The DOE fellowship program formats of funding students and requiring a practical research experience (practicum) at a DOE site has helped to combine the academic process with a practical work experience. Support for faculty in these programs is augmenting the benefits of the fellowship programs. The many job opportunities and funding sources for students which currently exists in the radioactive waste management area are fueling an increase in academic programs seeking recognition of their radioactive waste management curriculums

Analysis of laboratory intercomparison data: a matter of independence

Directory of Open Access Journals (Sweden)

Mauro F. Rebelo

2003-05-01

Full Text Available When laboratory intercomparison exercises are conducted, there is no a priori dependence of the concentration of a certain compound determined in one laboratory to that determined by another(s. The same applies when comparing different methodologies. A existing data set of total mercury readings in fish muscle samples involved in a Brazilian intercomparison exercise was used to show that correlation analysis is the most effective statistical tool in this kind of experiments. Problems associated with alternative analytical tools such as mean or paired 't'-test comparison and regression analysis are discussed.

Report on the intercomparison of determinations of {sup 89}Sr, {sup 90}Sr and {sup 137}Cs in liquid milk, A-9 (1975-76)

Energy Technology Data Exchange (ETDEWEB)

NONE

1976-05-01

The ever growing concern of modern societies about environmental pollution imposes serious responsibility on the analytical chemist who is entrusted with the task of monitoring the levels of both radioactive and conventional pollutants in various environmental samples. The main requirement for this service to be effective is that it must furnish reliable i.e. accurate and sufficiently precise results. Hence, the necessity of periodic checking of the analytical performance of any laboratory is now more and more widely recognized. Such a check-up is of importance both to laboratories newly entering the field which are but acquiring the necessary experience, as well as to renowned laboratories in which interchange of the staff, modifications of the procedure or simply excessive routine may also sometimes lead to erroneous results. The analytical quality control service of the IAEA has organized already in the past intercomparisons on the determination of certain radionuclides in simulated liquid milk. The success of these exercises has induced the Agency to organize the new intercomparison of this series in 1975-76, the results of which are presented in this report.

Intercomparison campaign of Contracted Partner Institutes 1997

International Nuclear Information System (INIS)

Reinen, H.A.J.M.; Tijsmans, M.H.; Van Tuinen, S.T.; Overwater, R.M.W.; Aldenkamp, F.J.

1998-01-01

The Dutch National Plan for Nuclear Emergency Planning and Response (EPR) is trained frequently. Intercomparison campaigns and exercises are part of this training for the Contracted Partner Institutes (CPI). The results of an intercomparison campaign in 1997 for the CPI are reported. Two carbon cartridges, one contaminated homogeneously and one inhomogeneously with 131 I, and a water sample contaminated with 134 Cs and 137 Cs were analysed by means of gamma spectroscopy. The results had to be faxed to RIVM within the time limits prescribed in the emergency protocols for CPI, i.e. 2 hours for the cartridges and 24 hours for the water sample. Most CPI reported in time. The results for the inhomogeneously contaminated cartridge are within 25% from the accepted reference value (ARV). For the homogeneously contaminated cartridge the results are within 40% from the ARV. In reality, the contamination of the cartridge will have an exponential profile, with most of the activity in the first few millimeters. In this situation results can be expected to be within 20% from the true value. The results for the water sample are within 5% from the ARV. Although most CPI have applied corrections for coincidence summing for 134 Cs there is still a systematic error of 4% for this nuclide. In regard of the requirements for measurements during emergency situations, the results of this intercomparison campaign are satisfactory

Assessment of the results of the 1998 Intercomparison of Individual Monitoring Systems under IAEA Model Project RLA/9/030

International Nuclear Information System (INIS)

Da Silva, Teogenes

1999-01-01

In this report the results of an intercomparison program within the framework of the IAEA model project RLA/9/030 are presented. This is the first phase of the study the main purpose was to establish a mechanism to identify and improve the current situation of each country as far as the performance of each individual monitoring system is concerned. This phase as was coordinated by Brazil through the Centro de Desenvolvimento da Tecnologia Nuclear that verified the performance of the participant laboratories. The following countries were invited to participate in the 1998 intercomparison: Bolivia, Costa Rica, Guatemala, Nicaragua, Panama, Jamaica and Paraguay. The performance of the laboratories was evaluated for dose assessment in terms of photon dose equivalent Hx

Intercomparison of the air kerma and absorbed dose to water therapy calibrations provided by NRPA and CPRH SSDLs

International Nuclear Information System (INIS)

Morales, J.A.; Campa, R.; Bjerke, H.; Jensen, H.

2001-01-01

The primary goal of any calibration laboratory is to routinely provide calibration services of the highest accuracy. To this end, the laboratory should be equipped with measuring standards of the highest metrological quality traceable to the international measuring system, should establish the appropriate calibration conditions and implement good measuring and working practices. In the case of the Secondary Standard Dosimetry Laboratory (SSDL) members of the IAEA/WHO Network of SSDLs, a great deal of the service quality relies on the appropriate laboratory design and implementation of the recommended calibration practices. Different approaches have been used by SSDLs to guarantee the traceability of the reference standard to the international measurement system. These include calibration of their standards at the IAEA Dosimetry Laboratory, direct calibration at a primary standards laboratory or at a national calibration laboratory. The stability of reference and working standards is usually checked by means of radioactive check source measurements. The most comprehensive way that a laboratory could test its overall measurement competence is by taking part in comparisons with other laboratories of the same or higher metrological level. Regular efforts have been done at the regional scale by organizing such intercomparison exercises where the evaluation of the accuracy of secondary standards or the validation of new calibration methods has been the main objectives. Perhaps, the most important contribution to the assessment of SSDLs quality has been the periodical external measurement audit provided by the IAEA during the last years. Mos of these efforts have, however, only been focused on in-air and recently in-water calibration at the 60 Co radiation quality. An intercomparison of the therapy calibration services available at the SSDLs of the Norwegian Radiation Protection Authority (NRPA) and of the Center for Radiation Protection and Hygiene (CPHR) was organized

Dosimetry audits and intercomparisons in radiotherapy: A Malaysian profile

International Nuclear Information System (INIS)

Noor, Noramaliza M.; Nisbet, A.; Hussein, M.; Chu S, Sarene; Kadni, T.; Abdullah, N.; Bradley, D.A.

2017-01-01

Quality audits and intercomparisons are important in ensuring control of processes in any system of endeavour. Present interest is in control of dosimetry in teletherapy, there being a need to assess the extent to which there is consistent radiation dose delivery to the patient. In this study we review significant factors that impact upon radiotherapy dosimetry, focusing upon the example situation of radiotherapy delivery in Malaysia, examining existing literature in support of such efforts. A number of recommendations are made to provide for increased quality assurance and control. In addition to this study, the first level of intercomparison audit i.e. measuring beam output under reference conditions at eight selected Malaysian radiotherapy centres is checked; use being made of 9 µm core diameter Ge-doped silica fibres (Ge-9 µm). The results of Malaysian Secondary Standard Dosimetry Laboratory (SSDL) participation in the IAEA/WHO TLD postal dose audit services during the period between 2011 and 2015 will also been discussed. In conclusion, following review of the development of dosimetry audits and the conduct of one such exercise in Malaysia, it is apparent that regular periodic radiotherapy audits and intercomparison programmes should be strongly supported and implemented worldwide. The programmes to-date demonstrate these to be a good indicator of errors and of consistency between centres. A total of ei+ght beams have been checked in eight Malaysian radiotherapy centres. One out of the eight beams checked produced an unacceptable deviation; this was found to be due to unfamiliarity with the irradiation procedures. Prior to a repeat measurement, the mean ratio of measured to quoted dose was found to be 0.99 with standard deviation of 3%. Subsequent to the repeat measurement, the mean distribution was 1.00, and the standard deviation was 1.3%. - Highlights: • We review significant factors that impact upon radiotherapy dosimetry, • We carried out the

Intercomparison of JAERI Torso Phantom lung sets

International Nuclear Information System (INIS)

Kramer, Gary H.; Hauck, Barry M.

2000-01-01

During the course of an IAEA sponsored In Vivo intercomparison using the JAERI phantom the Human Monitoring Laboratory was able to intercompare thirteen lung sets made by three suppliers. One set consisted of sliced lungs with planar inserts containing different radionuclides. The others consisted of whole lung sets with the activity homogeneously distributed throughout the tissue substitute material. Radionuclides in the study were: natural uranium, 3% enriched uranium, 241 Am, 238 Pu, 239 Pu, 152 Eu, and 232 Th Except for the 241 Am (59.5 keV) and occasionally one of the 232 Th (209 keV) photopeaks, the lung sets that had radioactivity homogeneously distributed throughout the tissue equivalent lung tissue material showed good agreement. The 241 Am lung set gave a counting efficiency that appeared 25% too high for all overlay plate configurations. This was observed by other participants. It exemplifies that the manufacture of tissue substitute lung sets is still something of a black art. Despite all precautions, this lung set is either inhomogeneous or has had the wrong activity added. Heterogeneity can lead to an error in the activity estimate of a factor of three if the activity was severely localised due to improper mixing. A factor of 1.25, which appears to be the discrepancy, could easily be explained in this way. It will not be known for some time, however, what the true reason is as the participants are still waiting for the destructive analysis of this lung set to determine the 'true' activity. The sliced lungs ( 241 Am, 152 Eu, and U-nat) manufactured by the Human Monitoring Laboratory are in excellent agreement with the other lung sets. The advantages of sliced lung sets and planar sources are manifold. Activity can be distributed in a known and reproducible manner to mimic either a homogeneous or heterogeneous distribution in the lung. Short lived radionuclides can be used. Cost is much less than purchasing or manufacturing lung sets that have the

Office of Civilian Radioactive Waste Management ensuring quality assurance in the waste management program

International Nuclear Information System (INIS)

Kehew, W.J.; Barrett, L.H.

1991-01-01

This paper focuses on the Quality Assurance (QA) program of the U.S. Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). It describes the objectives and philosophy of quality assurance and the plans and activities that OCRWM is undertaking to implement a fully qualified QA program prior to beginning new site characterization activities in Nevada. This paper outlines OCRWM's plan to implement and use a well-designed and effective QA program throughout all elements of the program. (author) 1 fig., 5 refs

Directory of certificates of compliance for radioactive materials packages: Summary report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1987-11-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1987. This directory makes available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Intercomparison of reactive transport models applied to degradation of a concrete / clay interface

International Nuclear Information System (INIS)

Burnol, A.; Blanc, P.; Tournassat, C.; Lassin, A.; Gaucher, E.C.

2005-01-01

Full text of publication follows: Assuming a future disposal of spent nuclear fuel in deep geologic formation of Callovian- Oxfordian argillite in France, concrete will be used extensively to construct the disposal chambers in the host formation, and also as radioactive waste containment material. After being sealed, the repository will become saturated with interstitial waters from the Callovian-Oxfordian argillite, which will produce high pH solutions through interaction with the concrete. The aggressiveness of these alkaline solutions may weaken the clay's confinement properties (bentonite and argillite) with respect to long-lived radionuclides by change of the mineralogy. Conversely, the clayey formation with a high partial pressure of CO 2 represents an aggressive media for the concrete. The hydrogeological and chemical reactions of deep-underground systems are therefore intimately coupled and reactive transport models are increasingly used for performance assessment of nuclear waste disposal [1]. The main objective of this study is to present an intercomparison study using different reactive transport codes, where among PHREEQC1D [2], PHAST [3] and TOUGHREACT [4] applied to determine, in space and time, the extension of the alkaline perturbation and the associated degradation of concrete. The calculations were carried out after the definition of a complete mineralogy for both media. The experimental work made in the European Ecoclay II project [5] allowed a selection of reaction paths and of new phases for the thermodynamic database. Calculations were carried out over a simulated period of 100,000 years at different temperatures. Results of the different codes are compared and discussed. [1] De Windt L., Burnol A., Montarnal P., Van Der Lee.J., (2003) Intercomparison of reactive transport models applied to UO 2 oxidative dissolution and uranium migration., Journal of Contaminant Hydrology, 61, 1-4, 303-312; [2] Parkhurst D.L., Appelo C.A.J. (1999) - User

Intercomparison of TCCON and MUSICA Water Vapour Products

Science.gov (United States)

Weaver, D.; Strong, K.; Deutscher, N. M.; Schneider, M.; Blumenstock, T.; Robinson, J.; Notholt, J.; Sherlock, V.; Griffith, D. W. T.; Barthlott, S.; García, O. E.; Smale, D.; Palm, M.; Jones, N. B.; Hase, F.; Kivi, R.; Ramos, Y. G.; Yoshimura, K.; Sepúlveda, E.; Gómez-Peláez, Á. J.; Gisi, M.; Kohlhepp, R.; Warneke, T.; Dohe, S.; Wiegele, A.; Christner, E.; Lejeune, B.; Demoulin, P.

2014-12-01

We present an intercomparison between the water vapour products from the Total Carbon Column Observing Network (TCCON) and the MUlti-platform remote Sensing of Isotopologues for investigating the Cycle of Atmospheric water (MUSICA), two datasets from ground-based Fourier Transform InfraRed (FTIR) spectrometers with good global representation. Where possible, comparisons to radiosondes are also included. The near-infrared TCCON measurements are optimized to provide precise monitoring of greenhouse gases for carbon cycle studies; however, TCCON's retrievals also produce water vapour products. The mid-infrared MUSICA products result from retrievals optimized to give precise and accurate information about H2O, HDO, and δD. The MUSICA water vapour products have been validated by extensive intercomparisons with H2O and δD in-situ measurements made from ground, radiosonde, and aircraft (Schneider et al. 2012, 2014), as well as by intercomparisons with satellite-based H2O and δD remote sensing measurements (Wiegele et al., 2014). This dataset provides a valuable reference point for other measurements of water vapour. This study is motivated by the limited intercomparisons performed for TCCON water vapour products and limited characterisation of their uncertainties. We compare MUSICA and TCCON products to assess the potential for TCCON measurements to contribute to studies of the water cycle, water vapour's role in climate and use as a tracer for atmospheric dynamics, and to evaluate the performance of climate models. The TCCON and MUSICA products result from measurements taken using the same FTIR instruments, enabling a comparison with constant instrumentation. The retrieval techniques differ, however, in their method and a priori information. We assess the impact of these differences and characterize the comparability of the TCCON and MUSICA datasets.

Dose intercomparison studies for standardization of high-dose dosimetry in Viet Nam

International Nuclear Information System (INIS)

Mai Hoang Hoa; Duong Nguyen Dinh; Kojima, T.

1999-01-01

The Irradiation Center of the Vietnam Atomic Energy Commission (IC-VAEC) is planning to establish a traceability system for high-dose dosimetry and to provide high-dose standards as a secondary standard dosimetry laboratory (SSDL) level in Vietnam. For countries which do not have a standard dosimetry laboratory, the participation in the International Dose Assurance Service (IDAS) operated by the International Atomic Energy Agency (IAEA) is the most common means to verify own dosimetry performance with a certain uncertainty. This is, however, only one-direction dose intercomparison with evaluation by IAEA including unknown parameter at participant laboratories. The SSDL level laboratory should have traceability as well as compatibility, ability to evaluate uncertainties of its own dosimetry performance by itself In the present paper, we reviewed our dosimetry performance through two-way dose intercomparison studies and self-evaluation of uncertainty in our dosimetry procedure. The performance of silver dichromate dosimeter as reference transfer dosimeter in IC-VAEC was studied through two-way blind dose intercomparison experiments between the IC-VAEC and JAERI. As another channel of dose intercomparison with IAEA, alanine dosimeters issued by IDAS were simultaneously irradiated with the IC-VAEC dichromate dosimeters at IC-VAEC and analyzed by IAEA. Dose intercomparison between IC-VAEC and JAERI results into a good agreement (better than ±2.5%), and IDAS results also show similar agreement within ±3.0%. The uncertainty was self-estimated on the basis of the JAERI alanine dosimetry, and a preliminary value of about 1.86% at a 68% confidence level is established. The results from these intercomparisons and our estimation of the uncertainty are consistent. We hope that our experience is valuable to other countries which do not have dosimetry standard laboratories and/or are planning to establish them. (author)

The PSACOIN level 1B exercise: A probabilistic code intercomparison involving a four compartment biosphere model

International Nuclear Information System (INIS)

Klos, R.A.; Sinclair, J.E.; Torres, C.; Mobbs, S.F.; Galson, D.A.

1991-01-01

The probabilistic Systems Assessment Code (PSAC) User Group of the OECD Nuclear Energy Agency has organised a series of code intercomparison studies of relevance to the performance assessment of underground repositories for radioactive wastes - known collectively by the name PSACOIN. The latest of these to be undertaken is designated PSACOIN Level 1b, and the case specification provides a complete assessment model of the behaviour of radionuclides following release into the biosphere. PSACOIN Level 1b differs from other biosphere oriented intercomparison exercises in that individual dose is the end point of the calculations as opposed to any other intermediate quantity. The PSACOIN Level 1b case specification describes a simple source term which is used to simulate the release of activity to the biosphere from certain types of near surface waste repository, the transport of radionuclides through the biosphere and their eventual uptake by humankind. The biosphere sub model comprises 4 compartments representing top and deep soil layers, river water and river sediment. The transport of radionuclides between the physical compartments is described by ten transfer coefficients and doses to humankind arise from the simultaneous consumption of water, fish, meat, milk, and grain as well as from dust inhalation and external γ-irradiation. The parameters of the exposure pathway sub model are chosen to be representative of an individual living in a small agrarian community. (13 refs., 3 figs., 2 tabs.)

Bico 2: second national intercomparison campaign of WBC centres working in Italy

International Nuclear Information System (INIS)

Castellani, C.M.; Battisti, P.; Tarroni, G.

1998-01-01

During the period November 1994 - May 1995 the coordinating group of WBC centres working in Italy organised the 2. national intercalibration and intercomparison campaign. A BOMAB phantom was used filled with four radionuclides gel solution with gamma energy emissions ranging between 100 keV and 2 MeV. 17 out of 21 Italian WBC centres took part in the campaign. Through the intercalibration, organised according to internationally accepted methodologies, each WBC centre could check its own calibration procedures. many intermediate data, collected for the methodologies and measurement procedures intercomparison, permitted analyses and comparison of uncertainly causes in a WBC measurement of the internal contamination. A proposal of MDA definition and assessment procedure resulted from the intercomparison campaign [it

The analysis of the program to develop the Nuclear Waste Management System: Allocated requirements for the Office of Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Woods, T.W.

1991-09-01

This report is volume 3, part B, of the program to satisfy the allocated requirements of the Office of Civilian Radioactive Waste Management Program, in the development of the nuclear waste management system. The report is divided into the following sections: regulatory compliance; external relations; international programs; strategic and contingency planning; contract business management; and administrative services. (CS)

A linear program for assessing the assignment and scheduling of radioactive wastes for disposal to sea

International Nuclear Information System (INIS)

Hutchinson, W.

1983-04-01

The report takes the form of a user guide to a computer program using linear programming techniques to aid the assignment and scheduling of radioactive wastes for disposal to sea. The program is aimed at the identification of 'optimum' amounts of each waste stream for disposal to sea without violating specific constraints values and/or fairness parameters. (author)

Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

International Nuclear Information System (INIS)

1995-11-01

In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ''Migration and Biological Transfer of Radionuclides from Shallow Land Burial'' during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs

Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ``Migration and Biological Transfer of Radionuclides from Shallow Land Burial`` during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs.

AQCS 1990. Intercomparison runs, reference materials

International Nuclear Information System (INIS)

1990-01-01

The purpose of the Analytical Quality Control Services (AQCS) programme provided by the International Atomic Energy Agency (Agency) is to assist laboratories engaged in the analysis of nuclear, environmental, biological, and materials of marine origin for radionuclide, major, minor and trace elements, as well as stable isotopes using atomic and nuclear analytical techniques, to check the quality of their work. Such a control is necessary since results of analytical activities may be the basis upon which economic, administrative, medical or legal decisions are taken; they must, therefore, be documented to be sufficiently reliable. The Agency has instituted the AQCS-programme which for 1990 will involve distributing samples for Intercomparison Runs and Reference Materials in a way similar to that of previous years. The Agency's Analytical Quality Control Services (AQCS) programme provides mainly three types of materials: materials which can be used in analytical laboratories working in the fields of nuclear technology and isotope hydrology. These include uranium ore Reference Materials and other substances of interest for nuclear fuel technology as well as stable isotope Reference Materials for mass spectrometric determination of isotope ratios in natural waters; materials with known content of uranium, thorium and/or transuranium elements or fission products for the determination of environmental radioactivity or control of nuclear safety; materials for use in the determination of stable trace elements in environmental, biomedical and marine research. Radiochemical methods such as neutron activation or isotope dilution analysis are often used in the determination of such trace elements and constitute an important contribution of nuclear techniques to applied science. Tabs

Total alpha and beta determination by liquid scintillation counting in water samples from a Brazilian intercomparison exercise

International Nuclear Information System (INIS)

Dias, Fabiana F.; Taddei, Maria Helena T.; Pontedeiro, Elizabeth May Braga Dulley

2009-01-01

This paper describes CNEN/LAPOC's participation in the Brazilian Intercomparison Exercise (PNI) for simultaneous determination of total radioactivity in water samples, which took place in August and December 2008. The Proficiency Test (PT) also involved a short description of the nuclear analytical technique employed, emphasizing sources of uncertainty. A Liquid Scintillation System (Packard TRICARB 2700) was used with appropriate corrections applied to final results, expressed as Bq L -1 . Participation and PT data provide independent information on performance of a Laboratory and have an important role in method validation; especially because it allows the assessment of method performance over an entire range of concentrations and matrices. PT is also an important tool to demonstrate equivalence of measurements, if not their metrological comparability, and to promote education and improvement of Lab practices. (author)

The Canadian National Calibration Reference Center for Bioassay and in-vivo Monitoring: A program summary

International Nuclear Information System (INIS)

Kramer, G.H.; Zamora, M.L.

1994-01-01

The Canadian National Calibration Reference Center for Bioassay and in-vivo Monitoring is part of the Radiation Protection Bureau, Department of Health. The Reference Center operates a variety of different intercomparison programs that are designed to confirm that workplace monitoring results are accurate and provide the necessary external verification required by the Canadian regulators. The programs administered by the Reference Center currently include urinalysis intercomparisons for tritium, natural uranium, and 14 C, and in-vivo programs for whole-body, thorax, and thyroid monitoring. The benefits of the intercomparison programs to the participants are discussed by example. Future programs that are planned include dual spiked urine sample which contain both tritium and 14 C and the in-vivo measurement of 99m Tc. 18 refs., 1 fig., 2 tabs

Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program. Revision 1

International Nuclear Information System (INIS)

1997-01-01

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) consists of a series of tests conducted on a regular frequency to evaluate the capability for nondestructive assay of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed with TRU waste characterization systems. Measurement facility performance will be demonstrated by the successful analysis of blind audit samples according to the criteria set by this Program Plan. Intercomparison between measurement groups of the DOE complex will be achieved by comparing the results of measurements on similar or identical blind samples reported by the different measurement facilities. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess the performance of measurement groups regarding compliance with established Quality Assurance Objectives (QAOs). As defined for this program, a PDP sample consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components, once manufactured, will be secured and stored at each participating measurement facility designated and authorized by Carlsbad Area Office (CAO) under secure conditions to protect them from loss, tampering, or accidental damage

Participation of the Nuclear Regulatory Authority in the uranium urinalysis intercomparisons

International Nuclear Information System (INIS)

Bonino, Nestor O.; Palacios, Miguel A.; Serdeiro, Nelida H.

1999-01-01

In the present work the results of the participation of Nuclear Regulatory Authority (NRA) Argentina, in the Uranium Urinalysis Intercomparison Program administered by the National Calibration Reference Centre for Bioassay, Radiation Protection Bureau, Health Canada, are detailed. This work is referred to the three participations of NRA in 1995, 1996, and 1997. The number of laboratories that have participated was 14, 12 and 12. A statistical analysis is presented. The performance criteria used for assessing the acceptability of results are those given in the American National Standard Institute (ANSI) 1989, N13.30. In addition, the applied radiochemical technique and the methodology are described. (author)

International NMR-based Environmental Metabolomics Intercomparison Exercise

Science.gov (United States)

Several fundamental requirements must be met so that NMR-based metabolomics and the related technique of metabonomics can be formally adopted into environmental monitoring and chemical risk assessment. Here we report an intercomparison exercise which has evaluated the effectivene...

International intercomparison on the neutron flux density spectrum just before the REAL-80 project

International Nuclear Information System (INIS)

Ertek, C.

1981-06-01

This work briefly presents the results of the international intercomparison on the neutron flux density spectrum just before the REAL-80 intercomparison project. Some of the results of this intercomparison with a smaller number of laboratories will be also reflected in the REAL-80 project, therefore, it has some significant issues. This work is performed within the IAEA programme on standardization of reactor radiation measurements, one of the important objectives of which is the assistance of laboratories in Member States to implement or intercompare the multiple foil activation techniques for different neutron field measurements

An overview of results obtained in intercomparison exercises for determination of actinides

International Nuclear Information System (INIS)

Benedik, L.

2013-01-01

In recent years the Jožef Stefan Institute participated in numerous intercomparison exercises for determination of natural and man-made radionuclides. The reported values were mostly in good agreement with the resulting reference values. This paper describes an analysis of the measurement results obtained in intercomparison exercises for determination of actinides in the period from 2009 to 2011, organised by the National Physical Laboratory and the Bundesamt für Strahlenschutz. The review covers neptunium, plutonium and americium radioisotopes over this period. - Highlights: • The goal of this study is an overview of results obtained in intercomparison exercises for determination of actinides. • The disagreement of results for Np-237 was evaluated. • Improvements in separation procedures were done

A programmatic response to the Secretary of Energy's review of the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Benson, A.B.

1994-01-01

On January 19, 1993, in response to a question during her confirmation hearing, Secretary of Energy Hazel R. O'Leary stated that she believed that a comprehensive review of nuclear waste disposal programs and policies was needed. Her preferred approach to such a review would be to engage in a consensus-seeking effort in which all involved parties would be brought to the table to deal with contentious issues. This paper describes both the process and the separate elements of the review of the civilian radioactive waste management program conducted in 1993 and 1994 by Secretary O'Leary. The paper will trace the review beginning with the Secretary's statement at her confirmation hearing, through her interim guidance redirecting certain aspects of the program. It describes some initiatives and changes that are already underway as a result of this review. Throughout the year, stakeholders expressed their concerns, opinions, and recommendations regarding the program. These communications reflected the diversity of perspective that has become a hallmark of the radioactive waste program

IAEA/ WHO TLD postal dose intercomparison results in Bangladesh

International Nuclear Information System (INIS)

Mollah, A.S.; Bhuiyan, N.U.; Rahman, S.

2001-01-01

Full text: For the accurate delivery of prescribed dose to the patients, high precision and accuracy in radiation dosimetry is required. The hospital/medical physicist is responsible for the accurate delivery of whole planned radiation doses to the patients prescribed by the radio therapist. The proper delivery of radiation doses depends upon the accurate output measurements of doses from the therapy machines. In Bangladesh, only six 60 Co units and five deep therapy machines are in use. Some more are expected to be installed soon. Still in 2001, none of the Government radiotherapy centers in Bangladesh was properly equipped with medical physicists as well as radiotherapy dosimetry equipment. Bangladesh Atomic Energy Commission (BAEC) is responsible for radiation safety in Bangladesh and BAEC has assigned Secondary Standard Dosimetry Laboratory (SSDL) of Bangladesh for providing dosimetry calibration to all radiotherapy centers in Bangladesh. The output measurements of therapy machines are performed once in a year by SSDL and the results are compared by participating in the annual TLD postal dose intercomparison program organized by IAEA/WHO SSDL Network. The absorbed dose to water is determined using IAEA dosimetry protocol (TRS 277 and 381) and water phantom of size 30 x 30 x 30 cm 3 , The measurements of SSDL are traceable to NPL of UK. The accuracy achieved in SSDL, Bangladesh has been found better than ± 3.5%, which is within the prescribed limit of dosimetry standard of IAEA. The methodology of output dose measurements in different radiotherapy centers in Bangladesh is described along with the IAEA/WHO intercomparison results

Development of knowledge building program concerning about high-level radioactive waste disposal

International Nuclear Information System (INIS)

Kimura, Hiroshi; Yamada, Kazuhiro; Takase, Hiroyasu

2005-01-01

Acquirement of knowledge about the high-level radioactive waste (HLW) disposal is one of the important factors for public to determine the social acceptance of HLW disposal. However in Japan, public do not have knowledge about HLW and its disposal sufficiently. In this work, we developed the knowledge building program concerning about HLW disposal based on Nonaka, and Takeuchi's SECI spiral model in knowledge management, and carried to the experiment on this program. In the results, we found that the participants' knowledge about the HLW disposal increased and changed from misunderstanding' or 'assuming' to 'facts' or 'consideration' through this experimental program. These results said that the experimental program leads participants to have higher quality of knowledge about the HLW disposal. In consequence, this knowledge building program may be effective in the acquirement of high quality knowledge. (author)

Personnel-dosimetry intercomparison studies at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Swaja, R.E.; Sims, C.S.

1982-01-01

Since 1974, seven annual personnel dosimetry intercomparison studies have been conducted at the Oak Ridge National Laboratory using the Health Physics Reactor. These studies have produced more than 2000 measurements by 72 participating organizations of neutron and gamma dose equivalents between 0.1 to 15.0 mSv in six mixed radiation fields. The relative performance of three basic types of personnel neutron dosimeters (nuclear emulsion film, thermoluminescent, and track-etch) and two basic types of gamma dosimeters (film and thermoluminescent) was assessed based on experimental results obtained during the seven intercomparisons

Radioactivity monitoring programme of Krsko nuclear power plant

International Nuclear Information System (INIS)

Miklavzic, U.; Martincic, R.; Kanduc, M.; Lulic, S.; Kovac, J.; Breznik, B.

1996-01-01

As a successor to the preoperational surveillance programme, the regular offsite radioactivity monitoring programme (RMP) of the Krsko Nuclear Power Plant (NPP) was implemented in 1982, when the power plant formally commenced operating. Observations collected during the first years of its operation were later also the basis for setting up the official 'Regulatory guide on monitoring of nuclear installations', issued not earlier than in 1986. The basic criterion which governed the selection of measuring methods, sampling techniques and locations, was the extent to which the data obtained could serve for the realistic assessment of the committed dose to a member of the population, and later on to members of a representative (critical) group. To be able to differentiate the radioactivity released through the liquid and gaseous effluents of the NPP from other radiation sources (natural radioactivity, global contamination), and especially because of the varying radiotoxicity of different radionuclides, in principle monitoring in the environment, as at the source, had to provide activity data for each individual radionuclide appearing in the effluents. Therefore, as early as 1982 the programme attributed the main weight to high resolution gamma spectrometry, combined with specific radiochemical analytical methods (e.g. 90 Sr/ 89 Sr, 3 H, 14 C, alpha spectrometry of Pu isotopes) which together made feasible determination of individual specific activities of the most significant man-made and natural radionuclides. By weighting the specific activities of the radionuclides identified and measured in the media surveyed by dose factors for intake, the quantity 'B' - the so-called 'radiological burden', was calculated and introduced in the yearly-summary tables. Expressed in relative units, from which the committed dose could be readily calculated, the burden B very lucidly disclosed the relative importance of different artificial pollutants and natural radioactivity present in

World wide intercomparison of trace element measurements in marine sediments SD-M-2/TM

International Nuclear Information System (INIS)

Mee, L.D.; Oregioni, B.

1991-09-01

The accurate and precise determination of trace elements in marine sediments is an important aspect of geochemical studies of the marine environment and for assessing the levels and pathways of marine pollutants. Past intercomparison studies conducted by the Marine Environment Laboratory of IAEA (formerly the International Laboratory of Marine Radioactivity) have focussed upon near-shore marine sediments where trace metal contamination is frequently observed. The present exercise was designed to study a typical oxidised deep-sea sediment characterized by a preponderance of fine particle clays. Analysis of such material is a routine matter for most geochemists but represents a ''baseline sample'' for marine pollution chemists. The present exercise represented a unique opportunity for chemists worldwide to intercompare their analytical methodologies for deep-sea sediments. By statistically examining the data from this study, the material can be certified for future use as a reference material - apparently the only one of its kind available throughout the world. 6 refs, figs and tabs

The AquaVIT-1 intercomparison of atmospheric water vapor measurement techniques

Science.gov (United States)

Fahey, D. W.; Gao, R.-S.; Möhler, O.; Saathoff, H.; Schiller, C.; Ebert, V.; Krämer, M.; Peter, T.; Amarouche, N.; Avallone, L. M.; Bauer, R.; Bozóki, Z.; Christensen, L. E.; Davis, S. M.; Durry, G.; Dyroff, C.; Herman, R. L.; Hunsmann, S.; Khaykin, S. M.; Mackrodt, P.; Meyer, J.; Smith, J. B.; Spelten, N.; Troy, R. F.; Vömel, H.; Wagner, S.; Wienhold, F. G.

2014-09-01

The AquaVIT-1 intercomparison of atmospheric water vapor measurement techniques was conducted at the aerosol and cloud simulation chamber AIDA (Aerosol Interaction and Dynamics in the Atmosphere) at the Karlsruhe Institute of Technology, Germany, in October 2007. The overall objective was to intercompare state-of-the-art and prototype atmospheric hygrometers with each other and with independent humidity standards under controlled conditions. This activity was conducted as a blind intercomparison with coordination by selected referees. The effort was motivated by persistent discrepancies found in atmospheric measurements involving multiple instruments operating on research aircraft and balloon platforms, particularly in the upper troposphere and lower stratosphere, where water vapor reaches its lowest atmospheric values (less than 10 ppm). With the AIDA chamber volume of 84 m3, multiple instruments analyzed air with a common water vapor mixing ratio, by extracting air into instrument flow systems, by locating instruments inside the chamber, or by sampling the chamber volume optically. The intercomparison was successfully conducted over 10 days during which pressure, temperature, and mixing ratio were systematically varied (50 to 500 hPa, 185 to 243 K, and 0.3 to 152 ppm). In the absence of an accepted reference instrument, the absolute accuracy of the instruments was not established. To evaluate the intercomparison, the reference value was taken to be the ensemble mean of a core subset of the measurements. For these core instruments, the agreement between 10 and 150 ppm of water vapor is considered good with variation about the reference value of about ±10% (±1σ). In the region of most interest between 1 and 10 ppm, the core subset agreement is fair with variation about the reference value of ±20% (±1σ). The upper limit of precision was also derived for each instrument from the reported data. The implication for atmospheric measurements is that the

Outline of the 1996-1998 IAEA co-ordinated research project on intercomparison for individual monitoring of external exposure from photon radiation

International Nuclear Information System (INIS)

Boehm, J.; Gustafsson, M.; Ouvrard, R.

1999-01-01

The outline of the IAEA Co-ordinated Research Project 1996-1998 on intercomparison for individual monitoring is described. The intercomparison focused on IAEA Member States in Eastern Europe and was based on the operational quantity personal dose equivalent, H p (10). The three phases of the intercomparison were: the preparatory phase including a workshop, the 'type-test' intercomparison, and the 'simulated workplace field' intercomparison. Details of the phases are given. (author)

Initial Results of an Intercomparison of AMS-Based Atmospheric 14CO2 Measurements

NARCIS (Netherlands)

Miller, John; Lehman, Scott; Wolak, Chad; Turnbull, Jocelyn; Dunn, Gregory; Graven, Heather; Keeling, Ralph; Meijer, Harro A. J.; Aerts-Bijma, Anita Th; Palstra, Sanne W. L.; Smith, Andrew M.; Allison, Colin; Southon, John; Xu, Xiaomei; Nakazawa, Takakiyo; Aoki, Shuji; Nakamura, Toshio; Guilderson, Thomas; LaFranchi, Brian; Mukai, Hitoshi; Terao, Yukio; Uchida, Masao; Kondo, Miyuki

2013-01-01

This article presents results from the first 3 rounds of an international intercomparison of measurements of Delta(CO2)-C-14 in liter-scale samples of whole air by groups using accelerator mass spectrometry (AMS). The ultimate goal of the intercomparison is to allow the merging of Delta(CO2)-C-14

IAEA/SSDL intercomparison of calibration factors for therapy level ionization chambers

International Nuclear Information System (INIS)

Lu Jilong; Cheng Jinsheng; Guo Zhaohui; Li Kaibao

2005-01-01

Objective: By participating in IAEA-SSDL intercomparison, a dose to water calibration factor was introduced in order to check the measuring accuracy of 60 Co radiotherapy dose level standard and ensure the reliability and consistency of our calibration. Methods: The authors carried out both air kerma and absorbed dose to water calibrations against 60 Co γ-rays for one of our field class ionization chambers, and sent the results together with the chamber to IAEA dosimetry laboratory for calibration, then IAEA calibrated it and gave the deviation of the intercomparison. Results: The deviation of our air kerma calibration factors is -0.5%, and the deviation of our absorbed dose to water calibration factors is 0.4%. Conclusion: The deviation of calibration factors between IAEA and SSDL should be no more than ±1.5%. Therefore, the result of this intercomparison is considered satisfactory. (authors)

UK laboratory intercomparison on internal dosimetry

Energy Technology Data Exchange (ETDEWEB)

Speed, J.; Birchall, A.; Bull, R.; Cockerill, R.; Jarvis, N.S.; Marsh, J.W.; Peace, M.S.; Roberts, G.; Scarlett, C.; Spencer, D.; Stewart, P

2003-07-01

A laboratory intercomparison for internal dose assessment from a variety of intake scenarios is described. This is the first UK intercomparison using the revised ICRP Human Respiratory Tract and biokinetic models. Four United Kingdom laboratories participated and six cases were assessed. Overall, the agreement in internal dose assessments between laboratories was considered satisfactory with 79% of the assessed committed effective doses, e(50), for cases within a band of {+-}40% of the median value. The range (highest/lowest) in e(50) estimated by the laboratories was smallest (1.2) for a case involving inhalation of {sup 137}Cs. The range was greatest (6.0) for a case involving a wound with, and possible inhalation of, {sup 238}Pu, {sup 239}Pu and {sup 241}Am; the variation between laboratories in assessment of intakes could not be considered to be satisfactory in this case. Judgements on the most appropriate data to use in estimating intakes, choice of parameter values for use with the ICRP models and allowing for the effects of treatment with DTPA were important sources of variability between laboratories. (author)

Primary standardization of cesium-137 for international intercomparison

International Nuclear Information System (INIS)

Srivastava, P.K.

1977-01-01

Primary standards of cesium-137 are of great importance for precise radiation measurements because, due to its simple decay-scheme and long half-life, it is widely used for the calibration of radiation detectors. Also 137 Cs is used for the measurement of fission-yield and uranium burn-up in reactor engineering studies. In view of these, an international intercomparison was organised on a limited scale to correlate the standards established at the Bhabha Atomic Research Centre (BARC), Bombay(India) and Physikalisch-Technische Bundesanstalt (PTB), West Germany. The ''efficiency tracing technique'' was developed at BARC for the primary standardization of 137 Cs for this intercomparison. Two tracers, namely 82 Br and 60 Co, were employed to trace the beta efficiency of the 4 πβ-γ coincidence counting system. It is shown that this technique offers high accuracy and inherent reliability. The ''tracing-technique'' for 137 Cs standardization is briefly described. The gravimetric method of dilution and preparation of mixed sources of 137 Cs - 82 Br and 137 Cs - 60 Co are given. The various counting parameters and settings are included. Data reduction and the estimation of systematic and statistical errors are discussed. The results of the intercomparison, which are also included, show that the agreement between the measurments of BARC and PTB is within 0.5%. (author)

Radioactive Control of Krsko Nuclear Power Plant Environment in the Year 1997

International Nuclear Information System (INIS)

Lulic, S.; Miklavzic, U.; Franic, Z.; Kanduc, M.

1998-01-01

Regular Krsko Nuclear Power Plant (NPPK) radioactivity control comprises the supervisions of the inventory of liquid and gaseous emissions at the source, and the independent supervisions of the input of radionuclides into larger environment (imisson). The controlled environment area consists primarily of a 12 kilometers large circle around the object, where the largest values of imission could be expected, and where possible changes in the Sava river and the underground waters could first be noticed. The circle has been enlarged upon the territory of the Republic of Croatia (RC) from Jesenice on Dolenjsko until Podsused (30 km of air - line distance). As reference points relevant for the readiness in the case of accident, especially for detection of iodine and aerosol air transport, the program comprises also measuring points in the RC at larger distances (from 14 to 27 km) in the direction of Zagreb its larger western surroundings (passive Thermoluminescent (TL) dosimeters in the each 42 km long). Continuous control of emission is performed by the radiological service of KNPP by routine procedures, supplemented by adequate measurements from other authorized institutions (intercomparisons, parallel measurements of representative and other samples). Summarised results of radioactive measurements for man-made and natural radionuclides are presented for different transfer media and exposure pathways in the form of assessed effective doses. Conservatively estimated dose burdens received by a member of the reference (critical) population group as the result of NPP emissions amount to a value of the committed effective dose equivalent smaller than 20 μSv/year. This value represents less than 1 % of the annual dose received on average from natural and artificial sources by a member of the general public in the normal environment. The yearly doses from natural radioactivity, global contamination (Chernobyl, atmospheric nuclear explosions), non-nuclear industries and

The radioactive waste management program of The Commission of the European Communities: Past, present, and future trends

International Nuclear Information System (INIS)

Orlowski, S.M.

1983-01-01

The radioactive waste management program started in the mid-1970s is being carried out by the Commission of European Communities (CEC) Joint Research Centre and by research bodies within the European community under CEC coordination and partial financing. The program deals with the management of the radioactive waste resulting from uranium-plutonium fuel cycle. During its first phase (1973-1979), various treatment and conditioning processes were investigated; high temperature incineration and acid digestion of alpha-bearing waste, immobilization of highly active waste in borosilicate glasses, inter alia, appeared promising. Geological disposal was recognized as a feasible option; transmutation of long-lived products did not appear to be an advantageous alternative to geological disposal, and the studies were discontinued. The second phase (1980-1984) of the program is a followup to the first. The needs of the European nuclear industry and of the national radioactive waste agencies or operators recently created are, however, taken into account. The continuity of the RandD effort is ensured by a ''Community plan of action on waste management,'' (1980-1992). A third phase, 1984-1989, should demonstrate the availability and validity of the waste management techniques and be convincing about their safety

Forecasting of the radioactive material transport demand for the Brazilian Nuclear Program and the security aspects

International Nuclear Information System (INIS)

Meldonian, Nelson Leon

1979-01-01

In the nuclear fuel cycle, a lot of radioactive materials are produced. These radioactive materials must be transported in order to promote the integration of the fuel cycle units. Considerations about the transport characteristics of radioactive material were made for each section of the fuel cycle. These considerations were based on the experience of several countries and in accordance with the International Atomic Energy Agency regulations. A prediction of transport demands for the Brazilian Nuclear Program until year 2.010 was made. The prediction refers mainly to the quantity of radioactive material produced in each section of the cycle the quantity of vehicles needed for the transport of these materials. Several safety aspects were considered specially, the accidents predictions for years 2.000 and 2.010. The accident probability in Brazilian railroads and highways was compared with that of the USA. (author)

UNIDOSE - a computer program for the calculation of individual and collective doses from airborne radioactive pollutants

International Nuclear Information System (INIS)

Karlberg, O.; Schwartz, H.; Forssen, B.-H.; Marklund, J.-E.

1979-01-01

UNIDOSE is a program system for calculating the consequences of a radioactive release to the atmosphere. The program is applicable for computation of dispersion in a rnage of 0 - 50 km from the release point. The Gaussion plume model is used for calculating the external dose from activity in the atmosphere, on the ground and the internal dose via inhalation. Radioactive decay, as well as growth and decay of daughter products are accounted for. The influence of dry deposition and wash-out are also considered. It is possible to treat time-dependent release-rates of 1 - 24 hours duration and constant release-rates for up to one year. The program system also contains routines for the calculation of collective dose and health effects. The system operates in a statistical manner. Many weather-situations, based on measured data, can be analysed and statistical properties, such as cumulative frequences, can be calculated. (author)

Program of environmental radiological surveillance of the radioactive wastes storage center of Maquixco in the period January-December 1991

International Nuclear Information System (INIS)

Gaso P, M.I.

1991-12-01

The primary objective of all program of environmental radiological surveillance (PVRA), it is to follow the evolution of the radioactive content of the links of the chains that constitute the different ways of transfer of the radioactivity toward the man, with the purpose of making a realistic evaluation of the environmental impact produced by the installation under surveillance. In the CADER in Mexico, only accidents or escapes of radioactivity of slow evolution can be detected. At the moment the radioactive wastes in this installation are not treated. In this report the results obtained during the year 1991 are presented. (Author)

Intercomparison of characterization techniques of filter radiometers in the ultraviolet region

International Nuclear Information System (INIS)

Abu-Kassem, I.; Karha, P.; Harrison, N. J.; Nevas, S.; Hartree, W. S.

2008-01-01

Narrow-band filter radiometers at 248 nm, 313 nm, 330 nm and 368 nm wavelengths were used to compare calibration facilities of spectral (irradiance) responsivity at HUT, NPL and BNM-INM. The results are partly in agreement within the stated uncertainties. Use of demanding artefacts in the intercomparison revealed that the wavelength scales of the participating institutes deviate more than expected. Such effects cannot be seen in typical intercomparisons of spectral responsivity or spectral transmittance, where spectrally neutral samples are used.(author)

The issue resolution process in the Civilian Radioactive Waste Transportation Program

International Nuclear Information System (INIS)

Holm, J.A.; Denny, S.

1987-01-01

The Civilian Radioactive Waste Management (OCRWM) Program consists of various technical and institutional program activities which engender concern from the general public and from policymakers at federal, state, and local levels. Most familiar are the concerns centered around selection of a site for a repository; however, the transportation portion of the OCRWM program also engenders similar concerns for safety, efficiency and effectiveness. The major Transportation institutional issues were detailed in the Institutional Plan, issued in 1986, and include topics such as liability, defense waste, routing, emergency response, risk identification and mitigation, cash integrity, inspection and enforcement of high-level waste shipments and use of overweight trucks as part of the modal mix. This paper will define the process being used to identify and resolve institutional issues, show how the technical and institutional issues interface and are addressed, and briefly describe four specific activities which illustrate the process of resolving institutional issues in the Transportation program

International intercomparison of neutron spectra evaluating methods using activation detectors

International Nuclear Information System (INIS)

Fischer, A.

1975-06-01

The international intercomparison of neutron spectrum evaluation methods using activation detectors was organized by the IAEA in 1971 - 1972. All of the contributions and the results of a critical evaluation are presented here. The spectra of different contributors are compared to a reference spectrum by means of different integrals and weighting functions. Different cross section sets, foil numbers, energy point systems, guess spectra used by the contributors cause differences in the resulting spectra. The possible ways of separating these effects are also investigated. Suggestions are made for the organization of a new intercomparison on the basis of more uniform input data. (orig.) [de

Development of a low-level radioactive waste shipper model. National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1983-03-01

During 1982, Inter/Face Associates, Inc., conducted a low-level radioactive waste management survey of Nuclear Regulatory Commission (NRC) licensees in Massachusetts for the US Department of Energy's National Low-Level Waste Management Program. In the process of conducting the survey, a model was developed, based on existing NRC license classification systems, that would identify licensees who ship low-level waste for disposal. This report presents the model and documents the procedures used in developing and testing it. After the model was tested, several modifications were developed with the goal of determining the model's ability to identify waste shippers under different parameters. The report includes a discussion of the modifications

C.E.C. program on radioactive waste management disposal and risk assessment

International Nuclear Information System (INIS)

Orlowski, S.; Girardi, F.; Bresesti, M.

1976-01-01

The Commission of the European Communities (CEC) has been involved many years with the radioactive waste problem; but a major effort started in 1973 when a specific program was given to the Commission's own laboratories (C.E.C. Joint Research Center, Ispra Establishment). This effort is very much enlarged since June 1975, when the Commission was authorized to start a coordinated program with the national laboratories of the nine member states, financed on a 50/50 basis. The contribution of the Commission for the 1975-79 plan amounts to $19 million. The overall program now involves several laboratories and does represent a significant European effort to contribute to solving a world scale problem; it is intended to promote a large international cooperation

The intercomparison of 137Cs irradiator output measurement and personal dose equivalent, Hp(10), using TLD and film

International Nuclear Information System (INIS)

Nazaroh; Susetyo Trijoko; Sri Inang Sunaryati

2010-01-01

Intercomparison of output measurement of 137 Cs irradiator and personal dose equivalent, Hp(10) using TLD and film have been carried out in the year of 2006 to 2008. According to IAEA recommendation, intercomparison is one of audit activities but it is performed in the spirit of collaboration and support rather than in the spirit of inspection. The aim of intercomparison of output measurement of 137 Cs irradiator is to verify the dose stated by the participant laboratories. Intercomparison is also to assess the competency of the participant, to keep traceability and consistency of measurement result, to assure that instrument work correctly and the result of evaluation was in agreement, and also for fulfilling one of the clauses of ISO-17025-2005. Besides that, this intercomparison aimed to facilitate link between the system and members of national measurement and transfer of experience in measurement technique and dose evaluation of radiation. The benefit of intercomparison is important among others as tests of proficiency in dose evaluation or measurement, upgrading quality of service and for obeying supervisor body legislation (BAPETEN). TLD was used as a means of output 137 Cs irradiator measurement, whereas film and TLD were used for dose intercomparison. This paper presented result of intercomparison of output measurement and evaluation of personal dose equivalent, Hp(10) in the year of 2006 to 2008 followed by 6 participants: Balai Pengamanan Fasilitas Kesehatan (BPFK) Jakarta, Medan, Surabaya, Makasar, PTLR and Laboratory of Keselamatan dan Kesehatan Lingkungan (KKL)-PTKMR BATAN. In this intercomparison, the dose of TLD stated by participant were compared with the dose measured by Radiation Metrology Laboratory (LMR), and the results showed the differences were within 10 %, so it was satisfied. The results of intercomparison of personal dose equivalent, Hp(10) were evaluated based on ISO/IEC Guide 43-1, 1997 analysis and expressed as E n . The values of E n

PIDIE, plutonium isotopic determination inter-comparison exercise

International Nuclear Information System (INIS)

Harry, R.J.S.

1990-07-01

PIDIE (Plutonium Isotopic Determination Inter-comparison Exercise) is one of the projects of the ESARDA Working Group on Techniques and Standards for Non-Destructive Analysis. PIDIE is placed against the historical background of the general development of international standards. Its results are also reviewed in the light of the original purpose of the project. Sets of seven sealed Pu samples of different isotopic composition, each containing 0,45 grammes, were sent to the 9 participating laboratories for three separate determinations of the unknown isotopic composition, to investigate error sources and , if possible to improve the knowledge of γ-emission probabilities. An additional question was to examine the possible improvement of such measurements using reference samples. No important bias has been observed in the results of this inter-comparison. The apparent improvement in the precision and accuracy of the result seems to arise from both better equipment and more elaborate spectrum evaluation methods. (author). 39 refs.; 1 fig.; 5 tabs

Summary of 'IAEA intercomparison of IBA software'

International Nuclear Information System (INIS)

Barradas, N.P.; Arstila, K.; Battistig, G.; Bianconi, M.; Dytlewski, N.; Jeynes, C.; Kotai, E.; Lulli, G.; Mayer, M.; Rauhala, E.; Szilagyi, E.; Thompson, M.

2008-01-01

The International Atomic Energy Agency has sponsored a formal intercomparison exercise for the seven depth profiling ion beam analysis codes, which are: GISA, RUMP, RBX, DEPTH, DataFurnace, SIMNRA and MCERD. This intercomparison is published in Nucl. Instr. and Meth. B [N.P. Barradas, K. Arstila, G. Battistig, M. Bianconi, N. Dytlewski, C. Jeynes, E. Kotai, G. Lulli, M. Mayer, E. Rauhala, E. Szilagyi, M. Thompson, Nucl. Instr. and Meth. B 262 (2007) 281-303] and summarised here. The codes implement all known physical effects and they are all evaluated. We demonstrate that there is agreement between codes often better than 0.1%; and also detailed agreement with real spectra, showing in particular that the SRIM 2003 stopping powers for Si are correct to 0.6% for 1.5 MeV He. For the case of heavy ion elastic recoil detection (HI-ERD) the single scattering codes performed poorly for scattered particles, although recoiled particles were calculated correctly

Intercomparison Contracted Partner Institutes for Nuclear Emergency 2007; Ringonderzoek waakvlaminstituten kernongevallenbestrijding 2007

Energy Technology Data Exchange (ETDEWEB)

Overwater-van Buuren, R.M.W.; Glastra, P.; Tukker, K.

2009-07-01

The quality of the so-called Contracted Partner Institutes (CPI's) is amply complying with the objectives. Nonetheless, some desirable improvements remain, especially issues concerning the calibration of the measuring equipment. These issues emerged during an investigation performed by RIVM, in which the quality of the analysis of water and air samples was tested. In the Netherlands there are eight CPI's, evenly spread across the country, who can inform the government about radioactivity in air and water. The CPIs are part of the Dutch National Plan for Nuclear Emergency Planning and Response, which has been drawn up after the nuclear disaster in Chernobyl. RIVM is coordinating the activities of the CPI's. The Contracted Partner Institutes are tested on a two-yearly base by way of intercomparisons. In these intercomparisons, testing is done on both the timely reporting of the results and on the agreement with the reference value within pre-defined boundaries. Most CPI's were able to deliver the air results within two hours, and the water results within 24 hours. The results of the air samples for one institute were outside the pre-defined boundaries. Four samples were prepared for the intercomparison: an aerosol filter, a charcoal filter, a charcoal cartridge and a water sample. All four contained radionuclides characteristic for nuclear accidents. [Dutch] De kwaliteit van de zogeheten Waakvlaminstituten (WVI's) voldoet in 2007 ruimschoots aan de doelstellingen. Wel zijn enkele verbeteringen wenselijk, vooral op het gebied van kalibratie van de meetopstellingen. Dit blijkt uit onderzoek van het RIVM waarin de kwaliteit is getest van de analyse van water- en luchtmonsters. In Nederland bestaan er verspreid over het land acht WVI's die bij een kernongeval de overheid informeren over radioactiviteit in lucht en water. De WVI's zijn een onderdeel van het Nationaal Plan Kernongevallenbestrijding (NPK), dat is opgesteld enkele jaren na

Report on intercomparison exercise SR-54. Determination of impurities in U3O8

International Nuclear Information System (INIS)

Doubek, N.; Bagliano, G.; Deron, S.

1984-04-01

The report presents results of a laboratory intercomparison of impurities in U 3 O 8 sample organized by the IAEA's Analytical Quality Control Service. Twelve laboratories in 11 countries sent their results. The framework of the intercomparison was therefore conceived mainly as a ''mean'' to laboratories dealing with analysis of impurities in uranium samples to check the reliability of their results. The evaluation was based on 97 laboratory means obtained with emission spectroscopy, atomic absorption techniques and neutron activation analysis. The concentration of three elements could be certified as a result of this intercomparison; informational values could be established for an additional six elements

Intercomparison of methods for determining 90Sr and 137Cs in plant samples

International Nuclear Information System (INIS)

Sha Lianmao; Zhao Min; Tian Guizhi

1986-01-01

The results of intercomparison of methods for determining 90 Sr and 137 Cs in plant samples are reported. Nine laboratories participated in the intercomparison. The samples used in intercomparison were reed and tea powders. The analytical results of 90 Sr in reed and 137 Cs in tea from different laboratories show good comparability and follow the normal-distribution. Some results reported of 137 Cs in reed are apparently lower than others. The results of 90 Sr in tea from different laboratories have poor comparability. The results obtained by HDEHP rapid extraction chromatograph appear to be too high, and it's cause is discussed. The 95% confidence intervals of content of 90 Sr and 137 Cs in reed and tea samples are given

Environmental radioactivity in Canada 1986

International Nuclear Information System (INIS)

1987-01-01

The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. During 1986 the program was strongly influenced by radioactive fallout on Canada resulting from the Chernobyl nuclear reactor accident on April 26, 1986 in the Soviet Ukraine. The Environmental Radiation Hazards Division (ERHD) increased its frequency of analyses of environmental samples immediately following the accident. Interim screening limits for foodstuffs were developed. A measurement program for radioactivity in domestic and imported foods was implemented. The ERHD measurement program was supplemented by additional measurements conducted by many other private and government laboratories. Radiation doses to Canadian from Chernobyl fallout were extremely low with no group in the population receiving more than 10 microsieverts

DOE reassesses civilian radioactive waste management program

International Nuclear Information System (INIS)

Yates, M.

1990-01-01

This article reports on the announcement by the Department of Energy (DOE) that the opening of a high-level radioactive nuclear waste repository site will be delayed for seven years. The article discusses DOE's reassessment plan, the restructuring of the Office of Civilian Radioactive Waste Management, site access and evaluation, the Monitored Retrievable Storage Commission proposal, and the industry's response

A computer program to calculate the committed dose equivalent after the inhalation of radioactivity

International Nuclear Information System (INIS)

Van der Woude, S.

1989-03-01

A growing number of people are, as part of their occupation, at risk of being exposed to radiation originating from sources inside their bodies. The quantification of this exposure is an important part of health physics. The International Commission on Radiological Protection (ICRP) developed a first-order kinetics compartmental model to determine the transport of radioactive material through the human body. The model and the parameters involved in its use, are discussed. A versatile computer program was developed to do the following after the in vivo measurement of either the organ- or whole-body activity: calculate the original amount of radioactive material which was inhaled (intake) by employing the ICRP compartmental model of the human body; compare this intake to calculated reference levels and state any action to be taken for the case under consideration; calculate the committed dose equivalent resulting from this intake. In the execution of the above-mentioned calculations, the computer program makes provision for different aerosol particle sizes and the effect of previous intakes. Model parameters can easily be changed to take the effects of, for instance, medical intervention into account. The computer program and the organization of the data in the input files are such that the computer program can be applied to any first-order kinetics compartmental model. The computer program can also conveniently be used for research on problems related to the application of the ICRP model. 18 refs., 25 figs., 5 tabs

Intruder dose pathway analysis for the onsite disposal of radioactive wastes: the ONSITE/MAXI1 computer program

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Kennedy, W.E. Jr.; Neuder, S.M.

1984-10-01

Because of uncertainties associated with assessing the potential risks from onsite burials of radioactive waste, the US Nuclear Regulatory Commission (NRC) has amended its regulations to provide greater assurance that buried radioactive material will not present a hazard to public health and safety. The amended regulations now require licensees to apply for approval of proposed procedures for onsite disposal pursuant to 10 CFR 20.302. The NRC technically reviews these requests on a case-by-case basis. These technical reviews require modeling potential pathways to man and projecting radiation dose commitments. This document contains a summary of our efforts to develop human-intrusion scenarios and to modify a version of the MAXI computer program for potential use by the NRC in reviewing applications for onsite radioactive waste disposal. The documentation of the ONSITE/MAXI computer program is written for two audiences. The first (Audience A) includes persons concerned with the mathematical models and computer algorithms. The second (Audience B) includes persons concerned with exercising the computer program and scenarios for specific onsite disposal applications. Five sample problems are presented and discussed to assist the user in operating the computer program. Summaries of the input and output for the sample problems are included along with a discussion of the hand calculations performed to verify the correct operation of the computer program. Computer listings of the ONSITE/MAXI1 computer program with an abbreviated data base listing are included as Appendix 1 to this document. Finally, complete listings of the data base with listings of the special codes used to create the data base are included in Appendix 2 as a microfiche attachment to this document

Handbook of high-level radioactive waste transportation

International Nuclear Information System (INIS)

Sattler, L.R.

1992-10-01

The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government's system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government's program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project

Evaluating public involvement in the National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1982-09-01

The Department of Energy contracted with the Keystone Center to evaluate the effectiveness of the National Low-Level Radioactive Waste Management Program's public-involvement efforts. The Center chose six evaluators with diverse training and experience related to low-level waste management and public-participation programs. Keystone's evaluation was based on (a) observations by the evaluators who attended the National Program-sponsored strategy review meetings and fairs; (b) interviews with low-level waste generators, local government officials, state legislators, public-interest groups, and members of the general public; and (c) observations of the final National Program strategy task force meeting. The evaluators concluded that, overall, the public-participation processes yielded some very positive results - for policy development and for DOE and the EG and G staff. They judged the strategy document to be complete, concise, and helpful to public dialogue on low-level waste issues. They also made specific recommendations for improvements to the public-participation program

Intercomparison of radon gas detectors 1997 at PSI

International Nuclear Information System (INIS)

Schuler, Christoph; Butterweck-Dempewolf, Gernot

1998-05-01

Between Nov 14 and Nov 20, 1997, the Reference Laboratory for Radon Gas Activity Concentration Measurements at Paul Scherrer Institut performed the 1997 Radon Intercomparison Exercise. Radon gas detectors and instruments were exposed in the PSI Radon Chamber during seven days in a reference atmosphere with an average radon gas concentration of 3860 Bqm -3 . The majority of the participants at this intercomparison were Swiss Radon Gas Measurement Laboratories acknowledged by the Swiss Federal Office for Health. Criteria for this acknowledgement are a deviation of the measurement results to the reference value below 15% (traceability criterion) and a standard deviation of the mean of five detector measurement results below 15% (reproducibility criterion). With the exception of three participants, the results of electret ionisation chambers, track etch detectors and measuring instruments fulfilled the demanded traceability and reproducibility criteria. (author)

TLD Intercomparison in accelerators for radiotherapy in three Latin american countries; Intercomparacion TLD en aceleradores para radioterapia en tres paises latinoamericanos

Energy Technology Data Exchange (ETDEWEB)

Gaona, E.; Azorin N, J.; Perez, M.A.; Picon, C.; Castellanos, E.; Plazas, M.C.; Murcia, G.; Archundia, L. [Depto. El Hombre y su Ambiente. Universidad Autonoma Metropolitana, Calz. Del Hueso 1100, 04960 Mexico D.F. (Mexico)

1998-12-31

In Radiotherapy one of the objectives is to establish and to give follow up to quality assurance programs which make sure that the doses administered to the patients with cancer are a high probability of a success in external radiation. Likewise, one of the present preoccupations of the United Nations Agencies as well as the International Atomic Energy Agency and the Pan-American Health Organization is the optimal employment of the radiations in the treatment of cancer patients since the administered dose in Radiotherapy suffers considerable variations by the lack of quality assurance programs. The use of Electron linear accelerators requires a program of quality assurance that includes expert personnel, equipment and adequate facilities. The more used methodology for the dosimetry calibration and characterization of X-ray beams and high energy electrons for radiotherapy use is using a ionization chamber dosemeter calibrated in a regional secondary standardization laboratory. However, to establish and give follow up to the quality assurance programs it is necessary the dosimetric intercomparison through TLD. In this study it was designed plastic phantoms with TLD crystals and it was made its characterization to realize an absorbed dose analysis in the crystals exposed at X-ray beams 6 MV and high energy electrons 10 and 12 MeV to standardize the dosimetric procedures and proceeding to realize an International Pilot intercomparison of absorbed doses in TLD crystals in three Latin American countries: Mexico, Peru and Colombia with the participation of accelerators of five different institutions. The found results show that the majority of the measured doses with TLD in the different accelerators were in the 0.95-1.05 range though it had two cases outside of this range. The use of the phantoms with TLD crystals shows that they are of excellent aid to make analysis of the doses administered to the patients and an intercomparison of results to standardize procedures at

Argentine intercomparison programme for personal dosimetry

International Nuclear Information System (INIS)

Gregori, B.N.; Papadopulos, S.B.; Cruzate, J.; Kunst, J.J.; Saravi, M.

2005-01-01

Full text: In 1997 began in Argentine, sponsored by Nuclear Regulatory Authority (ARN) the intercomparison program for personal dosimetry laboratories, on a voluntary basis. Up to know 6 exercises have been done. The program began with a workshop to present the quantities, personal dose equivalent, Hp(10) and extremities dose equivalent, Hs(d). The first aim of this program was to know the true sate of personal dosimetry laboratories in the country, and then introduce the personal dose equivalent, Hp(10) into the dose measurements. The Regional Reference Center for Dosimetry (CCR), belonging to CNEA and the Physical Dosimetry Laboratory of ARN performed the irradiation. Those were done air free and on ICRU phantom, using x-ray, quality ISO: W60, W110 and W200; and 137 Cs and 60 Co gamma rays. The irradiation was made following ISO 4037 (2) recommendations. There are studied the dose, energy and angular response of the different measuring system. The range of the dose analyzed was from 0.2 mSv up to 80 mSv. The beam incidence was normal and also 20 o and 60 o . The dosimeters irradiation's were performed kerma in free in air and in phantom in order to study the availability of the service to evaluate the behavior as a function of kerma free in air or Hp(10). At the same time several items have been asked to each participant referring to the action range, the detectors characteristics, the laboratory procedures, the existence of an algorithm and its use for the dosimeter evaluation and the wish to participate in a quality assurance program. The program worked in writing a standard of personal dosimetry laboratories, that was published in 2001. In this work the results of each laboratory and its performance based on the ICRP-60 and ICRP-35 acceptance criteria are shown. Also the laboratory evolution and inquiry analyses have been included. (author)

Joint Assessment of Renewable Energy and Water Desalination Research Center (REWDC) Program Capabilities and Facilities In Radioactive Waste Management

International Nuclear Information System (INIS)

Bissani, M; Fischer, R; Kidd, S; Merrigan, J

2006-01-01

The primary goal of this visit was to perform a joint assessment of the Renewable Energy and Water Desalination Center's (REWDC) program in radioactive waste management. The visit represented the fourth technical and scientific interaction with Libya under the DOE/NNSA Sister Laboratory Arrangement. Specific topics addressed during the visit focused on Action Sheet P-05-5, ''Radioactive Waste Management''. The Team, comprised of Mo Bissani (Team Lead), Robert Fischer, Scott Kidd, and Jim Merrigan, consulted with REWDC management and staff. The team collected information, discussed particulars of the technical collaboration and toured the Tajura facility. The tour included the waste treatment facility, waste storage/disposal facility, research reactor facility, hot cells and analytical labs. The assessment team conducted the first phase of Task A for Action Sheet 5, which involved a joint assessment of the Radioactive Waste Management Program. The assessment included review of the facilities dedicated to the management of radioactive waste at the Tourja site, the waste management practices, proposed projects for the facility and potential impacts on waste generation and management

Penn State continuing education program on low-level radioactive waste disposal and management: lessons learned

International Nuclear Information System (INIS)

Vincenti, J.R.

1985-01-01

Since November of 1983, The Pennsylvania State University, Institute for Research on Land and Water Resources has provided the citizens of the Commonwealth of Pennsylvania with information on low-level radioactive waste disposal and management through a continuing education program called the PIER (Public Involvement and Education on Radiation) Program. This paper will review the form, function, and development of this continuing education program and some of the lessons learned in providing citizens of the Commonwealth with information in both formal and informal educational settings

Subseabed radioactive waste disposal feasibility program: ocean engineering challenges for the 80's

International Nuclear Information System (INIS)

Talbert, D.M.

1980-11-01

The objective of the Subseabed Disposal Program is to assess the feasibility of disposing of high-level radioactive wastes or spent fuel in suitable geologic formations beneath the deep ocean floor. The program is entering a phase which will address engineering feasibility. While the current phase of the program to determine the scientific and environmental feasibility of the concept is not yet complete, activities to assess the engineering aspects are being initiated in parallel to facilitate the development of the concept on a time scale commensurate with related programs both in the United States and abroad. It is anticipated that engineering aspects will become the central focus of the program during the early 80's and will continue so through the establishment of a pilot-plant level activity which could occur by the mid-90's

Subseabed Radioactive Waste Disposal Feasibility Program: ocean engineering challenges for the 80's

International Nuclear Information System (INIS)

Talbert, D.M.

1980-01-01

The objective of the Subseabed Disposal Program is to assess the feasibility of disposing of high-level radioactive wastes or spent fuel in suitable geologic formations beneath the deep ocean floor. The program is entering a phase which will address engineering feasibility. While the current phase of the program to determine the scientific and environmental feasibility of the concept is not yet complete, activities to assess the engineering aspects are being initiated in parallel to facilitate the development of the concept on a time scale commensurate with other related programs both in the United States and abroad. It is anticipated that engineering aspects will become the central focus of the program during the early 80's and will continue so through the establishment of a pilot-plant level activity which could occur by the mid-90's

Intercomparison of 131I and 99mTc activity measurements in Brazilian nuclear medicine services

International Nuclear Information System (INIS)

Iwahara, Akira; De Oliveira, Antonio E.; Tauhata, Luiz; Silva, Carlos J. da; Lopes, Ricardo T.

2001-01-01

This work outlines the quality assurance program for the activity measurements of the most used radionuclides at Brazilian Nuclear Medicine Services (NMS). The program aims to guarantee that the patient is given the correct prescribed amount of activity in diagnostic or therapeutic applications. This accurate administration depends upon proper use and calibration of the activity meters by the NMS. Underestimation of administered activity in diagnostic practices could delay correct diagnosis disturbing the value of the investigation. On the other hand, the overestimation would be worse, mainly in therapeutic applications, because an unnecessarily high absorbed dose would be delivered to the patient. The preliminary results of intercomparison for 131 I and 99m Tc showed that many activity meters used at NMS's present problems giving results up to 41% greater than the reference values determined at the National Metrology Laboratory for Ionizing Radiation (LNMRI) which is recognized as the Brazilian authorized metrology laboratory for ionizing radiation. These results have demonstrated that the NMS should improve the accuracy of the activity measurements of the radionuclides administered to the patients and establish the traceability to the national standards of measurements. These standards are based on a pressurized well-type ionization chamber installed at LNMRI and calibrated with reference sources standardized by absolute methods. The protocol of the intercomparison and recommendations made in order to minimize errors in measuring procedures are described and results are discussed

Development of the Office of Civilian Radioactive Waste Management's Self-Assessment Program

International Nuclear Information System (INIS)

Vlahakis, J.G.; Palabrica, R.J.; Goldsmith, S.

1993-01-01

This paper describes the development and implementation of the Self-Assessment (SA) Program of the Office of Civilian Radioactive Waste Management (RW). The basis for RW's SA Program is discussed, as well as RW's approach for meeting self-assessment requirements, RW's organization for self-assessment, actions to establish RW's SA Program, and planned RW SA implementation activities. This paper also discusses how self-assessment can support programmatic decisions and actions. The RW Director has approved and issued the Self-Assessment Management Plan that describes how RW will organize and manage its SA program. He has directed Associate/Office Directors to prepare individual Implementation Plans to provide specifics on how their Offices will meet the requirements of the RW SA Program. To assist in the preparation of these Implementation Plans, the RW Self-Assessment Unit (SAU), which manages the SA Program on behalf of the RW Director, has conducted a series of SA Implementation Workshops. The SAU has also developed an Annotated Outline for SA Implementation Plans. Following issuance of Office-specific Implementation Plans, independent evaluations by the SAU are planned

A review of a radioactive material shipping container including design, testing, upgrading compliance program and shipping logistics

International Nuclear Information System (INIS)

Celovsky, A.; Lesco, R.; Gale, B.; Sypes, J.

2003-01-01

Ten years ago Atomic Energy of Canada developed a Type B(U)-85 shipping container for the global transport of highly radioactive materials. This paper reviews the development of the container, including a summary of the design requirements, a review of the selected materials and key design elements, and the results of the major qualification tests (drop testing, fire test, leak tightness testing, and shielding integrity tests). As a result of the testing, improvements to the structural, thermal and containment design were made. Such improvements, and reasons thereof, are noted. Also provided is a summary of the additional analysis work required to upgrade the package from a Type B(U) to a Type B(F), i.e. essentially upgrading the container to include fissile radioisotopes to the authorized radioactive contents list. Having a certified shipping container is only one aspect governing the global shipments of radioactive material. By necessity the shipment of radioactive material is a highly regulated environment. This paper also explores the experiences with other key aspects of radioactive shipments, including the service procedures used to maintain the container certification, the associated compliance program for radioactive material shipments, and the shipping logistics involved in the transport. (author)

UK program: glasses and ceramics for immobilization of radioactive wastes for disposal

International Nuclear Information System (INIS)

Johnson, K.D.B.

1979-01-01

The UK Research Program on Radioactive Waste Management includes the development of processes for the conversion of high-level-liquid-reprocessing wastes from thermal and fast reactors to borosilicate glasses. The properties of these glasses and their behavior under storage and disposal conditions have been examined. Methods for immobilizing activity from other wastes by conversion to glass or ceramic forms are described. The UK philosophy of final solutions to waste management and disposal is presented

Controlling radioactive waste

International Nuclear Information System (INIS)

Wurtinger, W.

1992-01-01

The guideline of the Ministry for Environmental Protection for controlling radioactive waste with a negligible development of heat defines in detail what data are relevant to the control of radioactive waste and should be followed up on and included in a system of documentation. By introducing the AVK (product control system for tracing the course of waste disposal) the operators of German nuclear power plants have taken the requirements of this guideline into account. In particular, possibilities for determining the degree of radioactivity of radioactive waste, which the BMU-guidelines call for, were put into practice by means of the programming technology of the product control system's module MOPRO. (orig.) [de

Results of the third CEC intercomparison of active and passive detectors for the measurement of radon and radon decay products

International Nuclear Information System (INIS)

Miles, J.C.H.; Sinnaeve, J.

1988-01-01

In 1982 and 1984 the radiation protection research programme of the European Communities organized intercomparisons of radon and radon daughter measurement techniques, and the results were published (Miles et al., 1983; Miles and Sinnaeve, 1986. The second of these intercomparisons was carried out as part of a wider exercise sponsored jointly by the CEC and the OECD/NEA (OECD, 1983). The third CEC intercomparison, held at the National Radiological Protection Board (NRPB) in the United Kingdom in 1987, again constituted the European regional part of this wider exercise. The intercomparison on the European region was carried out in two stages, the first for passive integrating detectors and the second for active instruments, usually by spot measurements. Twenty-one laboratories participated in the intercomparison, of passive dosimetry and 17 in that for active dosimetry. Passive detectors have been used in many European countries to carry out surveys of exposure in homes and to monitor occupational exposure. The exposures for the intercomparison of passive detectors were carried out in June, July and August 1987 at NRPB. The intercomparison of active detectors was carried out over three days in October 1987, when scientists from the participating laboratories brought their equipment to NRPB

Low-level radioactive waste, mixed low-level radioactive waste, and biomedical mixed waste

International Nuclear Information System (INIS)

Anon.

1994-01-01

This document describes the proceedings of a workshop entitled: Low-Level Radioactive Waste, Mixed Low-Level Radioactive Waste, and Biomedical Mixed Waste presented by the National Low-Level Waste Management Program at the University of Florida, October 17-19, 1994. The topics covered during the workshop include technical data and practical information regarding the generation, handling, storage and disposal of low-level radioactive and mixed wastes. A description of low-level radioactive waste activities in the United States and the regional compacts is presented

Community Intercomparison Suite (CIS) v1.4.0: A tool for intercomparing models and observations

NARCIS (Netherlands)

Watson-Parris, Duncan; Schutgens, Nick; Cook, Nicholas; Kipling, Zak; Kershaw, Philip; Gryspeerdt, Edward; Lawrence, Bryan; Stier, Philip

2016-01-01

The Community Intercomparison Suite (CIS) is an easy-to-use command-line tool which has been developed to allow the straightforward intercomparison of remote sensing, in-situ and model data. While there are a number of tools available for working with climate model data, the large diversity of

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)

Australian participation in international intercomparisons of environmental dosemeters

International Nuclear Information System (INIS)

Boas, J.F.; David, R.C.; Jones, J.

2002-01-01

The Environmental Measurements Laboratory of the U.S. Department of Energy has conducted international intercomparisons of environmental dosemeters at regular intervals since 1974. This paper reports the results obtained in the 10th and 11th intercomparisons by JFB and JGY at the Australian Radiation Laboratory (in 1992 and 1996 respectively) and in the 12th intercomparison by JFB and DRCT at the Australian Radiation Protection and Nuclear Safety Agency and by JGY and JJ at Australian Radiation Serviceces during 2000 and 2001. The ARL/ARPANSA measurements used a simple dosemeter holder containing two CaSO 4 :Dy impregnated Teflon discs, one unshielded and the other shielded by approximately 2.4 mm of Cu. The ARS measurements used a commercially available TLD badge case containing a CaSO 4 :Dy impregnated Teflon card. The commercial badge case was not symmetrical in design. The filtration in the front and rear sections of the commercial badge case varied from an open area to an area shielded by copper, tin and cadmium. The results obtained were generally within ±15% of the reference values measured by EML using high-pressure ionisation chambers for dosemeters exposed hi the field to environmental radiation and for dosemeters given a single exposure to 137 Cs or 241 Am at EML or an associated laboratory. Similar agreement was obtained for dosemeters exposed in the field and also given a single exposure to 137 Cs radiation. In order to obtain this measure of agreement, the dosemeters were individually calibrated and the readouts corrected for fading. Copyright (2002) Australasian Radiation Protection Society Inc

Preliminary report: STOIC CGCM intercomparison - equatorial sections

International Nuclear Information System (INIS)

Davey, M; Huddleston, M; Sperber, K R.

1999-01-01

An intercomparison and assessment of the tropical behaviour of coupled general circulation models (CGCMs) is being carried out, to identify common strengths and weaknesses and thus guide future CGCM development. The work is being carried out as part of the CLIVAR climate research programme, as a WG-SIP (Working Group on Seasonal to Interannual Prediction) project called STOIC (Study of Tropical Oceans In CGCMs), organised by Michael Davey. This project complements a companion sub-project called ENSIP (El Ni no Simulation Intercomparison Project) organised by Mojib Latif (Max- Planck-Institute for Meteorology) that focusses on equatorial Pacific CGCM behaviour (Latif et al. 1999). Previous coupled model assessments (Mechoso et al. 1995, Neelin et al. 1992, and ENSIP) have focussed on tropical Pacific behaviour. The aim of STOIC is to look at model performance in all tropical ocean regions. This status report contains a sample of the STOIC assessment work, highlighting mean and inter- annual equatorial sea surface temperatures and zonal windstresses. The intention is to submit STOIC and ENSIP papers in mid-1999 for publication together in a refereed journal

Intercomparison of Aerosol Optical Depth from Brewer Ozone spectrophotometers and CIMEL sunphotometers measurements

Directory of Open Access Journals (Sweden)

A. Cheymol

2009-01-01

Full Text Available The Langley plot method applied on the Brewer Ozone measurements can provide accurate Aerosol Optical Depth (AOD in the UV-B. We present seven intercomparisons between AOD retrieved from Brewer Ozone measurements at 320 nm and AOD measured by CIMEL sunphotometer at 340 nm or 440 nm (shifted to 320 nm in using the Angström's law, which are stored in the international AERONET database. Only the intercomparisons between co-located instruments can be used to validate the Langley Plot Method applied to the Brewer measurements: in this case, all the correlation coefficients are above 0.82. If the instruments are not at the same site, the correlation between the AOD retrieved by both instruments is much lower. In applying the Angström's law the intercomparison is improved compared to previous study.

Asian/Australasian region intercalibration and intercomparison programme for radon, thoron and daughters. Asian/Australasian region radon intercomparison, September 1987 - September 1988

Energy Technology Data Exchange (ETDEWEB)

Peggie, J.R.; Gan, Tianghong; Solomon, S.B.

1993-05-01

The International Intercalibration and Intercomparison Programme for radon, thoron and daughters monitoring equipment, abbreviated IIIP, was a programme organized jointly by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development and the Radiation Protection Research Programme of the Commission of European Communities. The broad purpose of the IIIP was to determine if the diverse calibration procedures used in different countries were equivalent. The general approach was to select four regional reference laboratories and entrust then with the details of project definition and execution. The Australian Radiation Laboratory (ARL) was selected to co-ordinate IIIP activities between OECD member countries in the Pacific region. As the regional programme precluded the participation of non-OECD member countries in the Western Pacific Region, an intercomparison series for radon was initiated by ARL in 1987 between twenty eight laboratories from nine countries in the Asian/Australasian region. The methodology and protocols for grab sampler, solid state nuclear track detectors (SSNTD) and charcoal measurements are described in this report. Generally the results showed reasonable agreement between the majority of laboratories for grab sampler measurements consistent with previous intercomparison. However there were large systematic differences in the results of the passive monitors for some laboratories. For all samplers, it was found that the overall random uncertainty or replication error, which included random uncertainties associated with the counting and calibration, were the main sources of variability between individual measurements of participants and the ARL reference value, with calibration uncertainties predominating. 23 tabs.

Asian/Australasian region intercalibration and intercomparison programme for radon, thoron and daughters. Asian/Australasian region radon intercomparison, September 1987 - September 1988

International Nuclear Information System (INIS)

Peggie, J.R.; Gan, Tianghong; Solomon, S.B.

1993-05-01

The International Intercalibration and Intercomparison Programme for radon, thoron and daughters monitoring equipment, abbreviated IIIP, was a programme organized jointly by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development and the Radiation Protection Research Programme of the Commission of European Communities. The broad purpose of the IIIP was to determine if the diverse calibration procedures used in different countries were equivalent. The general approach was to select four regional reference laboratories and entrust then with the details of project definition and execution. The Australian Radiation Laboratory (ARL) was selected to co-ordinate IIIP activities between OECD member countries in the Pacific region. As the regional programme precluded the participation of non-OECD member countries in the Western Pacific Region, an intercomparison series for radon was initiated by ARL in 1987 between twenty eight laboratories from nine countries in the Asian/Australasian region. The methodology and protocols for grab sampler, solid state nuclear track detectors (SSNTD) and charcoal measurements are described in this report. Generally the results showed reasonable agreement between the majority of laboratories for grab sampler measurements consistent with previous intercomparison. However there were large systematic differences in the results of the passive monitors for some laboratories. For all samplers, it was found that the overall random uncertainty or replication error, which included random uncertainties associated with the counting and calibration, were the main sources of variability between individual measurements of participants and the ARL reference value, with calibration uncertainties predominating. 23 tabs

Spectroradiometer Intercomparison and Impact on Characterizing Photovoltaic Device Performance: Preprint

Energy Technology Data Exchange (ETDEWEB)

Habte, A.; Andreas, A.; Ottoson, L.; Gueymard, C.; Fedor, G.; Fowler, S.; Peterson, J.; Naranen, E.; Kobashi, T.; Akiyama, A.; Takagi, S.

2014-11-01

Indoor and outdoor testing of photovoltaic (PV) device performance requires the use of solar simulators and natural solar radiation, respectively. This performance characterization requires accurate knowledge of spectral irradiance distribution that is incident on the devices. Spectroradiometers are used to measure the spectral distribution of solar simulators and solar radiation. On September 17, 2013, a global spectral irradiance intercomparison using spectroradiometers was organized by the Solar Radiation Research Laboratory (SRRL) at the National Renewable Energy Laboratory (NREL). This paper presents highlights of the results of this first intercomparison, which will help to decrease systematic inter-laboratory differences in the measurements of the outputs or efficiencies of PV devices and harmonize laboratory experimental procedures.

A computer program for controlling a university radioactive material inventory: From confusion to computer to control

International Nuclear Information System (INIS)

Robb, D.B.; Riches, C.G.; O'Brian, M.J.; Riordan, F.J.

1984-01-01

The University of Washington is a large user of radioactive material. Over 250 authorized programs are working in over 600 labs with nearly 3500 orders of radioactive material per year. The state license sets limits on the total amount of material on campus. There are also limits on sewer disposal. To meet these needs it is necessary to know the amount of material on campus at any time. A computer program was developed which covered many aspects of the radiation safety record needs including inventory control. Inventory is now managed by tracking each order from purchase to disposal. A screen menu as part of the interactive program allows immediate and detailed information about the inventory at time of purchase approval and delivery. Because of this system our knowledge and control of radionuclide work on campus has increased dramatically. A description of how this system is used during ordering, delivery and disposal will be given. Details on the methods to check limits are included along with a summary of the reports made possible by the current data files

Integrated Management Program for Radioactive Sealed Sources in Egypt IMPRSS

International Nuclear Information System (INIS)

Hasan, A.; El-Adham, K.

2004-01-01

Sealed sources are usually in capsules made of stainless steel. They are the size of a pen or a finger and contain one of hundreds of radioactive elements (e.g., Iridium, Radium) or their isotopes. They are air-tight and very durable, contain the radioactive material but not radiation. They are used in the health sector, industry, military, and universities. Incidents occurred in Met Halfa, Egypt, 2000 (Iridium-192); Goiania, Brazil, 1987 (Cesium-137); Mexico and Southwest U.S., 1977 -1984 (Cobalt-60); Peru, 1999 (Iridium-1992); Poland 2001 (Cobalt-60). The IMPRSS Mission is based on a joined partnership between the Egyptian Atomic Energy Authority, the Egyptian Ministry of Health, the Sandia National Laboratories, the International Atomic Energy Agency and others. The IMPRSS Mission protects human health and the environment in Egypt from mismanaged sealed sources, is developed jointly with MOH and EAEA, provides capabilities for managing radioactive sealed sources in Egypt, increases public awareness, provides education and training, improves emergency response capabilities, develops a permanent disposal facility, ensures the program is self-sustaining and ensures close coordination with the IAEA. Infrastructure how to manage sealed sources is discussed. It includes awareness, tracking and inventory control, security, recovery, conditioning and storage, recycling and disposal. Emergency response, regulatory reform, education and training and its targets are provided. The government of Egypt can protect the people of Egypt and is ready for emergencies. Prevention is the first line of defence and detection is the second line of defence. Adequate Emergency Response saves lives and adequate control reduces risk of mismanaged uses or deliberate misuses of sources. A Cradle-to-Grave approach is built on existing capabilities at EAEA and MOH

Collaboration of the Dutch research program for radioactive waste disposal (OPERA) and TU Delft

International Nuclear Information System (INIS)

Bykov, D.M.; Kloosterman, J.L.

2015-01-01

Radioactive waste in the Netherlands is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval) in the interim storage facility for at least 100 a. After this period of long-term storage, geological disposal is foreseen. The policy is based on a step-wise decision process in which all decisions are taken to ensure safe disposal in a repository, but without excluding unforeseen alternative solutions that might develop in the future. OPERA is the Dutch acronym for research program into geological disposal of radioactive waste. It started in 2011 and is running for five years. The OPERA Research plan is developed by NRG in close collaboration with COVRA. Radioactive waste disposal in the Netherlands is at an early, conceptual phase. The aim of Opera is to develop a first preliminary safety case to structure the research necessary for the eventual deployment of a repository in the Netherlands. The OPERA research program aims at a close cooperation with the Belgian research program on radioactive waste disposal. The result of OPERA will be to detail a first roadmap for the long-term research on geological disposal of radioactive waste in the Netherlands, based initially on a re-evaluation of existing safety and feasibility studies conducted more than ten years ago, making use of present international and, wherever possible, national knowledge. This will be done by developing initial and conditional safety cases for generic GDFs in Zechstein rock salt and Boom Clay formations in the Netherlands. The goal in OPERA is to develop initial safety cases that are intended to mark the start of the research development process and to iterate these as knowledge grows to new developed insights. The safety case is conditional since plausible assumptions must later be confirmed in a safety case e.g. for site selection. Dutch, Belgian, German, English and French organizations participate in OPERA. These organizations can be found in the two documents with

Collaboration of the Dutch research program for radioactive waste disposal (OPERA) and TU Delft

Energy Technology Data Exchange (ETDEWEB)

Bykov, D.M.; Kloosterman, J.L. [TU Delft (Netherlands). Reactor Inst. Delft; Neeft, E.A.C.; Verhoef, E.V. [COVRA N.V., Nieuwdorp (Netherlands)

2015-07-01

Radioactive waste in the Netherlands is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval) in the interim storage facility for at least 100 a. After this period of long-term storage, geological disposal is foreseen. The policy is based on a step-wise decision process in which all decisions are taken to ensure safe disposal in a repository, but without excluding unforeseen alternative solutions that might develop in the future. OPERA is the Dutch acronym for research program into geological disposal of radioactive waste. It started in 2011 and is running for five years. The OPERA Research plan is developed by NRG in close collaboration with COVRA. Radioactive waste disposal in the Netherlands is at an early, conceptual phase. The aim of Opera is to develop a first preliminary safety case to structure the research necessary for the eventual deployment of a repository in the Netherlands. The OPERA research program aims at a close cooperation with the Belgian research program on radioactive waste disposal. The result of OPERA will be to detail a first roadmap for the long-term research on geological disposal of radioactive waste in the Netherlands, based initially on a re-evaluation of existing safety and feasibility studies conducted more than ten years ago, making use of present international and, wherever possible, national knowledge. This will be done by developing initial and conditional safety cases for generic GDFs in Zechstein rock salt and Boom Clay formations in the Netherlands. The goal in OPERA is to develop initial safety cases that are intended to mark the start of the research development process and to iterate these as knowledge grows to new developed insights. The safety case is conditional since plausible assumptions must later be confirmed in a safety case e.g. for site selection. Dutch, Belgian, German, English and French organizations participate in OPERA. These organizations can be found in the two documents with

Radioactivity and environment

Energy Technology Data Exchange (ETDEWEB)

Trivedi, R N [Fertilizer Association of India, New Delhi

1977-12-01

Power generation from radioisotopes is one of the major applications of nuclear energy for peaceful purposes and is in practice in over twenty countries including India. Other well-known applications of radioactive substances are in medicine, industry, scientific and industrial research programs, and nuclear weapons. The only serious disadvantage with the radioisotopes and their waste products is the constant release of radiation energy which contaminates the environment and endangers the life. An attempt has been made to identify the major sources of radioactivity in the environment and assess its potential impact on the environment. Recent developments in safety measures for prevention of contamination and control of radioactivity and in radioactive wastes management are also discussed.

University program in hazardous chemical and radioactive waste management

International Nuclear Information System (INIS)

Parker, F.L.

1987-01-01

The three main functions of a university program are education, training, and research. At Vanderbilt University, there is a Solid and Hazardous Waste option in the Master of Science in Engineering Program. The two main foci are treatment of wastes and environmental transport and transformation of the wastes. Courses in Hazardous Waste Engineering and Radioactive Waste Disposal present a synoptic view of the field, including legal, economic, and institutional aspects as well as the requisite technical content. The training is accomplished for some of the students through the aegis of an internship program sponsored by the US Department of Energy. In the summer between the two academic years of the program, the study works at a facility where decontamination and/or decommissioning and/or remedial actions are taking place. Progress in understanding the movement, transformation, and fate of hazardous materials in the environment is so rapid that it will not be possible to be current in the field without participating in that discovery. Therefore, their students are studying these processes and contributing to new knowledge. Some recent examples are the study of safety factors implicit in assuming a saturated zone below a hazardous waste landfill when an unsaturated zone exists, application of probabilistic risk assessment to three National Priority List sites in Tennessee, and the explanation of why certain organics precede pH, conductivity and nitrates through a clay liner at a hazardous waste disposal site

Directory of certificates of compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1988-12-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

BIPM project: Intercomparison of water triple-point cells

Science.gov (United States)

Chattle, M. V.; Butler, J.

1994-12-01

The paper presents the results of an intercomparison between 3 triple point of water cells circulated by the Bureau International des Poids et Measures (BIPM), and a cell which is one of those used as a reference cell at the National Physical Laboratory (NPL). All 4 cells were prepared, stored and measured in the manner normally adopted at NPL. The results of the intercomparison show that over the course of about 6 weeks the temperatures of the 3 circulated cells generally agreed within 0.20 mK, with a maximum difference of 0.27(7) mK. Over the same period, the total variations of temperature measured in the 3 individual cells were 0.04 mK, 0.08 mK and 0.18 mK, respectively; the NPL cell varied by 0.10 mK. Gallium point measurements made over a similar period confirmed that these differences were partly due to small drifts in the thermometer resistance or in the measuring system.

Intercomparison 2003 for Radon measurement services at PSI

CERN Document Server

Butterweck, G

2003-01-01

Twelve radon measurement services participated in the 2003 Radon Intercomparison Exercise performed at the Reference Laboratory for Radon Gas Activity Concentration Measurements at Paul Scherrer Institut (PSI) during March 13th to 24th, 2003. Ten of these laboratories were approved by the Swiss Federal Office of Public Health and their participation in the intercomparison exercise was a requirement to warrant quality of measurement. Radon gas detectors (etched-track and electret ionisation chambers) and instruments (ionisation chambers and electrostatic precipitation) were exposed in the PSI Radon Chamber in a reference atmosphere with an average radon gas concentration of 1950 Bqm sup - sup 3 leading to a radon gas exposure of 517 kBqhm sup - sup 3. Additional five electret-detectors of an approved measuring service were purchased by the Swiss Federal Office of Public Health for a spot check. Two of these were exposed as described above, two had an exposure of 247 kBqhm sup - sup 3 at an average radon concen...

An international intercomparison of passive dosemeters, electronic dosemeters and dose rate meters used for environmental radiation measurements

DEFF Research Database (Denmark)

Bøtter-Jensen, L.; Thompson, I.M.G.

1995-01-01

during 1994. The intercomparison was organised by the Physikalisch Technische Bundesanstalt (PTB), Braunschweig, Germany, and by the Riso National Laboratory, Roskilde, Denmark. This paper describes the intercomparison experiments performed at the newly established Riso Natural Environmental Radiation...

The role of the EPA radiation quality assurance program in the measurement quality assurance accreditation program for radioassay laboratories

Energy Technology Data Exchange (ETDEWEB)

Grady, T.M. [Environmental Monitoring Systems Laboratory, Las Vegas, NV (United States)

1993-12-31

As the nature and extent of radiological contamination becomes better documented and more public, radioanalytical laboratories are faced with a constantly expanding variety of new and difficult analytical requirements. Concurrent with those requirements is the responsibility to provide customers, regulatory officials, or the public with defensible data produced in an environment of verifiable, controlled quality. To meet that need, a quality assurance accreditation program for radioassay laboratories has been proposed by the American National Standards Institute (ANSI). The standard will provide the organizational framework and functional requirements needed to assure the quality of laboratory outputs. Under the proposed program, the U.S. Environmental Protection Agency`s (EPA`s) Laboratory Intercomparison Program plays a key role as a reference laboratory. The current and proposed roles of the EPA Intercomparison Program are discussed, as are the functional relationships between EPA, the accreditating organization, and the service and monitoring laboratories.

Airborne hygrometer calibration inter-comparison against a metrological water vapour standard

Science.gov (United States)

Smorgon, Denis; Boese, Norbert; Ebert, Volker

2014-05-01

Water vapour is the most important atmospheric greenhouse gas, which causes a major feedback to warming and other changes in the climate system. Knowledge of the distribution of water vapour and its climate induced changes is especially important in the upper troposphere and lower stratosphere (UT/LS) where vapour plays a critical role in atmospheric radiative balance, cirrus cloud formation, and photochemistry. But, our understanding of water in the UT/LS is limited by significant uncertainties in current UT/LS water measurements. One of the most comprehensive inter-comparison campaigns for airborne hygrometers, termed AQUAVIT (AV1) [1], took place in 2007 at the AIDA chamber at the Karlsruhe Institute of Technology (KIT) in Germany. AV1 was a well-defined, referred, blind inter-comparison of 22 airborne field instruments from 17 international research groups. One major metrological deficit of AV1, however, was, that no traceable reference instrument participated in the inter-comparison experiments and that the calibration procedures of the participating instruments were not monitored or interrogated. Consequently a follow-up inter-comparison was organized in April 2013, which for the first time also provides a traceable link to the international humidity scale. This AQUAVIT2 (AV2) campaign (details see: http://www.imk-aaf.kit.edu/aquavit/index.php/Main_Page) was again located at KIT/AIDA and organised by an international organizing committee including KIT, PTB, FZJ and others. Generally AV2 is divided in two parallel comparisons: 1) AV2-A uses the AIDA chamber for a simultaneous comparison of all instruments (incl. sampling and in-situ instruments) over a broad range of conditions characteristic for the UT/LS; 2) AV2-B, about which this paper is reporting, is a sequential comparison of selected hygrometers and (when possible) their reference calibration infrastructures by means of a chilled mirror hygrometer traced back to the primary National humidity standard

Radioactivity from Plowshare applications - Safety considerations

Energy Technology Data Exchange (ETDEWEB)

Tewes, H A [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

1970-05-01

When the Plowshare Program was first being seriously considered some 13 years ago, a number of applications immediately suggested themselves. However, it soon became obvious that most of these applications had the drawback of producing and distributing appreciable quantities of radioactivity to the environment. Thus, the Atomic Energy Commission, together with its contractors, formulated and put into effect a program aimed at dealing with this problem, both from the standpoint of reducing the amount of radioactivity released to the environment and understanding the impact of this radioactivity on the biosphere.

Radioactivity from Plowshare applications - Safety considerations

International Nuclear Information System (INIS)

Tewes, H.A.

1970-01-01

When the Plowshare Program was first being seriously considered some 13 years ago, a number of applications immediately suggested themselves. However, it soon became obvious that most of these applications had the drawback of producing and distributing appreciable quantities of radioactivity to the environment. Thus, the Atomic Energy Commission, together with its contractors, formulated and put into effect a program aimed at dealing with this problem, both from the standpoint of reducing the amount of radioactivity released to the environment and understanding the impact of this radioactivity on the biosphere

Statistical intercomparison of global climate models: A common principal component approach with application to GCM data

International Nuclear Information System (INIS)

Sengupta, S.K.; Boyle, J.S.

1993-05-01

Variables describing atmospheric circulation and other climate parameters derived from various GCMs and obtained from observations can be represented on a spatio-temporal grid (lattice) structure. The primary objective of this paper is to explore existing as well as some new statistical methods to analyze such data structures for the purpose of model diagnostics and intercomparison from a statistical perspective. Among the several statistical methods considered here, a new method based on common principal components appears most promising for the purpose of intercomparison of spatio-temporal data structures arising in the task of model/model and model/data intercomparison. A complete strategy for such an intercomparison is outlined. The strategy includes two steps. First, the commonality of spatial structures in two (or more) fields is captured in the common principal vectors. Second, the corresponding principal components obtained as time series are then compared on the basis of similarities in their temporal evolution

International program: Feasibility of the evacuation of high-level radioactive wastes under the ocean depths. (Seabed Program)

International Nuclear Information System (INIS)

Barbreau, A.

1990-01-01

The Seabed feasibility program is an international scientific program of research on the feasibility of the disposal of high-level radioactive wastes into the geological formations making up the floor of the great abyssal plains of the oceans. Decided in 1977, the program is aimed at answering the three following questions: 1) are there potentially favourable sites. 2) is the disposal of wastes possible. 3) does the operation present safety guarantees. First initiated by four countries (USA, UK, Japan and France), the program sponsored by the OECD nuclear energy agency was gathering ten countries and the Commission of the European communities in 1988. The techniques of waste disposal by means of drilling in consolidated sediments and penetrators in loose sediments have been studied. The penetrator technique has been the most thoroughly studied, especially through in situ experiments in the Atlantic ocean. The various factors affecting safety have been studied and the radiological consequences of a burial operation assessed through models. It has been concluded that such an operation could be carried out technically under quite satisfying conditions [fr

Environmental system applied to radioactive liquid effluent release

International Nuclear Information System (INIS)

Nisti, Marcelo Bessa

2009-01-01

The current environmental administration considers the productive activity as an environmental system, defined as a group of processes, interactions, parameters and factors involved in the production. This mastering dissertation evaluated the release of the liquid radioactive effluents at Instituto de Pesquisas Energeticas e Nucleares (IPEN), under a systemic environmental study. The study evaluated the source term at IPEN in the period from 2004 to 2008, making use of gamma-ray and alpha spectrometry, instrumental neutron activation analysis, liquid phase scintillation and atomic absorption spectrometry. The employed methodologies were verified using samples from the Intercomparison National Program - PNI/IRD and Reference Materials. The facilities that contributed the most in these releases were the Radiopharmaceutical Center (CR) and the Research Reactor Center (CRPq) with an average of 11,4% and 87,4%, respectively, relative to the present radioactive activity. The sewer system releases were within the radioactive protection regulations, showing the effectiveness of IPEN's Radioactive Effluents Monitoring Program. The concentration of the stable elements Ag, Cd, Cr, Fe, Mn, Ni, Pb and Zn was determined in the liquid effluent in ali the samples from the storage tanks TR1 and CR in the period from 2004 to 2008 and in some of the samples of other IPEN's facilities in the period from 2004 to 2007. Among the analyzed effluents, two samples were higher than the stable elements discharge standards established in the state of Sao Paulo, one sample was higher than the required value of the element cadmium and the other higher than required value of the element zinco The storage tank TR1 discharge flow was estimated in 10,9 ± 0,9 m3 h -1 . The dilution factor at discharge point E1 was estimated using a radiotracers the isotopes 3 H, 137 CS, 60 Co, 54 Mn and 65 Zn, which are commonly released into IPEN's sewer system. The executed radiotracer study was carried out

Status of environmental response efforts at radioactively contaminated sites in the united states air force installation restoration program

International Nuclear Information System (INIS)

Rowe, W.D. Jr.; McEntee, T.E. Jr.; Johnson, B.; Manning, L.

1995-01-01

The United States Air Force has identified approximately 170 radioactively contaminated sites at its domestic installations. These sites contain a variety of low level radioactive and mixed wastes and are classified as burial sites, landfills, buildings, and other disposal sites. Of these 170, approximately 70 are presently being evaluated under the Air Force Installation Restoration Program (IRP) in accordance with applicable laws and regulations. Removal and/or remedial actions have been taken at specific sites using site-specific residual radioactivity criteria. The remaining sites are either under investigation to determine the need for possible action or have been classified as response complete based on restricted or unrestricted future use. This paper describes past Air Force operations that generated radioactive waste materials; examines the current inventory of resulting radioactively contaminated sites in the Air Force IRP; reviews criteria used to evaluate sites for removal and/or remedial actions; provides summary information on actions taken at sites; and focuses on response actions and cleanup levels at two completed sites. The paper concludes with an assessment of outstanding issues relevant to the remediation of radioactively contaminated sites. (author)

An intercomparison exercise on radionuclides in sediment samples

Energy Technology Data Exchange (ETDEWEB)

Nielsen, S.P.

1996-07-01

An intercomparison exercise on artificial and natural radionuclides in two sediment samples, one from the Baltic Sea and one from the Kattegat, has been carried out under the EKO-1 project or the Nordic Safety Research Programme (NKS) for the period 1996-97. The measurement techniques have included direct gamma-ray spectrometry with Ge and NaI detectors, and radiochemical procedures followed by beta counting and alpha spectrometry. The participants have 21 laboratories. Results were submitted for Cs-137, Cs-134, Co-60, Sb-125, Pu-239,240, Pu-238, Am-241, Sr-90, Ra-226, Th-232 and K-40, Pb-210, Po-210 and U-235. The analytical performance of the participants was evaluated for those radionuclides where six or more data sets were received. Statistical tests were made to see if individual results agreed with overall average radionuclide concentrations in the two sediment materials within target standard deviations. The results of these tests show that for Cs-137, Cs-134, Ra-226, Th-232 and K-40 the analytical performance criteria were not met for 20-40% of the data sets. For plutonium isotopes the tests show that the performance criteria were not met for 13% of the data sets. Tests of overall analytical performance show that 61% of the data sets do not meet the combined performance criteria. This shows that there is room for considerable improvement of analytical quality for most of the laboratories that have participated in this intercomparison. The intercomparison exercise has furthermore demonstrated several elementary problems in analytical work. (au) 57 tabs., 16 ills., 1 ref.

An intercomparison exercise on radionuclides in sediment samples

International Nuclear Information System (INIS)

Nielsen, S.P.

1996-07-01

An intercomparison exercise on artificial and natural radionuclides in two sediment samples, one from the Baltic Sea and one from the Kattegat, has been carried out under the EKO-1 project or the Nordic Safety Research Programme (NKS) for the period 1996-97. The measurement techniques have included direct gamma-ray spectrometry with Ge and NaI detectors, and radiochemical procedures followed by beta counting and alpha spectrometry. The participants have 21 laboratories. Results were submitted for Cs-137, Cs-134, Co-60, Sb-125, Pu-239,240, Pu-238, Am-241, Sr-90, Ra-226, Th-232 and K-40, Pb-210, Po-210 and U-235. The analytical performance of the participants was evaluated for those radionuclides where six or more data sets were received. Statistical tests were made to see if individual results agreed with overall average radionuclide concentrations in the two sediment materials within target standard deviations. The results of these tests show that for Cs-137, Cs-134, Ra-226, Th-232 and K-40 the analytical performance criteria were not met for 20-40% of the data sets. For plutonium isotopes the tests show that the performance criteria were not met for 13% of the data sets. Tests of overall analytical performance show that 61% of the data sets do not meet the combined performance criteria. This shows that there is room for considerable improvement of analytical quality for most of the laboratories that have participated in this intercomparison. The intercomparison exercise has furthermore demonstrated several elementary problems in analytical work. (au) 57 tabs., 16 ills., 1 ref

Analysis of the REAL-84 intercomparison exercise

International Nuclear Information System (INIS)

1987-10-01

The document presents the conclusions and the recommendations of the specialists' meeting organized by the IAEA and held in Jackson Hole (USA) between 27-29 May 1987 as a result of the analysis of the REAL-84 intercomparison exercise for improving the accuracy in radiation damage predictions in the neutron environment using good quality input data and proper calculation methods. 6 refs

Teaching Radioactive Waste Management in an Undergraduate Engineering Program - 13269

Energy Technology Data Exchange (ETDEWEB)

Ikeda, Brian M. [Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada)

2013-07-01

The University of Ontario Institute of Technology is Ontario's newest university and the only one in Canada that offers an accredited Bachelor of Nuclear Engineering (Honours) degree. The nuclear engineering program consists of 48 full-semester courses, including one on radioactive waste management. This is a design course that challenges young engineers to develop a fundamental understanding of how to manage the storage and disposal of various types and forms of radioactive waste, and to recognize the social consequences of their practices and decisions. Students are tasked with developing a major project based on an environmental assessment of a simple conceptual design for a waste disposal facility. They use collaborative learning and self-directed exploration to gain the requisite knowledge of the waste management system. The project constitutes 70% of their mark, but is broken down into several small components that include, an environmental assessment comprehensive study report, a technical review, a facility design, and a public defense of their proposal. Many aspects of the project mirror industry team project situations, including the various levels of participation. The success of the students is correlated with their engagement in the project, the highest final examination scores achieved by students with the strongest effort in the project. (authors)

Teaching Radioactive Waste Management in an Undergraduate Engineering Program - 13269

International Nuclear Information System (INIS)

Ikeda, Brian M.

2013-01-01

The University of Ontario Institute of Technology is Ontario's newest university and the only one in Canada that offers an accredited Bachelor of Nuclear Engineering (Honours) degree. The nuclear engineering program consists of 48 full-semester courses, including one on radioactive waste management. This is a design course that challenges young engineers to develop a fundamental understanding of how to manage the storage and disposal of various types and forms of radioactive waste, and to recognize the social consequences of their practices and decisions. Students are tasked with developing a major project based on an environmental assessment of a simple conceptual design for a waste disposal facility. They use collaborative learning and self-directed exploration to gain the requisite knowledge of the waste management system. The project constitutes 70% of their mark, but is broken down into several small components that include, an environmental assessment comprehensive study report, a technical review, a facility design, and a public defense of their proposal. Many aspects of the project mirror industry team project situations, including the various levels of participation. The success of the students is correlated with their engagement in the project, the highest final examination scores achieved by students with the strongest effort in the project. (authors)

An intercomparison of Canadian external dosimetry processors for radiation protection

International Nuclear Information System (INIS)

1989-10-01

The five Canadian external dosimetry processors have participated in a two-stage intercomparison. The first stage involved dosimeters to known radiation fields under controlled laboratory conditions. The second stage involved exposing dosimeters to radiation fields in power reactor working environments. The results for each stage indicated the dose reported by each processor relative to an independently determined dose and relative to the others. The results of the intercomparisons confirm the original supposition: namely that the average differences in reported dose among five processors are much less than the uncertainty limits recommended by the ICRP. This report provides a description of the experimental methods as well as a discussion of the results for each stage. The report also includes a set of recommendations

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).

The results obtained by INR-Pitesti to an international in-situ intercomparison exercise

International Nuclear Information System (INIS)

Dobrin, Relu; Dulama, Cristian; Toma, Alexandru

2008-01-01

Full text: The determination of soil contamination, dose rate measurements and in-situ gamma spectrometry are well established and widely used measurement procedures, especially after large scale nuclear incidents. To support decision makers and first responders with a more comprehensive and accurate overview immediately after a large scale nuclear or radiological emergency, as releases from a nuclear power plant or a terrorist attack with a dirty bomb, a fast and clear presentation of measurement data is indispensable. In 2007, the Austrian Research Centers GmbH - ARC (Seibersdorf) in cooperation with IAEA and the Austrian NBC Defense School organized an international measurement campaign, 'In-Situ Intercomparison Scenario' ISIS 2007, with the focus on In-Situ Gamma Spectrometry and Dose Rate Measurements in Emergency Situations. 56 teams from 25 countries, worldwide, took part to this exercise. The only Romanian team was 'CROWN'. The CROWN Laboratory is part of the Radiation Protection Laboratory of the Institute for Nuclear Research - Pitesti, certified for characterization of radioactive wastes and nuclear materials. The paper presents results obtained during different tasks of the exercise: 'Dose rate mapping'; 'Localization - Drive by'; 'Simulation of a contamination'; 'Identification Shielded; 'Identification/Quantification'; 'Buried sources; 'Environmental measurement'. (authors)

Separating defence and civilian radioactive waste programs in Nevada: can the public navigate the maze?

International Nuclear Information System (INIS)

Nielsen, R.A.

1999-01-01

Nevada is at the centre of public policy debate with regards to high and low level radioactive waste disposal. Nevada's Yucca Mountain is the only site under consideration for a US geologic repository for commercial spent nuclear fuel and defence high level waste. The Nevada Test Site (NTS) has long been a low level waste (LLW) disposal facility for the Department of Energy (DOE) defence waste and is now expected to take even more LLW as the preferred site for a regional or centralised disposal facility. Furthermore, the primary mission at NTS, defence, continues to add more contamination to the site. Combined, these facts present a public policy enigma, confused further by the intentional separation of the programs by DOE, even though all are essentially conducted at the same site. Involving the public in policy decisions for these programs is a dilemma because the public does not make the same artificial distinctions between them as DOE, DOE credibility suffers from past public involvement efforts conducted during an era of Cold War secrecy and because DOE public involvement programs are operated independently, with little or no co-operation between programs. The public does not know where it fits into the DOE decision-making process or if it impacts the policy decisions being made that affect it. This paper examines the complex maze of radioactive policy and bureaucracy in order to unveil the enigma Nevada residents face. Are they able to navigate this maze to effectively participate in government policy and decision-making? Or, will they remain confused by the government bureaucracy which deliberately makes a mess of the situation and seeks to exploit a politically weak state with large tracts of federally controlled land? lt further evaluates the effect this enigma has in producing acceptable public policy for radioactive waste disposal in the US, the role of public participation in that policy, and the reason the public is disillusioned and disengaged in the

Artificial radioactivity in the environmental samples as IAEA reference materials

International Nuclear Information System (INIS)

Salagean, M.; Pantelica, A.

1998-01-01

Radioactivity levels of 110m Ag, 241 Am, 60 Co, 134 Cs, 137 Cs, 106 Ru, 125 Sb in some biological and environmental materials have been determined by gamma-ray spectrometry in the frame of 15 intercomparison runs organized by IAEA during 1986-1995. The investigated materials were polluted by various nuclear activities, as follows: 1. Nuclear experiments: IAEA-367, sediment collected in 1982 at the Enewetak Atoll (Marshall Islands in the Pacific Ocean). This atoll was used by the USA during 1948-1958 to test nuclear devices; IAEA-368, sediment collected in June 1989 from the Pacific Ocean at the Mururoa Atoll. Since 1966 this atoll has been used by France to test different nuclear devices. 2. Nuclear installations: IAEA-134, cockle flesh of Cardium edule collected in March 1991 from the Irish Sea (Morecambe Bay), England, about 45 km S-E of Sellafield radioactive discharge; IAEA-135, sediment collected in July 1991 in Lune Estuary-England. This area is influenced by the radioactive discharges of the nuclear installations of Sellafield; IAEA-326, soil collected in 1990 in the region of Kursk Atomic Power Plant (Russia). 3. Nuclear accidents (Chernobyl): IAEA-306, sediment collected in the Baltic Sea during October-November 1986; IAEA-307, seaplant Posidonia oceanica, collected in October 1986 in Mediterranean Sea along the shore, in the vicinity of the Principality of Monaco; IAEA-308, mixed seaweeds collected in October 1986 in Mediterranean Sea along the shore, in the vicinity of the Principality of Monaco; IAEA-156, clover collected during the summer harvest 1986 in Austria; IAEA-321, milk powder collected in autumn 1987 from a processing plant in Europe; IAEA-352, tuna fish flesh collected in April 1988 in the Western Mediterranean Sea; IAEA-373, grass collected from Kiev region during the summer harvest 1990; IAEA-375, soil collected in July 1990 from Brjansk region, Russia; IAEA-300, sediment collected in July 1992 in Bothnian Sea (Baltic Sea). 4

INTERCOMPARISON OF RESULTS FOR A PWR ROD EJECTION ACCIDENT

Energy Technology Data Exchange (ETDEWEB)

DIAMOND,D.J.; ARONSON,A.; JO,J.; AVVAKUMOV,A.; MALOFEEV,V.; SIDOROV,V.; FERRARESI,P.; GOUIN,C.; ANIEL,S.; ROYER,M.E.

1999-10-01

This study is part of an overall program to understand the uncertainty in best-estimate calculations of the local fuel enthalpy during the rod ejection accident. Local fuel enthalpy is used as the acceptance criterion for this design-basis event and can also be used to estimate fuel damage for the purpose of determining radiological consequences. The study used results from neutron kinetics models in PARCS, BARS, and CRONOS2, codes developed in the US, the Russian Federation, and France, respectively. Since BARS uses a heterogeneous representation of the fuel assembly as opposed to the homogeneous representations in PARCS and CRONOS, the effect of the intercomparison was primarily to compare different intra-assembly models. Quantitative comparisons for core power, reactivity, assembly fuel enthalpy and pin power were carried out. In general the agreement between methods was very good providing additional confidence in the codes and providing a starting point for a quantitative assessment of the uncertainty in calculated fuel enthalpy using best-estimate methods.

Radioactive waste management in Slovenia

International Nuclear Information System (INIS)

Fink, K.

1992-01-01

The problem of radioactive waste management is both scientifically and technically complex and also deeply emotional issue. In the last twenty years the first two aspects have been mostly resolved up to the point of safe implementation. In the Republic of Slovenia, certain fundamentalist approaches in politics and the use of radioactive waste problem as political marketing tool, make things even more complex. Public involvement in planning and development of radioactive waste management program must be perceived as essential for the success of the program. Education is a precursor to public comprehension and confidence which lead to adequate waste management decisions that will protect the public health, safety and environment without jeopardizing further progress and development. (author) [sl

Analysis of international intercomparisons results organized by Japan for integrating 222Rn-220Rn detectors

International Nuclear Information System (INIS)

Wu Yunyun; Cui Hongxing; Zhang Qingzhao; Shang Bing; Su Xu

2012-01-01

Objective: To guarantee the quality of measurements with the radon-thoron discriminative detectors of our laboratory. Methods: LD-P radon-thoron discriminative detector participated in the international intercomparison for integrating radon/thoron detectors organized by National Institute of Radiological Science (NIRS, Japan). Detectors were sent to NIRS for exposure. Radon intercomparison was conducted with radon chamber providing three levels of exposure: low, medium and high levels. Thoron intercomparison was carried out at thoron chamber, which also provided three levels of exposure: low, medium and high levels. Detectors were posted back to our laboratory for etching and analysis after exposure. Then the measured values were submitted to NIRS. Finally the reference values were informed of us. Results: The relative percent difference (RPD) between the measured value and the reference value for radon was -13.8%, -14.4% and -17.1% at low, medium and high levels respectively, and that of thoron were -14.4%, 8.9% and -3.2% at three levels respectively. Conclusions: Both radon and thoron measurement of our detectors rank as 'Category Ⅰ' in the 4th international intercomparisons for integrating radon/thoron detectors with the NIRS radon/thoron chambers. (authors)

Summary of national and international fuel cycle and radioactive waste management programs, 1984

Energy Technology Data Exchange (ETDEWEB)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-07-01

Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories.

Summary of national and international fuel cycle and radioactive waste management programs, 1984

International Nuclear Information System (INIS)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-07-01

Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories

Design and results of the ice sheet model initialisation initMIP-Greenland: an ISMIP6 intercomparison

Directory of Open Access Journals (Sweden)

H. Goelzer

2018-04-01

Full Text Available Earlier large-scale Greenland ice sheet sea-level projections (e.g. those run during the ice2sea and SeaRISE initiatives have shown that ice sheet initial conditions have a large effect on the projections and give rise to important uncertainties. The goal of this initMIP-Greenland intercomparison exercise is to compare, evaluate, and improve the initialisation techniques used in the ice sheet modelling community and to estimate the associated uncertainties in modelled mass changes. initMIP-Greenland is the first in a series of ice sheet model intercomparison activities within ISMIP6 (the Ice Sheet Model Intercomparison Project for CMIP6, which is the primary activity within the Coupled Model Intercomparison Project Phase 6 (CMIP6 focusing on the ice sheets. Two experiments for the large-scale Greenland ice sheet have been designed to allow intercomparison between participating models of (1 the initial present-day state of the ice sheet and (2 the response in two idealised forward experiments. The forward experiments serve to evaluate the initialisation in terms of model drift (forward run without additional forcing and in response to a large perturbation (prescribed surface mass balance anomaly; they should not be interpreted as sea-level projections. We present and discuss results that highlight the diversity of data sets, boundary conditions, and initialisation techniques used in the community to generate initial states of the Greenland ice sheet. We find good agreement across the ensemble for the dynamic response to surface mass balance changes in areas where the simulated ice sheets overlap but differences arising from the initial size of the ice sheet. The model drift in the control experiment is reduced for models that participated in earlier intercomparison exercises.

DOE program for improvement practices for shallow burial of radioactive waste

International Nuclear Information System (INIS)

Dieckhoner, J.E.

1978-01-01

The practice of burying solid radioactive waste in relatively shallow pits or trenches at government nuclear sites dates back to the Manhattan Project. In some cases, where local conditions were considered unfavorable, intersite shipment of waste has been required. This general concept was later used at commercially-operated sites under Federal or state regulation. The purpose, scope, and results of a DOE program begun several years ago for improvements of burial ground disposal methods are reviewed. The program includes the re-evaluation of the original siting and of operating practices at existing burial grounds (including monitoring for migration of activity); the development of improved criteria for siting of new grounds that might be required as the defense site operations continue; and development of corrective measures such as diking and better draining for possible unsatisfactory conditions that might be detected. The possible applications of these findings to commercial burial grounds is discussed

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

Final report of the Department of Energy pilot internship program on radioactive waste at Vanderbilt University (September 1, 1993-08/31, 1994)

Energy Technology Data Exchange (ETDEWEB)

Frank Parker

1999-08-31

This final report summarizes Vanderbilt's ten year program in radioactive waste management. The report describes the interns selected for the program, the interns' course of study, and their assignments.

Beta dosimetry using partial body dosimeters II. Results of intercomparison measurements of 1998/1999 - PTB report

International Nuclear Information System (INIS)

Ambrosi, P.; Helmstaedter, K.

2000-12-01

In 1998 the PTB organised a second series of intercomparison measurements for selected beta dosimeters worn on the extremities. In April 1999 these intercomparison measurements and the results obtained were discussed in a one day meeting. The contributions given and the results obtained and the conclusions drawn after extensive discussions are presented in this PTB report. (orig.) [de

Report on the intercomparison for the isotope standards limestone KH 2 and polyethylene foil PEF 1

International Nuclear Information System (INIS)

Gerstenberger, H.; Herrmann, M.

1983-01-01

The isotope abundance of 13 C and 18 O of a carbonate was measured by an intercomparison in order to create a new working standard for the mass spectrometric determination of isotopic variations in natural materials. For the same purpose a polyethylene was subjected an intercomparison and the abundance of 13 C and D has been determined. (author)

Development of the Discrimination Programs between the Internal and External Radioactive Contamination of Workers Using a Whole Body Counter

International Nuclear Information System (INIS)

Kong, T. Y.; Kim, H. G.; Lim, S. N.; Kim, H. J.; Jin, H. H.; Lee, S. G.; Park, S. C.

2006-01-01

A whole body counter (WBC) is used to identify and measure the radioactivity in the body of human beings in a nuclear power plant (NPP). In domestic NPPs, several whole body counters are in operation to monitor the internal radioactive contamination of workers. All workers take a whole body counting after radiation works if there is high possibility of radioactive contamination or the radioactivity is detected by portal monitoring. It is, however, found that the external contamination is occasionally estimated as the internal radioactive contamination. In this case, the worker is recommended to take showers for the decontamination of skin and take a whole body counting again. Although the detected radioactivity is reduced remarkably after several decontaminations, confirmed as the external contamination, it is determined finally as an internal contamination if the radioactivity is still detected in the body of worker. The amount of detected radioactivity can be much higher than that of the expected for this mistaken contamination since the radioisotopes attached to skin come to be close to the detectors of WBC. Finally, this makes not only the misjudgment of the external contamination as the internal contamination, but also the excessively conservative estimation of radioactive contamination. In this study, several experiments were carried out to set up the discrimination program between the internal and external radioactive contamination using the humanoid phantom and a whole body counter. After the analysis of experimental results, we found that the use of front and backside counts could be applied to the discrimination of the external contamination and the ratio of detected radioactivities between front and backside counts was more than about factor 2 for the external contamination

Preliminary report on an intercomparison of methods for processing Ge(Li) gamma-ray spectra

International Nuclear Information System (INIS)

Parr, R.M.; Houtermans, H.; Schaerf, K.

1978-01-01

An intercomparison has been organized by the IAEA for the purpose of evaluating methods for processing Ge(Li) gamma-ray spectra. These spectra cover an energy range of about 1MeV and, with one exception, contain only well separated single peaks; another spectrum contains double peaks with various relative intensities and degrees of overlap. The spectra were prepared in such a way that the areas and positions of all peaks, relative to a standard spectrum which is also provided, are known exactly. The intercomparison enables the user to test the ability of his methods (1) to detect small peaks near the limit of detectability; (2) to determine the position and area of more easily detectable peaks, and (3) to determine the position and area of overlapping double peaks. The method of preparation of the spectra and the organization of the intercomparison are described in this report. (author)

Total ozone measurement: Intercomparison of prototype New Zealand filter instrument and Dobson spectrophotometer

Science.gov (United States)

Basher, R. E.

1978-01-01

A five month intercomparison showed that the total ozone amounts of a prototype narrowband interference filter instrument were 7% less than those of a Dobson instrument for an ozone range of 0.300 to 0.500 atm cm and for airmasses less than two. The 7% bias was within the intercomparison calibration uncertainty. An airmass dependence in the Dobson instrument made the bias relationship airmass-dependent but the filter instrument's ozone values were generally constant to 2% up to an airmass of four. Long term drift in the bias was negligible.

Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Environmental monitoring and surveillance programs

International Nuclear Information System (INIS)

Denham, D.H.; Stenner, R.D.; Eddy, P.A.; Jaquish, R.E.; Ramsdell, J.V. Jr.

1988-07-01

Licensing of a facility for low-level radioactive waste disposal requires the review of the environmental monitoring and surveillance programs. A set of review criteria is recommended for the US Nuclear Regulatory Commission (NRC) staff to use in each monitoring phase---preoperational, operational, and post operational---for evaluating radiological and selected nonradiological parameters in proposed environmental monitoring and surveillance programs at low-level waste disposal facilities. Applicable regulations, industry standards, and technical guidance on low-level radioactive waste are noted throughout the document. In the preoperational phase, the applicant must demonstrate that the environmental monitoring program identifies radiation levels and radionuclide concentrations at the site and also provides adequate basic data on the disposal site. Data recording and statistical analyses for this phase are addressed

The influence of uncertainties of measurements in laboratory performance evaluation by intercomparison program in radionuclide analyses of environmental samples

International Nuclear Information System (INIS)

Tauhata, L.; Vianna, M.E.; Oliveira, A.E. de; Clain, A.F.; Ferreira, A.C.M.; Bernardes, E.M.

2000-01-01

The accuracy and precision of results of the radionuclide analyses in environmental samples are widely claimed internationally due to its consequences in the decision process coupled to evaluation of environmental pollution, impact, internal and external population exposure. These characteristics of measurement of the laboratories can be shown clearly using intercomparison data, due to the existence of a reference value and the need of three determinations for each analysis. In intercomparison studies accuracy in radionuclide assays in low-level environmental samples has usually been the main focus in performance evaluation and it can be estimated by taking into account the deviation between the experimental laboratory mean value and the reference value. The laboratory repeatability of measurements or their standard deviation is seldom included in performance evaluation. In order to show the influence of the uncertainties in performance evaluation of the laboratories, data of 22 intercomparison runs which distributed 790 spiked environmental samples to 20 Brazilian participant laboratories were compared, using the 'Normalised Standard Deviation' as statistical criteria for performance evaluation of U.S.EPA. It mainly takes into account the laboratory accuracy and the performance evaluation using the same data classified by normalised standard deviation modified by a weight reactor that includes the individual laboratory uncertainty. The results show a relative decrease in laboratory performance in each radionuclide assay: 1.8% for 65 Zn, 2.8% for 40 K, 3.4 for 60 Co, 3.7% for 134 Cs, 4.0% for 137 Cs, 4.4% for Th and U nat , 4.5% for 3 H, 6.3% for 133 Ba, 8.6% for 90 Sr, 10.6% for Gross Alpha, 10.9% for 106 Ru, 11.1% for 226 Ra, 11.5% for Gross Beta and 13.6% for 228 Ra. The changes in the parameters of the statistical distribution function were negligible and the distribution remained as Gaussian type for all radionuclides analysed. Data analyses in terms of

Rehabilitation of radioactive objects of Kirovo-Chepetsky chemical plant preliminary program of works

International Nuclear Information System (INIS)

Chesnokov, F.V.; Ivanov, O.P.; Pavlenko, V.I.; Semenov, S.G.; Stepanov, V.E.; Volkov, V.G.; Volkovich, A.G.; Zverkov, Yu.A.

2008-01-01

In 2007, the specialists of RRC Kurchatov Institute, jointly with MosNPO Radon, launched works on the radiation survey of radiation-contaminated objects and areas on the site of Kirovo-Chetetsky Chemical Plant (KCCP). This survey was launched with the object of subsequent development of the rehabilitation program and concept for buildings and storage sites left from shutdown uranium-processing facilities, as well as for sludge storage facilities and repositories of radioactive waste produced as a result of these facilities operation. Besides, radioactive contamination caused by the preceding operations involving radwaste and equipment contaminated at early stages of uranium hexafluoride (UHF) and tetrafluoride (UTF) processing technology mastering was detected in some spots at KCCP site. The radiation survey was performed in order to assess the amount of rehabilitation works, to identify the most critical objects and areas at KCCP site, and to develop the sequence of measures to be implemented in order to enhance the radiation safety of people living in the Kirov Region. (author)

Directory of Certificates of Compliance for Radioactive-Materials Packages. Summary report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1983-01-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

HPLC/DAD Intercomparison on Phytoplankton Pigments (HIP-1, HIP-2, HIP-3 and HIP-4)

OpenAIRE

CANUTI Elisabetta; RAS Josephine; GRUNG Merete; ROTTGERS Rudiger; COSTA GOELA Priscilla; ARTUSO Florinda; CATALDI Dario

2016-01-01

From 2009 to 2015, in the context of the MERIS (Medium Resolution Imaging Spectrometer) validation activities, the JRC Marine Optical Laboratory organised four HPLC Intercomparison exercises for Phytoplankton Pigment measurements (HIP-1, HIP-2, HIP-3 and HIP-4), involving seven European accredited and reference laboratories. The objectives of these intercomparison exercises were: creating a reference community at European level for phytoplankton pigment analysis capable of supporting satel...

Preliminary results of the alpha particle registration intercomparison ALRIT

International Nuclear Information System (INIS)

Paretzke, H.G.

1976-01-01

In view of the widespread interest in alpha particle registration with solid state nuclear track detectors, an international intercomparison of such measurements has been arranged. Sixteen sets of fourteen detectors each were sent to GSF-Neuherberg, there irradiated carefully with different alpha particle fields, and then returned for evaluation. Fourteen irradiation runs were made for each set simulating seven different irradiation situations commonly encountered in practical applications. The preliminary results of this intercomparison reported in this paper are based on the results of eight sets. They show good agreement with respect to the determination of track densities in the case of vertical incident alpha particles. Also the results obtained for determination of particle energies and angle of incidence in most cases were rather accurate. However, apparently it is still rather difficult to determine accurately and precisely the specific activity of alpha emitters on a thick filter positioned at some distance, i.e. for the case of 2π-incidence and a broad energy spectrum. (orig.) [de

Summary of 'IAEA intercomparison of IBA software'

Energy Technology Data Exchange (ETDEWEB)

Barradas, N.P. [Instituto Tecnologico e Nuclear, 2686-953 Sacavem (Portugal); Centro de Fisica Nuclear da Universidade de Lisboa, Av. 1649-003 Lisboa (Portugal); Arstila, K. [K.U.Leuven, Instituut voor Kern- en Stralingsfysica, B-3001 (Belgium); Battistig, G. [MFA Research Institute for Technical Physics and Material Science, H-1525 Budapest (Hungary); Bianconi, M. [CNR-IMM-Sezione di Bologna, Via P.Gobetti, 101, I-40129 Bologna (Italy); Dytlewski, N. [International Atomic Energy Agency, Wagramer Strasse 5, A-1400 Vienna (Austria); Jeynes, C. [University of Surrey Ion Beam Centre, Guildford GU2 7XH, England (United Kingdom)], E-mail: c.jeynes@surrey.ac.uk; Kotai, E. [KFKI Research Institute for Particle and Nuclear Physics, H-1525 Budapest (Hungary); Lulli, G. [CNR-IMM-Sezione di Bologna, Via P.Gobetti, 101, I-40129 Bologna (Italy); Mayer, M. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, D-85748 Garching (Germany); Rauhala, E. [Accelerator Laboratory, Department of Physics, University of Helsinki, FIN-00014 (Finland); Szilagyi, E. [KFKI Research Institute for Particle and Nuclear Physics, H-1525 Budapest (Hungary); Thompson, M. [Department of MS and E/Bard Hall 328, Cornell University, Ithaca, NY 14853 (United States)

2008-04-15

The International Atomic Energy Agency has sponsored a formal intercomparison exercise for the seven depth profiling ion beam analysis codes, which are: GISA, RUMP, RBX, DEPTH, DataFurnace, SIMNRA and MCERD. This intercomparison is published in Nucl. Instr. and Meth. B [N.P. Barradas, K. Arstila, G. Battistig, M. Bianconi, N. Dytlewski, C. Jeynes, E. Kotai, G. Lulli, M. Mayer, E. Rauhala, E. Szilagyi, M. Thompson, Nucl. Instr. and Meth. B 262 (2007) 281-303] and summarised here. The codes implement all known physical effects and they are all evaluated. We demonstrate that there is agreement between codes often better than 0.1%; and also detailed agreement with real spectra, showing in particular that the SRIM 2003 stopping powers for Si are correct to 0.6% for 1.5 MeV He. For the case of heavy ion elastic recoil detection (HI-ERD) the single scattering codes performed poorly for scattered particles, although recoiled particles were calculated correctly.

Data Quality Assessment of In Situ and Altimeter Observations Through Two-Way Intercomparison Methods

Science.gov (United States)

Guinehut, Stephanie; Valladeau, Guillaume; Legeais, Jean-Francois; Rio, Marie-Helene; Ablain, Michael; Larnicol, Gilles

2013-09-01

This proceeding presents an overview of the two-way inter-comparison activities performed at CLS for both space and in situ observation agencies and why this activity is a required step to obtain accurate and homogenous data sets that can then be used together for climate studies or in assimilation/validation tools. We first describe the work performed in the frame of the SALP program to assess the stability of altimeter missions through SSH comparisons with tide gauges (GLOSS/CLIVAR network). Then, we show how the SSH comparison between the Argo array and altimeter time series allows the detection of drifts or jumps in altimeter (SALP program) but also for some Argo floats (Ifremer/Coriolis center). Lastly, we describe how the combine use of altimeter and wind observations helps the detection of drogue loss of surface drifting buoys (GDP network) and allow the computation of a correction term for wind slippage.

The deterministic computational modelling of radioactivity

International Nuclear Information System (INIS)

Damasceno, Ralf M.; Barros, Ricardo C.

2009-01-01

This paper describes a computational applicative (software) that modelling the simply radioactive decay, the stable nuclei decay, and tbe chain decay directly coupled with superior limit of thirteen radioactive decays, and a internal data bank with the decay constants of the various existent decays, facilitating considerably the use of program by people who does not have access to the program are not connected to the nuclear area; this makes access of the program to people that do not have acknowledgment of that area. The paper presents numerical results for typical problem-models

Results of the 1982 intercomparison (collaborative test) on J 131 in milk

International Nuclear Information System (INIS)

Wiechen, A.; Bundesanstalt fuer Milchforschung, Kiel

1982-01-01

The quality control of J 131 measurements in milk in the Federal Republik of Germany by an intercomparison performed in March 1982 showed a reasonable result. About two thirds of the laboratories engaged in this intercomparison had no trouble with their analytical tools. To improve the standard of J 131 determinations, laboratories with deviations from the true value were pointed to possible systematic errors. In the Federal Republik of Germany those methods for the determination of J 131 in milk have been successfully used which concentrate the iodine of the milk on an anion exchanger column and measure the J 131 directly by gammaspectrometry. (orig.) [de

Reactor neutron activation analysis on reference materials from intercomparison runs

International Nuclear Information System (INIS)

Pantelica, A.; Salagean, M.

2003-01-01

A review of using the Instrumental Neutron Activation Analysis (INAA) technique in our laboratory to determine major, minor and trace elements in mineral and biological samples from international intercomparison runs organised by IAEA Vienna, IAEA-MEL Monaco, 'pb-anal' Kosice, INCT Warszawa and IPNT Krakow is presented. Neutron irradiation was carried out at WWR-S reactor in Bucharest (short and long irradiation) during 1982-1997 and at TRIGA reactor in Pitesti (long irradiation) during the later period. The following type of materials were analysed: soils, marine sediments, uranium phosphate ore, water sludge, copper flue dust, whey powder, yeast, cereal flour (rye and wheat), marine animal tissue (mussel, garfish and tuna fish), as well as vegetal tissue (seaweed, cabbage, spinach, alfalfa, algae, tea leaves and herbs). The following elements could be, in general, determined: Ag, As, Au, Ba, Br, Ca, Ce, Co, Cr, Cs, Eu, Fe, Hf, Hg, K, La, Lu, Mo, Na, Nd, Ni, Rb, Sb, Sc, Se, Sm, Sr, Ta, Tb, Th, U, W, Yb and Zn of long-lived radionuclides, as well as Al, Ca, Cl, Cu, Mg, Mn, and Ti of short-lived radionuclides. Data obtained in our laboratory for various matrix samples presented and compared with the intercomparison certified values. The intercomparison exercises offer to the participating laboratories the opportunity to test the accuracy of their analytical methods as well as to acquire valuable Reference Materials/ standards for future analytical applications. (authors)

National Bureau of Standards health physics radioactive material shipment survey, packaging, and labelling program under ICAO/IATA and DOT regulations

International Nuclear Information System (INIS)

Sharp, D.R.; Slaback, L.A.

1984-01-01

NBS routinely ships many radionuclides in small to moderate activities, with many shipments containing mixtures of radionuclides in a variety of combinations. The ICAO/IATA shipping regulations (and the new DoT regulations on their model) specify individual shipping parameters for every radionuclide. As a result, quality control in the shipment of these radioactive packages has become difficult to maintain. The authors have developed a computer program that will guide a Health Physics technician through package surveys and give exact packaging and labelling instructions. The program is a 27 kilobyte user-friendly BASIC program that runs on an Epson-HX20 notebook computer with microcassette drive and 16 kilobyte memory expansion unit. This small computer is more manageable than the regulation books for which it will be substituted and will be used in routine radioactive shipments

Understanding radioactive waste

International Nuclear Information System (INIS)

Murray, R.L.

1981-12-01

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes)

Understanding radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Murray, R.L.

1981-12-01

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Proposal of a monitoring program of occupational exposure by incorporation of radioactive material for nuclear medicine services in the Caja Costarricense del Seguro Social

International Nuclear Information System (INIS)

Badilla Segura, Mirta

2013-01-01

A monitoring program of the occupational exposure by incorporation of radioactive material is proposed. Nuclear medicine services of the Caja Costarricense del Seguro Social (CCSS) are evaluated. The monitoring program is based on the provisions of the International Atomic Energy Agency and of study of nuclear medicine services of the CCSS. Radionuclides are determined for monitoring of the occupational exposure, according to the radioactive material that is worked in nuclear medicine services of the CCSS. The appropriate and alternative techniques are established for the monitoring of the occupational exposure by incorporation of radioactive material, depending on the type of radionuclide that is worked in nuclear medicine services. The worker occupationally exposed (TOE) should be subject of monitoring and how often should be realized the monitoring of the occupational exposure. The monitoring of the radiation by radioactive material must be applied to personnel working in radiopharmacies and the worker has carried out therapeutic procedures for handling of significant amounts of 13 1 I. The calculation of the committed effective dose is proposed by incorporation of radioactive material with the TOE [es

Radioactive waste management in Korea

International Nuclear Information System (INIS)

Lee, Ik Hwan

1997-01-01

In order to meet the increasing energy demand in Korea, continuous promotion of nuclear power program will be inevitable in the future. However, the use of nuclear energy eventually requires effective and reliable radioactive waste management. For the safe and economical management of radioactive waste, first of all, volume reduction is essentially required and hence the development of related technologies continuously be pursued. A site for overall radioactive waste management has to be secured in Korea. KEPCO-NETEC will improve public understanding by reinforcing PA and will maintain transparency of radioactive waste management. (author). 1 fig

The United States program for the safety assessment of geologic disposal of commercial radioactive wastes

International Nuclear Information System (INIS)

Claiborne, H.C.

1977-01-01

The safe disposal of commercial radioactive wastes in deep geologic formations is the goal of the National Waste Terminal Storage (NWTS) Program. Safety assessment begins with selection of a disposal site; that is, all geologic and hydrologic factors must indicate long-term stability of the formation and prospective isolation of wastes from circulating ground waters for hundreds of thousands of years. The long-term stability of each site under thermal loading must then be demonstrated by sophisticated rock mechanic analyses. Therefore, it can be expected that the sites that are chosen will effectively isolate the waste for a very long period of time. However, to help provide answers on the mechanisms and consequences of an unlikely breach in the integrity of the repository, a Waste Isolation Safety Assessment Program (WISAP) is studied. The overall objective of this program is an assessment of the safety associated with the long-term disposal of high-level radioactive waste in a geologic formation. This objective will be achieved by developing methods and generating data necessary to characterize the safety of generic geological waste disposal concepts, which are to be applied in the assessment of specific sites. It is expected that no one particular model will suffice. Both deterministic and probabilistic approaches will be used, and the entire spectrum of phenomena that could influence geologic isolation will be considered

Material Not Categorized As Waste (MNCAW) data report. Radioactive Waste Technical Support Program

Energy Technology Data Exchange (ETDEWEB)

Casey, C.; Heath, B.A.

1992-11-01

The Department of Energy (DOE), Headquarters, requested all DOE sites storing valuable materials to complete a questionnaire about each material that, if discarded, could be liable to regulation. The Radioactive Waste Technical Support Program entered completed questionnaires into a database and analyzed them for quantities and type of materials stored. This report discusses the data that TSP gathered. The report also discusses problems revealed by the questionnaires and future uses of the data. Appendices contain selected data about material reported.

Contribution to the study on and evaluation of radioactive waste generation in connection with the Brazilian Nuclear Program

International Nuclear Information System (INIS)

Melo, J.M.D. de.

1978-12-01

A general description is given of the causes of pollution in the nuclear industry. Emphasis was given to the radioactive pollution, especially radioactivity of fission products (FP). Physical mathematical models were established to calculate the FP activities 'in' and 'out' of the reactor and the yearly accumulated activities. To calculate FP activities 'in' reactor, all physical process of formation and destruction of nuclides were considered: nuclear fission; neutron absorption and radioactivity decay. The necessary input data were analysed and criticised. The specific activities of the discharged fuel were calculated and also their evolution outside reactor. The annual accumulation of FP activities were also calculated for the reference case: the Brazilian Nuclear Program for a 50 year horizon. The results were commented and specific discussions and comparison with other similar studies were made. (Author) [pt

Programs of recovery of radioactive wastes from the trenches and land decontamination of the radioactive waste storage center; Programas de recuperacion de los desechos radiactivos de las trincheras y de descontaminacion del predio del centro de almacenamiento de desechos radiactivos

Energy Technology Data Exchange (ETDEWEB)

Jimenez D, J.; Reyes L, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1999-06-15

In this report there are the decontamination program of the land of the Radioactive Waste Storage Center, the Program of Recovery of the radioactive waste of the trenches, the recovery of polluted bar with cobalt 60, the recovery of minerals and tailings of uranium and of earth with minerals and tailings of uranium, the recovery of worn out sealed sources and the waste recovery with the accustomed corresponding actions are presented. (Author)

Office of Civilian Radioactive Waste Management: Support for university research and education

International Nuclear Information System (INIS)

Brownstein, A.B.

1990-01-01

The U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM) currently sponsors two programs that provide funding to universities and graduate students. The OCRWM graduate fellowship program and the OCRWM research program for historically black colleges and universities (HBCU) are designed to enhance the involvement of universities in the nation's high-level radioactive waste program. The specific goals of these programs are to (a) attract talented young scientists and engineers into OCRWM and OCRWM support contractor high-level radioactive waste management programs, (b) improve the quality of graduate education in disciplines directly related to high-level radioactive waste management, and (c) encourage university faculty to become involved in OCRWM mission-related activities

A study of production of radioactive environmental reference materials used for proficiency testing program in Taiwan

International Nuclear Information System (INIS)

Peng, En-Chi; Wang, Jeng-Jong

2013-01-01

To realise radioactive environmental reference materials in Taiwan, seven environmental materials of soil, water, vegetation, meat, airborne particles (filter paper), milk and mushroom samples that are frequently encountered were used to establish the preparation of the reference materials. These seven environmental materials were collected, checked for freedom from radioactivity and prepared according to their properties. The preparation was carried out by using activity about 10–100 times that of the minimum detectable activity (MDA) in routine measurements in the radioactive standard used to spike the inactive material and this standard is traceable to national ionising radioactivity standards (TAF, 2004). To demonstrate sample traceability to the added standard, each sample was carefully measured and its uncertainty evaluated. Based on the recommendations of ISO Guide 35 for evaluation of reference materials and with the above assessment and verification procedures, the uncertainties (k=1) of the spike activity used in making reference materials were: 60 Co≤4.6%, 134 Cs≤4.7%, 137 Cs≤5.0%, total β≤0.6% and 3 H≤1.3%. - Highlights: • Seven kinds environmental materials were used to establish the production of the RMs. • Spiking the traceable standard radioactive source to the blank substance. • Each sample was carefully evaluated for its uncertainty. • The performance of the RMs was estimated with the Proficiency Testing program report. • The ability of the environment RMs in the configuration is quite good

Report to Congress on reassessment of the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

1989-11-01

In the Report of the House Committee on Appropriations (House Report No. 101-96) on the Energy and Water Development Appropriation Act, 1990 (P.L. 101-101), the Committee directed the Department of Energy (DOE) ''hor-ellipsis to submit a report within 60 days of enactment hor-ellipsis which describes in detail how the Department plans to respond to the Committee's hor-ellipsis concerns dealing with endemic schedule slips, problems in management structure, and lack of integrated contractor efforts.'' This report has been prepared in response to the above-mentioned Congressional directive. It is based on a comprehensive review that the Secretary of Energy has recently completed of the Civilian Radioactive Waste Management Program. The Secretary's review has led to the development of a three-point action plan for restructuring the program. This plan is explained in this report

Assessing doses to terrestrial wildlife at a radioactive waste disposal site: inter-comparison of modelling approaches.

Science.gov (United States)

Johansen, M P; Barnett, C L; Beresford, N A; Brown, J E; Černe, M; Howard, B J; Kamboj, S; Keum, D-K; Smodiš, B; Twining, J R; Vandenhove, H; Vives i Batlle, J; Wood, M D; Yu, C

2012-06-15

Radiological doses to terrestrial wildlife were examined in this model inter-comparison study that emphasised factors causing variability in dose estimation. The study participants used varying modelling approaches and information sources to estimate dose rates and tissue concentrations for a range of biota types exposed to soil contamination at a shallow radionuclide waste burial site in Australia. Results indicated that the dominant factor causing variation in dose rate estimates (up to three orders of magnitude on mean total dose rates) was the soil-to-organism transfer of radionuclides that included variation in transfer parameter values as well as transfer calculation methods. Additional variation was associated with other modelling factors including: how participants conceptualised and modelled the exposure configurations (two orders of magnitude); which progeny to include with the parent radionuclide (typically less than one order of magnitude); and dose calculation parameters, including radiation weighting factors and dose conversion coefficients (typically less than one order of magnitude). Probabilistic approaches to model parameterisation were used to encompass and describe variable model parameters and outcomes. The study confirms the need for continued evaluation of the underlying mechanisms governing soil-to-organism transfer of radionuclides to improve estimation of dose rates to terrestrial wildlife. The exposure pathways and configurations available in most current codes are limited when considering instances where organisms access subsurface contamination through rooting, burrowing, or using different localised waste areas as part of their habitual routines. Crown Copyright © 2012. Published by Elsevier B.V. All rights reserved.

Design and results of the ice sheet model initialisation experiments initMIP-Greenland: an ISMIP6 intercomparison

Science.gov (United States)

Goelzer, Heiko; Nowicki, Sophie; Edwards, Tamsin; Beckley, Matthew; Abe-Ouchi, Ayako; Aschwanden, Andy; Calov, Reinhard; Gagliardini, Olivier; Gillet-Chaulet, Fabien; Golledge, Nicholas R.; Gregory, Jonathan; Greve, Ralf; Humbert, Angelika; Huybrechts, Philippe; Kennedy, Joseph H.; Larour, Eric; Lipscomb, William H.; Le clec'h, Sébastien; Lee, Victoria; Morlighem, Mathieu; Pattyn, Frank; Payne, Antony J.; Rodehacke, Christian; Rückamp, Martin; Saito, Fuyuki; Schlegel, Nicole; Seroussi, Helene; Shepherd, Andrew; Sun, Sainan; van de Wal, Roderik; Ziemen, Florian A.

2018-04-01

Earlier large-scale Greenland ice sheet sea-level projections (e.g. those run during the ice2sea and SeaRISE initiatives) have shown that ice sheet initial conditions have a large effect on the projections and give rise to important uncertainties. The goal of this initMIP-Greenland intercomparison exercise is to compare, evaluate, and improve the initialisation techniques used in the ice sheet modelling community and to estimate the associated uncertainties in modelled mass changes. initMIP-Greenland is the first in a series of ice sheet model intercomparison activities within ISMIP6 (the Ice Sheet Model Intercomparison Project for CMIP6), which is the primary activity within the Coupled Model Intercomparison Project Phase 6 (CMIP6) focusing on the ice sheets. Two experiments for the large-scale Greenland ice sheet have been designed to allow intercomparison between participating models of (1) the initial present-day state of the ice sheet and (2) the response in two idealised forward experiments. The forward experiments serve to evaluate the initialisation in terms of model drift (forward run without additional forcing) and in response to a large perturbation (prescribed surface mass balance anomaly); they should not be interpreted as sea-level projections. We present and discuss results that highlight the diversity of data sets, boundary conditions, and initialisation techniques used in the community to generate initial states of the Greenland ice sheet. We find good agreement across the ensemble for the dynamic response to surface mass balance changes in areas where the simulated ice sheets overlap but differences arising from the initial size of the ice sheet. The model drift in the control experiment is reduced for models that participated in earlier intercomparison exercises.

Results of the European Community's beta intercomparison programme of individual dosemeters in 1986

International Nuclear Information System (INIS)

Bigard, T.; Sequin, H.; Chartier, J.L.; Christensen, P.; Francis, T.M.; Lembo, L.

1988-01-01

For over 20 years, the Commission of the European Communities, in collaboration with competent laboratories in the member states, has been conducting intercomparisons of individual dosemeters with the objective of improving technique for monitoring ionizing radiation and establishing a common basis for dose assessment within the Community. These programmes not only serve the participants with an opportunity to validate their calibration and measuring procedures but also help to create a forum in which to exchange information and discuss experience with other participants. The performance and results of such an intercomparison exercise conducted in 1986 are reported here

Program for responsible and safe disposal of spent fuel elements and radioactive wastes (National disposal program)

International Nuclear Information System (INIS)

2015-01-01

The contribution covers the following topics: fundamentals of the disposal policy; amount of radioactive wastes and prognosis; disposal of radioactive wastes - spent fuel elements and wastes from waste processing, radioactive wastes with low heat production; legal framework of the nuclear waste disposal in Germany; public participation, cost and financing.

ARANO - a computer program for the assessment of radiological consequences of atmospheric radioactive releases

International Nuclear Information System (INIS)

Savolainen, I.; Vuori, S.

1980-09-01

A short description of the calculation possibilities, methods and of the structure of the computer code system ARANO is given, in addition to the input quide. The code can be employed in the calculation of environmental radiological consequences caused by radioactive materials released to atmosphere. Results can be individual doses for different organs at given distances from the release point, collective doses, numbers of persons exceeding given dose limits, numbers of casualties, areas polluted by deposited activity and losses of investments or production due to radioactive contamination. Both a case with a single release and atmospheric dispersion situation and a group of radioactive release and dispersions with discrete probability distributions can be considered. If the radioactive releases or the dispersion conditions are described by probability distributions, the program assesses the magnitudes of the specified effects in all combinations of the release and dispersion situations and then calculates the expectation values and the cumulative probability distributions of the effects. The vertical mixing in the atmosphere is described with a Ksub(Z)-model. In the lateral direction the plume is assumed to be Gaussian, and the release duration can be taken into account in the σsub(y)-values. External gamma dose from the release plume is calculated on the basis of a data file which has been created by 3-dimensional integration. Dose due to inhalation and due to gamma radiation from the contaminated ground are calculated by using appropriate dose conversion factors, which are collected into two mutually alternative block data subprograms. (author)

Report on the intercomparison run IAEA-155 trace elements in whey powder

International Nuclear Information System (INIS)

Zeiller, E.; Strachnov, V.; Dekner, R.

1990-11-01

Analytical results need to be reliable, and analysts are well serviced to test their complete analytical systems, methods, instruments, personnel, data reduction, etc., on a frequent basis. Besides the use of standard reference materials, the intercomparison runs provide an excellent opportunity for the determination of accuracy. By comparing their results with results obtained by different methods of preparation and measurement, the participating laboratories have the opportunity to check their analytical performances. At the same time the IAEA's AQCS can establish the concentration of some elements for certification purposes. The participants were requested to determine as many elements as possible with emphasis on ''essential'' and ''toxic'' elements related to human health and environmental pollution in the intercomparison whey powder sample (IAEA-155) as well as in the control sample IAEA. It was expected that the results for IAEA would improve the evaluation of the intercomparison results of IAEA-155 as the concentrations of some inorganic constituents were well established in the IAEA sample. In total 69 laboratories from 24 different countries participated in this exercise. As a basis for the evaluation, 580 laboratory means were reported comprising 2699 individual results for 45 elements. For 3 additional elements information was supplied that the value was below the detection limits of the methods. Even though information and data on 48 elements were reported for IAEA-155 only 4 elements are assigned Class A and 13 elements Class B recommended values. The elements Mg, Mn, Na and P were assigned ''Class A''. But contrary to some former intercomparison exercises, this time sufficient results could be obtained to set ''Class B'' recommended values for some ''difficult to determine'' elements like Cd, Co, Cr, Hg, Ni, Pb, Se. Figs, 45 tabs

Specification of a test problem for HYDROCOIN [Hydrologic Code Intercomparison] Level 3 Case 2: Sensitivity analysis for deep disposal in partially saturated, fractured tuff

International Nuclear Information System (INIS)

Prindle, R.W.

1987-08-01

The international Hydrologic Code Intercomparison Project (HYDROCOIN) was formed to evaluate hydrogeologic models and computer codes and their use in performance assessment for high-level radioactive waste repositories. Three principal activities in the HYDROCOIN Project are Level 1, verification and benchmarking of hydrologic codes; Level 2, validation of hydrologic models; and Level 3, sensitivity and uncertainty analyses of the models and codes. This report presents a test case defined for the HYDROCOIN Level 3 activity to explore the feasibility of applying various sensitivity-analysis methodologies to a highly nonlinear model of isothermal, partially saturated flow through fractured tuff, and to develop modeling approaches to implement the methodologies for sensitivity analysis. These analyses involve an idealized representation of a repository sited above the water table in a layered sequence of welded and nonwelded, fractured, volcanic tuffs. The analyses suggested here include one-dimensional, steady flow; one-dimensional, nonsteady flow; and two-dimensional, steady flow. Performance measures to be used to evaluate model sensitivities are also defined; the measures are related to regulatory criteria for containment of high-level radioactive waste. 14 refs., 5 figs., 4 tabs

Avoiding dual regulation of the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Vlahakis, J.G.; Palabrica, R.J.

1994-01-01

The Office of Civilian Radioactive Waste Management (RW) has successfully negotiated the issuance of a Department of Energy (DOE) Headquarters Order that provides for exemption of RW from certain DOE directives. This exemption assures precedence of Nuclear Regulatory Commission (NRC) requirements in radiation protection, nuclear safety (including quality assurance), and safeguards and security of nuclear materials. This Order is necessary to avoid the unwarranted cost and potential confusion resulting from dual regulation of RW facilities and activities by DOE and NRC. Development of this Order involved a systematic review of applicable DOE directives and NRC requirements to identify potential overlaps and duplication when applied to the RW program. Following this review and extensive negotiations with appropriate DOE organizations responsible for directives development, this Order was issued as HQ 1321.1 on December 22, 1993

Management of radioactive wastes in China

International Nuclear Information System (INIS)

Pan Ziqiang

1994-01-01

The policy and principles on management of radioactive wastes are stipulated. Cement solidification and bituminization unit has come into trial run. Solid radioactive waste is stored in tentative storage vault built in each of nuclear facilities. Seventeen storages associated with applications of nuclear technology and radioisotopes have been built for provinces. Disposal of low and intermediate level radioactive wastes pursues the policy of 'regional disposal'. Four repositories have been planned to be built in northwest, southwest, south and east China respectively. A program for treatment and disposal of high level radioactive waste has been made

Intercomparison of Operational Ocean Forecasting Systems in the framework of GODAE

Science.gov (United States)

Hernandez, F.

2009-04-01

One of the main benefits of the GODAE 10-year activity is the implementation of ocean forecasting systems in several countries. In 2008, several systems are operated routinely, at global or basin scale. Among them, the BLUElink (Australia), HYCOM (USA), MOVE/MRI.COM (Japan), Mercator (France), FOAM (United Kingdom), TOPAZ (Norway) and C-NOOFS (Canada) systems offered to demonstrate their operational feasibility by performing an intercomparison exercise during a three months period (February to April 2008). The objectives were: a) to show that operational ocean forecasting systems are operated routinely in different countries, and that they can interact; b) to perform in a similar way a scientific validation aimed to assess the quality of the ocean estimates, the performance, and forecasting capabilities of each system; and c) to learn from this intercomparison exercise to increase inter-operability and collaboration in real time. The intercomparison relies on the assessment strategy developed for the EU MERSEA project, where diagnostics over the global ocean have been revisited by the GODAE contributors. This approach, based on metrics, allow for each system: a) to verify if ocean estimates are consistent with the current general knowledge of the dynamics; and b) to evaluate the accuracy of delivered products, compared to space and in-situ observations. Using the same diagnostics also allows one to intercompare the results from each system consistently. Water masses and general circulation description by the different systems are consistent with WOA05 Levitus climatology. The large scale dynamics (tropical, subtropical and subpolar gyres ) are also correctly reproduced. At short scales, benefit of high resolution systems can be evidenced on the turbulent eddy field, in particular when compared to eddy kinetic energy deduced from satellite altimetry of drifter observations. Comparisons to high resolution SST products show some discrepancies on ocean surface

Propertis of solidified radioactive wastes from commercial LWRs

International Nuclear Information System (INIS)

Neilson, R.M. Jr.; Colombo, P.

1978-01-01

A study has been performed to characterize the properties of solidified radioactive wastes generated in the liquid radwaste treatment systems at LWRs. The properties which have been studied are those which are pertinent in defining the relative potential for the release of radionuclides to the environment as well as others relating to the evaluation of various solidification agents on an economic and feasibility basis. The use of standard testing procedures in measuring these properties allows an intercomparison of respective properties between various types of solidified waste forms. The leachability, mechanical properties, thermal stability, radiation stability, and thermal properties of hydraulic cement, ureaformaldehyde, bitumen, and addition type polymer waste forms have been measured. In addition, the chemical sensitivity, volumetric efficiency and radiation shielding characteristics of these waste forms have been studied. Emphasis in this paper is placed on the results of studies concerning chemical compatibility of solidification agents with specific waste streams, volumetric efficiency, free standing water, and leachability

Dosimetric intercomparison in Cobalt 60 unities using TLD-100 crystals and CaSO{sub 4}: Dy + Ptfe; Intercomparacion dosimetrica en unidades de cobalto 60 usando cristales de TLD-100 y CaSO{sub 4}: Dy + PTFE

Energy Technology Data Exchange (ETDEWEB)

Gaona, E. [Universidad Autonoma Metropolitana Xochimilco, Mexico D.F. (Mexico); Azorin N, J. [Universidad Autonoma Metropolitana Iztapalapa, Mexico D.F. (Mexico); Perez P, M.A. [Instituto Nacional de Cancerologia, Mexico D.F. (Mexico); Castillo H, M. [Centro Medico Nacional 20 de Noviembre, ISSSTE, Mexico D.F. (Mexico); Flores F, F. [Unidad de Oncologia, Centro Medico Nacional, IMSS, Mexico D.F. (Mexico); Guzman R, L.V. [Unidad de Oncologia, Hospital General de Mexico, Mexico D.F. (Mexico)

1999-07-01

The purpose of this work is to design and construct a phantom in basis of thermoplastic polymer of methyl methacrylate that is reutilizable and which allows to do an analysis of the absorbed doses in thermoluminescent crystals (Tl) exposed to cobalt 60 to establish the dosimetric intercomparison in cobalt units which allows to do the follow-up of the Quality assurance programs, standardization of calibration procedures, dosimetry and TLD post intercomparison in radiotherapy. This work allows also prove new thermoluminescent materials of national manufacture developed by Juan Azorin and collaborators as the CaSO{sub 4}: Dy + Ptfe. This is a first study which is realized in Mexico with the system crystal-phantom for aims to intercomparison in cobalt 60 units. In this work participate eight unities of cobalt 60 of different trades belonging at four radiotherapy centers. The results of the dose intercomparison of the eight unities of cobalt 60 were in the range 0.95-1.13, taking in account that the values between 0.95 and 1.05 were considered acceptable in terms of the requirements by the standing legislation. (Author)

Low-level radioactive waste program of the US Geological Survey - in transition

International Nuclear Information System (INIS)

Fischer, J.N.

1983-01-01

In 1983, the US Geological Survey will publish final reports of geohydrologic investigations at five commercial low-level, radioactive-waste burial sites in the United States. These reports mark the end of the first phase of the US Geological Survey program to improve the understanding of earth-science principles related to the effective disposal of low-level wastes. The second phase, which was initiated in 1981, is being developed to address geohydrologic issues identified as needing greater attention based upon results of the first-phase site studies. Specific program elements include unsaturated-zone hydrology, geochemistry, clay mineralogy, surface geophysical techniques, and model development and testing. The information and expertise developed from these and previous studies will allow the US Geological Survey to provide sound technical assistance to State low-level waste compacts, the Department of Energy, the Nuclear Regulatory Commission, and the Environmental Protection Agency. 11 references

Dosimetry audits and intercomparisons in radiotherapy: A Malaysian profile

Science.gov (United States)

M. Noor, Noramaliza; Nisbet, A.; Hussein, M.; Chu S, Sarene; Kadni, T.; Abdullah, N.; Bradley, D. A.

2017-11-01

Quality audits and intercomparisons are important in ensuring control of processes in any system of endeavour. Present interest is in control of dosimetry in teletherapy, there being a need to assess the extent to which there is consistent radiation dose delivery to the patient. In this study we review significant factors that impact upon radiotherapy dosimetry, focusing upon the example situation of radiotherapy delivery in Malaysia, examining existing literature in support of such efforts. A number of recommendations are made to provide for increased quality assurance and control. In addition to this study, the first level of intercomparison audit i.e. measuring beam output under reference conditions at eight selected Malaysian radiotherapy centres is checked; use being made of 9 μm core diameter Ge-doped silica fibres (Ge-9 μm). The results of Malaysian Secondary Standard Dosimetry Laboratory (SSDL) participation in the IAEA/WHO TLD postal dose audit services during the period between 2011 and 2015 will also been discussed. In conclusion, following review of the development of dosimetry audits and the conduct of one such exercise in Malaysia, it is apparent that regular periodic radiotherapy audits and intercomparison programmes should be strongly supported and implemented worldwide. The programmes to-date demonstrate these to be a good indicator of errors and of consistency between centres. A total of ei+ght beams have been checked in eight Malaysian radiotherapy centres. One out of the eight beams checked produced an unacceptable deviation; this was found to be due to unfamiliarity with the irradiation procedures. Prior to a repeat measurement, the mean ratio of measured to quoted dose was found to be 0.99 with standard deviation of 3%. Subsequent to the repeat measurement, the mean distribution was 1.00, and the standard deviation was 1.3%.

Radioactive-site-remediation technologies seminar. Speaker slide copies

International Nuclear Information System (INIS)

1992-06-01

The contents of this report include the following: approaches to sampling radioactive heterogeneous waste; soil characterization methodology for determining application of soil washing; vorce (volume reduction/chemical extraction) program; treatment of radioactive compounds in water; polymer solidification of low-level radioactive, hazardous, and mixed waste; in situ vitrification of soils contaminated with radioactive and mixed wastes; decontamination of contaminated buildings; incineration of radioactive waste; in situ stabilization/solidification with cement-based grouts; environmental restoration and waste management; removal of contaminants from soils by electrokinetics; and treatment, compaction, and disposal of residual radioactive waste

Extremity ring dosimetry intercomparison in reference and workplace fields

International Nuclear Information System (INIS)

Ginjaume, M.; Carinou, E.; Donadille, L.; Jankowski, J.; Rimpler, A.; Sans Merce, M.; Vanhavere, F.; Denoziere, M.; Daures, J.; Bordy, J. M.; Itie, C.; Covens, P.

2008-01-01

An intercomparison of ring dosemeters has been organised with the aim of assessing the technical capabilities of available extremity dosemeters and focusing on their performance at clinical workplaces with potentially high extremity doses. Twenty-four services from 16 countries participated in the intercomparison. The dosemeters were exposed to reference photon ( 137 Cs) and beta ( 147 Pm, 85 Kr and 90 Sr/ 90 Y) fields together with fields representing realistic exposure situations in interventional radiology (direct and scattered radiation) and nuclear medicine ( 99m Tc and 18 F). It has been found that most dosemeters provided satisfactory measurements of H p (0.07) for photon radiation, both in reference and realistic fields. However, only four dosemeters fulfilled the established requirements for all radiation qualities. The main difficulties were found for the measurement of low-energy beta radiation. Finally, the results also showed a general under-response of detectors to 18 F, which was attributed to the difficulties of the dosimetric systems to measure the positron contribution to the dose. (authors)

Regional inter-comparison of measurements of personal dose equivalent Hp(10) using photon beams

International Nuclear Information System (INIS)

Bero, M.; Zahili, M.; Kharita, M.H.

2012-11-01

The overall objective is to verify performance and to improve the Individual Monitoring services (IMS). This can be achieved with the following specific objectives of the intercomparison:1. To assess the capabilities of the dosimetry services to measure the quantity H p (10) in photon (gamma and x-ray) fields. 2. To help the participating Member States in achieving sufficiently accurate dosimetry service and, if necessary, 3. To provide guidelines for improvements and not simply a test of the performance of the existing dosimetric service. Actually a significant improvement has been achieved by the participants in the accuracy of evaluating personal dose equivalent from 15% in the first phase to 5% in the second phase. Some participants used the results of the inter-comparison to verify the calibration and to improve their dosimetric procedures, but from the results it was clear that some participants need to a technical support especially in calibration and using their measuring system in the field of personal monitoring. The conclusion contains advises, solutions, propositions and evaluation for all situations which noticed during the intercomparison. (authors)

The effects of intervening interference on working memory for sound location as a function of inter-comparison interval.

Science.gov (United States)

Ries, Dennis T; Hamilton, Traci R; Grossmann, Aurora J

2010-09-01

This study examined the effects of inter-comparison interval duration and intervening interference on auditory working memory (AWM) for auditory location. Interaural phase differences were used to produce localization cues for tonal stimuli and the difference limen for interaural phase difference (DL-IPD) specified as the equivalent angle of incidence between two sound sources was measured in five different conditions. These conditions consisted of three different inter-comparison intervals [300 ms (short), 5000 ms (medium), and 15,000 ms (long)], the medium and long of which were presented both in the presence and absence of intervening tones. The presence of intervening stimuli within the medium and long inter-comparison intervals produced a significant increase in the DL-IPD compared to the medium and long inter-comparison intervals condition without intervening tones. The result obtained in the condition with a short inter-comparison interval was roughly equivalent to that obtained for the medium inter-comparison interval without intervening tones. These results suggest that the ability to retain information about the location of a sound within AWM decays slowly; however, the presence of intervening sounds readily disrupts the retention process. Overall, the results suggest that the temporal decay of information within AWM regarding the location of a sound from a listener's environment is so gradual that it can be maintained in trace memory for tens of seconds in the absence of intervening acoustic signals. Conversely, the presence of intervening sounds within the retention interval may facilitate the use of context memory, even for shorter retention intervals, resulting in a less detailed, but relevant representation of the location that is resistant to further degradation. Copyright (c) 2010 Elsevier B.V. All rights reserved.

EURADOS intercomparisons in external radiation dosimetry: similarities and differences among exercises for whole-body photon, whole-body neutron, extremity, eye-lens and passive area dosemeters

International Nuclear Information System (INIS)

Romero, Ana M.; Grimbergen, Tom; McWhan, Andrew; Stadtmann, Hannes; Fantuzzi, Elena; Clairand, Isabelle; Neumaier, Stefan; Dombrowski, Harald; Figel, Markus

2016-01-01

The European Radiation Dosimetry Group (EURADOS) has been organising dosimetry intercomparisons for many years in response to an identified requirement from individual monitoring services (IMS) for independent performance tests for dosimetry systems. The participation in intercomparisons gives IMS the opportunity to show compliance with their own quality management system, compare results with other participants and develop plans for improving their dosimetry systems. In response to growing demand, EURADOS has increased the number of intercomparisons for external radiation dosimetry. Most of these fit into the programme of self-financing intercomparisons for dosemeters routinely used by IMS. This programme is being coordinated by EURADOS working group 2 (WG2). Up to now, this programme has included four intercomparisons for whole-body dosemeters in photon fields, one for extremity dosemeters in photon and beta fields, and one for whole-body dosemeters in neutron fields. Other EURADOS working groups have organised additional intercomparisons including events in 2014 for eye-lens dosemeters and passive area dosemeters for environmental monitoring. In this paper, the organisation and achievements of these intercomparisons are compared in detail focusing on the similarities and differences in their execution. (authors)

Psacoin level 1B intercomparison: An International code intercomparison exercise on a hypothetical safety assessment case study for radioactive waste disposal systems

International Nuclear Information System (INIS)

Klos, R.A.; Sinclair, J.E.; Torres, C.; Bergstroem, U.; Galson, D.A.

1993-06-01

This report focuses on the biosphere modelling aspects of the assessment of the radiological impact of the disposal of radioactive waste in greater detail. Seven exposure pathways are modelled: drinking water, freshwater fish, meat, milk and grain consumption as well as external gamma irradiation and contaminated dust inhalation. The accumulation of radionuclides, released in groundwaters, in the upper soil is also modelled. The objectives of this Level 1b exercise can be summarized as follows: 1 to gain experience in the application of probabilistic systems assessment methodology to transport and radiological exposure sub-models for the biosphere and hence to methods of estimating the total risk to individuals or groups of individuals; 2 to contribute to the verification of biosphere transport and exposure sub-models; 3 to investigate the effects of parameter uncertainty in the biosphere transport and exposure sub-models on the estimate of mean dose to individuals exposed via several exposure pathways

Environmental radioactivity in Canada - 1982

International Nuclear Information System (INIS)

Tracey, B.L.

1984-01-01

The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. Special investigations were carried out during 1982 on metabolism of natural radionuclides and on the accumulation of radon in energy-efficient homes. The pre-operational phase of the monitoring program at the Point Lepreau Nuclear Generating Station was completed. Dose commitments have been estimated for the ongoing natural radioactivity, fallout and reactor studies. All measurements made during the year are below the limits recommended by the International Commission on Radiological Protection

Intercomparison run for uranium and tritium determination in urine samples, organised by Nuclear Regulatory Authority, Argentina

International Nuclear Information System (INIS)

Serdeiro, Nelida H.; Equillor, Hugo E.; Bonino, Nestor O.

2003-01-01

The Nuclear Regulatory Authority (ARN), Argentina, has carried out an intercomparison run for tritium and uranium determination in urine, in November 2002. The aim of this exercise was to assess the performance of the laboratories that usually inform these radionuclides and to provide technical support in order to have an appropriate occupational monitoring in vitro. In the present work, the results of the intercomparison and the assessment of each laboratory are published. (author)

Intercomparison run for uranium and tritium determination in urine samples, organised by Nuclear Regulatory Authority, Argentina

CERN Document Server

Serdeiro, N H; Equillor, H E

2003-01-01

The Nuclear Regulatory Authority (ARN), Argentina, has carried out an intercomparison run for tritium and uranium determination in urine, in November 2002. The aim of this exercise was to assess the performance of the laboratories that usually inform these radionuclides and to provide technical support in order to have an appropriate occupational monitoring in vitro. In the present work, the results of the intercomparison and the assessment of each laboratory are published.

Results of the 2001 NRPB intercomparison of passive radon detectors

CERN Document Server

Howarth, C B

2002-01-01

As in previous years, an intercomparison of passive radon detectors was held at NRPB in 2001. Forty-seven laboratories submitted 62 sets of passive detectors to this intercomparison. The exercise included three exposures to radon and its decay products at different equilibrium factors. An additional exposure at the CERN - EU high Energy Reference Facility (CERF) to a simulated cosmic ray spectrum was also offered to participants. After exposure, the detectors were returned to their originating laboratories for assessment. Participants reported the estimated exposure for each detector before they were notified of the exposures given to the detectors. The results obtained by participating laboratories were classified according to the spread of results from detectors exposed together and by the difference between the mean result of each group and the actual exposure given. Thirty-five percent of the laboratories achieved the highest classification for accuracy, while 9% were in the lowest category. The proportio...

Tropospheric ozone lidar intercomparison experiment, TROLIX '91, field phase report

International Nuclear Information System (INIS)

Boesenberg, J.; Ancellet, G.; Bergwerff, H.; Cossart, G. v.; Fiedler, J.; Jonge, C. de; Mellqvist, J.; Mitev, V.; Sonnemann, G.; Swart, D.; Wallinder, E.

1993-01-01

The Tropospheric Ozone Lidar Intercomparison Experiment TROLIX '91 has been initiated as part of the TESLAS subproject of the cooperative programme EUROTRAC. It has been performed in June 1991 at the Rijksinstitut voor Volksgezondheid en Milieuhygiene (RIVM) in Bilthoven, The Netherlands. The experiment was based on the simultaneous operation of different types of differential absorption lidars (DIAL), a special version of a Differential Optical Absorption Spectroscopy Instrument (DOAS), helicopter borne in situ instruments, and many other supporting measurements. After a short introduction to the general methodology the instruments are described, the experimental operations are explained, and a selection of data are presented. Some examples are given for the results of the intercomparison, as far as they have been available at the present stage of evaluation. The main purpose of this report, however, is to provide an overview over the material collected during the experiment, on order to facilitate further detailed studies in cooperation between the different groups which have participated. (orig.)

Report on the intercomparison run IAEA-306 radionuclides in Baltic Sea sediment

International Nuclear Information System (INIS)

Ballestra, S.; Vas, D.; Lopez, J.J.; Noshkin, V.

1989-10-01

The results of an intercomparison exercise on a Baltic Sea sediment sample, coded as IAEA-306, designed for the determination of artificial and natural radionuclide levels, are reported. This sample was collected in the fall 1986. It was anticipated that the concentrations of the artificial radionuclides in this sediment would be higher than the environmental levels usually found and, therefore, would constitute an excellent intercomparison sample. The data from 84 laboratories representing 34 countries have been evaluated. The most frequently measured radionuclides are: 90 Sr, 125 Sb, 134 Cs, 137 Cs, 238 Pu, 239+240 Pu, 241 Am, 40 K, 210 Pb- 210 Po, 226 Ra, 228 Ra, 228 Th, 230 Th, 232 Th, 234 U and 238 U. 6 refs, 13 tabs

Radioactive waste management: a utility view

International Nuclear Information System (INIS)

Draper, E.L.

1982-01-01

The management of radioactive waste continues to be a matter of public concern and discussion. There is broad agreement among members of the technical community that the various types of waste radioactive species can be managed without jeopardizing public health and safety. Despite this consensus, one of the major reasons cited by opponents of commercial nuclear power for their opposition is the lack of a fully deployed waste management program. Such a program has been suggested but implementation is not yet complete. It is essential that a program be undertaken so as to dispel the impression that past inaction on waste disposal represents an inability to deal safely with wastes

Management of Radioactive Wastes in Developing Countries

International Nuclear Information System (INIS)

Abdel Ghani, A.H.

1999-01-01

The management of radioactive wastes is one area of increasing interest especially in developing countries having more and more activities in the application of radioisotopes in medicine, research and industry. For a better understanding of radioactive waste management in developing countries this work will discuss the following items:Classification of countries with respect to waste management programs. Principal Radionuclides used in medicine, biological research and others and the range of radioactivity commonly used. Estimation of radioactive waste volumes and activities. Management of liquid wastes Collection. Treatment. Management of small volumes of organic liquid waste. Collection Treatment. Packaging and storage of radioactive wastes

MANAGEMENT OF RADIOACTIVE WASTES IN CHINA

Institute of Scientific and Technical Information of China (English)

潘自强

1994-01-01

The policy and principles on management of radioactive wastes are stipulated.Cement solidification and bituminization unit has come into trial run.Solid radioactive waste is stored in tentative storage vault built in each of nuclear facilities.Seventeen storages associated with applications of nuclear technology and radioisotopes have been built for provinces.Disposal of low and intermediate level radioactive wastes pursues the policy of “regional disposal”.Four repositories have been planned to be built in northwest.southwest,south and east China respectively.A program for treatment and disposal of high level radioactive waste has been made.

Regulatory aspects of the radioactive waste management in Argentina

International Nuclear Information System (INIS)

Siraky, Graciela

2000-01-01

these wastes, and are presented in the paper. Regarding the safety assessment associated to the final disposal of radioactive wastes the NRA has developed models that have participated of the intercomparison exercise NSARS (IAEA). At the moment, NRA is taking part of the IAEA's Co-ordinated Research Programs ISAM and BIOMASS. Also at international level, the NRA has contributed to the formulation of recommendations of agencies such as IAEA or ICRP, and at present, it is taking part of the IAEA's Waste Safety Standards Advisory Committee (WASSAC). (author)

EURADOS intercomparison on measurements and Monte Carlo modelling for the assessment of Americium in a USTUR leg phantom

International Nuclear Information System (INIS)

Lopez, M. A.; Broggio, D.; Capello, K.; Cardenas-Mendez, E.; El-Faramawy, N.; Franck, D.; James, A. C.; Kramer, G. H.; Lacerenza, G.; Lynch, T. P.; Navarro, J. F.; Navarro, T.; Perez, B.; Ruehm, W.; Tolmachev, S. Y.; Weitzenegger, E.

2011-01-01

A collaboration of the EURADOS working group on 'Internal Dosimetry' and the United States Transuranium and Uranium Registries (USTUR) has taken place to carry out an intercomparison on measurements and Monte Carlo modelling determining americium deposited in the bone of a USTUR leg phantom. Preliminary results and conclusions of this intercomparison exercise are presented here. (authors)

Intercomparison exercise on external gamma dose rate under field conditions at the laboratory of natural radiation (Saelices el Chico, Spain)

International Nuclear Information System (INIS)

Gutierrez-Villanueva, J. L.; Sainz-Fernandez, C.; Fuente-Merino, I.; Saez-Vergara, J. C.; Correa-Garce, E.; Quindos-Poncela, L. S.

2013-01-01

The last nuclear accident in Fukushima nuclear power plant has increased the necessity for measuring radiation in the environment. Therefore, radiation monitors providing results traceable throughout the country become essential and it is very important to test them under the same environmental conditions. The first intercomparison of natural radioactivity under field conditions was held in Saelices el Chico (Salamanca, Spain) in May 2011, including an exercise on environmental dose rate. This article presents the results achieved by 19 instruments belonging to 12 institutions from 7 different countries. The tested detectors are proportional counters, ionisation chambers, Geiger-Mueller and scintillators measuring dose rate in three stations with reference values from 110 to 1800 nGy h -1 All the results were given in terms of air kerma (nGy h -1 ) and the measurements show agreement within 25 % in all the sites. Evaluation criteria based on accuracy and statistical uncertainty were also carried out and 25 % of participants passed the test in all sites. (authors)

The Radioactive Ion Beams in Brazil (RIBRAS) facility. Description, program, main results, future plans

Science.gov (United States)

Lépine-Szily, A.; Lichtenthäler, R.; Guimarães, V.

2014-08-01

RIBRAS (Radioactive Ion Beams in Brazil) is a facility installed at the Institute of Physics of the University of São Paulo (IFUSP), Brazil. The RIBRAS system consists of two superconducting solenoids and uses the "in-flight method" to produce radioactive ion beams using the primary beam provided by the 8UD Pelletron Tandem of IFUSP. The ion beams produced so far by RIBRAS are 6He, 8Li, 7Be, 10Be, 8B, 12B with intensities that can vary from 104 to 106 pps. Initially the experimental program covered the study of elastic and inelastic scattering with the objective to study the interaction potential and the reaction mechanisms between weakly bound (RIB) and halo (6He and 8B projectiles on light, medium and heavy mass targets. With highly purified beams, the study of resonant elastic scattering and resonant transfer reactions, using inverse kinematics and thick targets, has also been included in our experimental program. Also, transfer reactions of astrophysical interest and fusion reactions induced by halo nuclei are part of the near-future research program. Our recent results on elastic scattering, alpha-particle production and total reaction cross sections, as well as the resonant elastic and transfer reactions, are presented. Our plans for the near future are related to the installation of a new beam line and a cave for gamma-ray detection. We intend to place in operation a large area neutron detector available in our laboratory. The long-range plans could be the move of the RIBRAS system to the more energetic beam line of the LINAC post-accelerator (10MeV/nucleon primary beams) still in construction in our laboratory.

World-wide and regional intercomparison for the determination of trace elements in polluted marine sediment IAEA-356. Report no.56

Energy Technology Data Exchange (ETDEWEB)

Horvat, M; Mee, L D; Oregioni, B [International Atomic Energy Agency, Marine Environment Laboratory, Monaco (Monaco)

1994-09-01

The accurate and precise determination of trace elements in marine sediment samples is an important aspect of geochemical marine pollution studies and for assessing the levels and pathways of marine pollutants. Past intercomparison exercise conducted by the Marine Environment Laboratory of IAEA (formerly the International Laboratory of Marine Radioactivity) has focused upon the near shore sediment (1) and deep sea marine sediment (2) where trace levels of elements was rather low. The present intercomparison exercise on sediment taken from a polluted coastal lagoon was designed in order to fulfill the increased demand for certified reference materials of various origin and the number of parameters that should be studied. Additionally, different instrumental techniques, both nuclear and non-nuclear, were compared, and evaluated. By statistically examining the data from this study, the material can be certified for future use as a reference material. The current exercise was designed not only to test the intercomparability of different instrumental techniques, but also to evaluate the effectiveness of different procedures for sample digestion. Participants were invited to perform 'total' analyses involving, except in the case of neutron activation analysis, a simple partial extraction with 1M hydrochloric acid (2 hours, room temperature). This partial dissolution had a twofold purpose: (i) to differentiate between instrumental (plus contamination during work-up) errors and those resulting from method-specific (matrix) effects; and (ii) to evaluate a simple screening test for the more labile ('easily leached') fraction of trace elements of particular interest to environmental chemists. The present report presents the entire experimental data set and a statistical evaluation of the results for each parameter.

Presence of radioactivity in a sewage system: a proposal for radioactivity control

International Nuclear Information System (INIS)

Serradell, Vicente; Ballesteros, Luisa; Ortiz, Josefina

2008-01-01

Most hospitals use radioisotopes in diagnostics and to a lesser extent in therapy. The liquid residues thus generated are usually subjected to treatment before being discharged into the sewage system. Nevertheless, a certain amount of these residues escape from the treatment system and are poured directly into the sewer. In addition, other radioactive products used for research and industrial purposes may also be disposed of in the same way. The waste waters in many sewage systems can therefore be expected to be radiologically contaminated and the need for at least a basic control system in such situations seems obvious. When designing a procedure to measure radioactivity, certain conditions should be borne in mind: 1) The control program has to be simple and inexpensive; 2) Samples must be taken from the appropriate places; 3) Short life radionuclides will probably be present in significant amounts, so that specific recipes should be prepared; 4) Iodine is also frequently present. Special precautions should be taken to keep it in solution. In recent years, the Environmental Radioactivity Laboratory of the Universidad Politecnica de Valencia (Spain) has carried out a series of tests on the Valencia city sewage system and sewage treatment plant in order to design a permanent program to control radioactive contamination of the city's sewage system. This paper presents a proposal which we believe can provide the answer to this problem. (author)

Report on intercomparison exercise SR-74 determination of impurities in U3O8

International Nuclear Information System (INIS)

Doubek, N.; Deron, S.

1987-06-01

The report presents results of a laboratory intercomparison of the determination of impurities in U 3 O 8 sample organized by the IAEA. Seven laboratories of six countries, sent their results regarding 31 elements. The evaluation was based on 121 laboratory means. The majority of the results were obtained by emission spectroscopy and by flame atomic absorption techniques. As a result of this intercomparison, recommended certification values can be assigned for the concentration of Cr, Cu and Mg. Information values can be provided for an additional twelve elements (Al, B, Co, Fe, Mn, Mo, Ni, P, Pb, Sn, V, and Zn)

Results of the IAEA/RCA personal dosemeter intercomparison in the Asian and Pacific region

International Nuclear Information System (INIS)

Murakami, H.; Minami, K.; Griffith, R.V.

1994-01-01

In 1988, the International Atomic Energy Agency started the Regional Co-operative Agreement project for strengthening the radiation protection infrastructure in the Asian and Pacific region. One component of the initial programme was a regional personal dosimetry intercomparison, which was subsequently conducted in three phases over three years during the period 1990 to 1992. Seventeen organisations of all 14 member states participated in the programmes. Irradiations and data compilation were conducted by the Japan Atomic Energy Research Institute. This paper describes the results of the intercomparison programmes and discusses some features and personal dosimetry problems in the RCA member states. (author)

Data Processing and Programming Applied to an Environmental Radioactivity Laboratory

International Nuclear Information System (INIS)

Trinidad, J. A.; Gasco, C.; Palacios, M. A.

2009-01-01

This report is the original research work presented for the attainment of the author master degree and its main objective has been the resolution -by means of friendly programming- of some of the observed problems in the environmental radioactivity laboratory belonging to the Department of Radiological Surveillance and Environmental Radioactivity from CIEMAT. The software has been developed in Visual Basic for applications in Excel files and it solves by macro orders three of the detected problems: a) calculation of characteristic limits for the measurements of the beta total and beta rest activity concentrations according to standards MARLAP, ISO and UNE and the comparison of the three results b) Pb-210 and Po-210 decontamination factor determination in the ultra-low level Am-241 analysis in air samples by alpha spectrometry and c) comparison of two analytical techniques for measuring Pb-210 in air ( direct-by gamma spectrometry- and indirect -by radiochemical separation and alpha spectrometry). The organization processes of the different excel files implied in the subroutines, calculations and required formulae are explained graphically for its comprehension. The advantage of using this kind of programmes is based on their versatility and the ease for obtaining data that lately are required by tables that can be modified as time goes by and the laboratory gets more data with the special applications for describing a method (Pb-210 decontamination factors for americium analysis in air) or comparing temporal series of Pb-210 data analysed by different methods (Pb-210 in air). (Author)

Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Washington

International Nuclear Information System (INIS)

2003-01-01

This ''Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement'' (HSW EIS) covers three primary aspects of waste management at Hanford--waste treatment, storage, and disposal. It also addresses four kinds of solid waste--low-level waste (LLW), mixed (radioactive and chemically hazardous) low-level waste (MLLW), transuranic (TRU) waste, and immobilized low-activity waste (ILAW). It fundamentally asks the question: how should we manage the waste we have now and will have in the future? This EIS analyzes the impacts of the LLW, MLLW, TRU waste, and ILAW we currently have in storage, will generate, or expect to receive at Hanford. The HSW EIS is intended to help us determine what specific facilities we will continue to use, modify, or construct to treat, store, and dispose of these wastes (Figure S.1). Because radioactive and chemically hazardous waste management is a complex, technical, and difficult subject, we have made every effort to minimize the use of acronyms (making an exception for our four waste types listed above), use more commonly understood words, and provide the ''big picture'' in this summary. An acronym list, glossary of terms, and conversions for units of measure are provided in a readers guide in Volume 1 of this EIS

Strategic program for deep geological disposal of high level radioactive waste in China

International Nuclear Information System (INIS)

Wang Ju

2004-01-01

A strategic program for deep geological disposal of high level radioactive waste in China is proposed in this paper. A '3-step technical strategy': site selection and site characterization-site specific underground research laboratory-final repository, is proposed for the development of China's high level radioactive waste repository. The activities related with site selection and site characterization for the repository can be combined with those for the underground research laboratory. The goal of the strategy is to build China's repository around 2040, while the activities can be divided into 4 phases: 1) site selection and site characterization; 2) site confirmation and construction of underground research laboratory, 3) in-situ experiment and disposal demonstration, and 4) construction of repository. The targets and tasks for each phase are proposed. The logistic relationship among the activities is discussed. It is pointed out that the site selection and site characterization provide the basis for the program, the fundamental study and underground research laboratory study are the key support, the performance assessment plays a guiding role, while the construction of a qualified repository is the final goal. The site selection can be divided into 3 stages: comparison among pre-selected areas, comparison among pre-selected sites and confirmation of the final site. According to this strategy, the final site for China's underground research laboratory and repository will be confirmed in 2015, where the construction of an underground laboratory will be started. In 2025 the underground laboratory will have been constructed, while in around 2040, the construction of a final repository is to be completed

Italian Antarctic Research Program: environmental radioactivity survey around the Italian base (1987-1991) Terra Nova Bay - Ross Sea region

Energy Technology Data Exchange (ETDEWEB)

Tubertini, O.; Bettoli, M.G.; Cantelli, L. [Bologna Univ. (Italy)] [and others

1995-12-31

Investigations have been carried out by the Italian Antartic Research Program to determine the natural and artificial radioactivity levels of both the marine and terrestrial environments. Also, natural and anthropogenic fluxes of aerosol particles onto the Antartic surface have been examined. (Author).

Italian Antarctic Research Program: environmental radioactivity survey around the Italian base (1987-1991) Terra Nova Bay - Ross Sea region

International Nuclear Information System (INIS)

Tubertini, O.; Bettoli, M.G.; Cantelli, L.

1995-01-01

Investigations have been carried out by the Italian Antartic Research Program to determine the natural and artificial radioactivity levels of both the marine and terrestrial environments. Also, natural and anthropogenic fluxes of aerosol particles onto the Antartic surface have been examined. (Author)

Directory of Certificates of Compliance for Radioactive Materials Packages. Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages. Volume 3. Revision 5

International Nuclear Information System (INIS)

1985-10-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1985. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory. Shipments of radioactive material utilizing these packages must be in accordance with the provisions of 49 CFR Section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with a Nuclear Regulatory Commission approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR Section 71.12 does not authorize the receipt, possession, use or transfer of byproduct, source or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, or 70

Results of the argentinian intercomparison on internal dosimetry 2014. Measurement of thyroid burden

International Nuclear Information System (INIS)

Rojo, A.M.; Puerta, N.; Gossio, S.; Gómez Parada, I.

2015-01-01

Internal dosimetry intercomparisons are essential for the verification of the capability to perform direct measurements of “1”3”1I thyroid burden and the expertise in the interpretation of these data for dose assessment. To that aim, in 2014 the National Intercomparison Exercise was organized and coordinated by the Internal Dosimetry Laboratory of the Autoridad Regulatoria Nuclear (ARN) of Argentina. The exercise counted with the participation of six internal dosimetry services: nuclear power plants (NA-SA CNA and NA-SA CNE), CNEA Atomic Centres: Bariloche (CAB) and Ezeiza (CAE), Roffo Institute (UBA – CNEA) and ARN. This report shows a complete analysis of the participant’s results in this exercise. (authors) [es

Biological dosimetry after criticality accidents. Intercomparison exercise in the Silene Reactor - France

International Nuclear Information System (INIS)

Di Giorgio, Marina; Vallerga, Maria B.; Taja, Maria R.

2004-01-01

The Institute of Radiation Protection and Nuclear Safety Institute (IRSN) organized an international biological dosimetry intercomparison, at the SILENE experimental reactor (Valduc, France), simulating different criticality scenarios: bare source 4 Gy, lead shield source 1 and 2 Gy and gamma pure 60 Co source 2 Gy. Fifteen laboratories were involved in this exercise, including the Argentine Biological Dosimetry Laboratory. The purposes of the intercomparison were: 1) To compare the unstable chromosome aberration (UCA) frequency observed by the different laboratories; and 2) To compare the dose estimation for gamma rays and neutrons. The objects of the present work were: I) To compare the mean frequency of UCA observed by the Argentine laboratory with the mean frequency observed by the participant laboratories as a whole. II) To compare the dose estimates performed by the Argentine lab with those estimated by the other laboratories involved in the second stage of the intercomparison. Overall, the mean frequencies of UCA and the correspondent 95% confidence limits obtained by the Argentine lab were consistent with the results obtained by the laboratories as a whole. For the gamma pure scenario, smaller variations were observed among laboratories in terms of dose (CV=18,2%) than in terms of frequency (CV=30,1%). For the mixed field scenarios, only four laboratories, including the Argentine lab, estimated gamma and neutron components of the total dose and just two (Argentine lab and lab 12) were in agreement with the given physical doses. The 1 Gy experiment presented lesser variations both in terms of frequency and dose than the other two scenarios. For the 4 and 2 Gy experiments, variations in neutron dose were more significant than variations in gamma dose, related to the magnitude of the dose. The results suggest that intercomparison exercises jointly with the accreditation of biological dosimetry by cytogenetic service laboratories, in compliance with ISO

The Agricultural Model Intercomparison and Improvement Project (AgMIP): Overview and Progress

Science.gov (United States)

Rosenzweig, C.; Hatfield, J.; Jones, J. W.; Ruane, A. C.

2012-12-01

The Agricultural Model Intercomparison and Improvement Project (AgMIP) is an international effort to assess the state of global agricultural modeling and to understand climate impacts on the agricultural sector. AgMIP connects the climate science, crop modeling, and agricultural economic modeling communities to generate probabilistic projections of current and future climate impacts. The goals of AgMIP are to improve substantially the characterization of risk of hunger and world food security due to climate change and to enhance adaptation capacity in both developing and developed countries. This presentation will describe the general approach of AgMIP and highlight its findings and activities. AgMIP crop model intercomparisons have been established for wheat (27 models participating), maize (25 models), and rice (15+ models), and are being established for sugarcane, soybean, sorghum/millet, and peanut. In coordination with these pilots, methodologies to utilize weather generators and downscaled climate simulations for agricultural applications are under development. An AgMIP global agricultural economics model intercomparison with participation of 11 international groups is ongoing, and a number of global biophysical models are currently being evaluated for future climate impacts on agricultural lands both as part of the Inter-Sectoral Impact Model Intercomparison Project (ISI-MIP) and for contribution to the IPCC Fifth Assessment Report (AR5). AgMIP is also organizing regional research efforts, and has already held workshops in South America, Sub-Saharan Africa, South Asia, Europe, and North America. Outcomes from these meetings have informed AgMIP activities, and 10 research teams from Sub-Saharan Africa and South Asia have been selected for project funding. Additional activities are planned for Australia and East Asia. As the AgMIP research community continues to work towards its goals, three key cross-cutting scientific challenges have emerged and are being

Feasibility study of radiophotoluminescent glass rod dosimeter postal dose intercomparison for high energy photon beam

International Nuclear Information System (INIS)

Rah, Jeong-Eun; Kim, Siyong; Cheong, Kwang-Ho; Lee, Jeong-Woo; Chung, Jin-Beom; Shin, Dong-Oh; Suh, Tae-Suk

2009-01-01

A radiophotoluminescent glass rod dosimeter (GRD) system has recently become commercially available. In this study we evaluated whether the GRD would be suitable for external dosimetric audit program in radiotherapy. For this purpose, we introduced a methodology of the absorbed dose determination with the GRD by establishing calibration coefficient and various correction factors (non-linearity dose response, fading, energy dependence and angular dependence). A feasibility test of the GRD postal dose intercomparison was also performed for eight high photon beams by considering four radiotherapy centers in Korea. In the accuracy evaluation of the GRD dosimetry established in this study, we obtained within 1.5% agreements with the ionization chamber dosimetry for the 60 Co beam. It was also observed that, in the feasibility study, all the relative deviations were smaller than 3%. Based on these results, we believe that the new GRD system has considerable potential to be used for a postal dose audit program

Radioactive waste management in perspective

International Nuclear Information System (INIS)

1996-01-01

This report drafted by the Nuclear Energy Agency (NEA) deals with the basic principles and the main stages of radioactive waste management. The review more precisely focuses on what relates to environment protection, safety assessment, financing, social issues, public concerns and international co-operation. An annex finally summarises the radioactive waste management programs that are implemented in 15 of the NEA countries. (TEC). figs

1983 international intercomparison of nuclear accident dosimetry systems at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Swaja, R.E.; Greene, R.T.; Sims, C.S.

1985-04-01

An international intercomparison of nuclear accident dosimetry systems was conducted during September 12-16, 1983, at Oak Ridge National Laboratory (ORNL) using the Health Physics Research Reactor operated in the pulse mode to simulate criticality accidents. This study marked the twentieth in a series of annual accident dosimetry intercomparisons conducted at ORNL. Participants from ten organizations attended this intercomparison and measured neutron and gamma doses at area monitoring stations and on phantoms for three different shield conditions. Results of this study indicate that foil activation techniques are the most popular and accurate method of determining accident-level neutron doses at area monitoring stations. For personnel monitoring, foil activation, blood sodium activation, and thermoluminescent (TL) methods are all capable of providing accurate dose estimates in a variety of radiation fields. All participants in this study used TLD's to determine gamma doses with very good results on the average. Chemical dosemeters were also shown to be capable of yielding accurate estimates of total neutron plus gamma doses in a variety of radiation fields. While 83% of all neutron measurements satisfied regulatory standards relative to reference values, only 39% of all gamma results satisfied corresponding guidelines for gamma measurements. These results indicate that continued improvement in accident dosimetry evaluation and measurement techniques is needed

Participation of the Nuclear Regulatory Authority in the 'Third European Intercomparison Exercise on Internal Dose Assessment'

International Nuclear Information System (INIS)

Rojo, Ana Maria; Gomez Parada, Ines Maria

2001-01-01

This paper resume the participation of the Argentine Nuclear Regulatory Authority (ARN) in the 'Third European Intercomparison Exercise on Internal Dose Assessment'. It takes place during 5 months in 1998 and the final meeting was held in Weimar, Germany, on May 1999. This exercise involved the previous distribution of seven cases, simulated and real, describing possible incorporations of radioactive materials. There was a description of the event, data of retention or excretion measurements and air concentration data. The fifty participants belong to twenty three countries had do solve the cases and informed the results to the organizers, mainly the incorporation and effective dose was required. The objective was to review the methodology, the codes and the different assumptions used by the participants for discussing the consistent of the result. The results are shown through tables including the maximum and minimum values gave for the final report and the results informed by ARN. This exercise allowed to compare the methodology used by the ARN internal dosimetry group with other choose by several international groups to assure that the codes, assumptions and methodology were satisfactory to solve the different cases given by the organizers. (author)

CRUSH1: a simplified computer program for impact analysis of radioactive material transport casks

Energy Technology Data Exchange (ETDEWEB)

Ikushima, Takeshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1996-07-01

In drop impact analyses for radioactive transport casks, it has become possible to perform them in detail by using interaction evaluation, computer programs, such as DYNA2D, DYNA3D, PISCES and HONDO. However, the considerable cost and computer time are necessitated to perform analyses by these programs. To meet the above requirements, a simplified computer program CRUSH1 has been developed. The CRUSH1 is a static calculation computer program capable of evaluating the maximum acceleration of cask bodies and the maximum deformation of shock absorbers using an Uniaxial Displacement Method (UDM). The CRUSH1 is a revised version of the CRUSH. Main revisions of the computer program are as follows; (1) not only main frame computer but also work stations (OS UNIX) and personal computer (OS Windows 3.1 or Windows NT) are available for use of the CRUSH1 and (2) input data set are revised. In the paper, brief illustration of calculation method using UDM is presented. The second section presents comparisons between UDM and the detailed method. The third section provides a use`s guide for CRUSH1. (author)

CRUSH1: a simplified computer program for impact analysis of radioactive material transport casks

International Nuclear Information System (INIS)

Ikushima, Takeshi

1996-07-01

In drop impact analyses for radioactive transport casks, it has become possible to perform them in detail by using interaction evaluation, computer programs, such as DYNA2D, DYNA3D, PISCES and HONDO. However, the considerable cost and computer time are necessitated to perform analyses by these programs. To meet the above requirements, a simplified computer program CRUSH1 has been developed. The CRUSH1 is a static calculation computer program capable of evaluating the maximum acceleration of cask bodies and the maximum deformation of shock absorbers using an Uniaxial Displacement Method (UDM). The CRUSH1 is a revised version of the CRUSH. Main revisions of the computer program are as follows; (1) not only main frame computer but also work stations (OS UNIX) and personal computer (OS Windows 3.1 or Windows NT) are available for use of the CRUSH1 and (2) input data set are revised. In the paper, brief illustration of calculation method using UDM is presented. The second section presents comparisons between UDM and the detailed method. The third section provides a use's guide for CRUSH1. (author)

United States high-level radioactive waste management program: Current status and plans

International Nuclear Information System (INIS)

Williams, J.

1992-01-01

The inventory of spent fuel in storage at reactor sites in the United States is approximately 20,000 metric tons heavy metal (MTHM). It is increasing at a rate of 1700 to 2100 MTHM per year. According to current projections, by the time the last license for the current generation of nuclear reactors expires, there will be an estimated total of 84,000 MTHm. No commercial reprocessing capacity exists or is planned in the US. Therefore, the continued storage of spent fuel is required. The majority of spent fuel remains in the spent fuel pools of the utilities that generated it. Three utilities are presently supplementing pool capacity with on-site dry storage technologies, and four others are planning dry storage. Commercial utilities are responsible for managing their spent fuel until the Federal waste management system, now under development, accepts spent fuel for storage and disposal. Federal legislation charges the Office of Civilian Radioactive Waste Management (OCRWM) within the US Department of Energy (DOE) with responsibility for developing a system to permanently dispose of spent fuel and high level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. We are developing a waste management system consisting for three components: a mined geologic repository, with a projected start date of 2010; a monitored retrievable storage facility (MRS), scheduled to begin waste acceptance in 1998; and a transportation system to support MRS and repository operations. This paper discusses the background and framework for the program, as well as the current status and plans for management of spent nuclear fuel at commercial utilities; the OCRWM's development of a permanent geologic repository, an MRS, and a transportation system; the OCRWM's safety approach; the OCRWM's program management initiatives; and the OCRWM's external relations activities

Intercomparison of preliminary MFR, SBUV, TOMS, and TOVS total ozone data

International Nuclear Information System (INIS)

Luther, F.M.

1992-01-01

The High Altitude Pollution Program of the Federal Aviation Administration is sponsoring a comparative study of total ozone data derived from various satellite instruments. The instruments included in the study are the Defense Meteorological Satellite Program's Multichannel Filter Radiometer (MFR), the NASA Solar Backscatter Ultraviolet Ozone Experiment (SBUV), the NASA Total Ozone Mapping Spectrometer (TOMS), and the NOAA Tiros Operational Vertical Sounder (TOVS). The two periods chosen for data intercomparison are January 1 - February 15, 1979 and June 1-30, 1979. These two data periods cover summer and winter regimes in both hemispheres. The January 1 - February 15, 1979 period includes a significant stratospheric warming event that began about January 15. Each of the satellite instruments has its own strengths and weaknesses. No instrument is universally better than or worse than any other in terms of accuracy, although they appear to have definite biases in certain geographical areas. The differences between the satellite systems is greatest at high latitudes where cloudiness and ozone variabilities are greatest. The Dobson data show a bias and differing degrees of ozone variability between nearby Dobson stations, which indicates there may be problems with using the Dobson data as a standard for comparison. The data used in this comparative study are preliminary in nature

Intercomparison and validation of computer codes for thermalhydraulic safety analysis of heavy water reactors

International Nuclear Information System (INIS)

2004-08-01

Activities within the frame of the IAEA's Technical Working Group on Advanced Technologies for HWRs (TWG-HWR) are conducted in a project within the IAEA's subprogramme on nuclear power reactor technology development. The objective of the activities on HWRs is to foster, within the frame of the TWG-HWR, information exchange and co-operative research on technology development for current and future HWRs, with an emphasis on safety, economics and fuel resource sustainability. One of the activities recommended by the TWG-HWR was an international standard problem exercise entitled: Intercomparison and validation of computer codes for thermalhydraulics safety analyses. Intercomparison and validation of computer codes used in different countries for thermalhydraulics safety analyses will enhance the confidence in the predictions made by these codes. However, the intercomparison and validation exercise needs a set of reliable experimental data. The RD-14M Large-Loss Of Coolant Accident (LOCA) test B9401 simulating HWR LOCA behaviour that was conducted by Atomic Energy of Canada Ltd (AECL) was selected for this validation project. This report provides a comparison of the results obtained from six participating countries, utilizing four different computer codes. General conclusions are reached and recommendations made

The radioactive waste management videoconference training series for an international audience

International Nuclear Information System (INIS)

Callan, C.; Hylko, J.M.

1996-01-01

A proven cost-effective method for delivering new educational opportunities to employees in different locations simultaneously is by using the live videoconference format. Also, the videotapes produced from this format allows employees to participate who are not routinely available for traditional classroom training. However, the primary challenge is to design a distance learning series that meets the requirements of a diverse audience. The National Environmental Technology Network (NETN), a program associated with the College of Engineering at the University of New Mexico, has a proven track record in developing and producing effective videoconference and distance learning programs for industry, government, national laboratories, and universities. Specifically, The Radioactive Waste Management Videoconference Training Series is comprised of eight individual programs: (1) Introduction to Radioactive Waste Management, (2) Interactions Between Radiation and Matter; (3) Decommissioning and Decontamination; (4) Transportation; (5) Low-Level Radioactive Waste; (6) High-Level Radioactive Waste; (7) Transuranic Waste; and (8) New and Other Technologies for Radioactive Waste Management. Each program consists of a tiered approach featuring an introduction, case studies, legal and regulatory issues, radioactive waste characteristics, disposal Options, and transfer of technology. The participants receive a packet containing a full outline of the course, including charts and illustrations used by the presenters. At the conclusion of each program, the interactive question/answer period allows viewers to ask pertinent questions and to participate as a group

Intercomparison of radiation dosimeters for individual monitoring

International Nuclear Information System (INIS)

1993-05-01

The Co-ordinated Research Programme on Intercomparison for Individual Monitoring was established to provide participants with an opportunity to assess (1) their ability to measure external photon radiation fields and (2) the potential impact of introduction of the new operational quantities on their dosimetry programmes. Twenty-four laboratories from 18 IAEA Member States and three international organizations, including the IAEA, participated. The results of phase II of the CRP are presented in this document, which includes a compilation of the presentations and conclusions from the meeting. Refs, figs and tabs

Quality audit of dosimetry in radiotherapy centers using postal dose TLD intercomparison in India

International Nuclear Information System (INIS)

Ramanathan, G.; Kadam, V.D.; Vinatha, S.P.; Soman, A.T.; Vijayam, M.; Shaha, V.V.; Abani, M.C.

2001-01-01

The national quality audit of dosimetry in radiation therapy centers using mailed TLDs is being carried out by RSS/ASSD of BARC since 1976, in collaboration with IAEA/WHO for India and neighbouring countries such as Mayanmar, Sri Lanka and Nepal. The importance of the programme comes from the fact that consistent, high accuracy ( 60 Co machines ∼35 linear accelerators are being covered by the programme. This paper brings out the materials and methods used in the intercomparison. The results of intercomparison are analyzed to find the steps to improve the performance in quality audit of those centers whose results are outside the limit of acceptable deviation

Nuclear accident dosimetry measurements at the fourth IAEA intercomparison, Harwell, United Kingdom, April 1975

International Nuclear Information System (INIS)

Majborn, B.

1975-11-01

During the fourth IAEA intercomparison at Harwell, teams from several countries compared their systems for assessing doses in criticality accidents. The dosimeters were exposed to mixed pulses of neutron and gamma radiation produced by the VIPER reactor at AWRE, Aldermaston. Risoe participated in this intercomparison with the routine personnel dosimeters employed in 'criticality areas' at Risoe. These include the UKAEA criticality dosimeter for the measurement of neutron doses and the Risoe TLD badge for the measurement of gamma doses. The final results of the Risoe measurements are presented in this report in a form designed for ease of comparison with results of other pparticipants. (author)

Annual radioactive waste tank inspection program: 1995

International Nuclear Information System (INIS)

McNatt, F.G. Sr.

1996-01-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1995 to evaluate these vessels and evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

Annual radioactive waste tank inspection program - 1992

International Nuclear Information System (INIS)

McNatt, F.G.

1992-01-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1992 to evaluate these vessels and evaluations based on data accrued by inspections made since the tanks were constructed are the subject of this report

Annual radioactive waste tank inspection program - 1991

International Nuclear Information System (INIS)

McNatt, F.G.

1992-01-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1991 to evaluate these vessels and evaluations based on data accrued by inspections made since the tanks were constructed are the subject of this report

SimilarityExplorer: A visual inter-comparison tool for multifaceted climate data

Science.gov (United States)

J. Poco; A. Dasgupta; Y. Wei; W. Hargrove; C. Schwalm; R. Cook; E. Bertini; C. Silva

2014-01-01

Inter-comparison and similarity analysis to gauge consensus among multiple simulation models is a critical visualization problem for understanding climate change patterns. Climate models, specifically, Terrestrial Biosphere Models (TBM) represent time and space variable ecosystem processes, for example, simulations of photosynthesis and respiration, using algorithms...

Report on the intercomparison run for the determination of radionuclides in soils. IAEA-326 and IAEA-327

International Nuclear Information System (INIS)

Bojanowski, R.; Radecki, Z.; Campbell, M.J.; Burns, K.I.; Trinkl, A.

2001-04-01

Intercomparison programmes have the potential to improve the level of agreement between the results of measurements obtained on natural matrices by different methods and by various laboratories world-wide. They could also be able to help the participants trace the causes of departure of their data from the true values, if sufficient information is provided to the organiser. As the true values are unknown, they are usually replaced by consensus values derived from the data that have met a number of defined quality criteria. The previous evaluation process of intercomparison exercises did not allow the full benefits of exercise to be obtained. The reference values were set on the basis of 'the law of the majority' ('consensus' values) and were not traceable to internationally agreed primary units (SI units). Traceability of measurements can be achieved by providing a link between the data generated in participants' laboratories and a stipulated reference point through an unbroken chain of comparisons, enabling assessment of the quality of their measurements by quantifying the combined uncertainty of all the links in the chain. In radioactivity measurements, the shortest chain is achieved in γ-spectrometry. It can be obtained by proper calibration of instruments, using standard sources certified by primary measurement laboratories and propagating the uncertainties throughout the whole measurement process. Matrix effects and coincidence losses must be given due attention as well. Traceability of results obtained by isotope dilution alpha- spectrometry requires, in addition, a quantitative budget of uncertainties associated with sample treatment up to the stage when isotope exchange is assured. The most difficult cases are methods based on beta counting because each stage of the numerous analytical operations can break the traceability chain and because beta-radiation has a continuous spectrum which is difficult to quantify. In this Intercomparison, an attempt was made

The Radioactive Ion Beams in Brazil (RIBRAS) facility. Description, program, main results, future plans

Energy Technology Data Exchange (ETDEWEB)

Lepine-Szily, A.; Lichtenthaeler, R.; Guimaraes, V. [Instituto de Fisica, Universidade de Sao Paulo (Brazil)

2014-08-15

RIBRAS (Radioactive Ion Beams in Brazil) is a facility installed at the Institute of Physics of the University of Sao Paulo (IFUSP), Brazil. The RIBRAS system consists of two superconducting solenoids and uses the ''in-flight method'' to produce radioactive ion beams using the primary beam provided by the 8UD Pelletron Tandem of IFUSP. The ion beams produced so far by RIBRAS are {sup 6}He, {sup 8}Li, {sup 7}Be, {sup 10}Be, {sup 8}B, {sup 12}B with intensities that can vary from 10{sup 4} to 10{sup 6} pps. Initially the experimental program covered the study of elastic and inelastic scattering with the objective to study the interaction potential and the reaction mechanisms between weakly bound (RIB) and halo ({sup 6}He and {sup 8}B) projectiles on light, medium and heavy mass targets. With highly purified beams, the study of resonant elastic scattering and resonant transfer reactions, using inverse kinematics and thick targets, has also been included in our experimental program. Also, transfer reactions of astrophysical interest and fusion reactions induced by halo nuclei are part of the near-future research program. Our recent results on elastic scattering, alpha-particle production and total reaction cross sections, as well as the resonant elastic and transfer reactions, are presented. Our plans for the near future are related to the installation of a new beam line and a cave for gamma-ray detection. We intend to place in operation a large area neutron detector available in our laboratory. The long-range plans could be the move of the RIBRAS system to the more energetic beam line of the LINAC post-accelerator (10MeV/nucleon primary beams) still in construction in our laboratory. (orig.)

Establishment and utilization of radiological protection programs for the transport of radioactive material

International Nuclear Information System (INIS)

Lopez V, J.; Capadona, N.

2006-01-01

The present work has by objective to indicate rules for the establishment and the use of the Radiological Protection Programs (PPR) that are of application to the transport of radioactive materials according to that required by the Transport Regulation of the International Atomic Energy Agency (IAEA). The PPR are established and applied in systematic form for remittent, transport and addressees, to consider the measures of radiological protection and its appropriately control during the transport stages of radioactive material. In particular, in the work it is analyzed the PPR applied to the operative stage, in the one that can be considered as one of the more important documents to use since it summarizes the evaluations and the necessary controls of radiological protection. Also it is analyzed the importance that this document gets ready on the base that it converges in the the analyses, evaluations and data that have been kept in mind during the previous stages of design of bundles and production of packings, the types and quantities of involved bundles, as well as of considering the quantities of expeditions and its frequencies, the ways of transport, etc. It is included a brief description of the parts that the PPR conforms on the base of that suggested in the advanced draft of the TS-G-1.5 Guide 'Radiation Protection Programmes for Transport of Radioactive Material', of October, 2005, of the IAEA: objectives. necessity, scope, basic elements of a PPR in function of the occupational dose. assignment of functions and responsibilities for the establishment of a PPR, evaluation and dose optimization, surface contamination, segregation and other protection measures, responses in emergencies. training and administration systems for baled and transport of radioactive material. Next an example of PPR for the transport of bundles of the A Type by lorry with content of radiopharmaceuticals that are the bundles more used worldwide in the expeditions of radioactive

Operational radioactive waste management plan for the Nevada Test Site

International Nuclear Information System (INIS)

1980-11-01

The Operational Radioactive Waste Management Plan for the Nevada Test Site establishes procedures and methods for the safe shipping, receiving, processing, disposal, and storage of radioactive waste. Included are NTS radioactive waste disposition program guidelines, procedures for radioactive waste management, a description of storage and disposal areas and facilities, and a glossary of specifications and requirements

Institutional storage and disposal of radioactive materials

International Nuclear Information System (INIS)

St Germain, J.

1986-01-01

Storage and disposal of radioactive materials from nuclear medicine operations must be considered in the overall program design. The storage of materials from daily operation, materials in transit, and long-term storage represent sources of exposure. The design of storage facilities must include consideration of available space, choice of material, occupancy of surrounding areas, and amount of radioactivity anticipated. Neglect of any of these factors will lead to exposure problems. The ultimate product of any manipulation of radioactive material will be some form of radioactive waste. This waste may be discharged into the environment or placed within a storage area for packaging and transfer to a broker for ultimate disposal. Personnel must be keenly aware of packaging regulations of the burial site as well as applicable federal and local codes. Fire codes should be reviewed if there is to be storage of flammable materials in any area. Radiation protection personnel should be aware of community attitudes when considering the design of the waste program

Implementation of the program law from June 28, 2006 on the sustainable management of radioactive materials and wastes

International Nuclear Information System (INIS)

2009-07-01

This presentation, given by the national agency of radioactive waste management (ANDRA) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), describes the two projects of the ANDRA in the framework of the program law of June 28, 2006 about the sustainable management of radioactive materials and wastes. The first project is a reversible deep geologic waste disposal facility for high level/long living wastes. The second project is a low depth waste storage facility for low level/long living wastes. For each project, the site selection, the type of waste and its conditioning, and the concept and specifications of the facility are presented. (J.S.)

The review of radioactive waste management in the world

International Nuclear Information System (INIS)

Jalilzadeh, R.; Mirzahosseini, A.; Rahnomaei, N. A.

2008-01-01

Radioactive waste is generally classified on the basis of how much radiation and the type of radiation it emits as well as the length of time over which it will continue to emit radiation. Many activities dealing with radioactive materials produce nuclear wastes, including civilian nuclear power programs (nuclear Power plant operations and nuclear fuel-cycle activities), defense nuclear programs (nuclear weapons production, naval nuclear reactor programs, and related R and D), and industrial and institutional activities (scientific research, medical operations, and other industrial uses of Radioisotopic sources or Radio chemicals). To minimize the potential adverse health and environment impacts to people and other systems including of animals, plant and etc, during the entire lifetime of the radionuclides involved, nuclear waste must be carefully and properly managed. The scope of nuclear - waste management encompasses generation, processing (treatment and packaging), storage, transport, and disposal. in this research the effect of radioactive waste on environment and also disposal methods and radioactive waste management in countries is surveyed

Fifteen years of radioactive waste management at Ontario Hydro

International Nuclear Information System (INIS)

Carter, T.J.; Rao, P.K.M.

1985-01-01

Ontario Hydro is a large Canadian utility producing 84% (7394 MWe) of the Nuclear Electricity generated in Canada. The low- and intermediate-level radioactive wastes generated by the Ontario Hydro program are currently being managed at the Bruce Nuclear Power Development with various volume reduction, packaging and interim storage systems. Ontario Hydro also owns and operates a radioactive waste transportation system. Studies are in progress for final disposal of these wastes in a suitable geology in Ontario. Since its inception in 1971, Ontario Hydro's radioactive waste management program has evolved into providing a full fledged radioactive waste management capability to the utility's two nuclear generation centres at Pickering and Bruce, and later in the decade, to Darlington. This paper summarizes the various developments in this program; highlights the major facilities both in-service and planned to be built; reviews the experiences gained over fifteen years of in-house waste management; and discusses the proposed reorientation towards ultimate disposal of these wastes. 2 refs., 8 figs., 1 tab

Current status and prospect on the radioactive waste management program in the Republic of Korea. Focusing on recent development

International Nuclear Information System (INIS)

Park, Hyun-Soo; Chang, In-Soon

1996-01-01

Since its first commercial operation at Kori near the city of Pusan in 1978, nuclear energy has become one of the prime resources for the electricity. However, proper treatment of its byproducts, radioactive wastes, has been the national concern. Despite vigorous effort by the Korean Government and NEMAC(Nuclear Environment Management Center), the series of attempts for the site selection to build the national radioactive waste complex has been ruined. After the failure at Guleop Island, the Government recently amended its policy so that the major tasks on the management program of radioactive wastes shall be transferred to KEPCO(Korea Electric Power Corporation), sole national electric utility, while the current authority, KAERI(Korea Atomic Energy Research Institute)/NEMAC is limited to focus on the research and development in the safe management of spent fuels. Detailed plan to support the Government redirection is under discussion among concerned institutes. (author)

Meeting the regulatory information needs of users of radioactive materials

International Nuclear Information System (INIS)

MacDurmon, G.W.

1996-01-01

The use of radioactive materials is one of the most regulated areas of research. Researchers face ever increasing regulatory requirements and issues involving the disposal of radioactive material, while meeting the demands of higher productivity. Radiation safety programs must maximize regulatory compliance, minimize barriers, provide services and solutions, and effectively communicate with users of radioactive materials. This talk will discuss methods by which a radiation safety program can meet the needs of both the research staff and regulatory compliance staff

Meeting the regulatory information needs of users of radioactive materials

Energy Technology Data Exchange (ETDEWEB)

MacDurmon, G.W. [American Cyanamid Company, Princeton, NJ (United States)

1996-10-01

The use of radioactive materials is one of the most regulated areas of research. Researchers face ever increasing regulatory requirements and issues involving the disposal of radioactive material, while meeting the demands of higher productivity. Radiation safety programs must maximize regulatory compliance, minimize barriers, provide services and solutions, and effectively communicate with users of radioactive materials. This talk will discuss methods by which a radiation safety program can meet the needs of both the research staff and regulatory compliance staff.

BRDF Characterization and Calibration Inter-Comparison between Terra MODIS, Aqua MODIS, and S-NPP VIIRS

Science.gov (United States)

Chang, Tiejun; Xiong, Xiaoxiong (Jack); Angal, Amit; Wu, Aisheng

2016-01-01

The inter-comparison of reflective solar bands (RSB) between Terra MODIS, Aqua MODIS, and SNPP VIIRS is very important for assessment of each instrument's calibration and to identify calibration improvements. One of the limitations of using their ground observations for the assessment is a lack of the simultaneous nadir overpasses (SNOs) over selected pseudo-invariant targets. In addition, their measurements over a selected Earth view target have significant difference in solar and view angles, and these differences magnify the effects of Bidirectional Reflectance Distribution Function (BRDF). In this work, an inter-comparison technique using a semi-empirical BRDF model is developed for reflectance correction. BRDF characterization requires a broad coverage of solar and view angles in the measurements over selected pseudo-invariant targets. Reflectance measurements over Libya 1, 2, and 4 desert sites from both the Aqua and Terra MODIS are regressed to a BRDF model with an adjustable coefficient accounting for the calibration difference between the two instruments. The BRDF coefficients for three desert sites for MODIS bands 1 to 9 are derived and the wavelength dependencies are presented. The analysis and inter-comparison are for MODIS bands 1 to 9 and VIIRS moderate resolution radiometric bands (M bands) M1, M2, M4, M5, M7, M8, M10 and imaging bands (I bands) I1-I3. Results show that the ratios from different sites are in good agreement. The ratios between Terra and Aqua MODIS from year 2003 to 2014 are presented. The inter-comparison between MODIS and VIIRS are analyzed for year 2014.

Nineteenth nuclear accident dosimetry intercomparison study, August 9-13, 1982

International Nuclear Information System (INIS)

Greene, R.T.; Sims, C.C.; Swaja, R.E.

1983-11-01

The Nineteenth Nuclear Accident Dosimetry Intercomparison Study was held August 9 to 13, 1982, at the Oak Ridge National Laboratory using the Health Physics Research Reactor operated in the pulse mode to simulate nuclear criticality accidents. Participants from eight organizations measured neutron and gamma doses at air stations and on phantoms for three different shielding conditions. Measured results were compared to nuclear industry guidelines for criticality accident dosimeters which suggest accuracies of +-25% for neutron dose and +-20% for gamma dose. Seventy-two percent of the neutron dose measurements using foil activation, sodium activation, hair sulfur activation, and thermoluminescent methods met the guidelines while less than 40% of the gamma dose measurements were within +-20% of reference values. The softest neutron energy spectrum (also lowest neutron/gamma dose ratio) provided the most difficulty in measuring neutron and gamma doses. Results of this study indicate the need for continued intercomparison and testing of nuclear accident dosimetry systems and for training of evaluating personnel. 14 references, 7 figures, 16 tables

International codes and model intercomparison for intermediate energy activation yields

International Nuclear Information System (INIS)

Rolf, M.; Nagel, P.

1997-01-01

The motivation for this intercomparison came from data needs of accelerator-based waste transmutation, energy amplification and medical therapy. The aim of this exercise is to determine the degree of reliability of current nuclear reaction models and codes when calculating activation yields in the intermediate energy range up to 5000 MeV. Emphasis has been placed for a wide range of target elements ( O, Al, Fe, Co, Zr and Au). This work is mainly based on calculation of (P,xPyN) integral cross section for incident proton. A qualitative description of some of the nuclear models and code options employed is made. The systematics of graphical presentation of the results allows a quick quantitative measure of agreement or deviation. This code intercomparison highlights the fact that modeling calculations of energy activation yields may at best have uncertainties of a factor of two. The causes of such discrepancies are multi-factorial. Problems are encountered which are connected with the calculation of nuclear masses, binding energies, Q-values, shell effects, medium energy fission and Fermi break-up. (A.C.)

Intercomparison of natural radionuclide measurements in marine sediment sample SD-N-1/2

International Nuclear Information System (INIS)

1985-06-01

This intercomparison exercise was organized with the aim of providing to the participating laboratories a possibility of testing the performance of their analytical methods and to acquire basic data for establishing reference values for a number of natural radionuclides in the sediment material SD-N-1/2 from the North Sea floor. In tables are presented results expressed in mBq.g -1 on potassium, uranium isotopes, thorium-232 with the respective decay products, thorium-230, radium-226 and lead-210. Altogether 98 laboratories from 42 Member States joined this intercomparison. The results show generally good agreement, but more analytical work is needed to improve the present status of the lead-210 certification. Gamma and alpha spectroscopy were the most frequently used as the analytical techniques

Ice Sheet Model Intercomparison Project (ISMIP6) contribution to CMIP6

NARCIS (Netherlands)

Nowicki, Sophie M J; Payne, Anthony; Larour, Eric; Seroussi, Helene; Goelzer, Heiko|info:eu-repo/dai/nl/412549123; Lipscomb, William; Gregory, Jonathan; Abe-Ouchi, Ayako; Shepherd, Andrew

2016-01-01

Reducing the uncertainty in the past, present, and future contribution of ice sheets to sea-level change requires a coordinated effort between the climate and glaciology communities. The Ice Sheet Model Intercomparison Project for CMIP6 (ISMIP6) is the primary activity within the Coupled Model

Strategy on radioactive waste management in Lithuania

International Nuclear Information System (INIS)

Poskas, P.; Adomaitis, J.E.

2003-01-01

In Lithuania about 70-80% of all electricity is generated at a single power station, Ignalian NPP which has two non-upgradable RBMK-1500 type reactors. The unit 1 will be closed by 2005. The decision on unit 2 should be made in Lithuanian Parliament very soon taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. The Government approved the Strategy on Radioactive Waste Management in 2002. Objectives of this strategy are to develop the radioactive waste management infrastructure based on modern technologies and provide for the set of practical actions that shall bring management of radioactive waste in Lithuania in compliance with radioactive waste management principles of IAEA and with good practices in force in EU Member States. Ignalina NPP is undertaking a program of decommissioning support projects, financed by grants from the International Ignalina Decommissioning Support Fund, administered by the European Bank for Reconstruction and Development. This program comprises also the implementation of investment projects in a number of pre-decommissioning facilities including the management of radioactive waste and spent nuclear fuel. (orig.)

Radioactive material (RAM) accident/incident data analysis program

International Nuclear Information System (INIS)

Emerson, E.L.; McClure, J.D.

1985-03-01

This report describes the development of the Radioactive Material Transportation Accident/Incident Data Base (RAM-AIDB), which contains information on the occurrences of transportation accidents and incidents, for radioactive materials (RAM) that are involved in the process of transportation, loading and unloading operation, or temporary storage. These transportation operations are in support of the nuclear fuel cycle for electrical energy generation. This study analyzes in some detail basic accident/incident statistical data, RAM packaging accident response data, and the health effects associated with RAM transport accidents/incidents. This report presents a summary of US RAM transport accident/incident experience for the period 1971 through December 1981. In addition, a sample annual summary of accident/incident experience is presented for the calendar year 1981

Annual radioactive waste tank inspection program - 1999

International Nuclear Information System (INIS)

Moore, C.J.

2000-01-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1999 to evaluate these vessels and auxiliary appurtenances along with evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

Economics of low-level radioactive waste disposal

International Nuclear Information System (INIS)

Schafer, J.; Jennrich, E.

1983-01-01

Regardless of who develops new low-level radioactive waste disposal sites or when, economics will play a role. To assist in this area the Department of Energy's Low-Level Radioactive Waste Management Program has developed a computer program, LLWECON, and data base for projecting disposal site costs. This program and its non-site specific data base can currently be used to compare the costs associated with various disposal site development, financing, and operating scenarios. As site specific costs and requirements are refined LLWECON will be able to calculate exact life cycle costs for each facility. While designed around shallow land burial, as practiced today, LLWECON is flexible and the input parameters discrete enough to be applicable to other disposal options. What the program can do is illustrated

Packaging and transportation of radioactive materials: summary program

International Nuclear Information System (INIS)

1978-01-01

This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference

Government/Industry Partnership on the Security of Radioactive Sources

International Nuclear Information System (INIS)

Cefus, Greg; Colhoun, Stefan C.; Freier, Keith D.; Wright, Kyle A.; Herdes, Gregory A.

2006-01-01

In the past, industry radiation protection programs were built almost exclusively around radiation safety and the minimization of radiation dose exposure to employees. Over the last decade, and especially the last few years, the emphasis has shifted to include the physical security and enhanced control of radioactive materials. The threat of nuclear and radiological terrorism is a genuine international security concern. In May 2004, the U.S. Department of Energy/U.S. National Nuclear Security Administration unveiled the Global Threat Reduction Initiative (GTRI) to respond to a growing international concern for the proper control and security of radioactive and nuclear materials. An integral part of the GTRI, the International Radiological Threat Reduction (IRTR) Program, was established in February 2002, originally as a Task Force. The IRTR Program is foremost a government-to-government cooperative program with the mission to reduce the risk posed by vulnerable radioactive materials that could be used in a Radioactive Dispersal Device (RDD). However, governments alone cannot prevent the misuse and illicit trafficking of radioactive sources. By expanding the role of private industry as a partner, existing government regulatory infrastructures can be enhanced by formulating and adopting industry self-regulation and self-policing measures. There is international concern regarding the security and control of the vast number of well-logging sources used during oil exploration operations. The prevalence of these sources, coupled with their portability, is a legitimate security concern. The energy exploration industry has well established safety and security protocols and the IRTR Program seeks to build on this foundation. However, the IRTR Program does not have sufficient resources to address the issue without industry assistance, so it is looking to the oil and gas industry to help identify alternative means for accomplishing our mutual objectives. This paper describes

In-situ gammaspectrometry intercomparison exercise in Salzburg/Austria

International Nuclear Information System (INIS)

Steger, F.; Lovranich, E.; Lettner, H.; Andrasi, A.

1996-01-01

In-situ gamma-spectrometry has become a useful method of assessing the nuclide concentrations of man-made and natural gamma-emitters in the soil. For the quality assurance of the measurements, periodically conducted intercomparison exercises are essential. Therefore exercises were organized in different European countries since 1990, the last one was conducted in Salzburg /Austria in September 1994. The participation of 24 measurement-teams from all over Europe emphasizes the importance of the intercomparison. Salzburg was selected because the Province of Salzburg /Austria was among the most heavily contaminated regions outside the former USSR by the Chernobyl fallout. Two different typical sites were selected for the measurements: Site 1 was inside the urban area of Salzburg on intensively used grassland which had not been tilled since the deposition of the fallout. This site is representative for intensively used agricultural regions in the Province of Salzburg. Site 2 was in the mountainous regions of the Hohe Tauern at an elevated altitude of 1600 m, representing the agricultural soil- and contamination conditions of the Alpine regions in the Tauern. The two sites differ significantly in terms of soil characteristics, a crucial parameter for the evaluation of in-situ gamma-spectra. The participants used different approaches for the evaluation of the gamma-spectra in terms of considering the depth distribution. In the paper the results from the 24 European teams are presented. (author)

LLNL radioactive waste management plan as per DOE Order 5820.2

International Nuclear Information System (INIS)

1984-01-01

The following aspects of LLNL's radioactive waste management plan are discussed: program administration; description of waste generating processes; radioactive waste collection, treatment, and disposal; sanitary waste management; site 300 operations; schedules and major milestones for waste management activities; and environmental monitoring programs (sampling and analysis)

Intercomparison exercise on internal dose assessment. Final report of a joint IAEA-IDEAS project

International Nuclear Information System (INIS)

2007-09-01

There have been several intercomparison exercises organized already at national and international levels for the assessment of occupational exposure due to intakes of radionuclides. These intercomparison exercises revealed significant differences in approaches, methods and assumptions, and consequently in the results. Because of the relevance of the issue for internal dosimetrists, the IAEA organized a new intercomparison exercise in cooperation with the IDEAS project General Guidelines for the Evaluation of Incorporation Monitoring Data, launched under the 5th EU Framework Programme (EU Contract No. FIKR-CT2001-00160). This new intercomparison exercise focused especially on the effect of the guidelines for harmonization of internal dosimetry. It also considered the following aspects: - to provide possibilities for the participating laboratories to check the quality of their internal dose assessment methods in applying the recent ICRP recommendations (e.g. for the new respiratory tract model); - to compare different approaches in interpretation of internal contamination monitoring data; - to quantify the differences in internal dose assessments based on the new guidelines or on other procedures, respectively; - to provide some figures for the influence of the input parameters on the monitoring results; and - to provide a broad forum for information exchange. Several cases have been selected for this exercise with the aim of covering a wide range of practices in the nuclear fuel cycle and in medical applications. The cases were: 1. Acute intake of HTO; 2. Acute inhalation of fission products 137 Cs and 90 Sr; 3. Intake of 60 Co; 4. Repeated intakes of 131 I; 5. Intake of enriched uranium; 6. Single intake of plutonium radionuclides and 241 Am. An Internet based approach had been used for the presentation of the cases, collection of responses and potential discussion of the results. Solutions to these cases were reported by 80 participants worldwide. This report

Packaging and transportation of radioactive materials: summary program

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-01

This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference. (DC)

Assessing doses to terrestrial wildlife at a radioactive waste disposal site: Inter-comparison of modelling approaches

Energy Technology Data Exchange (ETDEWEB)

Johansen, M.P., E-mail: mathew.johansen@ansto.gov.au [Australian Nuclear Science and Technology Organisation, Locked Bag 2001, Kirrawee DC, NSW, 2232 (Australia); Barnett, C.L., E-mail: clb@ceh.ac.uk [Centre for Ecology and Hydrology, Lancaster (United Kingdom); Beresford, N.A., E-mail: nab@ceh.ac.uk [Centre for Ecology and Hydrology, Lancaster (United Kingdom); Brown, J.E., E-mail: justin.brown@nrpa.no [Norwegian Radiation Protection Authority, Oesteraas (Norway); Cerne, M., E-mail: marko.cerne@ijs.si [Jozef Stefan Institute, Ljubljana (Slovenia); Howard, B.J., E-mail: bjho@ceh.ac.uk [Centre for Ecology and Hydrology, Lancaster (United Kingdom); Kamboj, S., E-mail: skamboj@anl.gov [Argonne National Laboratory, IL (United States); Keum, D.-K., E-mail: dkkeum@kaeri.re.kr [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Smodis, B. [Jozef Stefan Institute, Ljubljana (Slovenia); Twining, J.R., E-mail: jrt@ansto.gov.au [Australian Nuclear Science and Technology Organisation, Locked Bag 2001, Kirrawee DC, NSW, 2232 (Australia); Vandenhove, H., E-mail: hvandenh@sckcen.be [Belgian Nuclear Research Centre, Mol (Belgium); Vives i Batlle, J., E-mail: jvbatll@sckcen.be [Belgian Nuclear Research Centre, Mol (Belgium); Wood, M.D., E-mail: m.d.wood@salford.ac.uk [University of Salford, Manchester (United Kingdom); Yu, C., E-mail: cyu@anl.gov [Argonne National Laboratory, IL (United States)

2012-06-15

Radiological doses to terrestrial wildlife were examined in this model inter-comparison study that emphasised factors causing variability in dose estimation. The study participants used varying modelling approaches and information sources to estimate dose rates and tissue concentrations for a range of biota types exposed to soil contamination at a shallow radionuclide waste burial site in Australia. Results indicated that the dominant factor causing variation in dose rate estimates (up to three orders of magnitude on mean total dose rates) was the soil-to-organism transfer of radionuclides that included variation in transfer parameter values as well as transfer calculation methods. Additional variation was associated with other modelling factors including: how participants conceptualised and modelled the exposure configurations (two orders of magnitude); which progeny to include with the parent radionuclide (typically less than one order of magnitude); and dose calculation parameters, including radiation weighting factors and dose conversion coefficients (typically less than one order of magnitude). Probabilistic approaches to model parameterisation were used to encompass and describe variable model parameters and outcomes. The study confirms the need for continued evaluation of the underlying mechanisms governing soil-to-organism transfer of radionuclides to improve estimation of dose rates to terrestrial wildlife. The exposure pathways and configurations available in most current codes are limited when considering instances where organisms access subsurface contamination through rooting, burrowing, or using different localised waste areas as part of their habitual routines. - Highlights: Black-Right-Pointing-Pointer Assessment of modelled dose rates to terrestrial biota from radionuclides. Black-Right-Pointing-Pointer The substantial variation among current approaches is quantifiable. Black-Right-Pointing-Pointer The dominant variable was soil

A directory of computer programs for assessment of radioactive waste disposal in geological formations. Volume 2

International Nuclear Information System (INIS)

Ashton, J.; Broyd, T.W.; Jones, M.A.; Knowles, N.C.; Liew, S.K.; Mawbey, C.S.; Read, D.; Smith, S.L.

1993-01-01

This directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post-closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, geomechanics, heat transfer, groundwater flow, radionuclide migration, biosphere modelling, safety assessment and site evolution. A total of 320 programs are identified, of which 84 are reviewed in detail, 192 in summary and 44 in tabular fashion. Originally published in 1983, the directory was updated in 1985 with the addition of new programs and the revision of some of the existing program reviews. This directory has been completely rewritten in 1991 with the addition of more new programs and a full revision of all the existing program reviews, some of which have been deleted as they are no longer in general use. Although the directory is specific to the post-closure assessment of a repository site, some of the programs described can also be used in other areas of repository (e.g. repository design). This directory is composed of two volumes, the present volume is the second

A directory of computer programs for assessment of radioactive waste disposal in geological formations. Volume 1

International Nuclear Information System (INIS)

Ashton, J.; Broyd, T.W.; Jones, M.A.; Knowles, N.C.; Liew, S.K.; Mawbey, C.S.; Read, D.; Smith, S.L.

1993-01-01

This directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post-closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, geomechanics, heat transfer, groundwater flow, radionuclide migration, biosphere modelling, safety assessment and site evolution. A total of 320 programs are identified of which 84 are reviewed in detail, 192 in summary and 44 in tabular fashion. Originally published in 1983, the directory was updated in 1985 with the addition of new programs and the revision of some of the existing program reviews. This directory has been completely rewritten in 1991 with the addition of more new programs and a full revision of all the existing program reviews, some of which have been deleted as they are no longer in general use. Although the directory is specific to the post-closure assessment of a repository site, some of the programs described can also be used in other areas of repository (e.g. repository design). This directory is composed of two volumes, the present volume is the first

Establishing community trust at radioactively contaminated sites

International Nuclear Information System (INIS)

Simpson, E.

1999-01-01

Establishing community trust is an essential element in the successful remediation of a radioactively contaminated site. The US Environmental Protection Agency (EPA), Region 2 has been involved in the clean up of numerous radioactively contaminated Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), Resource Conservation Recovery Act (RCRA), and Formerly Utilized Site Remedial Action Program (FUSRAP) sites in New Jersey and New York. Each site presented a unique challenge which centered around establishing and, often, re-establishing the trust of the surrounding community. Thanks to the United States government's history regarding the use of radioactive materials, people question whether governmental regulators could possibly have the public's best interests in mind when it comes to addressing radioactively contaminated sites. It has been our experience that EPA can use its position as guardian of the environment to help establish public confidence in remedial actions. The EPA can even use its position to lend credibility to remedial activities in situations where it is not directly responsible for the clean-up. Some ways that we have found to instill community confidence are: establishing radioanalytical cross-check programs using EPA's National Air and Radiation Environmental Laboratory to provide analytical quality assurance; and establishing an environmental radiation monitoring program for the contaminated site and surrounding community. (author)

In-situ-gamma-spectrometry intercomparison exercise in Salzburg, Austria, September 26-30, 1994

International Nuclear Information System (INIS)

Steger, F.; Lettner, H.; Andrasi, A.

1996-06-01

In-situ gamma spectrometry has become a useful method to assess the nuclide concentration of artificial and natural gamma-emitters in the soil. With such measurements it is possible to calculate the activity concentration in soil and also the nuclide specific exposure rates 1 m above ground. For the quality assurance of the measurements periodically intercomparison exercises are essential. To meet this requirement exercises were organised in different European countries since 1989. The last exercise in September 1994 was organised in Salzburg / Austria. The participation of 24 measurement teams from all over Europe emphasises the importance of the intercomparison. Salzburg was selected because the Province of Salzburg / Austria was among the heaviest contaminated region outside the former USSR by the Chernobyl fallout. Two different typical sites were selected for the measurements: Site 1 was inside the urban area of Salzburg on intensively used agricultural land which had not been disturbed since the fallout. This site is representative for intensively used agricultural regions in the Province of Salzburg. Site 2 was in the mountainous region of the Tauern on elevated altitude of approx. 1700 m. This site represents the soil and contamination conditions of the Alpine region. Both sites differ significantly in terms of different soil distribution and contents of natural and artificial radionuclides. Results of the intercomparison exercise are presented. (author)

DRDC Ottawa Participation in the SILENE Accident Dosimetry Intercomparison Exercise. June 10-21, 2002

National Research Council Canada - National Science Library

Prud'homme-Lalonde, L

2002-01-01

.... The SILENE International Accident Dosimetry Intercomparison Exercise at Valduc, France in June 2002 coincided with DRDC Ottawa work designed to refine its proposed criticality dosimetry system...

Report on the intercomparison run F-1 U and K(Th) in feldspar

International Nuclear Information System (INIS)

1990-01-01

The present report deals with a recent intercomparison on the determination of uranium, thorium and potassium in potassium feldspar, carried out in 1976-77 and involving the participation of 20 institutes who returned a total of 196 individual results on three elements. Analytical techniques employed by the participating institutes included gamma spectrometry, emission spectroscopy, atomic absorption, X-ray fluorescence, fluorimetry and neutron activation. Each of these techniques has its own particular weakness: The basic principles of gamma-spectrometric technique for the determination of U, Th and K are well known. It is, however, difficult to determine the low concentrations of radioactive nuclides which can be found in geological materials due to systematic errors arising from non-equilibration of decay chains in the samples and from other sources including calibration. Determination of uranium in geological materials by non-destructive neutron activation analysis also has some problems. Elements such as Th, Ta, Pt, Ru, Zn and Ba when irradiated in a nuclear reactor with thermal and epithermal neutrons yield radioactive isotopes, the gamma rays of which interfere with those used in uranium determination. Detection limits for three elements U, Th and K for thermal neutron activation have been reported as 0.7, 1.0 and 10 ppb respectively, however, this seems over-optimistic to expect in real-life situations. Measurement of delayed neutrons and fission track methods for uranium and thorium also have interference problems. Fluorimetry is a suitable method for uranium at low concentrations (down to 0.1 ppm) but one has to take care to overcome quenching by removing, or at least diluting, interfering elements. The determination of some important elements in geochemical samples is often difficult because of their small concentration as well as of the presence of interfering matrix elements in the samples. Some systematic differences seem to exist between the methods

An intercomparison of Monte Carlo codes used for in-situ gamma-ray spectrometry

International Nuclear Information System (INIS)

Hurtado, S.; Villa, M.

2010-01-01

In-situ gamma-ray spectrometry is widely used for monitoring of natural as well as man-made radionuclides and corresponding gamma fields in the environment or working places. It finds effective application in the operational and accidental monitoring of nuclear facilities and their vicinity, waste depositories, radioactive contamination measurements and environmental mapping or geological prospecting. In order to determine accurate radionuclide concentrations in these research fields, Monte Carlo codes have recently been used to obtain the efficiency calibration of in-situ gamma-ray detectors. This work presents an inter-comparison between two Monte Carlo codes applied to in-situ gamma-ray spectrometry. On the commercial market, Canberra has its LABSOCS/ISOCS software which is relatively inexpensive. The ISOCS mathematical efficiency calibration software uses a combination of Monte Carlo calculations and discrete ordinate attenuation computations. Efficiencies can be generated in a few minutes in the field and can be modified easily if needed. However, it has been reported in the literature that ISOCS computation method is accurate on average only within 5%, and additionally in order to use LABSOCS/ISOCS it is necessary a previous characterization of the detector by Canberra, which is an expensive process. On the other hand, the multipurpose and open source GEANT4 takes significant computer time and presents a non-friendly but powerful toolkit, independent of the manufacturer of the detector. Different experimental measurements of calibrated sources were performed with a Canberra portable HPGe detector and compared to the results obtained using both Monte Carlo codes. Furthermore, a variety of efficiency calibrations for different radioactive source distributions were calculated and tested, like plane shapes or containers filled with different materials such as soil, water, etc. LabSOCS simulated efficiencies for medium and high energies were given within an

Physical countermeasures to sustain acceptable living and working conditions in radioactively contaminated residential areas

CERN Document Server

Andersson, K G; Roed, J

2003-01-01

The Chernobyl accident highlighted the need in nuclear preparedness for robust, effective and sustainable countermeasure strategies for restoration of radioactively contaminated residential areas. Under the EC-supporter STRATEGY project a series of investigations were made of countermeasures that were deemed potentially applicable for implementation in such events in European Member States. The findings are presented in this report, in a standardised data sheet format to clarify the features of the individual methods and facilitate intercomparison. The aspects of averted doses and management of wastes generated by countermeasures had to be described separately to provide room for the required level of detail. The information is mainly intended as a tool for decision makers and planners and constitutes of basis for the STRATEGY decision framework for remediation of contaminated urban areas. (au)

Physical countermeasures to sustain acceptable living and working conditions in radioactively contaminated residential areas

Energy Technology Data Exchange (ETDEWEB)

Andersson, K G; Roed, J; Eged, K [and others

2003-02-01

The Chernobyl accident highlighted the need in nuclear preparedness for robust, effective and sustainable countermeasure strategies for restoration of radioactively contaminated residential areas. Under the EC-supporter STRATEGY project a series of investigations were made of countermeasures that were deemed potentially applicable for implementation in such events in European Member States. The findings are presented in this report, in a standardised data sheet format to clarify the features of the individual methods and facilitate intercomparison. The aspects of averted doses and management of wastes generated by countermeasures had to be described separately to provide room for the required level of detail. The information is mainly intended as a tool for decision makers and planners and constitutes of basis for the STRATEGY decision framework for remediation of contaminated urban areas. (au)

A directory of computer programs for assessment of radioactive waste disposal in geological formations

International Nuclear Information System (INIS)

Broyd, T.W.; Dean, R.B.; Hobbs, G.D.; Knowles, N.C.; Putney, J.M.; Wrigley, J.

1984-01-01

This Directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, stress analysis, heat transfer, groundwater flow and radionuclide transport. Biosphere modelling, surface water flow and risk analysis are not covered. A total of 248 programs are identified, of which 50 are reviewed in detail, 134 in summary and 64 in tabular fashion. The directory has been compiled using a combination of literature searches, telephone and postal correspondence and meetings with recognised experts in the respective areas of work covered. It differs from previous reviews of computer programs for similar topics areas in two main respects. Firstly, the method of obtaining information has resulted in program descriptions of considerable breadth and detail. Secondly, the Directory has concentrated wherever possible on European codes, whereas most previous work of this nature has looked solely at programs developed in North America. The reviews are presented in good faith, but it has not been possible to run any of the programs on a computer, and so truly objective comparisons may not be made. Finally, although the Directory is specific to the post-closure assessment of a repository site, some of the programs described could also be used in other areas of repository analysis (eg repository design)

Legal, political, and institutional implications of the seabed assessment program for radioactive waste disposal

International Nuclear Information System (INIS)

Deese, D.A.

1977-01-01

Sub-seabed disposal of high-level radioactive waste is discussed. The following conclusions are drawn: The outcome will be determined largely by the national political stances taken toward a sub-seabed disposal program. Political and diplomatic responses from individual countries should be expected to be heavily influenced by the number, type, and timing of options available for high-level waste disposal. The budgetary and institutional support Washington gives to the sub-seabed program will have a crucial influence on the progress of sub-seabed science and technology over the next three to five years. Despite the growing need of nations, such as Japan and Britain, for a high-level waste disposal option, a sub-seabed program will probably not be employed if it is not strongly funded and supported by the United States. Clearly, there are enough level and political obstacles to destroy or delay a sub-seabed disposal program. The nontechnical hurdles to seabed disposal at least equal the scientific and technical ones. But, on the other hand, there are important potential social and political benefits to be gained from any serious attempt to mount a successful sub-seabed program. These lie principally in international cooperation on waste management, environmental protection, nonproliferation of nuclear weapons, and governing the deep seabed

Managing Uncertainties Associated With Radioactive Waste Disposal: Task Group 4 Of The IAEA PRISM Project

International Nuclear Information System (INIS)

Seitz, R.

2011-01-01

It is widely recognized that the results of safety assessment calculations provide an important contribution to the safety arguments for a disposal facility, but cannot in themselves adequately demonstrate the safety of the disposal system. The safety assessment and a broader range of arguments and activities need to be considered holistically to justify radioactive waste disposal at any particular site. Many programs are therefore moving towards the production of what has become known as a Safety Case, which includes all of the different activities that are conducted to demonstrate the safety of a disposal concept. Recognizing the growing interest in the concept of a Safety Case, the International Atomic Energy Agency (IAEA) is undertaking an intercomparison and harmonization project called PRISM (Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal). The PRISM project is organized into four Task Groups that address key aspects of the Safety Case concept: Task Group 1 - Understanding the Safety Case; Task Group 2 - Disposal facility design; Task Group 3 - Managing waste acceptance; and Task Group 4 - Managing uncertainty. This paper addresses the work of Task Group 4, which is investigating approaches for managing the uncertainties associated with near-surface disposal of radioactive waste and their consideration in the context of the Safety Case. Emphasis is placed on identifying a wide variety of approaches that can and have been used to manage different types of uncertainties, especially non-quantitative approaches that have not received as much attention in previous IAEA projects. This paper includes discussions of the current results of work on the task on managing uncertainty, including: the different circumstances being considered, the sources/types of uncertainties being addressed and some initial proposals for approaches that can be used to manage different types of uncertainties.

Naturally Occurring Radioactive Materials (NORM)

International Nuclear Information System (INIS)

Gray, P.

1997-01-01

This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards they present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training)

Naturally Occurring Radioactive Materials (NORM)

Energy Technology Data Exchange (ETDEWEB)

Gray, P. [ed.

1997-02-01

This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards they present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training).

Thematic network on the analysis of thorium and its isotopes in workplace materials. Report on the 2nd intercomparison exercise

International Nuclear Information System (INIS)

Howe, A.; White, M.

2000-12-01

Work Package 2 (WP 2) of the EC Thematic Network on ''The analysis of thorium and its isotopes in workplace materials'' is concerned with ''Examination and comparison of analytical techniques for the determination of thorium and its progeny in bulk materials and the development of standards, both for the calibration of associated metrological facilities, and for routine quality control purposes''. The primary objective of WP 2 is ''To evaluate appropriate techniques and determine best practice for analysis of 232 Th at workplace levels and environments'', and is to be achieved through a series of intercomparison exercises. Following the results of the 1st intercomparison exercise, a 2nd intercomparison exercise was designed to evaluate the capability of the analytical methods currently being used by European laboratories to determine thorium at very low levels in the presence of a complex inorganic matrix. The intercomparison exercise involved the analysis of three samples of thorium in solution, prepared by the United Kingdom National Physical Laboratory. One sample was the equilibrium solution, analysed in the 1st intercomparison exercise. The other two samples were prepared by dilution of a non-equilibrium thorium solution, one of which was spiked with impurity elements. (i) The results showed a further improvement in the accuracy of measurements in the equilibrium solution, when compared with the results from the 1st intercomparison study. There was an overall drop in u-test values and the number of u-test values above the upper limit of significance fell from 6 to 3. (ii) Overall, participating laboratories also performed well in the analysis of the low level non-equilibrium solutions. However, several laboratories using y-spectrometry had insufficient sensitivity for measurement of low level non-equilibrium sample solutions and did not report results. (iii) There was little evidence that the presence of impurities had a detrimental effect on measurements made

Lessons learnt from an international intercomparison of national network systems used to provide early warning of a nuclear accident

International Nuclear Information System (INIS)

Saez-Vergara, J.C.; Thompson, I.M.G.; Funck, E.; Andersen, C.E.; Neumaier, S.; Botter-Jensen, L.

2003-01-01

As part of the European Research Council's Fourth Framework Programme, the EURADOS Action Group on Monitoring of External Exposures held an intercomparison of national network systems. This took place during May/June 1999 at the Riso Natural Environmental Radiation Measurement Station in Denmark and at the Underground Laboratory for Dosimetry and Spectrometry of the Physikalisch-Technische Bundesanstalt in Germany. The network systems are used continuously to monitor radiation levels throughout a country in order to give early warning of nuclear accidents having transboundary implications. The radiation levels measured are used to estimate the radiation risks to people arising from the accident. Seven European countries participated in the intercomparison with detector systems used in their national network systems as well as with detectors being developed for future use. Since different radiation quantities were measured by the systems (namely exposure, air kerma and ambient dose equivalent), the initial analysis of the intercomparison results was made in terms of the quantity air kerma rate. This report completes the analysis of the results and these are given in terms of air kerma rate in order to be consistent with the preliminary report. In addition, in some cases the results are also given in terms of the quantity measured by each national network system. The experience gained from this intercomparison is used to help organise a follow-up intercomparison to be held at the PTB Braunschweig in September 2002 and in which a further seven or eight countries from Europe will participate. (author)

Manual of respiratory protection against airborne radioactive materials

International Nuclear Information System (INIS)

Caplin, J.L.; Held, B.J.; Catlin, R.J.

1976-10-01

The manual supplements Regulatory Guide 8.15, ''Acceptable Programs for Respiratory Protection''. It provides broad guidance for the planned use of respirators to protect individuals from airborne radioactive materials that might be encountered during certain operations. The guidance is intended for use by management in establishing and supervising programs and by operating personnel in implementing programs. Guidance is primarily directed to the use of respirators to prevent the inhalation of airborne radioactive materials. Protection against other modes of intake (e.g., absorption, swallowing, wound injection) is, in general, not covered nor is the use of protective equipment for head, eye, or skin protection

PROGER - Management program for radioactive wastes in research institutions; PROGER - Programa para gerenciamento de rejeitos em instituicoes de pesquisa

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Rubemar S.; Costa, Maria Regina Ferro; Ramos Junior, Anthenor C.; Esposito, Irapoan; Vaz, Solange dos Reis e; Pontedeiro, Elizabeth May; Gomes, Carlos de Almeida [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Superintendencia de Licenciamento e Controle. Supervisao de Rejeitos Radioativos

1997-12-31

This article demonstrates the feasibility of a program, denominated PROGER, and aimed at the improvement of radioactive waste management activities in research institutions in Brazil. This program involves implementation, correction and updating of waste management techniques in those institutions that already possess a waste management system or its full set-up for the institutions where it is non-existent. Partial results are presented, concerning characteristics and quantities of wastes, and the methodology utilized by PROGER discussed 6 refs., 2 figs., 4 tabs.

Radioactive waste management

International Nuclear Information System (INIS)

Tang, Y.S.; Saling, J.H.

1990-01-01

The purposes of the book are: To create a general awareness of technologies and programs of radioactive waste management. To summarize the current status of such technologies, and to prepare practicing scientists, engineers, administrative personnel, and students for the future demand for a working team in such waste management

Commercial low-level radioactive waste management

International Nuclear Information System (INIS)

Coleman, J.A.

1982-01-01

The goals, objectives and activities of the Department of Energy's Low-Level Radioactive Waste Management program are reviewed. The goal of the overall Program is to support development of an acceptable, nationwide, near surface waste disposal system by 1986. The commercial LLW program has two major functions: (1) application of the technology improvements for waste handling, treatment and disposal, and (2) assistance to states as they carry out their responsibilities under the Low-Level Radioactive Waste Policy Act of 1980. The priorities for the commercial side of the Low-Level Waste Management Program have been established to meet one goal: to support development of an effective commercial management system by 1986. The first priority is being given to supporting state efforts in forming the institutional structures needed to manage the system. The second priority is the state and industry role in transferring and demonstrating treatment and disposal technologies

Media analysis of radioactive wastes

International Nuclear Information System (INIS)

Janowski, M.J.

1989-01-01

The radioactive waste cleanup community has not effectively utilized its most powerful communications tool to inform the general public; the print and broadcast media. Environmental interest groups have known of the value of accessing the media for their message for years and have used it effectively. The radioactive waste cleanup community's efforts to date have not been focused on education of the media so that they in turn can inform the public of our cleanup mission. Their focus must be to learn of the importance of the media, develop training programs that train technical people in how to know and respond to the media's needs for information, and then incorporate that training into a comprehensive program of public information in which access to the media is a key communications tool. This paper discusses how media education and access is a cost-effective means of accomplishing community relations goals of public information and public participation in radioactive waste cleanup and has been effectively utilized at the Weldon Spring Site Remedial Action Project

Radioactivity in the hydrologic environment

International Nuclear Information System (INIS)

Werner, L.B.

1969-01-01

Certain proposed uses of nuclear explosives for peaceful purposes will introduce radioactive debris into the natural hydrologic environment. Consideration must therefore be given in each situation to the extent and significance to man of resulting radioactively contaminated water. For contained underground detonations, space-time - concentration predictions of radioactive materials in ground water are dependent on several factors: radionuclide production and initial distribution, radioactive decay, sorption on geologic materials, and dispersion during hydrologic transport. For uncontained (cratering) detonations, other aspects of the hydrologic cycle, particularly rainfall, and watershed characteristics must be considered. Programs sponsored principally by the U.S. Atomic Energy Commission have investigated these factors. Examination of their net effects on radioactivity concentration in water shows that areas if any, underlain by water exceeding permissible concentrations tend first to increase in size, then decrease, and finally disappear. Hydrologic processes at the surface remove or redistribute radioactive debris deposited on a watershed to other locations. Where sufficient information is available, predictions of location and concentration of radionuclides in natural waters can be made. Any potentially hazardous conditions arising from a particular detonation can then be evaluated. (author)

Radioactivity in the hydrologic environment

Energy Technology Data Exchange (ETDEWEB)

Werner, L B [Isotopes, Inc., Palo Alto, CA (United States)

1969-07-01

Certain proposed uses of nuclear explosives for peaceful purposes will introduce radioactive debris into the natural hydrologic environment. Consideration must therefore be given in each situation to the extent and significance to man of resulting radioactively contaminated water. For contained underground detonations, space-time - concentration predictions of radioactive materials in ground water are dependent on several factors: radionuclide production and initial distribution, radioactive decay, sorption on geologic materials, and dispersion during hydrologic transport. For uncontained (cratering) detonations, other aspects of the hydrologic cycle, particularly rainfall, and watershed characteristics must be considered. Programs sponsored principally by the U.S. Atomic Energy Commission have investigated these factors. Examination of their net effects on radioactivity concentration in water shows that areas if any, underlain by water exceeding permissible concentrations tend first to increase in size, then decrease, and finally disappear. Hydrologic processes at the surface remove or redistribute radioactive debris deposited on a watershed to other locations. Where sufficient information is available, predictions of location and concentration of radionuclides in natural waters can be made. Any potentially hazardous conditions arising from a particular detonation can then be evaluated. (author)

Results Assessment of Intercomparison Exercise CSN/CIEMAT-2010 among Spanish National Laboratories of Environmental Radioactivity (Diet Ashes); Evaluacion de la Intercomparacion CSN/CIEMAT-2010 entre los Laboratorios Nacionales de Radiactividad Ambiental (Ceniza de Dieta)

Energy Technology Data Exchange (ETDEWEB)

Gasco, C.; Trinidad, J. A.; Llaurado, M.; Suarez, J. A.

2012-06-08

This report describes the results assessment of the intercomparison exercise among environmental radioactivity laboratories, organised by Spanish Regulatory Institution (CSN) and prepared and evaluated by UAB and CIEMAT respectively. The exercise has been carried out following the international standards ISO-43 and ISO/IUPAC that provide a useful guide to perform proficiency tests and inter-laboratories comparisons. The selected matrix for this year (2010) was a diet ash obtained from the ashing of a whole fresh diet (breakfast, lunch and dinner), that was enriched with artificial radionuclides (Cs-137, Co-60,Fe-55,Ni-63,Sr-90,Am-241,Pu-238,Pu-239,240 y C-14) and contained natural radionuclides (U-234, U-238, U-natural Th-230, Th-234, Ra-226, Ra-228, Pb-210, Pb-212, Pb-214, Bi-214, Ac-228, Tl-208, K-40) at environmental level of activity concentration. The z-score test was applied to determine how much the laboratories differ from the reference value. The reference value for this exercise was the median of the results from the different laboratories and their standard deviations to achieve a more complete and objective study of the laboratories performance. The participant laboratories have demonstrated a satisfactory quality level for measuring the natural and artificial radionuclides content in this matrix. The reference values obtained through the medians show a negative bias for Pb-210 and Th-234 when comparing to the given values of external qualified laboratories from ENEA and IRSN and positive one for K-40. (Author)